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1

Radiological verification survey results at 14 Peck Ave., Pequannock, New Jersey (PJ001V)  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) conducted remedial action during 1993 at the Pompton Plains Railroad Spur and eight vicinity properties in the Wayne and Pequannock Townships in New Jersey as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are in the vicinity of the DOE-owned Wayne Interim Storage Site (WISS), formerly the W. R. Grace facility. The property at 14 Peck Ave., Pequannock, New Jersey is one of these vicinity properties. At the request of DOE, a team from Oak Ridge National Laboratory conducted an independent radiological verification survey at this property. The purpose of the survey, conducted between September and December 1993, was to confirm the success of the remedial actions performed to remove any radioactive materials in excess of the identified guidelines. The verification survey included surface gamma scans and gamma readings at 1 meter, beta-gamma scans, and the collection of soil and debris samples for radionuclide analysis. Results of the survey demonstrated that all radiological measurements on the property at 14 Peck Ave. were within applicable DOE guidelines. Based on the results of the remedial action data and confirmed by the verification survey data, the portions of the site that had been remediated during this action successfully meet the DOE remedial action objectives.

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

1995-05-01T23:59:59.000Z

2

Radiological verification survey results at 7 Peck Ave., Pequannock, New Jersey (PJ003V)  

SciTech Connect (OSTI)

The US Department of Energy (DOE) conducted remedial action during 1993 at the Pompton Plains Railroad Spur and eight vicinity properties in the Wayne and Pequannock Townships in New Jersey as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are in the vicinity of the DOE-owned Wayne Interim Storage Site (WISS), formerly the W.R. Grace facility. The property at 7 Peck Ave., Pequannock, New Jersey is one of these vicinity properties. At the request of DOE, a team from Oak Ridge National Laboratory conducted an independent radiological verification survey at this property. The purpose of the survey, conducted between September and December 1993, was to confirm the success of the remedial actions performed to remove any radioactive materials in excess of the identified guidelines. The verification survey included surface gamma scans and gamma readings at 1 meter, beta-gamma scans, and the collection of soil samples for radionuclide analysis. Results of the survey demonstrated that all radiological measurements on the property at 7 Peck Ave. were within applicable DOE guidelines. Based on the results of the remedial action data and confirmed by the verification survey data, the portions of the site that had been remediated during this action successfully meet the DOE remedial action objectives.

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

1995-05-01T23:59:59.000Z

3

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

SciTech Connect (OSTI)

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.

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

1989-05-01T23:59:59.000Z

4

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

SciTech Connect (OSTI)

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.

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

1994-02-01T23:59:59.000Z

5

Results of the radiological and beryllium verification survey at the Sacandaga Site, Glenville, New York (SY002V)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted an independent verification radiological and non-radioactive beryllium survey at the Sacandaga Site, located on Sacandaga Road, Glenville, New York following limited remediation of the site by Allwash of Syracuse, Inc. At the time of this survey, only building P was still standing. A small concrete structure at the east of the property had been demolished and the debris hauled away, leaving only a pit. The purpose of the survey, conducted between April and August 1993, was to confirm the success of the remedial actions performed to remove any beryllium concentrations or radioactive materials in excess of the identified guidelines. The verification survey included surface gamma scans and gamma readings at 1 meter indoors and outdoors, alpha and beta scans inside building P, and the collection of soil, dust and debris samples and smears for radionuclide and beryllium analyses. Results of the survey demonstrated that all radiological and beryllium measurements on the property were within applicable DOE guidelines. Based on all data collected. the Sacandaga Site, Glenville, New York, conforms to all applicable radiological and non-radioactive beryllium guidelines established for this site by DOE and approved by the State of New York.

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

1994-09-01T23:59:59.000Z

6

Results of the radiological and beryllium verification survey at the Peek Street Site, Schenectady, New York (SY001V)  

SciTech Connect (OSTI)

At the request of the U.S. Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted an independent verification radiological and non-radioactive beryllium survey at the Peek Street site, located at 425 Peek Street, Schenectady, New York. The purpose of the survey, conducted during 1993 and continuing through January 1994, was to confirm the success of the remedial actions performed to remove any beryllium concentrations or radioactive materials in excess of the identified guidelines. The verification survey included surface gamma scans and gamma readings at one meter indoors and outdoors, alpha and beta scans inside the structure, and the collection of soil, dust and debris samples and smears for radionuclide and beryllium analyses. Results of the survey demonstrated that all radiological and beryllium measurements on the property were within applicable DOE guidelines. Based on all data collected, the industrial property at 425 Peek Street and the adjacent state-owned bike path in Schenectady, New York, conforms to all applicable radiological and non-radioactive beryllium guidelines established for this site by DOE and approved by the State of New York.

Foley, R.D.; Johnson, C.A.; Carrier, R.F.; Allred, J.F.

1994-10-01T23:59:59.000Z

7

Results of the radiological verification survey at the former Herring-Hall-Marvin Safe Company, 1550 Grand Boulevard, Hamilton Ohio (HO001V)  

SciTech Connect (OSTI)

During the period between the 1940s and early 1950s, the Herring-Hall-Marvin Safe Company, 1550 Grand Boulevard, Hamilton, Ohio, was one company under subcontract to the Manhattan Engineer District (MED), and the Atomic Energy Commission (AEC), the lead agencies in the development of nuclear energy for defense-related projects. The US Department of Energy (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, a radiological survey of the Herring-Hall-Marvin Safe Company facility was conducted, and after small fragments of uranium metal were removed, no beta or gamma radiation above background was detected and the building was dismissed from any additional DOE restrictions. In 1993, it was discovered that a portion of the actual machining work was conducted on the third floor of the facility, located in the southeastern comer of the building. At the request of DOE, this part of the facility was radiologically surveyed by an ORNL survey team to determine whether fixed surface contamination could be found that might exceed the DOE guidelines. Results of this radiological survey indicated {sup 238}U contamination in excess of the DOE criteria for surface contamination, and the site was recommended for remediation. In February and March of 1995, a verification survey of the third floor of the former Herring-Hall-Marvin Safe Company facility by an ORNL survey team was performed in conjunction with decontamination operations conducted under the supervision of Bechtel National Incorporated. The verification survey included gamma scans at the surface and at one meter, alpha and beta-gamma scans for fixed contamination, and smears for transferable contamination.

Murray, M.E.; allred, J.F.; Johnson, C.A.

1995-11-01T23:59:59.000Z

8

Results of the independent radiological verification survey of the remedial action performed at 525 S. Main Street, Oxford, Ohio, (OXO002)  

SciTech Connect (OSTI)

Between October 1952 and February 1957, National Lead of Ohio (NLO), a primary contractor for the Atomic Energy Commission (AEC), subcontracted certain uranium machining operations to Alba Craft Laboratory, Incorporated, located at 10-14 West Rose Avenue, Oxford, Ohio. In 1992, personnel from Oak Ridge National Laboratory (ORNL) confirmed the presence of residual radioactive materials from the AEC-related operations in and around the facility in amounts exceeding the applicable Department of Energy (DOE) guidelines. Above-guideline radiation levels were also found both indoors and outdoors at 525 S. Main Street, a private residential property in the immediate vicinity of the Alba Craft site. This document reports the findings at this private residence. Although the amount of uranium found on the properties posed little health hazard if left undisturbed, the levels were sufficient to require remediation to bring radiological conditions into compliance with current guidelines, thus ensuring that the public and the environment are protected. A team from ORNL conducted a radiological verification survey of the property at 525 S. Main Street, between November 1993 and December 1994. The survey was conducted at the request of DOE and included directly measured radiation levels, the collection and analysis of soil samples to determine concentrations of uranium and certain other radionuclides, and comparison of these data to the guidelines.

Kleinhans, K.R.; Rice, D.E.; Murray, M.E.; Carrier, R.F.

1996-04-01T23:59:59.000Z

9

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

SciTech Connect (OSTI)

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.

Weaver, P.

2008-03-17T23:59:59.000Z

10

Interim Letter Report - Verification Survey Results for Activities Performed in March 2009 for the Vitrification Test Facility Warehouse at the West Valley Demonstration Project, Ashford, New York  

SciTech Connect (OSTI)

The objective of the verification activities was to provide independent radiological surveys and data for use by the Department of Energy (DOE) to ensure that the building satisfies the requirements for release without radiological controls.

B.D. Estes

2009-04-24T23:59:59.000Z

11

Radiological Habits Survey: Dungeness, 2005  

E-Print Network [OSTI]

exposure 39 4.9 Water based activities 42 5. TERRESTRIAL RADIATION PATHWAYS 44 5.1 Terrestrial survey area.1 Direct radiation survey area 50 6.2 Residential activities 51 6.3 Leisure activities 51 6.4 Commercial 12 2. THE SURVEY 14 2.1 Site activity 14 2.2 Survey objectives 15 2.3 Survey areas 16 2.4 Conduct

12

Radiological Scoping Survey of the Scotia Depot, Scotia, NY  

SciTech Connect (OSTI)

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.

Bailey, E. N.

2008-02-25T23:59:59.000Z

13

Autonomous mobile robot for radiologic surveys  

DOE Patents [OSTI]

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.

Dudar, Aed M. (Augusta, GA); Wagner, David G. (Augusta, GA); Teese, Gregory D. (Aiken, SC)

1994-01-01T23:59:59.000Z

14

Autonomous mobile robot for radiologic surveys  

DOE Patents [OSTI]

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.

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

1994-06-28T23:59:59.000Z

15

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)

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.

P.C. Weaver

2008-08-19T23:59:59.000Z

16

Radiological Habits Survey: Chapelcross Liquid Effluent Pipeline, 2002  

E-Print Network [OSTI]

Radiological Habits Survey: Chapelcross Liquid Effluent Pipeline, 2002 Science commissioned Pipeline, 2002 The Centre for Environment, Fisheries and Aquaculture Science Lowestoft Laboratory Pakefield OF SURVEY 5 2.1 Pipeline description 5 2.2 Occupancy 6 2.3 Gamma dose rate measurements 7 3 SURVEY FINDINGS

17

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

SciTech Connect (OSTI)

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.

Harpeneau, Evan M. [Oak Ridge Institute for Science and Education, Oak Ridge, TN (United States). Independent Environmental Assessment and Verification Program

2011-06-24T23:59:59.000Z

18

Radiological survey results at Beverly Harbor, Beverly, Massachusetts (VB025)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at Beverly Harbor, Beverly, Massachusetts. The survey was performed in may 1991. The purpose of the survey was to determine if uranium from work performed under government contract at the former Ventron facility had migrated off-site to the harbor and neighboring areas. The survey included a surface gamma scan and the collection of soil and biological samples for radionuclide analyses.

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

1992-08-01T23:59:59.000Z

19

Results of the independent verification survey at the Old Betatron Building, Granite City, Illinois  

SciTech Connect (OSTI)

A team from the Measurement Applications and Development Group, Oak Ridge National Laboratory (ORNL), conducted an independent verification of the radiological condition of the Old Betatron Building, Granite City, Illinois, at the request of the Department of Energy in June of 1993. The building is owned by the National Steel Corporation. The contamination present resulted from the handling of uranium slabs of metal during the time the betatron facility was used to x-ray the slabs for metallurgical defects. The designation survey did not characterize the entire floor space because of obstructing equipment and debris. Therefore, prior to remediation by Bechtel National, Incorporated (BNI), a thorough characterization of the floor was conducted, and the results were immediately conveyed to on-site staff of BNI. An independent verification assessment was also performed after the cleanup activities were performed under the direction of BNI. The process of characterization, remediation, and verification was accomplished within a five-day period. Based on results of the independent verification assessment, the Old Betatron Building was determined to meet the DOE radiological guidelines for unrestricted use.

Murray, M.E.; Brown, K.S.

1994-07-01T23:59:59.000Z

20

INDEPENDENT VERIFICATION REVIEW AND SURVEY of the Argonne National Laboratory Building 301 Footprint  

SciTech Connect (OSTI)

INDEPENDENT VERIFICATION REVIEW AND SURVEY of the Argonne National Laboratory Building 301 Footprint, Argonne Illinois 5061-SR-01-0

E.N. Bailey

2010-05-26T23:59:59.000Z

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Independent Verification Survey Report for the Long Island Solar Farm, Brookhaven National Laboratory, Upton, New York  

SciTech Connect (OSTI)

5119-SR-01-0 INDEPENDENT VERIFICATION SURVEY REPORT FOR THE LONG ISLAND SOLAR FARM, BROOKHAVEN NATIONAL LABORATORY

E.M. Harpenau

2010-11-15T23:59:59.000Z

22

Survey of Existing Tools for Formal Verification.  

SciTech Connect (OSTI)

Formal methods have come into wide use because of their effectiveness in verifying %22safety and security%22 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.

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

2014-12-01T23:59:59.000Z

23

An aerial radiological survey of the Nevada Test Site  

SciTech Connect (OSTI)

A team from the Remote Sensing Laboratory conducted an aerial radiological survey of the US Department of Energy's Nevada Test Site including three neighboring areas during August and September 1994. The survey team measured the terrestrial gamma radiation at the Nevada Test Site to determine the levels of natural and man-made radiation. This survey included the areas covered by previous surveys conducted from 1962 through 1993. The results of the aerial survey showed a terrestrial background exposure rate that varied from less than 6 microroentgens per hour (mR/h) to 50 mR/h plus a cosmic-ray contribution that varied from 4.5 mR/h at an elevation of 900 meters (3,000 feet) to 8.5 mR/h at 2,400 meters (8,000 feet). In addition to the principal gamma-emitting, naturally occurring isotopes (potassium-40, thallium-208, bismuth-214, and actinium-228), the man-made radioactive isotopes found in this survey were cobalt-60, cesium-137, europium-152, protactinium-234m an indicator of depleted uranium, and americium-241, which are due to human actions in the survey area. Individual, site-wide plots of gross terrestrial exposure rate, man-made exposure rate, and americium-241 activity (approximating the distribution of all transuranic material) are presented. In addition, expanded plots of individual areas exhibiting these man-made contaminations are given. A comparison is made between the data from this survey and previous aerial radiological surveys of the Nevada Test Site. Some previous ground-based measurements are discussed and related to the aerial data. In regions away from man-made activity, the exposure rates inferred from the gamma-ray measurements collected during this survey agreed very well with the exposure rates inferred from previous aerial surveys.

Hendricks, T J; Riedhauser, S R

1999-12-01T23:59:59.000Z

24

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

SciTech Connect (OSTI)

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.

P.C. Weaver

2008-06-12T23:59:59.000Z

25

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)

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.

Weaver, Phyllis C.

2012-08-29T23:59:59.000Z

26

Radiological survey results at 4400 Piehl Road, Ottawa Lake, Michigan  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 4400 Piehl Road in Ottawa Lake, Michigan. The survey was performed in September, 1992. The purpose of the survey was to determine if materials containing uranium from work performed under government contract at the former Baker Brothers facility in Toledo, Ohio had been transported off-site to this neighboring area. The radiological survey included surface gamma scans indoors and outdoors, alpha and beta scans inside the house and attached garage, beta-gamma scans of the hard surfaces outside, and the collection of soil, water, and dust samples for radionuclide analyses. Results of the survey demonstrated that the majority of the measurements on the property were within DOE guidelines. However, the presence of isolated spots of uranium contamination were found in two areas where materials were allegedly transported to the property from the former Baker Brothers site. Uranium uptake by persons on the property by ingestion is fairly unlikely, but inhalation is a possibility. Based on these findings, it is recommended that the residential property at 4400 Piehl Road in Ottawa Lake, Michigan be considered for inclusion under FUSRAP.

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

1993-04-01T23:59:59.000Z

27

Radiological survey of the Shpack Landfill, Norton, Massachusetts  

SciTech Connect (OSTI)

The results of a radiological survey of the Shpack Landfill, Norton, Massachusetts, are given in this report. The survey was conducted over approximately eight acres which had received radioactive wastes from 1946 to 1965. The survey included measurement of the following: external gamma radiation at the surface and at 1 m (3 ft) above the surface throughout the site; beta-gamma exposure rates at 1 cm (0.4 in.) from the surface throughout the site; concentrations of /sup 226/Ra, /sup 238/U, and /sup 235/U in surface and subsurface soil on the site; and concentrations of /sup 226/Ra, /sup 238/U, /sup 235/U, /sup 230/Th, and /sup 210/Pb in groundwater on the site and in surface water on and near the site. Results indicate that the radioactive contamination is confined to the site and to the swamp immediately adjacent to the site.

Cottrell, W.D.; Haywood, F.F.; Witt, D.A.; Myrick, T.E.; Goldsmith, W.A.; Shinpaugh, W.H.; Loy, E.T.

1981-12-01T23:59:59.000Z

28

Northern Marshall Islands radiological survey: sampling and analysis summary  

SciTech Connect (OSTI)

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.

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

1981-07-23T23:59:59.000Z

29

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

SciTech Connect (OSTI)

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

W.C. Adams

2010-05-24T23:59:59.000Z

30

REVISED INDEPENDENT VERIFICATION SURVEY OF A AND B RADIOACTIVE WASTE TRANSFER LINES TRENCH BROOKHAVEN NATIONAL LABORATORY  

SciTech Connect (OSTI)

REVISED INDEPENDENT VERIFICATION SURVEY OF THE A AND B RADIOACTIVE WASTE TRANSFER LINES TRENCH, BROOKHAVEN NATIONAL LABORATORY 5062-SR-01-1

P.C. Weaver

2010-02-10T23:59:59.000Z

31

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

SciTech Connect (OSTI)

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

W.C. Adams

2010-07-21T23:59:59.000Z

32

The Northern Marshall Islands radiological survey: Data and dose assessments  

SciTech Connect (OSTI)

Fallout from atmospheric nuclear tests, especially from those conducted at the Pacific Proving Grounds between 1946 and 1958, contaminated areas of the Northern Marshall Islands. A radiological survey at some Northern Marshall Islands was conducted from September through November 1978 to evaluate the extent of residual radioactive contamination. The atolls included in the Northern Marshall Islands Radiological Survey (NMIRS) were Likiep, Ailuk, Utirik, Wotho, Ujelang, Taka, Rongelap, Rongerik, Bikar, Ailinginae, and Mejit and Jemo Islands. The original test sites, Bikini and Enewetak Atolls, were also visited on the survey. An aerial survey was conducted to determine the external gamma exposure rate. Terrestrial (soil, food crops, animals, and native vegetation), cistern and well water samples, and marine (sediment, seawater, fish and clams) samples were collected to evaluate radionuclide concentrations in the atoll environment. Samples were processed and analyzed for {sup 137}Cs, {sup 90}Sr, {sup 239+240}Pu and {sup 241}Am. The dose from the ingestion pathway was calculated using the radionuclide concentration data and a diet model for local food, marine, and water consumption. The ingestion pathway contributes 70% to 90% of the estimated dose. Approximately 95% of the dose is from {sup 137}Cs accounts for about 10% to 30% of the dose. {sup 239+240}Pu and {sup 241}Am are the major contributors to dose via the inhalation pathway; however, inhalation accounts for only about 1% of the total estimated dose, based on surface soil levels and resuspension studies. All doses are computed for concentrations decay corrected to 1996. The maximum annual effective dose from manmade radionuclides at these atolls ranges from .02 mSv y{sup -1}. The background dose in the Marshall Islands is estimated to be 2.4 mSv y{sup -1} to 4.5 mSv y{sup -1}. The 50-y integral dose ranges from 0.5 to 65 mSv. 35 refs., 2 figs., 9 tabs.

Robison, W.L.; Noshkin, V.E.; Conrado, C.L. [Lawrence Livermore National Lab., CA (United States)] [and others

1997-07-01T23:59:59.000Z

33

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

SciTech Connect (OSTI)

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).

M.A. Buchholz

2009-04-29T23:59:59.000Z

34

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

SciTech Connect (OSTI)

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.

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

1994-01-01T23:59:59.000Z

35

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

SciTech Connect (OSTI)

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.

Not Available

1984-08-01T23:59:59.000Z

36

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

SciTech Connect (OSTI)

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

W.C. Adams

2007-03-13T23:59:59.000Z

37

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

SciTech Connect (OSTI)

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.

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

1995-07-01T23:59:59.000Z

38

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

SciTech Connect (OSTI)

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).

King, David A.

2012-08-16T23:59:59.000Z

39

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

SciTech Connect (OSTI)

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

P.C. Weaver

2010-12-15T23:59:59.000Z

40

INFRARED PROPERTIES OF RADIO-SELECTED SUBMILLIMETER GALAXIES IN THE SPITZER FIRST LOOK SURVEY VERIFICATION FIELD  

E-Print Network [OSTI]

INFRARED PROPERTIES OF RADIO-SELECTED SUBMILLIMETER GALAXIES IN THE SPITZER FIRST LOOK SURVEY and infrared observations of 28 radio-selected galaxies in the Spitzer First Look Survey verification field counterparts at 24 m. The data show a wide range of infrared colors (S70 m=S24 m

Frayer, David

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Letter Report - Verification Survey of Final Grids at the David Witherspoon, Inc. 1630 Site Knoxville, Tennessee  

SciTech Connect (OSTI)

Conduct verification surveys of grids at the DWI 1630 Site in Knoxville, Tennessee. The independent verification team (IVT) from ORISE, conducted verification activities in whole and partial grids, as completed by BJC. ORISE site activities included gamma surface scans and soil sampling within 33 grids; G11 through G14; H11 through H15; X14, X15, X19, and X21; J13 through J15 and J17 through J21; K7 through K9 and K13 through K15; L13 through L15; and M14 through M16

P.C. Weaver

2009-02-17T23:59:59.000Z

42

Radiological survey results at 12 Cliff Street, Beverly, Massachusetts (VB010)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 12 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.

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

1992-08-01T23:59:59.000Z

43

Radiological survey results at 20 Cliff Street, Beverly, Massachusetts (VB013)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 20 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.

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

1992-08-01T23:59:59.000Z

44

Radiological survey results at 6 Cliff Street, Beverly, Massachusetts (VB008)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak ridge National Laboratory conducted a radiological survey at 6 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.

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

1992-08-01T23:59:59.000Z

45

Radiological survey results at 5 Porter Street, Beverly, Massachusetts (VB019)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 5 Porter Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium 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 Site Remedial Action Program guidelines.

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

1992-07-01T23:59:59.000Z

46

Radiological survey results at 19 Wellman Street, Beverly, Massachusetts (VB024)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 19 Wellman Street, Beverly, Massachusetts. The survey was performed in May 1991. The Purpose of the survey was to determine if uranium work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan, a beta-gamma scan of paved areas, 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 Site Action Program guidelines.

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

1992-07-01T23:59:59.000Z

47

Radiological survey results at 2 Porter Street, Beverly, Massachusetts (VB005)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 2 Porter 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 fore 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.

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

1992-08-01T23:59:59.000Z

48

Radiological survey results at 8 Cliff Street, Beverly, Massachusetts (VB009)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 8 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.

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

1992-08-01T23:59:59.000Z

49

Radiological survey results at 5 Cliff Street, Beverly, Massachusetts (VB018)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 5 Cliff Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium 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.

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

1992-08-01T23:59:59.000Z

50

Radiological survey results at 2 Cliff Street, Beverly, Massachusetts (VB007)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 2 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.

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

1992-08-01T23:59:59.000Z

51

Radiological survey results at 18 Cliff Street, Beverly, Massachusetts (VB012)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 18 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 mannerly Utilized Sites Remedial Action Program guidelines.

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

1992-08-01T23:59:59.000Z

52

Radiological survey results at 9 Porter Street, Beverly, Massachusetts (VB020)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 9 Porter Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium 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.

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

1992-07-01T23:59:59.000Z

53

Radiological survey results at 15 Cliff Street, Beverly, Massachusetts (VB014)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 15 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.

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

1992-08-01T23:59:59.000Z

54

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

SciTech Connect (OSTI)

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.

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

1992-08-01T23:59:59.000Z

55

Radiological survey results at Porter Street City Park, Beverly, Massachusetts (VB026)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the Porter Street City Park, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium 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

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

1992-08-01T23:59:59.000Z

56

Radiological survey results at 9 and 11 Congress Street, Beverly, Massachusetts (VB002)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 9 and 11 Congress Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium 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, a beta-gamma scan of paved areas, and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionucldie concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines.

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

1992-05-01T23:59:59.000Z

57

Radiological survey results at 13 Congress Street, Beverly, Massachusetts (VB003)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 13 Congress Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium 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, a beta-gamma scan of paved areas, 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.

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

1992-07-01T23:59:59.000Z

58

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

SciTech Connect (OSTI)

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.

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

1994-05-01T23:59:59.000Z

59

Verification Survey of Rooms 113, 114, and 208 of the Inhalation Toxicology Laboratory, Lovelace Respiratory Research Institute, Albuquerque, NM  

SciTech Connect (OSTI)

The objectives of the verification survey were to confirm that accessible surfaces of the three laboratories meet the DOE’s established criteria for residual contamination. Drain pipes and ductwork were not included within the survey scope.

T.J. Vitkus

2008-06-25T23:59:59.000Z

60

Radiological survey results at 15 Congress Street, Beverly, Massachusetts (VB004)  

SciTech Connect (OSTI)

At the request of the US Department of energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 15 Congress Street, Beverly, Massachusetts. The survey was to determine if uranium 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, a beta-gamma scan of paved areas, 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.

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

1992-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

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

SciTech Connect (OSTI)

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.

T.J. Vitkus

2008-04-07T23:59:59.000Z

62

Radiological Habits Survey, HM Naval Base Clyde, Faslane 2000  

E-Print Network [OSTI]

Environment Report RL 7/02 #12;2 SUMMARY 4 1. BACKGROUND 5 1.1 Regulation of radioactive waste discharges 5 1/y). Table 13. Adult consumption rates of potatoes from the survey area (kg/y). Table 14. Adult consumption

63

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

SciTech Connect (OSTI)

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.

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

2000-09-01T23:59:59.000Z

64

Radiological survey results at 30 Cliff Street, Beverly, Massachusetts (VB022)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 30 Cliff Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium 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, a beta-gamma scan of paved areas, 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. The radionuclide distributions were not significantly different from typical background levels in the Beverly, Massachusetts, area.

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

1992-07-01T23:59:59.000Z

65

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

SciTech Connect (OSTI)

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.

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

1997-08-01T23:59:59.000Z

66

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

SciTech Connect (OSTI)

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.

M.G. JADICK

2010-05-26T23:59:59.000Z

67

Characterization Investigation Study: Volume 3, Radiological survey of surface soils  

SciTech Connect (OSTI)

The Feed Materials Production Center was constructed to produce high purity uranium metal for use at various Department of Energy facilities. The waste products from these operations include general uncontaminated scrap and refuse, contaminated and uncontaminated metal scrap, waste oils, low-level radioactive waste, co-contaminated wastes, mixed waste, toxic waste, sludges from water treatment, and fly ash from the steam plant. This material is estimated to total more than 350,000 cubic meters. Other wastes stored in this area include laboratory chemicals and other combustible materials in the burn pit; fine waste stream sediments in the clear well; fly ash and waste oils in the two fly ash areas; lime-alum sludges and boiler plant blowdown in the lime sludge ponds; and nonradioactive sanitary waste, construction rubble, and asbestos in the sanitary landfill. A systematic survey of the surface soils throughout the Waste Storage Area, associated on-site drainages, and the fly ash piles was conducted using a Field Instrument for Detecting Low-Energy Radiation (FIDLER). Uranium is the most prevalent radioactive element in surface soil; U-238 is the principal radionuclide, ranging from 2.2 to 1790 pCi/g in the general Waste Storage Area. The maximum values for the next highest activity concentrations in the same area were 972 pCi/g for Th-230 and 298 pCi/g for U-234. Elevated activity concentrations of Th-230 were found along the K-65 slurry line, the maximum at 3010 pCi/g. U-238 had the highest value of 761 pCi/g in the drainage just south of pit no. 5. The upper fly ash area had the highest radionuclide activity concentrations in the surface soils with the maximum values for U-238 at 8600 pCi/g, U-235 at 2190 pCi/g, U-234 at 11,400 pCi/g, Tc-99 at 594 pCi/g, Ra-226 at 279 pCi/g, and Th-230 at 164 pCi/g.

Solow, A.J.; Phoenix, D.R.

1987-12-01T23:59:59.000Z

68

Interim Letter Report - Verification Survey of Partial Grids H19, J21, J22, X20, and X21 at the David Witherspoon, Inc. 1630 Site, Knoxville Tennessee  

SciTech Connect (OSTI)

Conduct verification surveys of available grids at the David Witherspoon Incorporated 1630 Site (DWI 1630) in Knoxville, Tennessee. The IVT conducted verification activities of partial grids H19, J21, J22, X20, and X21.

P.C. Weaver

2008-03-19T23:59:59.000Z

69

Radiological characterization survey results for Gaskill Hall, Miami University, Oxford, Ohio (OXO015)  

SciTech Connect (OSTI)

Between October 1952 and February 1957, National Lead of Ohio (NLO), a primary contractor for the Atomic Energy Commission (AEC), subcontracted certain uranium machining operations to Alba Craft Laboratory, Incorporated, located at 10-14 West Rose Avenue, Oxford, Ohio. In 1992, personnel from Oak Ridge National Laboratory (ORNL) confirmed the presence of residual radioactive materials from the AEC-related operations in and around the facility in amounts exceeding the applicable Department of Energy (DOE) guidelines. Although the amount of uranium found on the property posed little health hazard if left undisturbed, the levels were sufficient to require remediation to bring radiological conditions into compliance with current guidelines, thus ensuring that the public and the environment are protected. Because it was suspected that uranium may have been used in the past in the immediate vicinity of Alba Craft in a Miami University building a team from ORNL, performed a radiological characterization survey of that structure in January 1994. The survey was conducted at the request of DOE as a precautionary measure to ensure that no radioactive residuals were present at levels exceeding guidelines. The survey included the determination of directly measured radiation levels and the collection of smear samples to detect possible removable alpha and beta-gamma activity levels, and comparison of these data to the guidelines. Results of the survey showed that all measurements were below the applicable guideline limits set by DOE.

Kleinhans, K.R.; Murray, M.E.; Carrier, R.F.

1996-04-01T23:59:59.000Z

70

VERIFICATION SURVEY OF PHASE I REMEDIAL ACTIONS ALBANY RESEARCH CENTER  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledoSampling at the GrandSr:s I ]Unied States-SURVEY

71

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

SciTech Connect (OSTI)

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.

P.C. Weaver

2008-10-17T23:59:59.000Z

72

Anesthesia Practice and Clinical Trends in Interventional Radiology: A European Survey  

SciTech Connect (OSTI)

Purpose: To determine current European practice in interventional radiology regarding nursing care, anesthesia, and clinical care trends.Methods: A survey was sent to 977 European interventional radiologists to assess the use of sedoanalgesia, nursing care, monitoring equipment, pre- and postprocedural care, and clinical trends in interventional radiology. Patterns of sedoanalgesia were recorded for both vascular and visceral interventional procedures. Responders rated their preferred level of sedoanalgesia for each procedure as follows: (a) awake/alert, (b) drowsy/arousable, (c) asleep/arousable, (d) deep sedation, and (e) general anesthesia. Sedoanalgesic drugs and patient care trends were also recorded. A comparison was performed with data derived from a similar survey of interventional practice in the United States.Results: Two hundred and forty-three of 977 radiologists responded (25%). The total number of procedures analyzed was 210,194. The majority (56%) of diagnostic and therapeutic vascular procedures were performed at the awake/alert level of sedation, 32% were performed at the drowsy/arousable level, and 12% at deeper levels of sedation. The majority of visceral interventional procedures were performed at the drowsy/arousable level of sedation (41%), 29% were performed at deeper levels of sedation, and 30% at the awake/alert level. In general, more sedoanalgesia is used in the United States. Eighty-three percent of respondents reported the use of a full-time radiology nurse, 67% used routine blood pressure/pulse oximetry monitoring, and 46% reported the presence of a dedicated recovery area. Forty-nine percent reported daily patient rounds, 30% had inpatient hospital beds, and 51% had day case beds.Conclusion: This survey shows clear differences in the use of sedation for vascular and visceral interventional procedures. Many, often complex, procedures are performed at the awake/alert level of sedation in Europe, whereas deeper levels of sedation are used in the United States. Trends toward making interventional radiology a clinical specialty are evident, with 51% of respondents having day case beds, and 30% having inpatient beds.

Haslam, Philip J.; Yap, Bernard [Department of Radiology, Beaumont Hospital and Royal College of Surgeons in Ireland Medical School, Dublin 9 (Ireland); Mueller, Peter R. [Department of Radiology, WHT220, Massachusetts General Hospital, Harvard Medical School, 32 Fruit Street, Boston, MA 02114 (United States); Lee, Michael J. [Department of Radiology, Beaumont Hospital and Royal College of Surgeons in Ireland Medical School, Dublin 9 (Ireland)

2000-07-15T23:59:59.000Z

73

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

SciTech Connect (OSTI)

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.

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

1993-06-01T23:59:59.000Z

74

Results of the radiological survey at the Town of Tonawanda Landfill, Tonawanda, New York (TNY001)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the Town of Tonawanda Landfill, Tonawanda, New York. The survey was performed in September 1991. 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 deposited in the landfill. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey suggest that material originating at the Linde plant may have been deposited in the landfill. Soil samples S54 and B12 contained technologically enhanced levels of [sup 238]U not unlike the product formerly produced by the Linde plant. In contrast, samples B4A, B5A and B7B, containing elevated concentrations of [sup 226]Ra and [sup 230]Th with much lower concentrations of [sup 238]U, were similar to the residue or byproduct of the refinery operation conducted at the Linde plant. In 24 instances, soil samples from the Town of Tonawanda Landfill exceeded DOE guideline values for [sup 238]U, [sup 226]Ra, and/or [sup 230]Th in surface or subsurface soil. Nine of these samples contained radionuclide concentrations more than 30 times the guideline value.

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

1992-10-01T23:59:59.000Z

75

Results of the radiological survey at the Town of Tonawanda Landfill, Tonawanda, New York (TNY001)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the Town of Tonawanda Landfill, Tonawanda, New York. The survey was performed in September 1991. 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 deposited in the landfill. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey suggest that material originating at the Linde plant may have been deposited in the landfill. Soil samples S54 and B12 contained technologically enhanced levels of {sup 238}U not unlike the product formerly produced by the Linde plant. In contrast, samples B4A, B5A and B7B, containing elevated concentrations of {sup 226}Ra and {sup 230}Th with much lower concentrations of {sup 238}U, were similar to the residue or byproduct of the refinery operation conducted at the Linde plant. In 24 instances, soil samples from the Town of Tonawanda Landfill exceeded DOE guideline values for {sup 238}U, {sup 226}Ra, and/or {sup 230}Th in surface or subsurface soil. Nine of these samples contained radionuclide concentrations more than 30 times the guideline value.

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

1992-10-01T23:59:59.000Z

76

Preliminary results of the radiological survey at the former Dow Chemical Company site, Madison, Illinois  

SciTech Connect (OSTI)

During the late 1950s and early 1960s, the former Dow Chemical Company plant, now owned and operated by Spectrulite Consortium Inc., supplied materials and provided services for the Atomic Energy Commission (AEC) under purchase orders issued by the Mallinckrodt Chemical Company, a primary AEC contractor. Information indicates that research and development work involving gamma-phase extrusion of uranium metal was conducted at the Dow Chemical plant. Because documentation establishing the current radiological condition of the property was 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 indoor gamma exposure rates; collection and radionuclide analysis of dust and debris samples; and measurements to determine alpha and beta-gamma surface contamination. The results of the survey demonstrate that Building 6, the area uranium extrusion and rod-straightening work occurred, is generally free of radioactive residuals originating from former DOE-sponsored activities. However, {sup 238}U- and {sup 232}Th-contaminated dust was found on overhead beams at the south end of Building 6. These findings suggest that past DOE-supported operations were responsible for uranium-contaminated beam dust in excess of guidelines in Building 6. However, the contamination is localized and limited in extent, rendering it highly unlikely that under present use an individual working in or frequenting these remote areas would receive a significant radiation exposure. We recommend that additional scoping survey measurements and sampling be performed to further define the extent of indoor uranium contamination southward to include Building 4 and northward throughout Building 6. 5 refs., 11 figs., 4 tabs.

Cottrell, W.D.; Williams, J.K.

1990-12-01T23:59:59.000Z

77

Background Radiation Survey of the Radiological/Nuclear Countermeasures Test and Evaluation Center  

SciTech Connect (OSTI)

In preparation for operations at the Radiological/Nuclear Countermeasures Test and Evaluation Complex (Rad/NucCTEC), the Department of Homeland Security Domestic Nuclear Detection Office (DHS/DNDO) requested that personnel from the Remote Sensing Laboratory (RSL) conduct a survey of the present radiological conditions at the facility. The measurements consist of the exposure rate from a high-pressure ion chamber (HPIC), high-resolution spectra from a high-purity germanium (HPGe) system in an in situ configuration, and low-resolution spectra from a sodium iodide (NaI) detector in a radiation detection backpack. Measurements with these systems were collected at discrete locations within the facility. Measurements were also collected by carrying the VECTOR backpack throughout the complex to generate a map of the entire area. The area was also to be surveyed with the Kiwi (an array of eight-2-inch x 4-inch x 16-inch NaI detectors) from the Aerial Measuring Systems; however, conflicts with test preparation activities at the site prevented this from being accomplished.

Colin Okada

2010-09-16T23:59:59.000Z

78

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

SciTech Connect (OSTI)

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.

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

1992-10-01T23:59:59.000Z

79

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

SciTech Connect (OSTI)

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.

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

1993-06-01T23:59:59.000Z

80

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

SciTech Connect (OSTI)

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.

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

1992-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

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

SciTech Connect (OSTI)

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.

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

1992-10-01T23:59:59.000Z

82

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

SciTech Connect (OSTI)

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.

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

1992-10-01T23:59:59.000Z

83

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

SciTech Connect (OSTI)

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.

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

1992-10-01T23:59:59.000Z

84

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

SciTech Connect (OSTI)

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.

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

1992-10-01T23:59:59.000Z

85

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

SciTech Connect (OSTI)

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.

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

1992-10-01T23:59:59.000Z

86

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

SciTech Connect (OSTI)

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.

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

1992-10-01T23:59:59.000Z

87

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

SciTech Connect (OSTI)

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.

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

1997-09-01T23:59:59.000Z

88

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

SciTech Connect (OSTI)

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.

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

1997-09-01T23:59:59.000Z

89

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

SciTech Connect (OSTI)

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.

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

1997-09-01T23:59:59.000Z

90

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

SciTech Connect (OSTI)

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.

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

1997-09-01T23:59:59.000Z

91

An aerial radiological survey of the Salmon Site and surrounding area, Lamar County, Mississippi  

SciTech Connect (OSTI)

An aerial radiological survey was conducted over the former Atomic Energy Commission Test Site at the Salmon Site and surrounding area between April 20 and May 1, 1992. The Salmon Site is located in Lamar County, Mississippi, approximately 20 miles southwest of Hattiesburg, Mississippi. The purpose of the survey was to measure and document the gamma-ray environment of the Salmon Site and adjacent lands. A contour map showing gamma radiation exposure rates at 1 meter above ground level was constructed from the aerial data and overlaid on a rectified aerial photograph of the area. The exposure rates within the area are between 5 and 8 {mu}R/h. The reported exposure rates include a cosmic-ray contribution estimated to be 3.7 {mu}R/h. Radionuclide assays of soil samples and in situ measurements, taken with a pressurized ion chamber and a high-purity germanium detector, were obtained at 4 locations within the survey boundaries. These measurements were taken in support of and are in agreement with the aerial data.

Kernan, W.J.

1994-05-01T23:59:59.000Z

92

An aerial radiological survey of Pocatello and Soda Springs, Idaho and surrounding area, June--July 1986  

SciTech Connect (OSTI)

Three aerial radiological surveys were conducted during the period 16 June through 15 July 1986 over the towns of Pocatello, Soda Springs, and Fort Hall, Idaho and the surrounding areas. The surveys were performed for the United States Environmental Protection Agency (EPA) by the United States Department of Energy's (DOE) Remote Sensing Laboratory (RSL), utilizing the Aerial Measuring System (AMS). This work was completed in cooperation with a study by the EPA to conduct a dose assessment of human radiation exposure for industrial sources in Pocatello and Soda Springs, Idaho. The aerial surveys were performed to document the natural terrestrial radiological environment of the three localities and to map the spatial extent and degree of contamination due to phosphate milling operations. The results of these surveys will be used for planning ground-based measurements in addition to being incorporated into the dose assessment document. 4 refs., 14 figs., 6 tabs.

Berry, H.A.

1987-02-01T23:59:59.000Z

93

Radiological survey of the inactive uranium-mill tailings at Gunnison, Colorado  

SciTech Connect (OSTI)

The findings of a radiological survey of the inactive uranium-mill site at Gunnison, Colorado, conducted in May 1976, are presented. Results of surface soil sample analyses and direct gamma radiation measurements indicate limited spread of tailings off the site. The only significant above background measurements off the site were obtained in an area previously covered by the tailings pile. There was little evidence of contamination of the surface or of unconfined groundwater in the vicinity of the tailings pile; however, the hydrologic conditions at the site indicate a potential for such contamination. The concentration of /sup 226/Ra in all water samples except one from the tailings pile was well below the concentration guide for drinking water. The subsurface distribution of /sup 226/Ra in 14 bore holes located on and around the tailings pile was calculated from gamma ray monitoring data obtained jointly with Ford, Bacon and Davis Utah Inc.

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

1980-03-01T23:59:59.000Z

94

Radiological survey of the inactive uranium-mill tailings at Falls City, Texas  

SciTech Connect (OSTI)

Results of a radiological survey conducted at the Falls City, Texas, site in July 1976 are presented. There are seven partial to fully stabilized tailings piles, and an overburden pile from an open-pit mine. Above ground gamma-ray exposure rate measurements show moderate levels of contamination throughout the area with a maximum exposure rate of 500 ..mu..R/hr above tailings pile 2. The average exposure rate over the different areas varied from 14 ..mu..R/hr over the southwest end of tailings pile 7 to 207 ..mu..R/hr over the northeast end of the same pile. Analyses of surface soil and dry-wash sediment samples, as well as calculations of subsurface /sup 226/Ra distribution, serve to define the spread of tailings around the area. Water erosion of the tailings is evident, but, because of abundant growth of vegetation on the tailings piles, wind erosion probably is not a major problem.

Haywood, F.F.; Christian, D.J.; Loy, E.T.; Lorenzo, D.; Ellis, B.S.

1980-10-01T23:59:59.000Z

95

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

SciTech Connect (OSTI)

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.

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

1980-03-01T23:59:59.000Z

96

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

SciTech Connect (OSTI)

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.

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

1980-06-01T23:59:59.000Z

97

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

SciTech Connect (OSTI)

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.

Weaver, Phyllis C.

2012-05-08T23:59:59.000Z

98

Radiological survey results for the Peek Street site properties, Schenectady, New York  

SciTech Connect (OSTI)

The Peek Street Industrial Facility, located at 425 Peek Street, Schenectady, New York, was operated by the General Electric Company for the Atomic Energy Commission (AEC) between 1947 and 1955. A variety of operations using radioactive materials were conducted at the site, but the main activities were to design an intermediate breeder reactor and to develop a chemical process for the recovery of uranium and plutonium from spent reactor fuel. Nonradioactive beryllium metal was machined on the site for breeder reactor application. The 4.5-acre site was decommissioned and released in October 1955. A radiological survey was conducted by Oak Ridge National Laboratory in November 1989. The survey included scan and grid point measurements of direct radiation levels outdoors on the five properties and inside the factory building, and radionuclide analysis of samples collected from each property. Radionuclide concentrations were determined in outdoor surface and subsurface soil samples from each property and in dust, debris, and structural materials from inside the factory building. Auger holes were logged to assess location and extent of possible subsurface residual soil radioactivity. Radionuclide concentrations were deter-mined in both indoor and outdoor water samples and in selected samples of vegetation. The presence of fixed and transferable surface residual radioactivity was investigated inside the factory building and on discarded materials outdoors on the property. High-volume air samples as well as additional selected indoor and outdoor soil samples were analyzed to determine levels of elemental beryllium.

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

1992-08-01T23:59:59.000Z

99

Confirmatory radiological survey of the Grand Junction Projects Office Remedial Action Project exterior portions, 1989-1995  

SciTech Connect (OSTI)

The purpose of this independent assessment was to provide the U.S. Department of Energy (DOE) with an independent verification (IV) that the soil at the Grand Junction Projects Office (GJPO) complies with applicable DOE guidelines. Oak Ridge National Laboratory/ Environmental Technology Section (ORNL/ETS) which is also located at the GJPO, was assigned by DOE as the Independent Verification Contractor (IVC). The assessment included reviews of the decontamination and decommissioning plan, annual environmental monitoring reports, data in the pre- and post-remedial action reports, reassessment reports and IV surveys. Procedures and field methods used during the remediation were reviewed, commented on, and amended as needed. The IV surveys included beta-gamma and gamma radiation scans, soil sampling and analyses. Based on the data presented in the post-remedial action report and the results of the IV surveys, the remediation of the outdoor portions of the GJPO has achieved the objectives. Residual deposits of uranium contamination may exist under asphalt because the original characterization was not designed to identify uranium and subsequent investigations were limited. The IVC recommends that this be addressed with the additional remediation. The IVC is working with the remedial action contractor (RAC) to assure that final documentation WM be sufficient for certification. The IVC will address additional remediation of buildings, associated utilities, and groundwater in separate reports. Therefore, this is considered a partial verification.

Forbes, G.H.; Egidi, P.V.

1997-04-01T23:59:59.000Z

100

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

SciTech Connect (OSTI)

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.

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

1992-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Radiological survey of the former Baker Brothers, Inc. site, 2551--2555 Harleau Place, Toledo, Ohio (BTO001)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted investigative radiological surveys at the REMS, Inc., and the Doug Beet Company, 2551-2555 Harleau Place, Toledo, Ohio (BTO001) in 1988. The purpose of the surveys was to determine whether the property was contaminated with radioactive residues, principally {sup 238}U, as a result of work contracted to the Manhattan Engineer District (MED). The survey included gamma scans; directly measured alpha, beta, and gamma radiation levels; transferable contamination levels; and soil, dust, debris, and air sampling for radionuclide analyses. The survey and sampling covered accessible portions of the exterior ground surface, roof, and interiors of buildings. Results of the surveys demonstrated four general areas having radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria for {sup 238}U outdoors and as surface contamination on shelves in one building.

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

1992-03-01T23:59:59.000Z

102

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

SciTech Connect (OSTI)

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.

Weaver, Phyllis C.

2012-07-24T23:59:59.000Z

103

The Northern Marshall Islands radiological survey: A quality control program for radiochemical and gamma spectroscopy analysis  

SciTech Connect (OSTI)

From 1979 to 1989, approximately 25,000 Post Northern Marshall Islands Radiological Survey (PNMIRS) samples were collected, and over 71,400 radiochemical and gamma spectroscopy analyses were performed to establish the concentration of {sup 90}Sr, {sup 137}Cs, {sup 241}Am, and plutonium isotopes in soil, vegetation, fish, and animals in the Northern Marshall Islands. While the Low Level Gamma Counting Facility (B379) in the Health and Ecological Assessment (HEA) division accounted for over 80% of all gamma spectroscopy analyses, approximately 4889 radiochemical and 5437 gamma spectroscopy analyses were performed on 4784 samples of soil, vegetation, terrestrial animal, and marine organisms by outside laboratories. Four laboratories were used by Lawrence Livermore National Laboratory (LLNL) to perform the radiochemical analyses: Thermo Analytical Norcal, Richmond, California (TMA); Nuclear Energy Services, North Carolina State University (NCSU); Laboratory of Radiation Ecology, University of Washington (LRE); and Health and Ecological Assessment (HEA) division, LLNL, Livermore, California. Additionally, LRE and NCSU were used to perform gamma spectroscopy analyses. The analytical precision and accuracy were monitored by including blind duplicates and natural matrix standards in each group of samples analyzed. On the basis of reported analytical values for duplicates and standards, 88% of the gamma and 87% of the radiochemical analyses in this survey were accepted. By laboratory, 93% of the radiochemical analyses by TMA; 88% of the gamma-ray spectrometry and 100% of the radiochemistry analyses by NCSU; 89% of the gamma spectroscopy and 87% of the radiochemistry analyses by LRE; and 90% of the radiochemistry analyses performed by HEA`s radiochemistry department were accepted.

Kehl, S.R.; Mount, M.E.; Robison, W.L.

1995-09-01T23:59:59.000Z

104

Results of the radiological survey at the Sacandaga site Glenville, New York  

SciTech Connect (OSTI)

The Sacandaga site, located on Sacandaga Road, Glenville, New York, was operated by the General Electric Company for the Atomic Energy Commission (AEC) between 1947 and 1951. Originally used for the study and development of radar during World War II, the facilities housed later operations involving physics studies and sodium technology development in support of breeder reactor design and other AEC programs. Though not in use since the original equipment was dismantled and removed in the early 1950s, portions of the 51-acre site are known to contain buried rubble from demolished structures used in former operations. At the request of the Office of Naval Reactors through the Office of Remedial Action and Waste Technology, a characterization of current radiological conditions over the site was performed between August and October 1989. The survey included the measurement of direct radiation levels (gamma, alpha, and beta-gamma) over all surfaces both inside and outside the building and tunnel, radionuclide analysis of systematic, biased, and auger hole soil samples, and analysis of sediments from underground structures. Gamma logging of auger holes was conducted and removable contamination levels inside the tunnel were determined. Samples of soil and structural materials from within and around an excavated concrete bunker were analyzed to determine concentrations of radionuclides and nonradioactive elemental beryllium.

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

1992-08-01T23:59:59.000Z

105

Aerial radiological and photographic survey of eleven atolls and two islands within the Northern Marshall Islands. Dates of surveys, July-November 1978  

SciTech Connect (OSTI)

An aerial radiological survey was conducted over eleven atolls and two islands within the northern Marshall Islands between September and November 1978. This survey was part of a comprehensive radiological survey, which included extensive terrestrial and marine sampling, to determine possible residual contamination which might remain as a result of the United States nuclear testing program conducted at Bikini Enewetak Atolls between 1946 and 1958. A similar survey was conducted at Enewetak Atoll in 1972. The present survey covered those atolls known to have received direct fallout from the Bravo event, conducted in March 1954 at Bikini Atoll. These included Bikini, Rongelap, Rongerik, Ailinginae, Bikar, Taka, and Utirik Atolls. In addition, several atolls and islands which might have been at the fringes of the Bravo fallout were also surveyed, including Likiep and Ailuk Atolls, Jemo and Mejit Islands, and Wotho Atoll. Ujelang Atoll, which lies approximately 200 km southwest of Enewetak, was also surveyed. Island-averaged terrestrial exposure rates in the range of 30 to 50 ..mu..R/h were observed over parts of Bikini Atoll, including Bikini Island, and over the northern part of Rongelap Atoll. Levels over southern Rongelap and over Rongerik Atoll ranged from 4 to 7 ..mu..R/h. Levels were somewhat lower at Ailinginae Atoll (approximately 2 ..mu..R/h) and at Utirik Atoll (approximately 0.7 ..mu..R/h). The variations observed were consistent with what might be expected from the fallout pattern of the Bravo event. Levels at Ailuk, Likiep, Wotho and Ujelang Atolls and at Mejit and Jemo Islands were consistent with /sup 137/Cs activity, due to worldwide fallout, observed within the United States and at other locations in the central Pacific. These four atolls and the two islands, therefore, do not appear to have recieved any significant direct contamination from the Bravo event or the other tests conducted at Bikini and Enewetak Atolls.

Not Available

1981-06-01T23:59:59.000Z

106

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)

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.

Fournier, Sean Donovan; Beall, Patrick S [Sandia National Laboratories, Livermore, CA; Miller, Mark L.

2014-08-01T23:59:59.000Z

107

Results of the radiological survey at the former Alba Craft Laboratory site properties, Oxford, Ohio (OXO001)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the former Alba Craft Laboratory Site Properties, Oxford, Ohio. The survey was performed in July and September of 1992. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, primarily [sup 238]U, from uranium machining operations conducted for National Lead of Ohio, a prime Atomic Energy Commission contractor. The survey included scan measurement of direct radiation levels inside and outside the former laboratory, outdoors on eight properties adjoining the former laboratory, and the city right-of-way adjacent to the surveyed properties. Radionuclide concentrations were determined in outdoor surface and subsurface soil samples taken from each property and the exterior of the laboratory. Fixed surface residual radioactivity was measured inside the laboratory and outside the building. Air samples were collected, direct exposure was measured, and samples were collected to measure transferable radioactivity inside the building. Results of the survey indicate areas where surface and soil contamination level s are above the DOE guidelines for uncontrolled areas.

Murray, M.E.; Brown, K.S.; Mathis, R.A.

1993-03-01T23:59:59.000Z

108

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

SciTech Connect (OSTI)

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.

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

1992-07-01T23:59:59.000Z

109

Uranium Mill Tailings Remedial Action Program. Partial radiological survey of Shiprock vicinity property SH13 Shiprock, New Mexico, November 1982  

SciTech Connect (OSTI)

As part of a detailed radiological assessment of the vicinity properties at Shiprock, a comprehensive survey of the vicinity property designated as SH13 was initiated on November 19, 1982. At that time, a single residential structure existed in the northwest corner of the property. The lands surrounding the structure were extensively cluttered with junk. The initial assessment activities were limited to measurements within the residential structure of the ambient external penetrating radiation level at a 1-meter height and analyses of indoor air samples for airborne radioactivity. The external penetrating radiation exposure rate (12.3 ..mu..R/h) was less than the 20 ..mu..R/h above background limit specified in the EPA Standard (40 CFR 192.12(b)(2)). As determined by the air samples, the short-term radon daughter concentration within the structure (0.36 mWL) did not exceed the 0.02 WL (or 20 mWL) limit for average annual concentration including background as specified in the EPA Standard. Further measurements required to completely determine the radiological status of this vicinity property, such as measurements of surface radiation both indoors and outdoors and collection and analyses of soil samples, were planned for the final phase of this assessment. However, that phase of the program was terminated before these measurements were accomplished. Thus, the extent of outdoor radiological contamination is presently unknown, and the evaluation of indoor contamination (if any) is incomplete.

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

1984-05-01T23:59:59.000Z

110

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

SciTech Connect (OSTI)

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.

Harpenau, Evan M.; Weaver, Phyllis C.

2012-06-06T23:59:59.000Z

111

Results of the radiological survey at the former Associate Aircraft Tool and Manufacturing Company site, Fairfield, Ohio (FOH001)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from oak Ridge National Laboratory conducted a radiological survey of the former Associate Aircraft Tool and Manufacturing Company facility, Fairfield, Ohio. The survey was performed in July and September 1992. The purpose of the survey was to determine if the facility had become contaminated with residuals containing radioactive materials during the work performed under government contract from February to September, 1956. The survey included gamma scanning over a circumscribed area around and outside of the building, and gamma scanning over most accessible indoor floor surfaces as well as the collection of soil and other samples for radionuclide analyses. Roof trusses were beta-gamma scanned in locations where floor contamination was found. Results of the survey demonstrated radionuclide concentrations in indoor and outdoor samples, and radiation measurements over floor and overhead 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 the areas that had been used in the early government work.

Murray, M.E.; Carrier, R.F.; Mathis, R.A.

1993-03-01T23:59:59.000Z

112

Independent Verification Final Summary Report for the David Witherspoon, Inc. 1630 Site Knoxville, Tennessee  

SciTech Connect (OSTI)

The primary objective of the independent verification was to determine if BJC performed the appropriate actions to meet the specified “hot spot” cleanup criteria of 500 picocuries per gram (pCi/g) uranium-238 (U-238) in surface soil. Specific tasks performed by the independent verification team (IVT) to satisfy this objective included: 1) performing radiological walkover surveys, and 2) collecting soil samples for independent analyses. The independent verification (IV) efforts were designed to evaluate radioactive contaminants (specifically U-238) in the exposed surfaces below one foot of the original site grade, given that the top one foot layer of soil on the site was removed in its entirety.

P.C. Weaver

2009-04-29T23:59:59.000Z

113

ORNL/TM-11118 RESULTS OF THE RADIOLOGICAL SURVEY AT METPATH INCORPORAT...  

Office of Legacy Management (LM)

R.D. Foley - Field Survey Supervisor Survey Team Members A. C. Butler J. H. Rice C. Johnson C. A: Muhr W. Winton Work performed as part of the MEASUREMENT APPLICATIONS AND...

114

Confirmatory radiological survey of the BORAX-V turbine building Idaho National Engineering Laboratory, Idaho Falls, Idaho  

SciTech Connect (OSTI)

An independent assessment of the remediation of the BORAX-V (Boiling Water Reactor Experiment) turbine building at the Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho, was accomplished by the Oak Ridge National Laboratory Pollutant Assessments Group (ORNL/PAG). The purpose of the assessment was to confirm the site`s compliance with applicable Department of Energy guidelines. The assessment included reviews of both the decontamination and decommissioning Plan and data provided from the pre- and post-remedial action surveys and an independent verification survey of the facility. The independent verification survey included determination of background exposure rates and soil concentrations, beta-gamma and gamma radiation scans, smears for detection of removable contamination, and direct measurements for alpha and beta-gamma radiation activity on the basement and mezzanine floors and the building`s interior and exterior walls. Soil samples were taken, and beta-gamma and gamma radiation exposure rates were measured on areas adjacent to the building. Results of measurements on building surfaces at this facility were within established contamination guidelines except for elevated beta-gamma radiation levels located on three isolated areas of the basement floor. Following remediation of these areas, ORNL/PAG reviewed the remedial action contractor`s report and agreed that remediation was effective in removing the source of the elevated direct radiation. Results of all independent soil analyses for {sup 60}Co were below the detection limit. The highest {sup 137}Cs analysis result was 4.6 pCi/g; this value is below the INEL site-specific guideline of 10 pCi/g.

Stevens, G.H.; Coleman, R.L.; Jensen, M.K.; Pierce, G.A. [Oak Ridge National Lab., TN (US); Egidi, P.V.; Mather, S.K. [Oak Ridge Inst. for Science and Education, Grand Junction, CO (United States)

1993-07-01T23:59:59.000Z

115

Uranium mill tailings remedial action program. Radiological survey of Shiprock vicinity property SH03, Shiprock, NM, July-November 1982  

SciTech Connect (OSTI)

A comprehensive survey of the vicinity property designated as SH03 was conducted on an intermittent basis from July 26 to November 11, 1982. At the time of the survey, three structures were located on the property - a residential trailer, the main structure, and an old gas pump housing. The lands surrounding the structures were either sparsely covered with arid vegetation or paved. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air, soil, and other material samples. No evidence of radioactive contamination was found inside the trailer. However, the results of the radiological assessment did indicate the occurrence of elevated levels of gamma, surface alpha, and radon daughter radioactivity within the main structure. The short-term radon daughter measurements exceeded the limit of 0.02 Working Level for average annual concentration including background. The assessment also indicated elevated levels of radioactivity in the outdoor environs, encompassing about 32,000 ft/sup 2/ of the grounds adjacent to and surrounding the main structure on the east, south, and west sides. The contamination appeared to be due to the presence of unprocessed uranium ore. Analysis of surface soil samples collected from the environs indicated radium concentrations in excess of the limit of 5 pCi/g above background specified in the EPA Standard. Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is not known. Since the surface soil contamination levels exceeded the limits specified in the EPA Standard, remedial action for this vicinity site should be considered.

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

1984-04-01T23:59:59.000Z

116

Uranium mill tailings remedial action program. Radiological survey of Shiprock vicinity property SH12, Shiprock, NM, October-November 1982  

SciTech Connect (OSTI)

A comprehensive survey of the vicinity property designated as SH12 was conducted on an intermittent basis from October 27 to November 22, 1982. At the time of the survey, several exhibition halls and concession stands; an auction yard; a race track and rodeo arena with associated stands, shutes, and corrals; and a hogan were located on the property. The surrounding environs were either sparsely covered with arid vegetation or covered with gravel. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air, soil, and other material samples. The radiological assessment indicated elevated levels of radioactivity within only one of the structures. Background levels of radioactivity were indicated within all other structures. The assessment indicated elevated levels of radioactivity at the rodeo arena and nearby shutes and corrals, encompassing about 49,000 ft/sup 2/ of land. Radiochemical analysis of the soil sample collected from this general area indicated 23 +- 2 pCi/g for radium, which is in excess of the limit of 5 pCi/g above background, averaged over the first 15 cm of soil below the surface. Elevated levels of radioactivity were also found at the southern end of the west parking lot, encompassing about 7500 ft/sup 2/ of land, and at several areas in the southern section of the property, encompassing about 160,000 ft/sup 2/ of land. Radiochemical analyses of two of the soil samples collected from the southern section indicated radium concentrations of 43 +- 5 and 42 +- 5 pCi/g of soil, in excess of the limit of 5 pCi/g above background as specified in the EPA Standard. Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is not known.

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

1984-04-01T23:59:59.000Z

117

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

SciTech Connect (OSTI)

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.

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

1997-09-01T23:59:59.000Z

118

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

SciTech Connect (OSTI)

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.

Semler, M.O.; Blanchard, R.L. (Environmental Protection Agency, Montgomery, AL (USA). Eastern Environmental Radiation Facility)

1989-06-01T23:59:59.000Z

119

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

SciTech Connect (OSTI)

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.

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

1987-05-01T23:59:59.000Z

120

An aerial radiological survey of the Waste Isolation Pilot Plant and surrounding area, Carlsbad, New Mexico: Date of survey, April 1988  

SciTech Connect (OSTI)

An aerial radiological survey was conducted during the period April 8 to April 19, 1988 over a 404-square-kilometer (156-square-mile) area covering the Waste Isolation Pilot Plant (WIPP) located near Carlsbad, New Mexico, the surrounding area. The survey was conducted at a nominal altitude of 91 meters (300 feet) with a line spacing of 152 meters (500 feet). A contour map of the terrestrial exposure rates plus the cosmic exposure rate extrapolated to 1 meter above ground level was prepared and overlaid on an aerial photograph of the area. The average terrestrial exposure rates ranged from approximately 6.0 to 9.0 microroentgens per hour ({mu}R/h). Two areas of increased exposure rate were evident. Both areas indicated higher than normal concentrations of naturally occurring radionuclides. A machine-aided search of the data for man-made sources of radiation indicated the presence of Cs-137 at the Gnome Site, which was expected from previous survey work done in the area. No other sources of man-made radiation were found.

Not Available

1989-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Results of the radiological survey at the New Betatron Building, Granite City Steel facility, Granite City, Illinois (GSG002)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the New Betatron Building, located in the South Plant facility of Granite City Steel Division, 1417 State Street, Granite City, Illinois. 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) from 1958 to 1966. The survey included a surface gamma scan of the ground surface outdoors near the building, the floor and walls in all accessible areas inside the building, and the roof; measurement of beta-gamma dose rates, alpha radiation levels, and removable alpha and beta-gamma activity levels at selected locations inside the building and on the roof; and radionuclide analysis of outdoor soil samples and indoor samples of shield-wall fill material land debris. Analysis of soil, shield-wall fill material, debris, and smear samples showed no residual {sup 238}U attributable to former AEC-supported operations at this site. None of the indoor or outdoor gamma exposure rate measurements were elevated above DOE guidelines. The slight elevations in gamma levels found outdoors and on the roof over the shield wall are typical of naturally occurring radioactive substances present in coal ash and cinders in the fill material surrounding the building and in concrete and cinders used in constuction of the shield wall. The slightly elevated gamma levels measured at soil sampling locations can be attributed to the presence of naturally occurring radionuclides. In all samples, {sup 226}Ra and {sup 238}U appeared to be in equilibrium, indicating that these radionuclides were of natural origin and not derived from former AEC activities at this site.

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

1992-01-01T23:59:59.000Z

122

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)

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.

none,

2013-10-10T23:59:59.000Z

123

Uranium Mill Tailings Remedial Action Program. Partial radiological survey of Shiprock vicinity property SH14 Shiprock, New Mexico, October-November 1982  

SciTech Connect (OSTI)

As part of a detailed radiological assessment of the vicinity properties at Shiprock, a comprehensive survey of the vicinity property designated as SH14 was initiated during October and November 1982. At the time of the survey, vicinity property SH14 consisted of about 20 acres of open lands to the northeast of, and directly across the San Juan River from, the upper tailings pile at Shiprock. The lands consisted of a sandy soil, sparsley covered with trees and other vegetation. The partial assessment activities included determination of surface radiation levels on about a 2-meter grid spacing through direct instrument surveys and analysis of a soil sample collected from the area. The partial radiological assessment indicated elevated levels of radioactivity at several general areas within the open lands. Radiochemical analyses of the soil sample collected from one of these areas indicated a radium concentration of 18 +- 2 pCi/g, which is in excess of the limit of 5 pCi/g above background, averaged over the first 15 cm of soil below the surface, as specified in the EPA Standard (40 CFR 192). Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is not known. Further measurements required to completely determine and accurately report the radiological status of this vicinity property, including additional direct instrument surveys, collection and analyses of soil samples, and the establishment of a 200-ft grid system, were planned for the final phase of this assessment. However, that phase of the program was cancelled before these measurements were accomplished. The total extent of the radiological contamination of vicinity property SH14 is presently unknown. Nonetheless, since the surface soil contamination levels exceeded the limits specified in the EPA Standard, remedial action for this vicinity site should be considered.

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

1984-06-01T23:59:59.000Z

124

Uranium mill tailings remedial action program. Radiological survey of Shiprock vicinity property SH01, Shiprock, NM, August-November 1982  

SciTech Connect (OSTI)

A comprehensive survey of the vicinity property designated as SH01 was conducted on an intermittent basis from August 23 to November 11, 1982. At the time of the survey, three structures were located on the property - two residential structures and a residential trailer. In addition to the three residences, the frame from a former truck scale was still on the property. The lands surrounding the structures and former truck scale were sparsely covered with vegetation. The assessment activities included determination of indoor and outdoor surface radiation levels through direct instrument surveys and analysis of air and soil samples. No evidence of radioactive contamination was found inside the structures, although elevated levels of radioactivity due to proximity to or shine from contaminated soils were indicated within all. The short-term radon daughter measurements did not exceed the limit of 0.02 Working Level for average annual concentration including background, as specified in the EPA Standard 40 CFR 192. The assessment indicated elevated levels of radioactivity in the outdoor environs, encompassing about 32,000 ft/sup 2/ (2900 m/sup 2/) of land surrounding, and north of, the former truck scale. Analysis of a surface soil sample collected from the environs indicated a radium concentration considerably in excess of the limit of 5 pCi/g above background specified in the EPA Standard. Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is not known. Since the surface soil contamination level exceeded the limit specified in the EPA Standard, remedial action for this vicinity site should be considered.

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

1984-04-01T23:59:59.000Z

125

Combining Dark Energy Survey Science Verification Data with Near Infrared Data from the ESO VISTA Hemisphere Survey  

E-Print Network [OSTI]

detectors that cover a region of 0.595 sq-deg. In order to get contiguous cover- age of the 1.5 sq-deg field-of-view (1.02 deg in RA and 1.48 deg in DEC), six exposures are therefore required. These six exposures are termed pawprints and together... Energy Survey (DES) with near infrared data from the ESO VISTA Hemisphere Survey (VHS). The deep optical detections from DES are used to extract fluxes and associated errors from the shallower VHS data. Joint 7-band (grizY JK) photometric catalogues...

Banerji, Manda; Jouvel, S.; Lin, H.; McMahon, R. G.; Lahav, O.; Castander, F. J.; Abdalla, F. B.; Bertin, E.; Bosman, S. E.; Carnero, A.; Carrasco Kind, M.; da Costa, L. N.; Gerdes, D.; Gschwend, J.; Lima, M.; Maia, M. A. G.; Merson, A.; Miller, C.; Ogando, R.; Pellegrini, P.; Reed, S.; Saglia, R.; Sánchez, C.; Allam, S.; Annis, J.; Bernstein, G.; Bernstein, J.; Bernstein, R.; Capozzi, D.; Childress, M.; Cunha, Carlos E.; Davis, T. M.; DePoy, D. L.; Desai, S.; Diehl, H. T.; Doel, P.; Findlay, J.; Finley, D. A.; Flaugher, B.; Frieman, J.; Gaztanaga, E.; Glazebrook, K.; González-Fernández, C.; Gonzalez-Solares, E.; Honscheid, K.; Irwin, M. J.; Jarvis, M. J.; Kim, A.; Koposov, S.; Kuehn, K.; Kupcu-Yoldas, A.; Lagattuta, D.; Lewis, J. R.; Lidman, C.; Makler, M.; Marriner, J.; Marshall, Jennifer L.; Miquel, R.; Mohr, Joseph J.; Neilsen, E.; Peoples, J.; Sako, M.; Sanchez, E.; Scarpine, V.; Schindler, R.; Schubnell, M.; Sevilla, I.; Sharp, R.; Soares-Santos, M.; Swanson, M. E. C.; Tarle, G.; Thaler, J.; Tucker, D.; Uddin, S. A.; Wechsler, R.; Wester, W.; Yuan, F.; Zuntz, J.

2014-01-01T23:59:59.000Z

126

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

SciTech Connect (OSTI)

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.

ERIKA N. BAILEY

2012-02-29T23:59:59.000Z

127

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)

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 sampling and laboratory analyses are completed, the data are analyzed and included in an Environmental Baseline Summary (EBS) report for title transfer or in a Baseline Environmental Analysis Report (BEAR) for lease. The data from the BEAR is then used in a Screening-Level Human Health Risk Assessment (SHHRA) or a risk calculation (RC) to assess the potential risks to future owners/occupants. If title is to be transferred, release criteria in the form of specific activity concentrations called Derived Concentration Guideline Levels (DCGLs) will be developed for the each property. The DCGLs are based on the risk model and are used with the data in the EBS to determine, with statistical confidence, that the release criteria for the property have been met. The goal of the survey and sampling efforts is to (1) document the baseline conditions of the property (real or personal) prior to title transfer or lease, (2) obtain enough information that an evaluation of radiological risks can be made, and (3) collect sufftcient data so that areas that contain minimal residual levels of radioactivity can be identified and, following radiological control procedures, be released from radiological control. (It should be noted that release from radiological control does not necessarily mean free release because DOE may maintain institutional control of the site after it is released from radiological control). To meet the goals of this document, a Data Quality Objective (DQO) process will be used to enhance data collection efficiency and assist with decision-making. The steps of the DQO process involve stating the problem, identifying the decision, identifying inputs to the decision, developing study boundaries, developing the decision rule, and optimizing the design. This document describes the DQOs chosen for surveys and sampling efforts performed for the purposes listed above. The previous version to this document focused on the requirements for radiological survey and sampling protocols that are be used for leasing. Because the primary focus at this time is on title transfer, th

Cusick L.T.

2002-09-25T23:59:59.000Z

128

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)

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.

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

1992-10-01T23:59:59.000Z

129

Results of the radiological survey at the former ALCOA New Kensington Works, Pine and Ninth Streets, New Kensington, Pennsylvania (ANK002)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the former ALCOA New Kensington Works, Pine and Ninth Streets, 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, as a result of work done for the Manhattan Engineer District in 1944. The survey included a gamma scan of three bays inside Building 18; measurement of direct alpha and beta-gamma levels in the same area; and collection of a dust sample for radionuclide analysis from the center of each bay. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines for uranium. The radionuclide distributions were not significantly different from typical background levels in the Pittsburgh, Pennsylvania area.

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

1992-10-01T23:59:59.000Z

130

Results of the radiological survey at the former McKinney Tool and Manufacturing Company, 1688 Arabella Road, Cleveland, Ohio (MTC001 and MTC002)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the site of the former McKinney Tool and Manufacturing Company, 1688, Arabella Road, Cleveland, Ohio. The survey was performed on November 17 and 18, 1990. The purpose of the survey was to determine whether the property ws contaminated with radioactive residues, principally {sup 238}U, as a result of work done for the Manhattan Engineer District in 1944. The survey included a gamma scan, a beta-gamma scan, and measurement of alpha level; measurements of direct and removable alpha and beta-gamma levels; and the collection of soil and sediment, dust, and air samples for radionuclide analyses. The survey and sampling covered accessible areas of buildings currently occupied by Parker Rust-Proof and Meistermatic, Inc., and exterior areas immediately adjacent to these buildings.

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

1991-11-01T23:59:59.000Z

131

Radiological survey of the former uranium recovery pilot and process sites, Gardinier, Incorporated, Tampa, Florida. Final report  

SciTech Connect (OSTI)

A radiological survey was conducted at a former uranium recovery plant near Tampa, Florida, operated as a part of a phosphoric acid plant. The uranium recovery operations were conducted from 1951 through 1960, the primary goal being the extraction of uranium from phosphoric acid. Pilot operations were first carried out at a small plant, and full-scale extraction was later carried out at a larger adjacent process plant. The survey included measurement of the followng: beta-gamma dose rates at 1 cm from surfaces and external gamma radiation levels at the surfaces and 1 m above the floor inside the pilot operations building and process building and outdoors in areas around these buildings; fixed and transferable alpha and beta-gamma contamination levels on the floor, walls, ceilings, and roof of the process building and on the floor, walls, and ceiling of the pilot plant offices; concentrations of /sup 226/Ra and /sup 238/U in soil samples taken at grid points around the buildings and in residue samples taken inside the process building; concentrations of /sup 226/Ra and /sup 238/U in water and sediment samples taken outdoors on the site and the concentration of these same nuclides in background samples collected off the site. It was found that beta-gamma and/or alpha contamination levels on surfaces exceed current guidelines for the release of property for unrestricted use at some points inside the process building and in the outdoor area near the process building and pilot operations building. Some samples of soil and residue taken from the floor and equipment on the second level of the process building contained natural uranium in excess of 0.05% by weight and contained natural radium in excess of 900 pCi/g.

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

1981-03-01T23:59:59.000Z

132

Results of the radiological survey at the Sacandaga site Glenville, New York. Waste Management Research and Development Programs  

SciTech Connect (OSTI)

The Sacandaga site, located on Sacandaga Road, Glenville, New York, was operated by the General Electric Company for the Atomic Energy Commission (AEC) between 1947 and 1951. Originally used for the study and development of radar during World War II, the facilities housed later operations involving physics studies and sodium technology development in support of breeder reactor design and other AEC programs. Though not in use since the original equipment was dismantled and removed in the early 1950s, portions of the 51-acre site are known to contain buried rubble from demolished structures used in former operations. At the request of the Office of Naval Reactors through the Office of Remedial Action and Waste Technology, a characterization of current radiological conditions over the site was performed between August and October 1989. The survey included the measurement of direct radiation levels (gamma, alpha, and beta-gamma) over all surfaces both inside and outside the building and tunnel, radionuclide analysis of systematic, biased, and auger hole soil samples, and analysis of sediments from underground structures. Gamma logging of auger holes was conducted and removable contamination levels inside the tunnel were determined. Samples of soil and structural materials from within and around an excavated concrete bunker were analyzed to determine concentrations of radionuclides and nonradioactive elemental beryllium.

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

1992-08-01T23:59:59.000Z

133

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)

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.

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

1999-10-20T23:59:59.000Z

134

Radiological characterization survey of the former Diamond Magnesium Company Company site, 720 Fairport-Nursery Road, Painesville, Ohio (DMP001, DMP002)  

SciTech Connect (OSTI)

At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory performed an investigative radiological survey at the former Diamond Magnesium Company (DMC) site at 720 Fairport-Nursery Road, Painesville, Ohio, in September 1990. The purpose of the survey was to determine if the site is contaminated with radioactive residues as a result of federal government operation in the development of nuclear energy for defense-related projects. The survey of the site, separate parcels of which are currently owned by the Uniroyal Chemical Company (DMP001) and the Lonza Chemical Company (DMP002), included a gamma scan over the ground surface, determination of gamma exposure rates at the surface and at 1 m above the surface at grid points, collection and radionuclide analysis of soil samples, and directly measured radiation levels inside three buildings used during original DMC processing. Results of the survey revealed widespread radiological contamination outdoors on the Uniroyal property and several isolated spots of elevated radiation levels on the Lonza property. The contaminants consisted of radium, uranium, and thorium in surface and subsurface soil in concentrations exceeding DOE guidelines for the release of property for unrestricted use.

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

1991-12-01T23:59:59.000Z

135

ORNL-5680 Radiological Surveys  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C. 20545*.MSE Cores" _ ,' ,:.''DOVEV-0005/l

136

radiological | EMSL  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

radiological radiological Leads No leads are available at this time. Magnesium behavior and structural defects in Mg+ ion implanted silicon carbide. Abstract: As a candidate...

137

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)

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.

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

1980-01-01T23:59:59.000Z

138

Uranium Mill Tailings Remedial Action Program. Radiological survey of Shiprock vicinity property SH16, Shiprock, New Mexico, October-November 1982  

SciTech Connect (OSTI)

At the time of the survey, one residential structure was located on the property. The lands surrounding the structure were landscaped with lawn cover and other vegetation. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air and soil samples. No evidence of radioactive contamination was found in the residential structure; background levels of radioactivity were indicated throughout. Radiation exposure rates were less than the 20 ..mu..R/h above background limit. Short-term radon daughter measurements did not exceed the 0.02 WL limit for average annual concentration including background. The assessment indicated elevated levels of radioactivity at several areas in the outside environs. Three localized areas, or discrete hot spots, were found within the backyard. A general area of elevated radioactivity was found at the back alleyway, encompassing about 1200 ft/sup 2/. Radiochemical analyses of the soil sample collected from the backyard indicated a radium concentration of 14 +- 1 pCi/g, which is in excess of the limit of 5 pCi/g above background. Analyses of surface soil samples collected at the alleyway from nearly vicinity property sites also indicated radium concentrations in excess of the limit. Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is not known. Remedial action for this vicinity site should be considered.

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

1984-05-01T23:59:59.000Z

139

EMSL - radiological  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

radiological en Diffusional Motion of Redox Centers in Carbonate Electrolytes . http:www.emsl.pnl.govemslwebpublicationsdiffusional-motion-redox-centers-carbonate-electrolytes...

140

Uranium mill tailings remedial action program. Radiological survey of Shiprock vicinity property SH04, Shiprock, New Mexico, September-November 1982  

SciTech Connect (OSTI)

The radiological assessment conducted at the Shiprock vicinity property SH04 by the ANL Radiological Survey Group indicated background levels of radioactivity within the residential structure. Short-term radon daughter measurements did not exceed the 0.02 WL (or 20 mWL) limit for average annual concentration including background as specified in the EPA Standard (40 CFR 192.12(b)(1)). The assessment indicated elevated levels of radioactivity at several areas in the outside environs. Twelve discrete hot spots or localized areas were found in the backyard, most associated with small slabs of decorative flagstone. Radiochemical analyses of the stone sample collected from one of the localized areas indicated the presence of natural uranium ore. Radiochemical analysis of the soil sample collected from one other of the localized areas indicated a radium concentration of 33 +- 3 pCi/g, which is in excess of the limit of 5 pCi/g above background, averaged over the first 15 cm of soil below the surface, as specified in Section 192.12(a)(1) of the EPA Standard. From the analyses of the samples and the history of the site, the contaminating material in the general area at the backyard and alleyway, in the area in the frontyard, and at several of the discrete locations in the backyard appears to be residual radioactive material under the provisions of the Uranium Mill Tailings Radiation Control Act of 1978 in the form of radium-enhanced material (i.e., tailings) and natural uranium ore. Since the surface soil contamination levels exceed the limits specified in the EPA Standard, remedial action for this vicinity site should be considered. 10 references, 4 figures, 5 tables.

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

1984-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Uranium mill tailings remedial action program. Radiological survey of Shiprock vicinity property SH05, Shiprock, New Mexico, August-November 1982  

SciTech Connect (OSTI)

The radiological assessment conducted at the Shiprock vicinity property SH05 by the ANL Radiological Survey Group indicated background levels of radioactivity within the residential structure. Radiation exposure rates were less than the 20 ..mu..R/h above background limit specified in the EPA Standard (40 CFR 192.12(b)(2)). Short-term radon daughter measurements within the residence did not exceed the 0.02 WL (or 20 mWL) limit for average annual concentration including background as specified in the EPA Standard (Section 192.12(b)(1)). The assessment indicated elevated levels of radioactivity at several areas in the outside environs. One discrete hot spot or localized area was found in the frontyard, near the front porch of the residence. Radiochemical analysis of the soil sample collected there indicated a radium concentration of 352 +- 35 pCi/g, which is in excess of the limit of 5 pCi/g above background, averaged over the first 15 cm of soil below the surface, as specified in Section 192.12(a)(1) of the EPA Standard. From soil sample analyses and the history of the site, the contaminating material appears to be residual radioactive material under the provisions of the Uranium Mill Tailings Radiation Control Act of 1978 in the form of radium-enhanced material (i.e., tailings) and natural uranium ore. Since the surface soil contamination levels exceed the limits specified in the EPA Standard, remedial action for this vicinity site should be considered. 10 references, 4 figures, 5 tables.

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

1984-05-01T23:59:59.000Z

142

Uranium mill tailings remedial action program. Radiological survey of Shiprock vicinity property SH02 Shiprock, New Mexico, August-November 1984  

SciTech Connect (OSTI)

A comprehensive survey of the vicinity property designated as SH02 was conducted on an intermittent basis from August 3 to November 11, 1982. At the time of the survey, seven structures were located on the property - two residential trailers, one institutional building, two institutional trailers, a storage building, and a pump house. The lands surrounding the structures were either sparsely covered with vegetation or gravelled. The assessment activities included determination of indoor and outdoor surface radiation levels through direct instrument surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analysis of air and soil samples. No evidence of radioactive contamination was found inside the structures; background levels of radioactivity were indicated within all seven. The short-term radon daughter measurements did not exceed the limit of 0.02 Working Level for average annual concentration including background, as specified in the EPA Standard 40 CFR 192. The assessment indicated elevated levels of radioactivity at one general area in the outdoor environs, encompassing about 1400 ft/sup 2/ (130 m/sup 2/) of land along the property's northern boundary. Analysis of a surface soil sample collected from this area indicated a radium concentration considerably in excess of the limit of 5 pCi/g above background specified in the EPA Standard. Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is not known. Since the surface soil contamination level exceeded the limit specified in the EPA Standard, remedial action for this vicinity site should be considered.

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

1984-04-01T23:59:59.000Z

143

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

SciTech Connect (OSTI)

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.

NICK A. ALTIC

2012-09-20T23:59:59.000Z

144

Radiological Excavation Control and Radiological Verification of the Moab  

E-Print Network [OSTI]

requested that the U.S. Nuclear Regulatory Commission suspend the review and comment of the above referenced document. The reason for the request was that DOE wanted to re-evaluate the proposed process for inclusion/exclusion of Moab vicinity properties. Accordingly, enclosed for your review is a revised, simplified process flow chart for the inclusion/exclusion of vicinity properties and accompanying revised text section of the document. If you have any questions, please call me at (970) 248-7612.

Mr. Myron Fliegel; Donald R. Metzler; J. Elmer; K. Karp; Moab Inclusion/exclusion Surveys

2005-01-01T23:59:59.000Z

145

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)

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 allow for the safe exhumation of the Special Nuclear Material in existing SLDA trenches. (authors)

Norris, Phillip; Mihalo, Mark; Eberlin, John; Lambert, Mike [Cabrera Services (United States); Matthews, Brian [Nuclear Safety Associates (United States)

2012-07-01T23:59:59.000Z

146

Uranium Mill Tailings Remedial Action Program. Radiological survey of Shiprock vicinity property SH15, Shiprock, New Mexico, October-November 1982  

SciTech Connect (OSTI)

At the time of the survey, one residential structure was located on the property. The lands surrounding the structure were landscaped with lawn cover and other vegetation. The lands in the unlandscaped east section contained a large garden plot and a dirt driveway leading to the back easement. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air and soil samples. No evidence of radioactive contamination was found in the residential structure; background levels of radioactivity were indicated throughout. Radiation exposure rates were less than the 20 ..mu..R/h above background limit specified in the EPA Standard. Short-term radon daughter measurements did not exceed the 0.02 WL limit for average annual concentration including background as specified in the EPA Standard. The assessment indicated elevated levels of radioactivity in the outside environs. General areas of contamination were found in the backyard, along the back easement and encompassing about 1200 ft/sup 2/ of land area there, and extending into the unlandscaped east section, encompassing about 2400 ft/sup 2/ there. Several discrete hot spots or localized areas were found within these general areas. Radiochemical analysis of the soil samples collected from the areas indicated radium concentrations of 64 +- 6 and 82 +- 8 pCi/g, which are in excess of the limit of 5 pCi/g above background. Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is now known. Remedial action for this vicinity site should be considered.

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

1984-05-01T23:59:59.000Z

147

Uranium Mill Tailings Remedial Action Program. Radiological survey of Shiprock vicinity property SH11, Shiprock, New Mexico, October-November 1982  

SciTech Connect (OSTI)

At the time of the survey, one residential structure used as a business office was located on the property. The lands surrounding the structure were, for the most part, landscaped with lawn cover and other vegetation. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air and soil samples. No evidence of radioactive contamination was found in the residential structure; background levels of radioactivity were indicated throughout. Radiation exposure rates were less than the 20 ..mu..R/h above background limit. Short-term radon daughter measurements did not exceed the 0.02 WL limit for average annual concentration including background. The assessment did indicate elevated levels of radioactivity at a few areas in the outside environs. Two discrete hot spots or localized areas were found in the frontyard. A general area of elevated radioactivity was found at the back alleyway encompassing about 1100 ft/sup 2/. Radiochemical analyses of the sample collected from one of the localized areas indicated the presence of natural uranium ore and a radium concentration of 165 +- 17 pCi/g, which is in excess of the limit of 5 pCi/g above background. Analyses of surface soil samples collected at the alleyway from nearby vicinity property sites also indicated radium concentrations in excess of the limits. Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is not known. Remedial action for this vicinity site should be considered.

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

1984-05-01T23:59:59.000Z

148

Uranium Mill Tailings Remedial Action Program. Radiological survey of Shiprock vicinity property SH08, Shiprock, New Mexico, October-November 1982  

SciTech Connect (OSTI)

At the time of the survey, one residential structure was located on the property. The lands surrounding the structure were, for the most part, landscaped with lawn cover and other vegetation. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air and soil samples. No evidence of radioactive contamination was found in the residential structure; background levels of radioactivity were indicated throughout. Radiation exposure rates were less than the 20 ..mu..R/h above background limit. Short-term radon daughter measurements did not exceed the 0.02 WL limit for average annual concentration including background. The assessment did indicate elevated levels of radioactivity at a few areas in the outside environs. A general area of elevated radioactivity was found at the west edge of the property, paralleling the roadway and encompassing an area of about 70 ft/sup 2/; and another general area of contamination was found in the backyard, encompassing about 960 ft/sup 2/, and extending into the alleyway, encompassing a general area of about 1100 ft/sup 2/ there. Radiochemical analyses of the soil sample collected from the general area in the backyard indicated a radium concentration of 6.7 +- 0.7 pCi/g, which cannot be confidently interpreted to be below the limit of 5 pCi/g above background, averaged over the first 15 cm of soil below the surface. However, analyses of surface soil samples collected at the alleyway from nearby vicinity property sites indicated radium concentrations in excess of those limits. Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is not known. Remedial action for this vicinity site should be considered.

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

1984-05-01T23:59:59.000Z

149

Urandium mill tailings remedial action program. Radiological survey of Shiprock vicinity property SH06, Shiprock, New Mexico, August-November 1982  

SciTech Connect (OSTI)

The radiological assessment conducted at the Shiprock vicinity property SH06 by the ANL Radiological Survey Group indicated background levels of radioactivity within the residential structure. Radiation exposure rates were less than the 20 ..mu..R/h above background limit specified in the EPA Standard (40 CFR 192.12(b)(2)). Short-term radon daughter measurements did not exceed the 0.02 WL (or 20 mWL) limit for average annual concentration including background as specified in the EPA Standard (40 CFR 192.12(b)(1)). The assessment indicated elevated levels of radioactivity at several areas in the outside environs. General areas of elevated radioactivity were found over almost the entire frontyard, encompassing about 1300 ft/sup 2/ (120 m/sup 2/), and at the west side of the residence, encompassing about 460 ft/sup 2/ (43 m/sup 2/). Radiochemical analysis of the soil sample collected from the frontyard near the residence indicated a radium concentration of 24 +- 2 pCi/g, which is in excess of the limit of 5 pCi/g above background, averaged over the first 15 cm of soil below the surface, as specified in Section 192.12(a)(1) of the EPA Standard. Elevated levels were also found at a 37-ft/sup 2/ (3.4-m/sup 2/) strip of land along the east property line, and in the backyard, at a small shack encompassing about 21 ft/sup 2/ (2.0 m/sup 2/) of land. From soil sample analyses and the history of the site, the contaminating material appears to be residual radioactive material under the provisions of the Uranium Mill Tailings Radiation Control Act of 1978 in the form of radium-enhanced material (i.e., tailings). Since the surface soil contamination levels exceed the limits specified in the EPA Standard, remedial action for this vicinity site should be considered. 9 references, 4 figures, 5 tables.

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

1984-05-01T23:59:59.000Z

150

Radiological health aspects of uranium milling  

SciTech Connect (OSTI)

This report describes the operation of conventional and unconventional uranium milling processes, the potential for occupational exposure to ionizing radiation at the mill, methods for radiological safety, methods of evaluating occupational radiation exposures, and current government regulations for protecting workers and ensuring that standards for radiation protection are adhered to. In addition, a survey of current radiological health practices is summarized.

Fisher, D.R.; Stoetzel, G.A.

1983-05-01T23:59:59.000Z

151

I COMPREHENSIVE RADIOLOGICAL SURVEY I  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledo SiteTonawanda North - t ' v I tfi t7Bechtelim I

152

Radiological Habits Survey, Faslane, 2006  

E-Print Network [OSTI]

;3 SUMMARY 5 1. BACKGROUND 5 1.1 Regulation of radioactive waste discharges 5 1.2 The critical group concept' consumption rates of root vegetables in the Faslane area (kg/y) Table 12. Adults' consumption rates of potato

153

Radiological Habits Survey, Chapelcross, 2005  

E-Print Network [OSTI]

;2 #12;3 SUMMARY 6 1. BACKGROUND 6 1.1 Regulation of radioactive waste discharges 6 1.2 The critical of potato in the Chapelcross area (kg/y) Table 15. Adult consumption rates of domestic fruit. Children's consumption rates of potato in t

154

Radiological Habits Survey, Dounreay, 2003  

E-Print Network [OSTI]

;2 #12;3 SUMMARY 6 1. BACKGROUND 7 1.1 Regulation of radioactive waste discharges 7 1.2 The critical (kg/y) of potatoes in the Dounreay area Table 16. Adult consumption rates (kg/y) of domestic fruit/y) of potatoes in the Dounreay area Table 32. Children's consumption rates (k

155

Radiological Habits Survey, Hunterston 2001  

E-Print Network [OSTI]

;3 SUMMARY 6 1. BACKGROUND 7 1.1 Regulation of radioactive waste discharges 7 1.2 The critical group concept rates of root vegetables from the Hunterston area (kg/y) Table 15. Adult consumption rates of potatoes the Hunterston area (kg/y) Table 31. Children's consumption rates of potatoes from the Hunterston area (kg

156

ORISE: Characterization surveys  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

extent of radiological contamination at sites scheduled for decontamination and decommissioning (D&D). A fundamental aspect of all D&D projects, characterization surveys provide...

157

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)

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).

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

1996-06-01T23:59:59.000Z

158

Estimating radiological background using imaging spectroscopy  

SciTech Connect (OSTI)

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.

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

2014-06-13T23:59:59.000Z

159

Women in pediatric radiology  

E-Print Network [OSTI]

AM et al. (2001) Pediatric radiology at the millennium.a case study of pediatric radiology. J Am Coll Radiol 6:635–WORKPLACE Women in pediatric radiology M. Ines Boechat # The

Boechat, M. Ines

2010-01-01T23:59:59.000Z

160

Radiological Characterization and Final Facility Status Report Tritium Research Laboratory  

SciTech Connect (OSTI)

This document contains the specific radiological characterization information on Building 968, the Tritium Research Laboratory (TRL) Complex and Facility. We performed the characterization as outlined in its Radiological Characterization Plan. The Radiological Characterization and Final Facility Status Report (RC&FFSR) provides historic background information on each laboratory within the TRL complex as related to its original and present radiological condition. Along with the work outlined in the Radiological Characterization Plan (RCP), we performed a Radiological Soils Characterization, Radiological and Chemical Characterization of the Waste Water Hold-up System including all drains, and a Radiological Characterization of the Building 968 roof ventilation system. These characterizations will provide the basis for the Sandia National Laboratory, California (SNL/CA) Site Termination Survey .Plan, when appropriate.

Garcia, T.B.; Gorman, T.P.

1996-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Radiological Control Manual  

SciTech Connect (OSTI)

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.

Not Available

1993-04-01T23:59:59.000Z

162

Radiological survey and evaluation of the fallout area from the Trinity test: Chupadera Mesa and White Sands Missile Range, New Mexico  

SciTech Connect (OSTI)

Current radiological conditions were evaluated for the site of the first nuclear weapons test, the Trinity test, and the associated fallout zone. The test, located on White Sands Missile Range, was conducted as part of the research with nuclear materials for the World War II Manhattan Engineer District atomic bomb project. Some residual radioactivity attributable to the test was found in the soils of Ground Zero on White Sands Missile Range and the areas that received fallout from the test. The study considered relevant information including historical records, environmental data extending back to the 1940s, and new data acquired by field sampling and measurements. Potential exposures to radiation were evaluated for current land uses. Maximum estimated doses on Chupadera Mesa and other uncontrolled areas are less than 3% of the DOE Radiation Protection Standards (RPSs). Radiation exposures during visits to the US Army-controlled Ground Zero area are less than 1 mrem per annual visit or less than 0.2% of the RPS for a member of the public. Detailed data and interpretations are provided in appendixes. 14 figs., 45 tabs.

Hansen, W.R.; Rodgers, J.C.

1985-06-01T23:59:59.000Z

163

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)

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 conditions has proven successful. The radioactivity measuring devices for operation at high, non-uniform dose background were tested in the field and a new data of measurement of contamination distribution in the premises and installations were obtained. (authors)

Danilovich, Alexey; Ivanov, Oleg; Lemus, Alexey; Smirnov, Sergey; Stepanov, Vyacheslav; Volkovich, Anatoly [National Research Centre 'Kurchatov Institute', Moscow (Russian Federation)

2012-07-01T23:59:59.000Z

164

Uranium Mill Tailings Remedial Action Program. Radiological survey of Shiprock vicinity property SH07, Shiprock, New Mexico, September-November 1982  

SciTech Connect (OSTI)

At the time of the survey, one residential structure was located on the property. The lands surrounding the structure were, for the most part, landscaped with lawn cover and other vegetation. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air and soil samples. No evidence of radioactive contamination was found in the residential structure; background levels of radioactivity were indicated throughout. Radiation exposure rates were less than the 20 ..mu..R/h above background limit. Short-term radon daughter measurements did not exceed the 0.02 WL limit for average annual concentration including background. The assessment did indicate elevated levels of radioactivity at several areas in the outside environs. A general area of elevated radioactivity was found in the frontyard and alleyway, encompassing about 2300 ft/sup 2/. Elevated levels were also found in the northwest corner of the property, encompassing about 320 ft/sup 2/, and in the southeast corner, encompassing about 39 ft/sup 2/. An area of elevated radioactivity was found at a backyard slab, constructed of decorative flagstone and encompassing about 160 ft/sup 2/. Radiochemical analyses of the soil sample collected from the southeast corner indicated a radium concentration of 41 +- 5 pCi/g, which is in excess of the limit of 5 pCi/g above background. Analyses of a surface soil sample collected in the alley from an adjacent vicinity property site also indicated a radium concentration in excess of those limits. Subsurface soil sampling was not conducted. Remedial action for this vicinity site should be considered.

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

1984-05-01T23:59:59.000Z

165

Uranium Mill Tailings Remedial Action Program. Radiological survey of Shiprock vicinity property SH09, Shiprock, New Mexico, October-November 1982  

SciTech Connect (OSTI)

At the time of the survey, one residential structure was located on the property. The lands surrounding the structure were landscaped with lawn cover and trees. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air and soil samples. No evidence of radioactive contamination was found in the residential structure; background levels of radioactivity were indicated throughout. Radiation exposure rates were less than the 20 ..mu..R/h above background limit. Short-term radon daughter measurements did not exceed the 0.02 WL limit for average annual concentration including background as specified in the EPA Standard. The assessment indicated elevated levels of radioactivity at several areas in the outside environs. A general area was found along the west side of the residence, encompassing about 160 ft/sup 2/, and a discrete hot spot of localized area was found near the back porch of the residence. General areas of elevated radioactivity also were found at the west edge of the property, paralleling the roadway and encompassing about 120 ft/sup 2/, and at the alleyway, encompassing about 1300 ft/sup 2/. Radiochemical analyses of the soil sample collected from the west edge of the property indicated a radium concentration of 24 +- 2 pCi/g, which is in excess of the limit of 5 pCi/g above background. Analyses of surface soil samples collected at the alleyway from nearby vicinity property sites also indicated radium concentrations in excess of the limits. Subsurface soil sampling was not conducted. Remedial action for this vicinity site should be considered.

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

1984-05-01T23:59:59.000Z

166

Uranium Mill Tailings Remedial Action Program. Radiological survey of Shiprock vicinity property SH10, Shiprock, New Mexico, October-November 1982  

SciTech Connect (OSTI)

At the time of the survey, one residential structure was located on the property. The lands surrounding the structure were, for the most part, landscaped with lawn cover and other vegetation. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air and soil samples. No evidence of radioactive contamination was found in the residential structure; background levels of radioactivity were indicated throughout. Radiation exposure rates were less than the 20 ..mu..R/h above background limit. Short-term radon daughter measurements did not exceed the 0.02 WL limit for average annual concentration including background. The assessment did indicate elevated levels of radioactivity at several areas in the outside environs. A general area was found along the east edge of the property, paralleling the roadway and encompassing about 24 ft/sup 2/, and two discrete hot spots or localized areas were detected in the southeast corner of the property. Additionally, general areas were found near the southwest corner of the structure, encompassing about 6.8 ft/sup 2/; to the west of the structure, encompassing about 60 ft/sup 2/; and at the west edge of the property and alleyway, encompassing about 1400 ft/sup 2/. Radiochemical analyses of the soil sample collected from this area indicated a radium concentration of 19 +- 2 pCi/g, which is in excess of the limit of 5 pCi/g above background. Subsurface soil sampling was not conducted. Remedial action for this vicinity site should be considered.

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

1984-05-01T23:59:59.000Z

167

EMERGING RENEWABLES PROGRAM SYSTEMS VERIFICATION REPORT  

E-Print Network [OSTI]

survey that measured customer experience in applying to the ERP, receiving utility interconnection that instantaneous measurements showed most PV systems were operating in-line with expectations with modest, renewable energy, shading, solar, system performance, system verification, utility interconnection, wind #12

168

Uranium Mill Tailings Remedial Action Program. Radiological survey of Shiprock vicinity property SH17, Shiprock, New Mexico, August and November 1982  

SciTech Connect (OSTI)

The assessment activities included determination of indoor surface radiation levels in two buildings through direct instrument surveys, measurement of ambient external penetrating radiation levels at 1-meter heights, and analysis of air samples. No evidence of radioactive contamination was found inside either building; the assessment indicated no elevated levels of radioactivity that could not be attributed to the structural materials used in the construction of the buildings. The levels of radiation that were detected from these sources were considered normal for the glazed-tile and cement-block materials encountered. Radiation exposure rates were less than the 20 ..mu..R/h above background limit specified in the EPA Standard. Short-term radon daughter measurements within the buildings did not exceed the 0.02 WL limit for average annual concentrations including background as specified in the EPA Standard. The assessment did not indicate the presence of residual radioactive material under the provisions of the Uranium Mill Tailings Radiation Control Act of 1978. Remedial action for this vicinity site should not be considered.

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

1984-05-01T23:59:59.000Z

169

Radiological Assistance Program  

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

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

1992-04-10T23:59:59.000Z

170

Remaining Sites Verification Package for the 126-F-2, 183-F Clearwells, Waste Site Reclassification Form 2006-017  

SciTech Connect (OSTI)

The 126-F-2 site is the clearwell facility formerly used as part of the reactor cooling water treatment at the 183-F facility. During demolition operations in the 1970s, potentially contaminated debris was disposed in the eastern clearwell structure. The site has been remediated by removing all debris in the clearwell structure to the Environmental Restoration Disposal Facility. The results of radiological surveys and visual inspection of the remediated clearwell structure show neither residual contamination nor the potential for contaminant migration beyond the clearwell boundaries. The results of verification sampling at the remediation waste staging area demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River.

R. A. Carlson

2006-05-04T23:59:59.000Z

171

Verification Challenges at Low Numbers  

SciTech Connect (OSTI)

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.

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

2013-06-01T23:59:59.000Z

172

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)

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

T.J. Vitkus

2008-06-06T23:59:59.000Z

173

Verification and Validation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

include modeling simulation (which is a form of Test, Demonstration, and Analysis). INL system engineers specialize in helping projects through the Verification and Validation...

174

Treaty Verification | ornl.gov  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Verification SHARE Treaty Verification ORNL is a strong contributor to future nonproliferation and arms control initiatives through research and development of radiation...

175

ORISE: Independent verification  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

to determine the effectiveness of radiological cleanup at decontamination and decommissioning (D&D) projects across the United States. Since 1980, ORISE has performed...

176

Orc Verification Jayadev Misra  

E-Print Network [OSTI]

Orc Verification Jayadev Misra Department of Computer Science University of Texas at Austin http://orc.csres.utexas.edu WG 2.3, St. Petersburg June 5, 2013 #12;Orc Verification has been a disaster · Concurrency everywhere events but temporal ordering · Basic orc has no mutable variables, but sites do · Full functional

Misra, Jayadev

177

Radiological Habits Survey: Sellafield Review, 2005  

E-Print Network [OSTI]

Atomic Energy Authority (UKAEA) Windscale sites. It is also relevant to marine discharges from the Drigg

178

Radiological Habits Survey, Rosyth Business Park, 2005  

E-Print Network [OSTI]

;2 #12;3 SUMMARY 5 1. BACKGROUND 5 1.1 Regulation of radioactive waste discharges 5 1.2 The critical area (kg/y) Table 15. Adults' consumption rates of potato in the Rosyth area (kg/y) Table 16. Adults rates of root vegetables in the Rosyth area (kg/y) Table 29. Children's consumption rates of potato

179

Verification Testing Test Driven Development Testing with JUnit Verification  

E-Print Network [OSTI]

Verification Testing Test Driven Development Testing with JUnit Verification Any activity should be verified. #12;Verification Testing Test Driven Development Testing with JUnit Approaches to verification 1 Testing 2 Static Analysis · Peer review · Insepction/Walk-through/Structured review · Formal

Peters, Dennis

180

University of Massachusetts Amherst Measurement & Verification Guidelines  

E-Print Network [OSTI]

University of Massachusetts Amherst Measurement & Verification Guidelines & Template Plan 11 ..............................................................................................................1 UMASS AMHERST MEASUREMENT & VERIFICATION (M&V) GUIDELINES ..........3 PREFACE ....................................................................................................................................................................3 BENEFITS OF MEASUREMENT & VERIFICATION

Massachusetts at Amherst, University of

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Carbon Storage Monitoring, Verification and Accounting Research...  

Energy Savers [EERE]

Monitoring, Verification and Accounting Research Carbon Storage Monitoring, Verification and Accounting Research Reliable and cost-effective monitoring, verification and accounting...

182

Verification and Validation of Simulation Model  

E-Print Network [OSTI]

Verification and Validation of Simulation Model 1 Verification and Validation 2 #12;Verification · Examples ­ simulation model: open networks with exponential interarrival time distribution and uniform

Shihada, Basem

183

Voltage verification unit  

DOE Patents [OSTI]

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.

Martin, Edward J. (Virginia Beach, VA)

2008-01-15T23:59:59.000Z

184

SQA_CodeVerification_Survey_FINAL  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 ResourceAwards SAGE Awards ,#2446Smalln n u

185

Radiological worker training  

SciTech Connect (OSTI)

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.

NONE

1998-10-01T23:59:59.000Z

186

324 Building Baseline Radiological Characterization  

SciTech Connect (OSTI)

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.

R.J. Reeder, J.C. Cooper

2010-06-24T23:59:59.000Z

187

ORISE: Radiological program assessment services  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Environmental monitoring programs Operational environments Decontamination and decommissioning projects Compliance assessments Radiological release programs ORISE is actively...

188

Radiology of thoracic diseases  

SciTech Connect (OSTI)

This book presents the essential clinical and radiologic findings of a wide variety of thoracic diseases. The authors include conventional, CT and MR images of each disease discussed. In addition, they present practical differential diagnostic considerations for most of the radiographic findings or patterns portrayed.

Swensen, S.J.; Pugatch, R.D.

1989-01-01T23:59:59.000Z

189

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...

190

SOFTWARE TESTING, VERIFICATION AND RELIABILITY Softw. Test. Verif. Reliab. (2014)  

E-Print Network [OSTI]

. An industrial case study using reactor protection system software shows that the automatically generated test defined by the International Electrotechnical Commission (IEC). Industrial FBD testing relies mostlySOFTWARE TESTING, VERIFICATION AND RELIABILITY Softw. Test. Verif. Reliab. (2014) Published online

191

Electric Utility Measurement & Verification Program  

E-Print Network [OSTI]

Electric Utility Measurement & Verification Program Ken Lau, P.Eng., CMVP Graham Henderson, P.Eng., CMVP Dan Hebert, P.Eng.,CMVP Mgr, Measurement & Verification Engineering Team Leader Senior Engineer BC Hydro Burnaby, BC Canada...

Lau, K.; Henderson, G.; Hebert, D.

192

Quantum Money with Classical Verification  

E-Print Network [OSTI]

We construct a quantum money scheme that allows verification through classical communication with bank. This is the first demonstration that a secure quantum money scheme exists that does not require quantum communication for coin verification.

Gavinsky, Dmitry

2011-01-01T23:59:59.000Z

193

Nuclear disarmament verification  

SciTech Connect (OSTI)

Arms control treaties, unilateral actions, and cooperative activities -- reflecting the defusing of East-West tensions -- are causing nuclear weapons to be disarmed and dismantled worldwide. In order to provide for future reductions and to build confidence in the permanency of this disarmament, verification procedures and technologies would play an important role. This paper outlines arms-control objectives, treaty organization, and actions that could be undertaken. For the purposes of this Workshop on Verification, nuclear disarmament has been divided into five topical subareas: Converting nuclear-weapons production complexes, Eliminating and monitoring nuclear-weapons delivery systems, Disabling and destroying nuclear warheads, Demilitarizing or non-military utilization of special nuclear materials, and Inhibiting nuclear arms in non-nuclear-weapons states. This paper concludes with an overview of potential methods for verification.

DeVolpi, A.

1993-12-31T23:59:59.000Z

194

Verification and validation benchmarks.  

SciTech Connect (OSTI)

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 achievement in V&V activities, how closely related the V&V benchmarks are to the actual application of interest, and the quantification of uncertainties related to the application of interest.

Oberkampf, William Louis; Trucano, Timothy Guy

2007-02-01T23:59:59.000Z

195

Environmental Technology Verification Program  

E-Print Network [OSTI]

Environmental Technology Verification Program Quality Management Plan (QMP) for the ETV Materials Management and Remediation Center Version 1.0 #12;QUALITY MANAGEMENT PLAN (QMP) for the ETV MATERIALS MANAGEMENT AND REMEDIATION CENTER Version 1.0 (SIGNATURE ON FILE) Teri Richardson 3-13-09 EPA MMR CENTER

196

Nuclear & Radiological Activity Center (NRAC)  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Nuclear & Radiological Activity Center (NRAC) Where nuclear research and deployment capabilities come together to solve nuclear nonproliferation challenges. Skip Navigation Links...

197

Smart Radiological Dosimeter  

DOE Patents [OSTI]

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.

Kosslow, William J.; Bandzuch, Gregory S.

2004-07-20T23:59:59.000Z

198

Radiological Control Technician Training  

Broader source: Energy.gov (indexed) [DOE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergy 0611__Joint_DOE_GoJ_AMS_Data_v3.pptx More Documents &DOE.F 1325.8 (08-93) Radiological

199

Radiological Work Planning and Procedures  

E-Print Network [OSTI]

Each facility is tasked with maintaining personnel radiation exposure as low as reasonably achievable (ALARA). A continued effort is required to meet this goal by developing and implementing improvements to technical work documents (TWDs) and work performance. A review of selected TWDs from most facilities shows there is a need to incorporate more radiological control requirements into the TWD. The Radioactive Work Permit (RWP) provides a mechanism to place some of the requirements but does not provide all the information needed by the worker as he/she is accomplishing the steps of the TWD. Requiring the engineers, planners and procedure writers to put the radiological control requirements in the work steps would be very easy if all personnel had a strong background in radiological work planning and radiological controls. Unfortunately, many of these personnel do not have the background necessary to include these requirements without assistance by the Radiological Control organization at each facility. In add...

Kurtz, J E

2000-01-01T23:59:59.000Z

200

Quantum Money with Classical Verification  

E-Print Network [OSTI]

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.

Dmitry Gavinsky

2012-03-15T23:59:59.000Z

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Radiological Release Accident Investigation Report - Phase 1...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Radiological Release Accident Investigation Report - Phase 1 Radiation Report Radiological Release Accident Investigation Report - Phase 1 Radiation Report Phase 1 of this accident...

202

Standardized radiological dose evaluations  

SciTech Connect (OSTI)

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.

Peterson, V.L.; Stahlnecker, E.

1996-05-01T23:59:59.000Z

203

Assessment of Evaluation, Measurement, and Verification Methods...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Assessment of Evaluation, Measurement, and Verification Methods - 2014 BTO Peer Review Assessment of Evaluation, Measurement, and Verification Methods - 2014 BTO Peer Review...

204

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

Broader source: Energy.gov (indexed) [DOE]

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

205

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

Broader source: Energy.gov (indexed) [DOE]

Evaluation, Measurement, and Verification Overview Evaluation, Measurement, and Verification Overview This document provides an overview and definition of EM&V. What is EMV? More...

206

Radionuclide Inventory Distribution Project Data Evaluation and Verification White Paper  

SciTech Connect (OSTI)

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 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.

NSTec Environmental Restoration

2010-05-17T23:59:59.000Z

207

Stanford Radiology LPCH Fast Pediatric MRI  

E-Print Network [OSTI]

Stanford Radiology LPCH Fast Pediatric MRI Shreyas Vasanawala, MD/PhD Stanford University Lucile Radiology LPCH Thank you Par Lab Briefer, lighter, safer anesthesia for pediatric MRI #12; practice #12;Stanford Radiology LPCH #12;Stanford Radiology LPCH Current Solution INVASIVE LIMITS ACCESS

California at Berkeley, University of

208

Radiological Control Manual. Revision 0, January 1993  

SciTech Connect (OSTI)

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.

Not Available

1993-04-01T23:59:59.000Z

209

Radiological-dose assessments of atolls in the northern Marshall Islands  

SciTech Connect (OSTI)

The Marshall Islands in the Equatorial Pacific, specifically Enewetak and Bikini Atolls, were the site of US nuclear testing from 1946 through 1958. In 1978, the Northern Marshall Islands Radiological Survey was conducted to evaluate the radiological conditions of two islands and ten atolls downwind of the proving grounds. The survey included aerial external gamma measurements and collection of soil, terrestrial, and marine samples for radionuclide analysis to determine the radiological dose from all exposure pathways. The methods and models used to estimate doses to a population in an environment where natural processes have acted on the source-term radionuclides for nearly 30 y, data bases developed for the models, and results of the radiological dose analyses are described.

Robison, W.L.

1983-04-01T23:59:59.000Z

210

Radiation Shielding and Radiological Protection  

E-Print Network [OSTI]

Radiation Shielding and Radiological Protection J. Kenneth Shultis Richard E. Faw Department@triad.rr.com Radiation Fields and Sources ................................................ . Radiation Field Variables........................................................... .. Direction and Solid Angle Conventions ......................................... .. Radiation Fluence

Shultis, J. Kenneth

211

Radiological Emergency Response Plan (Vermont)  

Broader source: Energy.gov [DOE]

This legislation establishes a radiological emergency response plan fund, into which any entity operating a nuclear reactor or storing nuclear fuel and radioactive waste in this state (referred to...

212

TFE Verification Program  

SciTech Connect (OSTI)

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 (thermionic fuel element) 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 TFE Verification Program builds directly on the technology and data base developed in the 1960s and early 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 features of thermionic power conversion technology were recognized but concern was expressed over the lack of fast reactor irradiation data. The TFE Verification Program addresses this concern.

Not Available

1993-05-01T23:59:59.000Z

213

Radiological Protection for DOE Activities  

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

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)

1995-09-29T23:59:59.000Z

214

Learning Minimal Separating DFA's for Compositional Verification  

E-Print Network [OSTI]

version is evaluated on the LTSA benchmarks and compared with other automated com- positional verification

Clarke, Edmund M.

215

DOE standard: Radiological control  

SciTech Connect (OSTI)

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.

Not Available

1999-07-01T23:59:59.000Z

216

Recent Developments in Field Response for Mitigation of Radiological...  

Energy Savers [EERE]

of technologies and methods to detect, prepare, or manage radiological incidents or accidents . With any radiological accident, radiological dispersal device (RDD), or improvised...

217

Radiological Work Planning and Procedure  

SciTech Connect (OSTI)

Each facility is tasked with maintaining personnel radiation exposure as low as reasonably achievable (ALARA). A continued effort is required to meet this goal by developing and implementing improvements to technical work documents (TWDs) and work performance. A review of selected TWDs from most facilities shows there is a need to incorporate more radiological control requirements into the TWD. The Radioactive Work Permit (RWP) provides a mechanism to place some of the requirements but does not provide all the information needed by the worker as he/she is accomplishing the steps of the TWD. Requiring the engineers, planners and procedure writers to put the radiological control requirements in the work steps would be very easy if all personnel had a strong background in radiological work planning and radiological controls. Unfortunately, many of these personnel do not have the background necessary to include these requirements without assistance by the Radiological Control organization at each facility. In addition, there seems to be confusion as to what should be and what should not be included in the TWD.

KURTZ, J.E.

2000-01-01T23:59:59.000Z

218

Software Modeling and Verification Professors  

E-Print Network [OSTI]

Software Modeling and Verification Staff · Professors Prof. Dr. Ir. Joost-Pieter Katoen Prof. em) Mark Timmer (Uni Twente, NL) Dr. Olga Tveretina (Karlsruhe University, D) Ralf Wimmer (Universität

Ábrahám, Erika

219

Radiological control manual. Revision 1  

SciTech Connect (OSTI)

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.

Kloepping, R.

1996-05-01T23:59:59.000Z

220

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

SciTech Connect (OSTI)

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.

E.N. Bailey

2009-03-18T23:59:59.000Z

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Nuclear Radiological Threat Task Force Established | National...  

National Nuclear Security Administration (NNSA)

Radiological Threat Task Force Established | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

222

Radiological Assistance Program | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

Federal Radiological Monitoring and Assessment Center Emergency Response Accident Response Group Radiation Emergency Assistance Center Training Site National Atmospheric Release...

223

Mobile autonomous robotic apparatus for radiologic characterization  

DOE Patents [OSTI]

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.

Dudar, Aed M. (Dearborn, MI); Ward, Clyde R. (Aiken, SC); Jones, Joel D. (Aiken, SC); Mallet, William R. (Cowichan Bay, CA); Harpring, Larry J. (North Augusta, SC); Collins, Montenius X. (Blackville, SC); Anderson, Erin K. (Pleasanton, CA)

1999-01-01T23:59:59.000Z

224

Mobile autonomous robotic apparatus for radiologic characterization  

DOE Patents [OSTI]

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.

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

1999-08-10T23:59:59.000Z

225

Best practice techniques for environmental radiological monitoring  

E-Print Network [OSTI]

Best practice techniques for environmental radiological monitoring Science Report ­ SC030308/SR SCHO0407BMNL-E-P #12;ii Science Report Best Practice Techniques for Environmental Radiological #12;iv Science Report Best Practice Techniques for Environmental Radiological Monitoring Executive

226

International Data on Radiological Sources  

SciTech Connect (OSTI)

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.

Martha Finck; Margaret Goldberg

2010-07-01T23:59:59.000Z

227

RADIOLOGICAL & ENVIRONMENTAL MANAGEMENT GUIDANCE DOCUMENT  

E-Print Network [OSTI]

RADIOLOGICAL & ENVIRONMENTAL MANAGEMENT GUIDANCE DOCUMENT: Minors in Research Laboratories or Animal Facilities Page 1 of 4 PURPOSE: The purpose of this document is to provide guidance for Purdue sponsored programs which are designed for youth under the age of 15 and which have documented

Holland, Jeffrey

228

Departmental Radiological Emergency Response Assets  

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

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

2007-06-27T23:59:59.000Z

229

Generation of RTL verification input stimulus  

E-Print Network [OSTI]

This thesis presents an approach for generating input stimulus for verification of register-transfer level (RTL) design of VLSI circuits. RTL design is often subjected to a significant verification effort due to errors introduced during manual...

Selvarathinam, Anand Manivannan

2001-01-01T23:59:59.000Z

230

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)

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).

Evan Harpenau

2011-11-30T23:59:59.000Z

231

Understanding Mechanisms of Radiological Contamination  

SciTech Connect (OSTI)

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.

Rick Demmer; John Drake; Ryan James, PhD

2014-03-01T23:59:59.000Z

232

Robotic Surveying  

SciTech Connect (OSTI)

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-actuated functions to be controlled by an onboard computer. The computer-controlled Speedrower was developed at Carnegie Mellon University to automate agricultural harvesting. Harvesting tasks require the vehicle to cover a field using minimally overlapping rows at slow speeds in a similar manner to geophysical data acquisition. The Speedrower had demonstrated its ability to perform as it had already logged hundreds of acres of autonomous harvesting. This project is the first use of autonomous robotic technology on a large-scale for geophysical surveying.

Suzy Cantor-McKinney; Michael Kruzic

2007-03-01T23:59:59.000Z

233

Design for manufacturability Design verification  

E-Print Network [OSTI]

ITRS Design #12;Design · Design for manufacturability · Design verification #12;Design for Manufacturability · Architecture challenges · Logic and circuit challenges · Layout and physical design challenges · Expected to be the source of multiple DFM challenges · Invest in variability reduction or design

Patel, Chintan

234

Physics Division ESH Bulletin 2007-03 Radiological Survey Requirements  

E-Print Network [OSTI]

and found to contain no other radioactive material or contamination. The direct cause of this incident Area Airborne Radioactivity Area High Contamination Area Contamination Area Contamination Buffer Awareness Program (OAP) inspection, a small, unlabeled plastic bag that was emitting radioactivity

235

Health and Safety Research Division RESULTS OF THE RADIOLOGICAL SURVEY  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledo SiteTonawanda North - ConsequencesDGwen N

236

Health and Safety Research Divlsion RESULTS OF THE RADIOLOGICAL SURVEY  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledo SiteTonawanda North - ConsequencesDGwen

237

I RADIOLOGICAL SCOPING SURVEY OF FO,RMER MONSANTO' FACILITIES  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$ EGcG ENERGYELIkNATIONHEALXH: l ._ .r.,--I Is ILwrgv

238

Letter: Katy Trail Radiological Survey at Southeast Drainage.  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$ EGcG ENERGYELIkNATIONHEALXH:LTS Plan WorkshopI9 I

239

Roadmap: Radiologic Technology Radiology Department Management Technology Associate of Technical Study  

E-Print Network [OSTI]

Roadmap: Radiologic Technology ­ Radiology Department Management Technology ­ Associate-Nov-13/LNHD This roadmap is a recommended semester-by-semester plan of study for this major. However

Sheridan, Scott

240

Radiological Triage | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Data results provided back to the field within 30-60 minutes. All NNSA teams that conduct search, detection and identification operations, to include the Radiological...

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

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

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Training Clinicians for Response to a Radiological or Nuclear Terrorism Attack The Centers for Disease Control and Prevention and its Radiation Studies Branch in the National...

242

Radiological Assistance Program | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

(trained personnel and equipment) to evaluate, assess, advise, isotopically identify, search for, and assist in the mitigation of actual or perceived nuclear or radiological...

243

Software Verification and Testing Lecture Notes: Testing I  

E-Print Network [OSTI]

Software Verification and Testing Lecture Notes: Testing I #12;Motivation verification: · powerful · automated techniques rather limited testing: (as "poor man's verification") · can only detect presence mathematical skills 1 #12;Motivation verification vs testing: · verification used often in early stages

Struth, Georg

244

2012-2013 Diagnostic Radiology Fellows Cardiovascular Imaging  

E-Print Network [OSTI]

dbweinreb@ Pediatric Radiology Body Imaging 1st yr. Neuroradiology NCI Body Mammography Sonya Edwards 149042012-2013 Diagnostic Radiology Fellows Cardiovascular Imaging Nuclear Medicine David Weinreb 14895 14909 laxpati@ Michael Kim 14961 mjjkim@ Vascular and Interventional Radiology Charles Kosydar 14908

Sonnenburg, Justin L.

245

Nuclear Data Verification and Standardization  

SciTech Connect (OSTI)

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.

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

2011-10-01T23:59:59.000Z

246

Federal Radiological Monitoring and Assessment Center  

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

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.

1992-12-02T23:59:59.000Z

247

Memorandum, Reporting of Radiological Sealed Sources Transactions  

Broader source: 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.

248

Nevada Test Site Radiological Control Manual  

SciTech Connect (OSTI)

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.

Radiological Control Managers' Council Nevada Test Site

2010-02-09T23:59:59.000Z

249

Nevada Test Site Radiological Control Manual  

SciTech Connect (OSTI)

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.

Radiological Control Managers' Council - Nevada Test Site

2009-10-01T23:59:59.000Z

250

INL@Work Radiological Search & Response Training  

ScienceCinema (OSTI)

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.

Turnage, Jennifer

2013-05-28T23:59:59.000Z

251

Guide to good practices for independent verification  

SciTech Connect (OSTI)

This Guide to Good Practices is written to enhance understanding of, and provide direction for, Independent Verification, Chapter X of Department of Energy (DOE) Order 5480.19, ``Conduct of Operations Requirements for DOE Facilities.`` The practices in this guide should be considered when planning or reviewing independent verification activities. Contractors are advised to adopt procedures that meet the intent of DOE Order 5480.19. ``Independent Verification`` is an element of an effective Conduct of Operations program. The complexity and array of activities performed in DOE facilities dictate the necessity for coordinated independent verification activities to promote safe and efficient operations.

Not Available

1993-06-01T23:59:59.000Z

252

Guide to good practices for independent verification  

SciTech Connect (OSTI)

This Guide to Good Practices is written to enhance understanding of, and provide direction for, Independent Verification, Chapter X of Department of Energy (DOE) Order 5480.19, Conduct of Operations Requirements for DOE Facilities.'' The practices in this guide should be considered when planning or reviewing independent verification activities. Contractors are advised to adopt procedures that meet the intent of DOE Order 5480.19. Independent Verification'' is an element of an effective Conduct of Operations program. The complexity and array of activities performed in DOE facilities dictate the necessity for coordinated independent verification activities to promote safe and efficient operations.

Not Available

1993-06-01T23:59:59.000Z

253

Guide to good practices for independent verification  

SciTech Connect (OSTI)

This Guide to Good Practices is written to enhance understanding of, and provide direction for, Independent Verification, Chapter X of Department of Energy (DOE) Order 5480.19, Conduct of Operations Requirements for DOE Facilities. The practices in this guide should be considered when planning or reviewing independent verification activities. Contractors are advised to adopt procedures that meet the intent of DOE Order 5480.19. Independent Verification is an element of an effective Conduct of Operations program. The complexity and array of activities performed in DOE facilities dictate the necessity for coordinated independent verification activities to promote safe and efficient operations.

NONE

1998-12-01T23:59:59.000Z

254

Superior Energy Performance Measurement and Verification Protocol...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

and Verification Protocol for Industry (November 2012) More Documents & Publications Energy Intensity Baselining and Tracking Guidance EnPI V4.0 Tool Algorithm Superior Energy...

255

CRAD, Radiological Controls - Oak Ridge National Laboratory TRU...  

Broader source: Energy.gov (indexed) [DOE]

Radiological Controls - Oak Ridge National Laboratory TRU ALPHA LLWT Project CRAD, Radiological Controls - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 A...

256

Unified Resolve 2014: A Proof of Concept for Radiological Support...  

Office of Environmental Management (EM)

Unified Resolve 2014: A Proof of Concept for Radiological Support to Incident Commanders Unified Resolve 2014: A Proof of Concept for Radiological Support to Incident Commanders...

257

VERIFICATION SURVEY OF THE BAKER AND WILLIAMS WAREHOUSES  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C.Greentnv~ronmenrar ivronrrorrng L V ~ / O U U ~~

258

Oak Ridge Associated VERIFICATION SURVEY Universities OF THE  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C. 20545 OCT 28 1% - :NEW;ORAU 89/K-79 Prepared by

259

ENERGY STAR Test Procedures and Verification | Department of...  

Energy Savers [EERE]

ENERGY STAR ENERGY STAR Test Procedures and Verification ENERGY STAR Test Procedures and Verification The Department of Energy (DOE) is the lead agency in the development and...

260

DOE Verification Testing in Support of ENERGY STAR, April 22...  

Broader source: Energy.gov (indexed) [DOE]

the Energy Star Verification Testing Program Comment submitted by the Association of Home Appliance Manufacturers (AHAM) regarding the Energy Star Verification Testing Program...

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

ORO Verification of Employment Tracking System(VETS) PIA, Oak...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Verification of Employment Tracking System(VETS) PIA, Oak ridge Operations Office ORO Verification of Employment Tracking System(VETS) PIA, Oak ridge Operations Office ORO...

262

Developing an Evaluation Measurement and Verification Plan for...  

Broader source: Energy.gov (indexed) [DOE]

and Verification Plan for Your Energy Efficiency ProjectProgram Developing an Evaluation Measurement and Verification Plan for Your Energy Efficiency ProjectProgram...

263

CARB Verification of Catalyzed Diesel Particulate Filters for...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

CARB Verification of Catalyzed Diesel Particulate Filters for Emergency Generator Sets CARB Verification of Catalyzed Diesel Particulate Filters for Emergency Generator Sets 2005...

264

ADDRESSING PROCESS PLANNING AND VERIFICATION ISSUES WITH MTCONNECT  

E-Print Network [OSTI]

Surfaces in the Cybercut Process Planning Pipeline”, Trans.ADDRESSING PROCESS PLANNING AND VERIFICATION ISSUES WITHInc. Big Lake, MN KEYWORDS Process planning verification,

Vijayaraghavan, Athulan; Dornfeld, David; Artisanal Software; Remmele Engineering Inc.

2009-01-01T23:59:59.000Z

265

Lessons Learned from Independent Verification Activities  

Broader source: Energy.gov [DOE]

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

266

The monitoring and verification of nuclear weapons  

SciTech Connect (OSTI)

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.

Garwin, Richard L., E-mail: RLG2@us.ibm.com [IBM Fellow Emeritus, IBM Thomas J. Watson Research Center, P.O. Box 218, Yorktown Heights, NY 10598 (United States)

2014-05-09T23:59:59.000Z

267

Verification after Synthesis Alan Mishchenko Robert Brayton  

E-Print Network [OSTI]

in verification based on BDDs, SAT, and AIGs (And-Inverter Graphs), these results do not readily transfer to large are necessary to advance both synthesis and verification. We propose a methodology for scalable sequential it by a functionally equivalent one (up to complementation of outputs). (2) Retiming changes the positions of one

Brayton, Robert K.

268

Quantum Money with Classical Verification Dmitry Gavinsky  

E-Print Network [OSTI]

Quantum Money with Classical Verification Dmitry Gavinsky NEC Laboratories America, Inc. Princeton, NJ, U.S.A. Abstract 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

Gavinsky, Dmitry

269

Technical Documentation and Verification for the  

E-Print Network [OSTI]

PNNL-15202 Technical Documentation and Verification for the Buildings Module in the Visual Sample://www.ntis.gov/ordering.htm This document was printed on recycled paper. (9/2003) #12;PNNL-15202 Technical Documentation and Verification ...................................................................... 1 2.0 Documentation of Statistical Methods and Computations

270

Integrating pathology and radiology disciplines: an emerging opportunity?  

E-Print Network [OSTI]

Pediatric vascular malformations: pathophysiology, diagnosis, and the role of interventional radiology.

Sorace, James; Aberle, Denise R; Elimam, Dena; Lawvere, Silvana; Tawfik, Ossama; Wallace, W Dean

2012-01-01T23:59:59.000Z

271

Remaining Sites Verification Package for the 600-111, P-11 Critical Mass Laboratory Crib, and UPR-600-16, Fire and Contamination Spread Waste Sites, Waste Site Reclassification Form 2008-045  

SciTech Connect (OSTI)

The UPR-600-16, Fire and Contamination Spread waste site is an unplanned release that occurred on December 4, 1951, when plutonium contamination was spread by a fire that ignited inside the 120 Experimental Building. The 120 Experimental Building was a laboratory building that was constructed in 1949 and used for plutonium criticality studies as part of the P-11 Project. In November 1951, a criticality occurred in the 120 Experimental Building that resulted in extensive plutonium contamination inside the building. The confirmatory evaluation supports a reclassification of this site to Interim Closed Out. The current site conditions achieve the remedial action objectives and the corresponding remedial action goals established in the Remaining Sites ROD. The results of the extensive radiological survey of the surface soil and the confirmatory and verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

J. M. Capron

2008-10-28T23:59:59.000Z

272

Confirmatory Survey for the Partial Site Release at the ABB Inc. CE Winsor Site, Windsor, CT  

SciTech Connect (OSTI)

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.

W.C. Adams

2008-06-27T23:59:59.000Z

273

The Health Physics and Radiological Health  

E-Print Network [OSTI]

of the nuclear data required to compute this constant is available (Kocher 1981) for approximately 500 nuclides important to dosimetry and radiological assessment applications, and it has been used to compute a table

274

Radiological safety training for uranium facilities  

SciTech Connect (OSTI)

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.

NONE

1998-02-01T23:59:59.000Z

275

Apparatus for safeguarding a radiological source  

DOE Patents [OSTI]

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.

Bzorgi, Fariborz M

2014-10-07T23:59:59.000Z

276

CRAD, Radiological Controls - Idaho Accelerated Retrieval Project...  

Broader source: Energy.gov (indexed) [DOE]

Accelerated Retrieval Project Phase II CRAD, Radiological Controls - Idaho Accelerated Retrieval Project Phase II February 2006 A section of Appendix C to DOE G 226.1-2 "Federal...

277

Assessment of the radiological impact of a decommissioning nuclear power plant in Italy  

E-Print Network [OSTI]

The assessment of the radiological impact of a decommissioning Nuclear Power Plant is presented here through the results of an environmental monitoring survey carried out in the area surrounding the Garigliano Power Plant. The levels of radioactivity in soil, water, air and other environmental matrices are shown, in which {\\alpha}, {\\beta} and {\\gamma} activity and {\\gamma} equivalent dose rate are measured. Radioactivity levels of the samples from the Garigliano area are analyzed and then compared to those from a control zone situated more than 100 km away. Moreover, a comparison is made with a previous survey held in 2001. The analyses and comparisons show no significant alteration in the radiological characteristics of the area surroundings the plant, with an overall radioactivity depending mainly from the global fallout and natural sources.

A. Petraglia; C. Sabbarese; M. De Cesare; N. De Cesare; F. Quinto; F. Terrasi; A. D'Onofrio; P. Steier; L. K. Fifield; A. M. Esposito

2012-07-17T23:59:59.000Z

278

Assessment of the radiological impact of a decommissioning nuclear power plant in Italy  

E-Print Network [OSTI]

The assessment of the radiological impact of a decommissioning Nuclear Power Plant is presented here through the results of an environmental monitoring survey carried out in the area surrounding the Garigliano Power Plant. The levels of radioactivity in soil, water, air and other environmental matrices are shown, in which {\\alpha}, {\\beta} and {\\gamma} activity and {\\gamma} equivalent dose rate are measured. Radioactivity levels of the samples from the Garigliano area are analyzed and then compared to those from a control zone situated more than 100 km away. Moreover, a comparison is made with a previous survey held in 2001. The analyses and comparisons show no significant alteration in the radiological characteristics of the area surroundings the plant, with an overall radioactivity depending mainly from the global fallout and natural sources.

Petraglia, A; De Cesare, M; De Cesare, N; Quinto, F; Terrasi, F; D'Onofrio, A; Steier, P; Fifield, L K; Esposito, A M; 10.1051/radiopro/2012010

2012-01-01T23:59:59.000Z

279

US Department of Energy Radiological Control Manual  

SciTech Connect (OSTI)

This manual establishes practices for the conduct of radiological control activities. The Manual states DOE`s positions and views on the best courses of action currently available in the area of radiological controls. Accordingly, the provisions in the Manual should be viewed by contractors as an acceptable technique, method or solution for fulfilling their duties and responsibilities. This Manual shall be used by DOE in evaluating the performance of its contractors. (VC)

Not Available

1992-06-01T23:59:59.000Z

280

US Department of Energy Radiological Control Manual  

SciTech Connect (OSTI)

This manual establishes practices for the conduct of radiological control activities. The Manual states DOE's positions and views on the best courses of action currently available in the area of radiological controls. Accordingly, the provisions in the Manual should be viewed by contractors as an acceptable technique, method or solution for fulfilling their duties and responsibilities. This Manual shall be used by DOE in evaluating the performance of its contractors. (VC)

Not Available

1992-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Radiological Assessment for the Vance Road Facility Source Vault, Oak Ridge Institute for Science and Education, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

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.

J. R. Morton

2000-09-01T23:59:59.000Z

282

Contained radiological analytical chemistry module  

DOE Patents [OSTI]

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.

Barney, David M. (Scotia, NY)

1989-01-01T23:59:59.000Z

283

Contained radiological analytical chemistry module  

DOE Patents [OSTI]

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.

Barney, David M. (Scotia, NY)

1990-01-01T23:59:59.000Z

284

verification  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review of theOFFICE OF8/%2A ennike6/%2A en NGSI Safeguards by

285

CONFIRMATORY SURVEY OF THE DEFENSE LOGISTICS AGENCY, DEFENSE NATIONAL STOCKPILE CENTER NEW HAVEN DEPOT, NEW HAVEN, INDIANA  

SciTech Connect (OSTI)

The objectives of the radiological confirmatory survey were to collect adequate radiological data for use in evaluating the radiological condition of NHD land areas, warehouses, and support buildings. The data generated from the confirmatory survey activities were used to evaluate the results of the Final Status Survey Report (FSSR) submitted by Cabrera Services (Cabrera 2009). Cabrera has stated that all radioactive materials have been removed and that remediation of the open land areas and structure surfaces was complete, and that the NHD meets the criteria for unrestricted use.

E.M. Harpenau

2010-02-19T23:59:59.000Z

286

An evaluation of the management system verification pilot at Hanford  

SciTech Connect (OSTI)

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.

BRIGGS, C.R.

1998-11-12T23:59:59.000Z

287

RENEWABLES PORTFOLIO STANDARD 2005 PROCUREMENT VERIFICATION  

E-Print Network [OSTI]

CALIFORNIA ENERGY COMMISSION RENEWABLES PORTFOLIO STANDARD 2005 PROCUREMENT VERIFICATION RENEWABLES COMMITTEE John L. Geesman Presiding Member Jackalyne Pfannenstiel Associate Member B.B. Blevins Executive Director Jason Orta Heather Raitt Principal Authors Mark Hutchison Manager RENEWABLE ENERGY OFFICE

288

Runtime verification of object lifetime specifications  

E-Print Network [OSTI]

This thesis reports on the implementation of a runtime verification system for object lifetime specifications. This system is used to explore and evaluate the expressiveness object lifetime specifications. Object lifetime ...

Benjamin, Zev (Zev A.)

2009-01-01T23:59:59.000Z

289

The Mechanized Verification of Garbage Collector Implementations  

E-Print Network [OSTI]

Abstract The Mechanized Verification of Garbage Collector Implementations Andrew Evan Mc complex, requiring a garbage collector. Garbage collectors are becoming increasingly sophis- ticated to adapt them to high-performance, concurrent and real-time applications, making internal collector

290

Visual inspection for CTBT verification  

SciTech Connect (OSTI)

On-site visual inspection will play an essential role in future Comprehensive Test Ban Treaty (CTBT) verification. Although seismic and remote sensing techniques are the best understood and most developed methods for detection of evasive testing of nuclear weapons, visual inspection can greatly augment the certainty and detail of understanding provided by these more traditional methods. Not only can visual inspection offer ``ground truth`` in cases of suspected nuclear testing, but it also can provide accurate source location and testing media properties necessary for detailed analysis of seismic records. For testing in violation of the CTBT, an offending party may attempt to conceal the test, which most likely will be achieved by underground burial. While such concealment may not prevent seismic detection, evidence of test deployment, location, and yield can be disguised. In this light, if a suspicious event is detected by seismic or other remote methods, visual inspection of the event area is necessary to document any evidence that might support a claim of nuclear testing and provide data needed to further interpret seismic records and guide further investigations. However, the methods for visual inspection are not widely known nor appreciated, and experience is presently limited. Visual inspection can be achieved by simple, non-intrusive means, primarily geological in nature, and it is the purpose of this report to describe the considerations, procedures, and equipment required to field such an inspection.

Hawkins, W.; Wohletz, K.

1997-03-01T23:59:59.000Z

291

Monitoring and verification R&D  

SciTech Connect (OSTI)

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.

Pilat, Joseph F [Los Alamos National Laboratory; Budlong - Sylvester, Kory W [Los Alamos National Laboratory; Fearey, Bryan L [Los Alamos National Laboratory

2011-01-01T23:59:59.000Z

292

CONFIRMATORY SURVEY REPORT FOR THE SECTION 4 AREA AT THE RIO ALGOM AMBROSIA LAKE FACILITY NEW MEXICO  

SciTech Connect (OSTI)

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.

W.C. Adams

2010-02-12T23:59:59.000Z

293

GTRI's Nuclear and Radiological Material Removal | National Nuclear...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

and permanently disposing of excess, disused, unwanted, or abandoned radiological material overseas. This includes the recovery of Russian radioisotope thermoelectric...

294

E-Print Network 3.0 - arms aerial radiological Sample Search...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

General Diagnostic Radiology * Clinical Rotation Breast Imaging... * Clinical Rotation Pediatric Radiology * Clinical Rotation Nuclear Medicine Semester ... Source: VandeVord,...

295

E-Print Network 3.0 - anticipated radiological dose Sample Search...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

- thropomorphic models. II. Organ doses from computed tomographic examinations in pediatric radiology. Neuherberg... dose at CT in pediatric patients. Radiology...

296

Environmental Health & Safety Office of Radiological Safety  

E-Print Network [OSTI]

Environmental Health & Safety Office of Radiological Safety Page 1 of 2 FORM LU-1 Revision 01 1 safety training and submit this registration to the LSO prior to use of Class 3B or 4 lasers. A copy will be returned to the Laser Supervisor to be filed in the Laboratory Laser Safety Notebook. Both the Laser

Houston, Paul L.

297

Nuclear Engineering Catalog 2013 Radiological Concentration  

E-Print Network [OSTI]

Nuclear Engineering Catalog 2013 Radiological Concentration Fall Math 141 or 147 (4) FA, SP, SU-approved by the department. Courses in Nuclear Engineering other than 500, 502 or 598 may also be used as technical electives on academic performance. Factors considered include overall grade point average, performance in selescted

Tennessee, University of

298

Nuclear Engineering Catalog 2014 Radiological Concentration  

E-Print Network [OSTI]

Nuclear Engineering Catalog 2014 Radiological Concentration Fall Math 141 or 147 (4) FA, SP, SU-approved by the department. Courses in Nuclear Engineering other than 500, 502 or 598 may also be used as technical electives. No more than four (4) credit hours of nuclear engineering courses in which a C- or lower is the highest

Grissino-Mayer, Henri D.

299

A Tutorial on Text-Independent Speaker Verification  

E-Print Network [OSTI]

This paper presents an overview of a state-of-the-art text-independent speaker verification system. First, an introduction proposes a modular scheme of the training and test phases of a speaker verification system. Then, ...

Bimbot, Frederic

300

MODELING, VERIFICATION AND OPTIMIZATION OF HYBRID GROUND SOURCE HEAT PUMP  

E-Print Network [OSTI]

MODELING, VERIFICATION AND OPTIMIZATION OF HYBRID GROUND SOURCE HEAT PUMP SYSTEMS IN ENERGYPLUS, VERIFICATION AND OPTIMIZATION OF HYBRID GROUND SOURCE HEAT PUMP SYSTEMS IN ENERGYPLUS Thesis Approved by: Dr.................................................................................................................... 16 MODELING OF HYBRID GROUND SOURCE HEAT PUMP SYSTEMS IN ENERGYPLUS

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Measurement and Verification for Commissioning Projects: Challenges and Opportunities  

E-Print Network [OSTI]

ESL-IC-10/05-49 1 Measurement and Verification for Commissioning Projects: Challenges and Opportunities Kristin Heinemeier, Ph.D., P.E. Portland Energy Conservation, Inc., Sacramento CA Measurement and Verification (M&V) is a key...

Heinemeier, K.

2005-01-01T23:59:59.000Z

302

Plug-and-Play Architectural Design and Verification  

E-Print Network [OSTI]

uses finite-state verification techniques (e.g., SPIN [17], SMV [19], LTSA [22], FLAVERS [10]) to check

Massachusetts at Amherst, University of

303

Radiological assessment of residues from uranium and other ore mining and processing - A precondition for decisions on remedial measures  

SciTech Connect (OSTI)

In certain parts of Eastern Germany relics of uranium mining and milling as well as of traditional ore mining and processing may contribute to the environmental contamination and the radiation exposure of the public. Systematic investigations of the situation are the indispensable prerequisite for decisions upon the radiological relevance and remedial actions. In view of the large number and scattering of relics under consideration, a stepwise procedure with increasing intensity of investigation was developed to solve the task effectively and in an appropriate time. For the radiological evaluation following the steps of investigation generic criteria were derived. They are based on a primary reference dose of level (1 mSv/year) and on measureable radioactivity quantities recommend by the German Commission on Radiological Protection for unrestricted/restricted release of contaminated grounds. Applying the criteria established for the verification (gamma dose rate, volume of disposed material, area affected by waste materials) the investigations led to the result that no more than 30% of the objects of former mining have to be classified as {open_quotes}possibly relevant{close_quotes} and have to be investigated further on.

Ettenhuber, E; Roehnsch, W. [Bundesamt fuer Strahlenschutz, Berlin (Germany); Biesold, H. [Gesellschaft fuer Anlagen- und Reaktorsicherheit, Colonge (Germany)

1994-12-31T23:59:59.000Z

304

Active alignment/contact verification system  

DOE Patents [OSTI]

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.

Greenbaum, William M. (Modesto, CA)

2000-01-01T23:59:59.000Z

305

STATE OF CALIFORNIA CERTIFICATE OF FIELD VERIFICATION AND DIAGNOSTIC TESTING  

E-Print Network [OSTI]

-MECH-25 Refrigerant Charge Verification ­ Standard Measurement Procedure (Page 1 of 6) Site Address of a Charge Indicator Display (CID) is utilized as an alternative to refrigerant charge verification compliance with the refrigerant charge verification requirement. TMAH and STMS are not required

306

Paint for detection of radiological or chemical agents  

DOE Patents [OSTI]

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.

Farmer, Joseph C. (Tracy, CA); Brunk, James L. (Martinez, CA); Day, Sumner Daniel (Danville, CA)

2010-08-24T23:59:59.000Z

307

Measurement and Verification (M&V)  

E-Print Network [OSTI]

5. Continuous Commissioning Measures 6. Measurement and Verification 2 ESL-KT-14-11-39 CATEE 2014: Clean Air Through Efficiency Conference, Dallas, Texas Nov. 18-20 Measurement and Verification (M&V) Joseph T. Martinez, PCC Carlos Yagua, PE Hiroko...Workshop on the Continuous Commissioning® Process Joseph T. Martinez, PCC Carlos Yagua, PE Hiroko Masuda, Juan-Carlos Baltazar, PhD, PE Ahmet Ugursal, PhD Clean Air Through Energy Efficiency (CATEE) Conference, Dallas, Texas. November 18, 2014...

Masuda, H

2014-01-01T23:59:59.000Z

308

Fuel Retrieval System Design Verification Report  

SciTech Connect (OSTI)

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).

GROTH, B.D.

2000-04-11T23:59:59.000Z

309

CONFIRMATORY SURVEY OF THE FUEL OIL TANK AREA HUMBOLDT BAY POWER PLANT EUREKA, CALIFORNIA  

SciTech Connect (OSTI)

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.

WADE C. ADAMS

2012-04-09T23:59:59.000Z

310

Independent Confirmatory Survey Summary and Results for the Plum Brook Reactor Facility Sandusky OH  

SciTech Connect (OSTI)

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.

E.N. Bailey

2008-05-06T23:59:59.000Z

311

Results of radiological measurements taken in the Niagara Falls, New York, area (NF002)  

SciTech Connect (OSTI)

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.

Williams, J.K.; Berven, B.A.

1986-11-01T23:59:59.000Z

312

NV/YMP RADIOLOGICAL CONTROL MANUAL  

SciTech Connect (OSTI)

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.

U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE; BECHTEL NEVADA

2004-11-01T23:59:59.000Z

313

Formal Verification of SpecC Programs  

E-Print Network [OSTI]

;Outline 1. Old work: Bounded Model Checking for ANSI-C 2. Verification of concurrent ANSI-C programs using Predicate Abstraction SpecC Overview Abstraction Refinement 3. Current work: Hybrid Models #12;ANSI into equation Check equation using SAT Advantages: Completely automated Allows full set of ANSI-C, including

Saranlý, Uluç

314

RELAP-7 SOFTWARE VERIFICATION AND VALIDATION PLAN  

SciTech Connect (OSTI)

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.

Smith, Curtis L [Idaho National Laboratory; Choi, Yong-Joon [Idaho National Laboratory; Zou, Ling [Idaho National Laboratory

2014-09-01T23:59:59.000Z

315

EXPERIMENTAL VERIFICATION OF DYNAMIC OPERATION OF  

E-Print Network [OSTI]

- ponent mixtures can be separated into a number of product fractions, whereas in continuous distillationEXPERIMENTAL VERIFICATION OF DYNAMIC OPERATION OF CONTINUOUS AND MULTIVESSEL BATCH DISTILLATION to the paper "Evaluation of Dynamic Models of Distillation Columns with Emphasis on the Initial Response

Skogestad, Sigurd

316

Hybrid Systems: From Verification to Falsification  

E-Print Network [OSTI]

Hybrid Systems: From Verification to Falsification Erion Plaku, Lydia E. Kavraki, and Moshe Y}@cs.rice.edu Abstract. We propose HyDICE, Hybrid DIscrete Continuous Exploration, a multi­layered approach for hybrid. The discrete search uses the discrete transitions of the hybrid system and coarse­grained decompositions

Vardi, Moshe Y.

317

Hybrid Systems: From Verification to Falsification  

E-Print Network [OSTI]

Hybrid Systems: From Verification to Falsification Erion Plaku, Lydia E. Kavraki, and Moshe Y}@cs.rice.edu Abstract. We propose HyDICE, Hybrid DIscrete Continuous Exploration, a multi-layered approach for hybrid. The discrete search uses the discrete transitions of the hybrid system and coarse-grained decompositions

Kavraki, Lydia E.

318

SAVCBS 2003 Specification and Verification of  

E-Print Network [OSTI]

://www.cs.iastate.edu/SAVCBS/ September 1-2, 2003 Helsinki, Finland Workshop at ESEC/FSE 2003 9th European Software Engineering ConferenceSAVCBS 2003 Specification and Verification of Component-Based Systems ESEC/FSE 2003 9th European Software Engineering Conference and 11th ACM SIGSOFT Symposium on the Foundations of Software Engineering

Leavens, Gary T.

319

Compositional Algorithmic Verification of Software Product Lines  

E-Print Network [OSTI]

, and Siavash Soleimanifard2 1 Technische Universit¨at Braunschweig, Germany i.schaefer@tu-braunschweig.de 2 Royal Institute of Technology, Stockholm, Sweden {dilian,siavashs}@csc.kth.se Abstract. Software product expressiveness and a clean and simple model suitable for compositional verification. We generalize a previously

Gurov, Dilian

320

Nevada National Security Site Radiological Control Manual  

SciTech Connect (OSTI)

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 low-level radioactive waste and the handling of radioactive sources. Remediation of contaminated land areas may also result in radiological exposures.

Radiological Control Managers’ Council

2012-03-26T23:59:59.000Z

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Fixation of Radiological Contamination; International Collaborative Development  

SciTech Connect (OSTI)

A cooperative international project was conducted by the Idaho National Laboratory (INL) and the United Kingdom’s 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.

Rick Demmer

2013-03-01T23:59:59.000Z

322

ORISE: Radiological Assessment and Monitoring System (RAMS)  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratory |CHEMPACK MappingHistoryMedicalInternationalRadiological

323

Radiological standards and calibration laboratory capabilities  

SciTech Connect (OSTI)

The Radiological Standards and Calibrations Laboratory, a part of Pacific Northwest Laboratory (PNL), performs calibrations and upholds reference standards necessary to maintain traceability to national radiological standards. The facility supports U.S. Department of Energy (DOE) programs at the Hanford Site, programs sponsored by DOE Headquarters and other federal agencies, radiological protection programs at other DOE sites, and research programs sponsored through the commercial sector. The laboratory is located in the 318 Building of the Hanford Site`s 300 Area. The facility contains five major exposure rooms and several laboratories used for exposure work preparation, low-activity instrument calibrations, instrument performance evaluations, instrument maintenance, instrument design and fabrication work, and thermoluminescent and radiochromic dosimetry. The major exposure facilities are a low-scatter room used for neutron and photon exposures, a source well room used for high-volume instrument calibration work, an x-ray facility used for energy response studies, a high-exposure facility used for high-rate photon calibration work, and a beta standards laboratory used for beta energy response studies and beta reference calibrations. Calibrations are routinely performed for personnel dosimeters, health physics instrumentations, photon transfer standards and alpha, beta and gamma field sources used throughout the Hanford Site. This report describes the standards and calibrations laboratory. Photographs that accompany the text appear in the Appendix and are designated Figure A.1 through A.29.

Goles, R.W.

1995-01-01T23:59:59.000Z

324

Evolutionary Test Program Induction for Microprocessor Design Verification Fulvio Corno, Gianluca Cumani, Matteo Sonza Reorda, Giovanni Squillero  

E-Print Network [OSTI]

Evolutionary Test Program Induction for Microprocessor Design Verification Fulvio Corno, Gianluca is an assembly program able to maximize a predefined verification metric. Design verification of on-chip

Fernandez, Thomas

325

Data Summary Report for the Semiannual Tritium Survey for Fourmile Branch and the F- and H-Area Seeplines  

SciTech Connect (OSTI)

This report presents a summary of the definitive data validation and verification for the Semiannual Tritium Survey for Fourmile Branch and the F- and H-Area Seeplines. The survey was performed at the request of the WSRC ERD and conducted by WSRC/ESS. This report was prepared under the direction of EPD/EMS.

Koch, J. II [Westinghouse Savannah River Company, AIKEN, SC (United States) Exploration Resources

1996-12-16T23:59:59.000Z

326

Federal Radiological Monitoring and Assessment Center Monitoring Manual Volume 1, Operations  

SciTech Connect (OSTI)

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.

NSTec Aerial Measurement Systems

2012-07-31T23:59:59.000Z

327

Radiological and Nuclear Security in A Global Context  

E-Print Network [OSTI]

This paper considers the state of nuclear and radiological security in the UK and abroad and reports on the methods that could be employed by terrorists with radiological or nuclear material to cause destruction. It is shown that despite current safeguards that problems arise due to materials that are unaccounted for and poor implementation of detection regimes in some geographical regions. The prospect of a future terrorist event that involves nuclear or radiological materials seems likely despite best efforts of prevention.

Jones, Nick

2010-01-01T23:59:59.000Z

328

Rev. 04/2014: JAB Environmental and Radiological Health Sciences  

E-Print Network [OSTI]

Rev. 04/2014: JAB Environmental and Radiological Health Sciences Academic Policies, Guidelines....................................................................................................................... 3 Plan A Master of Science Program......................................................................................... 3 Plan B Master of Science Program

329

CRAD, Radiological Controls - Oak Ridge National Laboratory High...  

Broader source: Energy.gov (indexed) [DOE]

Oak Ridge National Laboratory High Flux Isotope Reactor CRAD, Radiological Controls - Oak Ridge National Laboratory High Flux Isotope Reactor February 2007 A section of Appendix C...

330

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

Office of Environmental Management (EM)

Response to Radiological Transportation Incidents.docx More Documents & Publications TEPP Model Needs Assessment Document First Responder Initial Response Procedure Hazardous...

331

NGSI: IAEA Verification of UF6 Cylinders  

SciTech Connect (OSTI)

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.

Curtis, Michael M.

2012-06-05T23:59:59.000Z

332

Conceptual design. Final report: TFE Verification Program  

SciTech Connect (OSTI)

This report documents the TFE Conceptual Design, which provided the design guidance for the TFE Verification program. The primary goals of this design effort were: (1) establish the conceptual design of an in-core thermionic reactor for a 2 Mw(e) space nuclear power system with a 7-year operating lifetime; (2) demonstrate scalability of the above concept over the output power range of 500 kW(e) to 5 MW(e); and (3) define the TFE which is the basis for the 2 MW (e) reactor design. This TFE specification provided the basis for the test program. These primary goals were achieved. The technical approach taking in the conceptual design effort is discussed in Section 2, and the results are discussed in Section 3. The remainder of this introduction draws a perspective on the role that this conceptual design task played in the TFE Verification Program.

Not Available

1994-03-01T23:59:59.000Z

333

GRIMHX verification and validation action matrix summary  

SciTech Connect (OSTI)

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.

Trumble, E.F.

1991-12-01T23:59:59.000Z

334

Radiological hazards of alpha-contaminated waste  

SciTech Connect (OSTI)

The radiological hazards of alpha-contaminated wastes are discussed in this overview in terms of two components of hazard: radiobiological hazard, and radioecological hazard. Radiobiological hazard refers to human uptake of alpha-emitters by inhalation and ingestion, and the resultant dose to critical organs of the body. Radioecological hazard refers to the processes of release from buried wastes, transport in the environment, and translocation to man through the food chain. Besides detailing the sources and magnitude of hazards, this brief review identifies the uncertainties in their estimation, and implications for the regulatory process.

Rodgers, J.C.

1982-01-01T23:59:59.000Z

335

Radiological Threat Reduction | ornl.gov  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared at 278, 298, and 323Program AccomplishmentsScienceRadiological

336

Logic verification using recursive learning, ATPG and transformations  

E-Print Network [OSTI]

17 Example Circuits for Verification Showing an Existing Condi- tional Don't Care Condition. 33 18 Justification of the Conditional Don't Care Condition in the Ex- ample Circuits. FIGURE Page Transformation Using Conditional Don't Care Condition... of the Implementation Verification phase, sometimes it is termed Design Verification as in [17j. In this case the specification and design are both at logic level. Logic circuits can be combinational or sequential. If the circuits being compared are combinational, i...

Paul, Debjyoti

1996-01-01T23:59:59.000Z

337

SAT-based Verification for Analog and Mixed-signal Circuits  

E-Print Network [OSTI]

The wide application of analog and mixed-signal (AMS) designs makes the verification of AMS circuits an important task. However, verification of AMS circuits remains as a significant challenge even though verification techniques for digital circuits...

Deng, Yue

2012-07-16T23:59:59.000Z

338

Optimization Online - Termination and Verification for Ill-Posed ...  

E-Print Network [OSTI]

Jun 17, 2005 ... Termination and Verification for Ill-Posed Semidefinite Programming Problems. Christian Jansson (jansson ***at*** tu-harburg.de). Abstract: ...

Christian Jansson

2005-06-17T23:59:59.000Z

339

assertions based verification: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

A possible explanation is given. 1 SCIAMACHY'S PMD CHANNELS Graaf, Martin de 418 LTSA-WS: a tool for modelbased verification of web service compositions and choreography...

340

Thermal Hydraulic Modeling: Cross-Verification, Validation and...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Aleks Obabko, Paul Fischer, and Tim Tautges, Argonne National Laboratory Thermal Hydraulic Modeling: Cross-Verification, Validation and Co-design PI Name: Paul F. Fischer PI...

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Measurement and Verification of Low Income Energy Efficiency...  

Open Energy Info (EERE)

Low Income Energy Efficiency Programs in Brazil: Methodological Challenges Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Measurement and Verification of Low Income...

342

addressing verification challenges: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Kulyukin Computer Technologies and Information Sciences Websites Summary: A Cartesian Robot for RFID Signal Distribution Model Verification Aliasgar Kutiyanawala Vladimir (PRF)...

343

automated verification process: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Kulyukin Computer Technologies and Information Sciences Websites Summary: A Cartesian Robot for RFID Signal Distribution Model Verification Aliasgar Kutiyanawala Vladimir (PRF)...

344

Measurement and Verification, Best Practices in Design and Implementation  

E-Print Network [OSTI]

. Measurement?and? Verification,?Best?Practices? in?Design?and? Implementation Tom?Martin? CMVP,?LEED?AP Homay?Khatami? CEM,?LEED?AP PMP,?CMC? 1. Definition?of?Measurement?and?Verification?(M&V) 2. Applications?of?M&V 3. Specific.... Analyze?? Reporting M&V,?Best?Practices?in?Design?and?Implementation ?Measurement?and?Verification?is?the?process? of?using?measurements?to?reliably?determine? actual?savings? International?Performance?Measurement?and? Verification?Protocol?? Vol I...

Martin, T.; Khatami, H.

2013-01-01T23:59:59.000Z

345

Advanced Waste Management Now Available as Accredited SEP Verification...  

Broader source: Energy.gov (indexed) [DOE]

"Our auditing teams provide robust, independent confirmation that a facility conforms to ISO 50001 and has really improved its energy performance." SEP Verification Bodies...

346

NEMVP: North American energy measurement and verification protocol  

SciTech Connect (OSTI)

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.

NONE

1996-03-01T23:59:59.000Z

347

A golden anniversary for space-based treaty verification  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

enabled serendipitous discoveries of remarkable natural phenomena such as cosmic gamma-ray bursts, X-ray novae and solar wind composition. Modern space-based verification systems...

348

Nuclear and Radiological Forensics and Attribution Overview  

SciTech Connect (OSTI)

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.

Smith, D K; Niemeyer, S

2005-11-04T23:59:59.000Z

349

THE RABIT: A RAPID AUTOMATED BIODOSIMETRY TOOL FOR RADIOLOGICAL TRIAGE  

E-Print Network [OSTI]

. Health Phys. 98(2):209­217; 2010 Key words: biological indicators; dosimetry; blood; cytogenetics-priority need in an environment of heightened concern over possible radiological or nuclear terrorist attacks of radiological injuries. A small improvised nuclear device (IND) would produce a major health emergency

350

Current Trends in Gamma Ray Detection for Radiological Emergency Response  

SciTech Connect (OSTI)

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.

Mukhopadhyay, S., Guss, P., Maurer, R.

2011-08-18T23:59:59.000Z

351

FRMAC Interactions During a Radiological or Nuclear Event  

SciTech Connect (OSTI)

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.

Wong, C T

2011-01-27T23:59:59.000Z

352

Professor (Open Rank) Department of Nuclear, Plasma, and Radiological Engineering  

E-Print Network [OSTI]

Professor (Open Rank) Department of Nuclear, Plasma, and Radiological Engineering University of Illinois at Urbana-Champaign The Department of Nuclear, Plasma, and Radiological Engineering-qualified candidates with background in areas related to reactor power engineering and other nuclear applications

Ma, Yi

353

healthcare.utah.edu/radiology What is Nuclear Medicine?  

E-Print Network [OSTI]

expensive diagnostic tests or surgery. Tissues such as intestines, muscles, and blood vessels are difficulthealthcare.utah.edu/radiology Radiology What is Nuclear Medicine? Nuclear Medicine is a specialized to visualize on a standard X-ray. In Nuclear Medicine, a radioactive tracer is used so the tissue is seen more

Feschotte, Cedric

354

Radiological Assistance Program | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

NM; RAP Region 4 Chicago, IL; RAP Region 5 Idaho Falls, ID; RAP Region 6 Oakland, CA; RAP Region 7 Richland, WA; RAP Region 8 RAP team members surveying vehicles Each region...

355

Recovery from chemical, biological, and radiological incidents :  

SciTech Connect (OSTI)

To restore regional lifeline services and economic activity as quickly as possible after a chemical, biological or radiological incident, emergency planners and managers will need to prioritize critical infrastructure across many sectors for restoration. In parallel, state and local governments will need to identify and implement measures to promote reoccupation and economy recovery in the region. This document provides guidance on predisaster planning for two of the National Disaster Recovery Framework Recovery Support Functions: Infrastructure Systems and Economic Recovery. It identifies key considerations for infrastructure restoration, outlines a process for prioritizing critical infrastructure for restoration, and identifies critical considerations for promoting regional economic recovery following a widearea disaster. Its goal is to equip members of the emergency preparedness community to systematically prioritize critical infrastructure for restoration, and to develop effective economic recovery plans in preparation for a widearea CBR disaster.

Franco, David Oliver; Yang, Lynn I.; Hammer, Ann E.

2012-06-01T23:59:59.000Z

356

Verification of Probabilistic Real-time Systems Marta Kwiatkowska1  

E-Print Network [OSTI]

widely taken up (downloaded more than 20,000 times) and used for quan- titative verification in a broad of (priced) probabilistic timed automata. These model systems exhibiting probabilistic, nondeterministic-time characteristics, through support for verification of (priced) probabilistic timed automata. PRISM already provides

Oxford, University of

357

Modular Verification of Timed Circuits Using Automatic Abstraction  

E-Print Network [OSTI]

Modular Verification of Timed Circuits Using Automatic Abstraction Hao Zheng, Eric Mercer, Member for verification of timed circuits using automatic abstraction. This approach partitions the design into modules by the RAPPID instruction length decoder designed at Intel [2]. This design was 3 times faster while using only

Zheng, Hao

358

VIS Analyzer: A Visual Assistant for VIS Verification and Analysis  

E-Print Network [OSTI]

in demonstrating the quality of safety-critical [1] systems such as nuclear power plants. We have used the VIS necessary to understand the full verification scenario accurately. Many nuclear engineers and verification and analysis, which can help nuclear engineers take full benefits of VIS without being overwhelmed

359

History Effects and Verification Christian Skalka and Scott Smith  

E-Print Network [OSTI]

. Verification consists of checking to make sure that histories are well-formed, i.e. the sequence of eventsHistory Effects and Verification Christian Skalka and Scott Smith The University of Vermont skalka@cs.uvm.edu The Johns Hopkins University, scott@cs.jhu.edu Abstract. This paper shows how type effect systems can

Smith, Scott F.

360

First Eye Movement Verification and Identification Competition at BTAS 2012  

E-Print Network [OSTI]

First Eye Movement Verification and Identification Competition at BTAS 2012 Pawel Kasprowski11,ak26}@txstate.edu Abstract--This paper presents the results of the first eye movement verification and methods used in the competition. The results highlight the importance of very careful eye positional data

Oleg, Komogortsev - Department of Computer Science, Texas State University

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

LUNAR SEISMIC PROFILING EXPERIMENT DESIGN VERIFICATION THERMAL PAGI OF  

E-Print Network [OSTI]

of the Analytical Model with Test Data 50 1. 1 5. 1. 2 5. 1. 3 5. I. 4 Lunar Surface and Cold Wall to ExperimentATM 1109 LUNAR SEISMIC PROFILING EXPERIMENT DESIGN VERIFICATION THERMAL PAGI OF VACUUM TEST DATE 9 /1 5I 72 This ATM summarizes the LSPE Design Verification Thermal Vacuum Test of the prototype model

Rathbun, Julie A.

362

Fast 3D Scanning for Biometric Identification and Verification  

E-Print Network [OSTI]

Fast 3D Scanning for Biometric Identification and Verification June 2011 Authors Anselmo., & Chen, A. (2011). Fast 3D Scanning for Biometric Identification and Verification. (Prepared by RTI..................................................10 Summary and Findings for Integration of Imperceptible Structured Lighting and SIS's 3D Snapshot

McShea, Daniel W.

363

Power Grid Voltage Integrity Verification Department of ECE  

E-Print Network [OSTI]

Power Grid Voltage Integrity Verification Maha Nizam Department of ECE University of Toronto devgan@magma-da.com ABSTRACT Full-chip verification requires one to check if the power grid is safe, i.e., if the voltage drop on the grid does not exceed a cer- tain threshold. The traditional simulation-based solution

Najm, Farid N.

364

Software Verification in the Google App-Engine Cloud  

E-Print Network [OSTI]

resources. In the last years, cloud services emerged as an inexpensive, flexible, and energy for verification. We chose the platform-as-a-service offer Google App Engine and ported the open are available on demand. This enables a verification process that is less expensive (only actual usage is paid

Beyer, Dirk

365

Optimal combination of data verification and materials accountancy  

SciTech Connect (OSTI)

Materials accountancy accompanied by data verification is one of the main elements in international safeguards of nuclear material. In this paper statistical combinations of materials accountancy and data verification are discussed with the boundary condition of a fixed total false-alarm probability.

Beedgen, R.; Hafer, J.F.

1982-01-01T23:59:59.000Z

366

FORECAST VERIFICATION OF EXTREMES: USE OF EXTREME VALUE THEORY  

E-Print Network [OSTI]

1 FORECAST VERIFICATION OF EXTREMES: USE OF EXTREME VALUE THEORY Rick Katz Institute for Study ON EXTREMES · Emil Gumbel (1891 ­ 1966) -- Pioneer in application of statistics of extremes (Germany, France) Conventional Methods (3) Extreme Value Theory (EVT) (4) Application of EVT to Verification (5) Frost

Katz, Richard

367

Core analysis workstation development and verification  

SciTech Connect (OSTI)

An engineering workstation utilizing a three-dimensional reactor simulator along with a series of auxiliary programs has been developed for use in predicting core reactivity and power distributions. This workstation can be used by both core analysis and core operations personnel. Expected applications are power distribution analyses, technical specification limit verification, and various types of reactivity analyses. Reactor operations personnel can quickly simulate load follow or other reactor maneuvers and, through the interactive graphics capability of the personal computer, the reactor responses, such as power distribution and control rod position, can be displayed and understood by operations personnel.

Mays, C.W.; Kochendarfer, R.A.; Mays, B.E.

1987-01-01T23:59:59.000Z

368

PUC's New Evaluation, Measurement and Verification Framework  

E-Print Network [OSTI]

Clean Air Through Energy Efficiency Conference December 16-18, 2013 San Antonio, Texas ESL-KT-13-12-11 CATEE 2013: Clean Air Through Energy Efficiency Conference, San Antonio, Texas Dec. 16-18 Evaluation, Measurement & Verification in Texas... Pam Osterloh, Senior EE/DR Coordinator AEP Texas December 17, 2013 ESL-KT-13-12-11 CATEE 2013: Clean Air Through Energy Efficiency Conference, San Antonio, Texas Dec. 16-18 ? A few simple words…… ? 82nd Texas Legislative Session in 2011 ? PURA 39...

Osterloh, P.

2013-01-01T23:59:59.000Z

369

NREL: Wind Research - Field Verification Project  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the Contributions andData andFleet Test andField Verification Project The mission of the

370

Monitoring/Verification Using DMS: TATP Example  

SciTech Connect (OSTI)

Field-rugged and field-programmable differential mobility spectrometry (DMS) networks provide highly selective, universal monitoring of vapors and aerosols at detectable levels from persons or areas involved with illicit chemical/biological/explosives (CBE) production. CBE sensor motes used in conjunction with automated fast gas chromatography with DMS detection (GC/DMS) verification instrumentation integrated into situational operationsmanagement systems can be readily deployed and optimized for changing application scenarios. The feasibility of developing selective DMS motes for a “smart dust” sampling approach with guided, highly selective, fast GC/DMS verification analysis is a compelling approach to minimize or prevent the illegal use of explosives or chemical and biological materials. DMS is currently one of the foremost emerging technologies for field separation and detection of gas-phase chemical species. This is due to trace-level detection limits, high selectivity, and small size. GC is the leading analytical method for the separation of chemical species in complex mixtures. Low-thermal-mass GC columns have led to compact, low-power field systems capable of complete analyses in 15–300 seconds. A collaborative effort optimized a handheld, fast GC/DMS, equipped with a non-rad ionization source, for peroxide-based explosive measurements.

Kevin Kyle; Stephan Weeks

2008-03-01T23:59:59.000Z

371

Comment submitted by Traulsen regarding the Energy Star Verification Testing Program  

Broader source: Energy.gov [DOE]

This document is a comment submitted by Traulsen regarding the Energy Star Verification Testing Program

372

Comment submitted by Consumers Union regarding the Energy Star Verification Testing Program  

Broader source: Energy.gov [DOE]

This document is a comment submitted by Consumers Union regarding the Energy Star Verification Testing Program

373

Comment submitted by Whirlpool Corporation regarding the Energy Star Verification Testing Program  

Broader source: Energy.gov [DOE]

This document is a comment submitted by Whirlpool Corporation regarding the Energy Star Verification Testing Program

374

Energy Savings Performance Contracting-Savings Measurement and Verification Transcript 2-24-2011.doc  

Broader source: Energy.gov [DOE]

Energy Savings Performance Contracting-Savings Measurement and Verification Transcript 2-24-2011.doc

375

State and Local Energy Savings Performance Contracting: Savings Measurement and Verification (M&V)  

Broader source: Energy.gov [DOE]

State and Local Energy Savings Performance Contracting: Savings Measurement and Verification (M&V) Webinar.

376

Developing an Evaluation Measurement and Verification Plan for Your Energy Efficiency Project/Program  

Broader source: Energy.gov [DOE]

Developing an Evaluation Measurement and Verification Plan for Your Energy Efficiency Project/Program

377

Survey Statisticians  

Gasoline and Diesel Fuel Update (EIA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) " ,"Click worksheet9,1,50022,3,,,,6,1,,781 2,328AdministrationRelease ScheduleU.S.Survey Statisticians The

378

Bayesian Network Analysis of Radiological Dispersal Device Acquisitions  

E-Print Network [OSTI]

It remains unlikely that a terrorist organization could produce or procure an actual nuclear weapon. However, the construction of a radiological dispersal device (RDD) from commercially produced radioactive sources and conventional explosives could...

Hundley, Grant Richard

2012-02-14T23:59:59.000Z

379

A review of the radiological treatment  

SciTech Connect (OSTI)

The Draft Waste Management Programmatic Environmental Impact Statement (WM PEIS) was released by the U.S. Department of Energy (DOE) for public comment on September 22, 1995. Prepared in accordance with the National Environmental Policy Act (NEPA), the Final WM PEIS is currently scheduled for release in late summer 1996. The Draft WM PEIS was published after about 3 years of effort to select and evaluated the best alternatives for treating, storing, and disposing of the 50-year legacy of radioactive and chemically hazardous wastes existing within the DOE complex. The evaluation examined the potential health and environmental impacts of integrated waste management alternatives for five categories of waste types at 54 DOE sites. A primary consideration as a potential source of human health impacts at all sites is that of radiological releases resulting from postulated accidents involving facilities used to treat radioactive wastes. This paper first provides a brief, updated summary of the approach used to define and perform treatment facility accident analyses in the Draft WM PEIS. It reviews the selection of dominant sequences for the major sites most affected by the preferred waste management alternatives and highlights the salient accident analysis results. Finally, it summarizes and addresses key public and state and federal agency comments relating to accident analysis that were received in the public comment process.

Mueller, C.J.; Folga, S.; Nabelssi, B.; Kohout, E.

1996-07-01T23:59:59.000Z

380

Automated Verification of Practical Garbage Collectors  

E-Print Network [OSTI]

Garbage collectors are notoriously hard to verify, due to their low-level interaction with the underlying system and the general difficulty in reasoning about reachability in graphs. Several papers have presented verified collectors, but either the proofs were hand-written or the collectors were too simplistic to use on practical applications. In this work, we present two mechanically verified garbage collectors, both practical enough to use for real-world C# benchmarks. The collectors and their associated allocators consist of x86 assembly language instructions and macro instructions, annotated with preconditions, postconditions, invariants, and assertions. We used the Boogie verification generator and the Z3 automated theorem prover to verify this assembly language code mechanically. We provide measurements comparing the performance of the verified collector with that of the standard Bartok collectors on off-the-shelf C# benchmarks, demonstrating their competitiveness.

Hawblitzel, Chris

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Idaho National Engineering Laboratory Radiological Environmental Surveillance Program 1995 annual report  

SciTech Connect (OSTI)

This report describes calendar year 1995 environmental surveillance activities of Environmental Monitoring and Water Resources of Lockheed Martin Idaho Technologies Company, performed at the following Waste Management Facilities: the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and tow surplus facilities. Results of the sampling performed by the Radiological Environmental Surveillance Program, Site Environmental Surveillance Program, and the United States Geological Survey at these facilities are included in this report. The primary purposes of monitoring are to evaluate environmental conditions, to provide and interpret data, to verify compliance with applicable regulations or standards and to ensure protection of human health and the environment. This report compares 1995 environmental surveillance data with US DOE Derived Concentration Guides and with data form previous years.

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

1996-08-01T23:59:59.000Z

382

Operation Cornerstone onsite radiological safety report for announced nuclear tests, October 1988--September 1989  

SciTech Connect (OSTI)

Cornerstone was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site (NTS) from October 1, 1988, through September 30, 1989. This report includes those experiments publicly announced. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Radiation Protection Technicians (RPT) with portable radiation detection instruments surveyed reentry routes into ground zeros (GZ) before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage were provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined.

Not Available

1990-08-01T23:59:59.000Z

383

Ion mobility spectrometer, spectrometer analyte detection and identification verification system, and method  

DOE Patents [OSTI]

Methods and apparatus for ion mobility spectrometry and analyte detection and identification verification system are disclosed. The apparatus is configured to be used in an ion mobility spectrometer and includes a plurality of reactant reservoirs configured to contain a plurality of reactants which can be reacted with the sample to form adducts having varying ion mobilities. A carrier fluid, such as air or nitrogen, is used to carry the sample into the spectrometer. The plurality of reactants are configured to be selectively added to the carrier stream by use inlet and outlet manifolds in communication with the reagent reservoirs, the reservoirs being selectively isolatable by valves. The invention further includes a spectrometer having the reagent system described. In the method, a first reactant is used with the sample. Following a positive result, a second reactant is used to determine whether a predicted response occurs. The occurrence of the second predicted response tends to verify the existence of a component of interest within the sample. A third reactant can also be used to provide further verification of the existence of a component of interest. A library can be established of known responses of compounds of interest with various reactants and the results of a specific multi-reactant survey of a sample can be compared against the library to determine whether a component detected in the sample is likely to be a specific component of interest.

Atkinson, David A. (Idaho Falls, ID)

2002-01-01T23:59:59.000Z

384

IT Licentiate theses Practical Verification of Real-Time Systems  

E-Print Network [OSTI]

IT Licentiate theses 2001-013 Practical Verification of Real-Time Systems ALEXANDRE DAVID UPPSALA UPPSALA SWEDEN Dissertation for the degree of Licentiate of Philosophy in Computer Science at Uppsala

David, Alexandre

385

IT Licentiate theses Practical Verification of RealTime Systems  

E-Print Network [OSTI]

IT Licentiate theses 2001­013 Practical Verification of Real­Time Systems ALEXANDRE DAVID UPPSALA UPPSALA SWEDEN Dissertation for the degree of Licentiate of Philosophy in Computer Science at Uppsala

David, Alexandre

386

INL/EXT-14-33201 RELAP-7 Software Verification  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

01 RELAP-7 Software Verification and Validation Plan Curtis L. Smith Yong-Joon Choi Ling Zou September 25, 2014 NOTICE This report was prepared as an account of work sponsored by...

387

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

Broader source: Energy.gov (indexed) [DOE]

M&V Guidelines: Measurement and Verifi cation for Federal Energy Projects Version 3.0 M&V Guidelines: Measurement and Verification for Federal Energy Projects Version 3.0 Prepared...

388

A Methodology for Automated Verification of Rosetta Specification Transformations  

E-Print Network [OSTI]

particular semantic vocabulary and modeling style. The following dissertation proposes a framework, semantics and methodology for automated verification of safety preservation over specification transformations between domains. Utilizing the ideas of lattice...

Lohoefener, Jennifer Lee

2011-04-11T23:59:59.000Z

389

Process Abstraction in the Verification of Temporal Properties   

E-Print Network [OSTI]

as abstraction operations. We show that an abstract process satisfies a property expressed as a temporal logic formula just if the original process satisfies a transformed formula. We define various abstraction operators and illustrate their use in verification...

Bruns, Glen R

390

How to deal with radiologically contaminated vegetation  

SciTech Connect (OSTI)

This report describes the findings from a literature review conducted as part of a Department of Energy, Office of Technology Development Biomass Remediation Task. The principal objective of this project is to develop a process or group of processes to treat radiologically contaminated vegetation in a manner that minimizes handling, processing, and treatment costs. Contaminated, woody vegetation growing on waste sites at SRS poses a problem to waste site closure technologies that are being considered for these sites. It is feared that large sections of woody vegetation (logs) can not be buried in waste sites where isolation of waste is accomplished by capping the site. Logs or large piles of woody debris have the potential of decaying and leaving voids under the cap. This could lead to cap failure and entrance of water into the waste. Large solid objects could also interfere with treatments like in situ mixing of soil with grout or other materials to encapsulate the contaminated sediments and soils in the waste sites. Optimal disposal of the wood includes considerations of volume reduction, treatment of the radioactive residue resulting from volume reduction, or confinement without volume reduction. Volume reduction consists primarily of removing the carbon, oxygen, and hydrogen in the wood, leaving an ash that would contain most of the contamination. The only contaminant that would be released by volume reduction would by small amounts of the radioactive isotope of hydrogen, tritium. The following sections will describe the waste sites at SRS which contain contaminated vegetation and are potential candidates for the technology developed under this proposal. The description will provide a context for the magnitude of the problem and the logistics of the alternative solutions that are evaluated later in the review. 76 refs.

Wilde, E.W.; Murphy, C.E.; Lamar, R.T.; Larson, M.J.

1996-12-31T23:59:59.000Z

391

Supplementary radiological and beryllium characterization of the facility at 425 Peek Street, Schenectady, New York  

SciTech Connect (OSTI)

At the request of the Office of Naval Reactors through the Office of Remedial Action and Waste Technology, a radiological survey of the Peek Street industrial facility, the adjacent state-owned bike path, and two nearby residential properties was conducted by Oak Ridge National Laboratory (ORNL) in November 1989. The results indicated small isolated areas that exceeded DOE guidelines. These areas totaled approximately 0.2 m{sup 2} of floor area and approximately 3 m{sup 2} of wall area inside the building, and two small areas totaling approximately 5 m{sup 2} outside the building. A small section of one of these areas extended beyond the fence on the east side of the industrial property onto the state-owned property. No residual radioactive material or elevated radiation levels were detected on any portion of the paved section of the bike path or the residential properties adjacent to the site. Because the elevated radiation levels were localized and limited in extent, any credible use scenario, including current use conditions, indicated that no significant radiation exposures would accrue to individuals frequenting the area. Samples were also analyzed for elemental beryllium since that material had formerly been used at the site. In conjunction with the planned remediation at the facility, a supplementary characterization survey was performed to further define the areas containing beryllium in excess of the identified guidelines. Additional radiological characterization of Ra-226, Th-232, and U-238 was also performed in areas that were largely inaccessible prior to the remediation efforts.

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

1994-10-01T23:59:59.000Z

392

Verification and Validation of RADTRAN 5.5.  

SciTech Connect (OSTI)

This document contains a description of the verification and validation process used for the RADTRAN 5.5 code. The verification and validation process ensured the proper calculational models and mathematical and numerical methods were used in the RADTRAN 5.5 code for the determination of risk and consequence assessments. The differences between RADTRAN 5 and RADTRAN 5.5 are the addition of tables, an expanded isotope library, and the additional User-Defined meteorological option for accident dispersion. 3

Osborn, Douglas.; Weiner, Ruth F.; Mills, George Scott; Hamp, Steve C.

2005-02-01T23:59:59.000Z

393

Enhanced verification test suite for physics simulation codes  

SciTech Connect (OSTI)

This document discusses problems with which to augment, in quantity and in quality, the existing tri-laboratory suite of verification problems used by Los Alamos National Laboratory (LANL), Lawrence Livermore National Laboratory (LLNL), and Sandia National Laboratories (SNL). The purpose of verification analysis is demonstrate whether the numerical results of the discretization algorithms in physics and engineering simulation codes provide correct solutions of the corresponding continuum equations.

Kamm, James R.; Brock, Jerry S.; Brandon, Scott T.; Cotrell, David L.; Johnson, Bryan; Knupp, Patrick; Rider, William J.; Trucano, Timothy G.; Weirs, V. Gregory

2008-09-01T23:59:59.000Z

394

Literature survey  

SciTech Connect (OSTI)

The residential amount(s) of fissionable materials remaining in process equipment after the runout of bulk materials processed is referred to as ''Process Holdup of Special Nuclear Materials.'' Locating regions of holdup and estimating the quantity of fissile materials remaining as holdup are important not only to materials accountability but also to process safety. Holdup is often referred to as a ''Hidden Inventory.'' In materials accounting terminology, hidden inventories are part of ''Materials Unaccounted For'' (MUF) or ''Inventory Difference'' (ID). MUF or ID could be construed as ''Loss'' or ''Diversion''. From a safeguards perspective, all these designations are undesirable. Another terminology that is relevant to holdup is ''In-Process Inventory.'' During process operations and temporary shutdown, the holdup within the facility is also known as the in-process inventory. Estimating this inventory is just as challenging as residuals after process runout. The role of hidden inventories, or holdup, as a safeguards problem is now recognized by almost everyone interested in establishing effective safeguards for special nuclear materials. As part of this effort to organize the first INMM-sponsored Technical Workshop on Process Holdup of Special Nuclear Materials, an attempt was made to update an earlier survey of open literature publications of relevance to holdup. An attempt was made to exclude from this list those documents recognized as internal documents, progress reports, preliminary reports, abstracts, etc.

Pillay, K.K.S. (Los Alamos National Lab., Los Alamos, NM (US))

1988-07-01T23:59:59.000Z

395

Radiological assessment. A textbook on environmental dose analysis  

SciTech Connect (OSTI)

Radiological assessment is the quantitative process of estimating the consequences to humans resulting from the release of radionuclides to the biosphere. It is a multidisciplinary subject requiring the expertise of a number of individuals in order to predict source terms, describe environmental transport, calculate internal and external dose, and extrapolate dose to health effects. Up to this time there has been available no comprehensive book describing, on a uniform and comprehensive level, the techniques and models used in radiological assessment. Radiological Assessment is based on material presented at the 1980 Health Physics Society Summer School held in Seattle, Washington. The material has been expanded and edited to make it comprehensive in scope and useful as a text. Topics covered include (1) source terms for nuclear facilities and Medical and Industrial sites; (2) transport of radionuclides in the atmosphere; (3) transport of radionuclides in surface waters; (4) transport of radionuclides in groundwater; (5) terrestrial and aquatic food chain pathways; (6) reference man; a system for internal dose calculations; (7) internal dosimetry; (8) external dosimetry; (9) models for special-case radionuclides; (10) calculation of health effects in irradiated populations; (11) evaluation of uncertainties in environmental radiological assessment models; (12) regulatory standards for environmental releases of radionuclides; (13) development of computer codes for radiological assessment; and (14) assessment of accidental releases of radionuclides.

Till, J.E.; Meyer, H.R. (eds.)

1983-09-01T23:59:59.000Z

396

Data Summary Report for the 1997 Semiannual Tritium Survey for Fourmile Branch and the F- and H-Area Seeplines  

SciTech Connect (OSTI)

This report presents a summary of the definitive data validation and verification for the 1997 RFI/RI semiannual tritium survey for Fourmile Branch and the F- and H-Area Seeplines. The RFI/RI was performed under the direction of WSRC ESS/Ecology. This report was prepared under the direction EPD/EMS.

Koch, J.W. II

1998-01-05T23:59:59.000Z

397

ASPECT Emergency Response Chemical and Radiological Mapping  

ScienceCinema (OSTI)

A unique airborne emergency response tool, ASPECT is a Los Alamos/U.S. Environmental Protection Agency project that can put chemical and radiological mapping tools in the air over an accident scene. The name ASPECT is an acronym for Airborne Spectral Photometric Environmental Collection Technology. Update, Sept. 19, 2008: Flying over storm-damaged refineries and chemical factories, a twin-engine plane carrying the ASPECT (Airborne Spectral Photometric Environmental Collection Technology) system has been on duty throughout the recent hurricanes that have swept the Florida and Gulf Coast areas. ASPECT is a project of the U.S. U.S. Environmental Protection Agencys National Decontamination Team. Los Alamos National Laboratory leads a science and technology program supporting the EPA and the ASPECT aircraft. Casting about with a combination of airborne photography and infrared spectroscopy, the highly instrumented plane provides emergency responders on the ground with a clear concept of where danger lies, and the nature of the sometimes-invisible plumes that could otherwise kill them. ASPECT is the nations only 24/7 emergency response aircraft with chemical plume mapping capability. Bob Kroutil of Bioscience Division is the project leader, and while he said the team has put in long hours, both on the ground and in the air, its a worthwhile effort. The plane flew over 320 targeted sites in four days, he noted. Prior to the deployment to the Gulf Coast, the plane had been monitoring the Democratic National Convention in Denver, Colorado. Los Alamos National Laboratory Divisions that are supporting ASPECT include, in addition to B-Division, CTN-5: Networking Engineering and IRM-CAS: Communication, Arts, and Services. Leslie Mansell, CTN-5, and Marilyn Pruitt, IRM-CAS, were recognized the the U.S. EPA for their outstanding support to the hurricane response of Gustav in Louisiana and Ike in Texas. The information from the data collected in the most recent event, Hurricane Ike, was sent to the EPA Region 6 Rapid Needs Assessment and the State of Texas Joint Field Office in Austin, Texas. It appears that though there is considerable damage in Galveston and Texas City, there are fewer chemical leaks than during either hurricanes Katrina or Rita. Specific information gathered from the data was reported out to the U.S. Environmental Protection Agency Headquarters, the Federal Emergency Management Agency, the Department of Homeland Security, and the State of Texas Emergency Management Agency.

LANL

2009-09-01T23:59:59.000Z

398

Final Status Survey Report for Corrective Action Unit 117 - Pluto Disassembly Facility, Building 2201, Nevada National Security Site, Nevada  

SciTech Connect (OSTI)

This document contains the process knowledge, radiological data and subsequent statistical methodology and analysis to support approval for the radiological release of Corrective Action Unit (CAU) 117 – Pluto Disassembly Facility, Building 2201 located in Area 26 of the Nevada National Security Site (NNSS). Preparations for release of the building began in 2009 and followed the methodology described in the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM). MARSSIM is the DOE approved process for release of Real Property (buildings and landmasses) to a set of established criteria or authorized limits. The pre-approved authorized limits for surface contamination values and corresponding assumptions were established by DOE O 5400.5. The release criteria coincide with the acceptance criteria of the U10C landfill permit. The U10C landfill is the proposed location to dispose of the radiologically non-impacted, or “clean,” building rubble following demolition. However, other disposition options that include the building and/or waste remaining at the NNSS may be considered providing that the same release limits apply. The Final Status Survey was designed following MARSSIM guidance by reviewing historical documentation and radiological survey data. Following this review a formal radiological characterization survey was performed in two phases. The characterization revealed multiple areas of residual radioactivity above the release criteria. These locations were remediated (decontaminated) and then the surface activity was verified to be less than the release criteria. Once remediation efforts had been successfully completed, a Final Status Survey Plan (10-015, “Final Status Survey Plan for Corrective Action Unit 117 – Pluto Disassembly Facility, Building 2201”) was developed and implemented to complete the final step in the MARSSIM process, the Final Status Survey. The Final Status Survey Plan consisted of categorizing each individual room into one of three categories: Class 1, Class 2 or Class 3 (a fourth category is a “Non-Impacted Class” which in the case of Building 2201 only pertained to exterior surfaces of the building.) The majority of the rooms were determined to fall in the less restrictive Class 3 category, however, Rooms 102, 104, 106, and 107 were identified as containing Class 1 and 2 areas. Building 2201 was divided into “survey units” and surveyed following the requirements of the Final Status Survey Plan for each particular class. As each survey unit was completed and documented, the survey results were evaluated. Each sample (static measurement) with units of counts per minute (cpm) was corrected for the appropriate background and converted to a value with units of dpm/100 cm2. With a surface contamination value in the appropriate units, it was compared to the surface contamination limits, or in this case the derived concentration guideline level (DCGLw). The appropriate statistical test (sign test) was then performed. If the survey unit was statistically determined to be below the DCGLw, then the survey unit passed and the null hypothesis (that the survey unit is above limits) was rejected. If the survey unit was equal to or below the critical value in the sign test, the null hypothesis was not rejected. This process was performed for all survey units within Building 2201. A total of thirty-three “Class 1,” four “Class 2,” and one “Class 3” survey units were developed, surveyed, and evaluated. All survey units successfully passed the statistical test. Building 2201 meets the release criteria commensurate with the Waste Acceptance Criteria (for radiological purposes) of the U10C landfill permit residing within NNSS boundaries. Based on the thorough statistical sampling and scanning of the building’s interior, Building 2201 may be considered radiologically “clean,” or free of contamination.

Jeremy Gwin and Douglas Frenette

2010-09-30T23:59:59.000Z

399

CTBT Integrated Verification System Evaluation Model  

SciTech Connect (OSTI)

Sandia National Laboratories has developed a computer based model called IVSEM (Integrated Verification System Evaluation Model) to estimate the performance of a nuclear detonation monitoring system. The IVSEM project was initiated in June 1994, by Sandia`s Monitoring Systems and Technology Center and has been funded by the US Department of Energy`s Office of Nonproliferation and National Security (DOE/NN). IVSEM is a simple, top-level, modeling tool which estimates the performance of a Comprehensive Nuclear Test Ban Treaty (CTBT) monitoring system and can help explore the impact of various sensor system concepts and technology advancements on CTBT monitoring. One of IVSEM`s unique features is that it integrates results from the various CTBT sensor technologies (seismic, infrasound, radionuclide, and hydroacoustic) and allows the user to investigate synergy among the technologies. Specifically, IVSEM estimates the detection effectiveness (probability of detection) and location accuracy of the integrated system and of each technology subsystem individually. The model attempts to accurately estimate the monitoring system`s performance at medium interfaces (air-land, air-water) and for some evasive testing methods such as seismic decoupling. This report describes version 1.2 of IVSEM.

Edenburn, M.W.; Bunting, M.L.; Payne, A.C. Jr.

1997-10-01T23:59:59.000Z

400

Organics Verification Study for Sinclair and Dyes Inlets, Washington  

SciTech Connect (OSTI)

Sinclair and Dyes Inlets near Bremerton, Washington, are on the State of Washington 1998 303(d) list of impaired waters because of fecal coliform contamination in marine water, metals in sediment and fish tissue, and organics in sediment and fish tissue. Because significant cleanup and source control activities have been conducted in the inlets since the data supporting the 1998 303(d) listings were collected, two verification studies were performed to address the 303(d) segments that were listed for metal and organic contaminants in marine sediment. The Metals Verification Study (MVS) was conducted in 2003; the final report, Metals Verification Study for Sinclair and Dyes Inlets, Washington, was published in March 2004 (Kohn et al. 2004). This report describes the Organics Verification Study that was conducted in 2005. The study approach was similar to the MVS in that many surface sediment samples were screened for the major classes of organic contaminants, and then the screening results and other available data were used to select a subset of samples for quantitative chemical analysis. Because the MVS was designed to obtain representative data on concentrations of contaminants in surface sediment throughout Sinclair Inlet, Dyes Inlet, Port Orchard Passage, and Rich Passage, aliquots of the 160 MVS sediment samples were used in the analysis for the Organics Verification Study. However, unlike metals screening methods, organics screening methods are not specific to individual organic compounds, and are not available for some target organics. Therefore, only the quantitative analytical results were used in the organics verification evaluation. The results of the Organics Verification Study showed that sediment quality outside of Sinclair Inlet is unlikely to be impaired because of organic contaminants. Similar to the results for metals, in Sinclair Inlet, the distribution of residual organic contaminants is generally limited to nearshore areas already within the actively managed Puget Sound Naval Shipyard and Intermediate Maintenance Facility Superfund Site, where further source-control actions and monitoring are under way.

Kohn, Nancy P.; Brandenberger, Jill M.; Niewolny, Laurie A.; Johnston, Robert K.

2006-09-28T23:59:59.000Z

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Intelligent Sensor Management in Nuclear Searches and Radiological Surveys A.V. Klimenko1  

E-Print Network [OSTI]

background has a cosmic ray component and a component from naturally occurring radioactive isotopes Special nuclear materials (SNMs) are weak emitters of radiation and are difficult to detect, especially in the presence of natural backgrounds. Success in this difficult task of detection depends largely

Tanner, Herbert G.

402

Radiological survey of the inactive uranium-mill tailings at Green River, Utah  

SciTech Connect (OSTI)

The uranium-mill tailings at Green River, Utah, are relatively low in /sup 226/Ra content and concentration (20 Ci and 140 pCi/g, respectively) because the mill was used to upgrade the uranium ore by separating the sand and slime fractions; most of the radium was transported along with the slimes to another mill site. Spread of tailings was observed in all directions, but near-background gamma exposure rates were reached at distances of 40 to 90 m from the edge of the pile. Water erosion of the tailings is evident and, since a significant fraction of the tailings pile lies in Brown's Wash, the potential exists for repetition of the loss of a large quantity of tailings such as occurred during a flood in 1959. In general, the level of surface contamination was low at this site, but some areas in the mill site, which were being used for nonuranium work, have gamma-ray exposure rates up to 143 ..mu..R/hr.

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

1980-03-01T23:59:59.000Z

403

COT"IPREITENS IVE RADIOLOGICAL SURVEY OFF-SITE PROPERTY P NIAGARA FALIS STORAGE SITE  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledo SiteTonawanda North SiteD&D D&DKEY

404

RADIOLOGICAL SURVEY OF A PORTION OF PROPERTY OWNED BY MODERN LANDFILL, INC. -  

Office of Legacy Management (LM)

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405

Radiological Survey Data for 38 Grove Avenue, Rochelle Park, l'lew Jersey  

Office of Legacy Management (LM)

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406

NNSA to Conduct Aerial Radiological Surveys Over Washington, D.C. and  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledoSampling at the

407

Health and Safety Research Division RESULTS FROM A RADIOLOGICAL SURVEY ON YARDEORO AVENUE,  

Office of Legacy Management (LM)

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408

ORNL/TM-11118 RESULTS OF THE RADIOLOGICAL SURVEY AT METPATH INCORPORATED,  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C. 20545 OCT 28 1% - :NEW; I.-'7-TAC~$,.5/4

409

PRELIMINqRY RADIOLOGICAL SURVEY REPORT OF THE FORMER STATEN ISLAND WAREHOUSE SITE  

Office of Legacy Management (LM)

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410

RADIOLOGICAL SURVEY AT 5823/5849 NORTH RAVENSWOOD AVEXJE CHICAGO, ILLINOIS  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C. 20545 OCT 28 1%AU62 & 199344S. Driof,h '

411

RADIOLOGICAL SURVEY OF THE GUN FORGING MACHINE BUILDING ITHACA GUN COMPANY  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C. 20545 OCT 28 1%AU62 & 199344S. Driof,h

412

Radiological Habits Survey: Torness, 2006 This page has been intentionally left blank  

E-Print Network [OSTI]

intentionally left blank #12;3 SUMMARY 5 1. INTRODUCTION 6 1.1 Regulation of radioactive waste discharges 6 1 vegetables in the Torness area (kg/y) Table 20. Adults' consumption rates of potato in the Torness area (kg

413

Radiological engineering evaluation of the delay time line air scrubber located at the Clinton P. Anderson Meson Physics Facility (LAMPF)  

SciTech Connect (OSTI)

The purpose of this study was to determine the effects of the addition of an air scrubber to an already existing delay line and whether it would scrub {sup 11}CO{sub 2}. There were three main objectives of this study. The first objective was to determine the scrubbing efficiency of the scrubber. The scrubbing efficiency was then used to predict the dose rates in the scrubber area and compare those values with measurements from radiological surveys. The third objective was to determine if the shield blocks were effective in reducing the dose rates in the scrubber area. The activities were measured before and during scrubber operation and this information was used to calculate the scrubbing efficiency and the efficiency of {sup 11}CO{sub 2} removal was determined to be around 50%. Microshield was then used to predict dose rates and compared those values with measurements from radiological surveys. This was also used to determine the that the shield blocks around the scrubber were effective in reducing the dose rates from the radiation field produced by the radionuclides in the scrubber.

Huneycutt, S.E.

1996-05-01T23:59:59.000Z

414

Hanford Radiological Protection Support Services Annual Report for 2000  

SciTech Connect (OSTI)

During calendar year 2000, the Pacific Northwest National Laboratory performed its customary radiological protection support services in support of the U.S. Department of Energy Richland Operations Office and the Hanford contractors. These services included: 1) external dosimetry, 2) internal dosimetry, 3) in vivo monitoring, 4) radiological records, 5) instrument calibration and evaluation, and 6) calibration of radiation sources traceable to the National Institute of Standards and Technology. Each program summary describes the routine operations, program changes and improvements, program assessments, supporting technical studies, and professional activities.

Lynch, Timothy P.; Bihl, Donald E.; Johnson, Michelle L.; Maclellan, Jay A.; Piper, Roman K.

2001-05-07T23:59:59.000Z

415

Mobile Pit verification system design based on passive special nuclear material verification in weapons storage facilities  

SciTech Connect (OSTI)

A mobile 'drive by' passive radiation detection system to be applied in special nuclear materials (SNM) storage facilities for validation and compliance purposes has been designed through the use of computational modeling and new radiation detection methods. This project was the result of work over a 1 year period to create optimal design specifications to include creation of 3D models using both Monte Carlo and deterministic codes to characterize the gamma and neutron leakage out each surface of SNM-bearing canisters. Results were compared and agreement was demonstrated between both models. Container leakages were then used to determine the expected reaction rates using transport theory in the detectors when placed at varying distances from the can. A 'typical' background signature was incorporated to determine the minimum signatures versus the probability of detection to evaluate moving source protocols with collimation. This established the criteria for verification of source presence and time gating at a given vehicle speed. New methods for the passive detection of SNM were employed and shown to give reliable identification of age and material for highly enriched uranium (HEU) and weapons grade plutonium (WGPu). The finalized 'Mobile Pit Verification System' (MPVS) design demonstrated that a 'drive-by' detection system, collimated and operating at nominally 2 mph, is capable of rapidly verifying each and every weapon pit stored in regularly spaced, shelved storage containers, using completely passive gamma and neutron signatures for HEU and WGPu. This system is ready for real evaluation to demonstrate passive total material accountability in storage facilities. (authors)

Paul, J. N.; Chin, M. R.; Sjoden, G. E. [Nuclear and Radiological Engineering Program, George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, 770 State St, Atlanta, GA 30332-0745 (United States)

2013-07-01T23:59:59.000Z

416

Method for warning of radiological and chemical substances using detection paints on a vehicle surface  

DOE Patents [OSTI]

A system for warning of corrosion, chemical, or radiological substances. The system comprises painting a surface with a paint or coating that includes an indicator material and monitoring the surface for indications of the corrosion, chemical, or radiological substances.

Farmer, Joseph C. (Tracy, CA)

2012-03-13T23:59:59.000Z

417

Surface with two paint strips for detection and warning of chemical warfare and radiological agents  

DOE Patents [OSTI]

A system for warning of corrosion, chemical, or radiological substances. The system comprises painting a surface with a paint or coating that includes an indicator material and monitoring the surface for indications of the corrosion, chemical, or radiological substances.

Farmer, Joseph C.

2013-04-02T23:59:59.000Z

418

Paint for detection of corrosion and warning of chemical and radiological attack  

DOE Patents [OSTI]

A system for warning of corrosion, chemical, or radiological substances. The system comprises painting a surface with a paint or coating that includes an indicator material and monitoring the surface for indications of the corrosion, chemical, or radiological substances.

Farmer, Joseph C. (Tracy, CA)

2010-08-24T23:59:59.000Z

419

Temporal Dependency based Checkpoint Selection for Dynamic Verification of Fixed-time Constraints  

E-Print Network [OSTI]

.4 [Software Engineering]: Software/Program Verification. General Term Algorithms, Design, Reliability, Theory strategy, the corresponding unnecessary verification can be avoided. The comparison and experimental simulation further demonstrate that our new strategy can improve the efficiency of overall temporal

Yang, Yun

420

VERIFICATION BASED ECG BIOMETRICS WITH CARDIAC IRREGULAR CONDITIONS USING HEARTBEAT LEVEL AND SEGMENT LEVEL INFORMATION FUSION  

E-Print Network [OSTI]

VERIFICATION BASED ECG BIOMETRICS WITH CARDIAC IRREGULAR CONDITIONS USING HEARTBEAT LEVEL propose an ECG based robust human verification system for both healthy and cardiac irregular conditions% relatively on the PTB database. Index Terms-- ECG biometrics, beat normalization, outlier re- moval

Li, Xin

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

E-Print Network 3.0 - aspects radiological aspects Sample Search...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

in Radiological Health Sciences (1994) from Colorado State University. Her fields... , dosimetry, radiation protection, radiochemistry, societal aspects of nuclear technology,...

422

Los Alamos National Laboratory's environmental surveillance and radiological emergency vehicle and the Co-60 incident  

SciTech Connect (OSTI)

A 4-wheel drive van has been outfitted at Los Alamos for environmental surveillance and radiological emergencies. The van's capabilities were described at this conference in 1982. The rapid gamma search and spectral analysis capabilities were utilized in conjunction with the cobalt-60 (/sup 60/Co) teletherapy source incident in Juarez, Mexico. Assistance was requested by the State of New Mexico (through DOE/Albuquerque Area Office) in January 1984 to perform initial in-situ isotopic identification of the contaminated steel that was first discovered in the United States by Los Alamos. The van's capabilities were again called upon in March 1984 to survey the New Mexico highways using the highly sensitive delta count rate monitoring system for /sup 60/Co pellets that may have been tracked into the state. This paper provides (1) setup and results of the surveys conducted with the van, (2) interactions with the press, and (3) an evaluation of the van's usefulness in such an emergency response. 2 references, 5 figures.

Van Etten, D.M.; Ahlquist, A.J.; Hansen, W.R.

1984-01-01T23:59:59.000Z

423

STEP Participant Survey Report  

Broader source: Energy.gov [DOE]

STEP Participant Survey Report, from the Tool Kit Framework: Small Town University Energy Program (STEP).

424

The Role of Gamma-ray Imaging in Performing Radiological Characterisation at the Magnox Storage Ponds at the Bradwell Decommissioning Site - 13628  

SciTech Connect (OSTI)

A gamma-ray imaging device has been used to perform radiological characterisation work at the spent fuel ponds complex at the site of the Bradwell Magnox Power Station, which is currently undergoing accelerated decommissioning. The objective of using a gamma-ray imaging system was to independently verify previous radiological survey work and to evaluate the adequacy of the random distribution of the destructive core sampling which had been performed. In performing this work the gamma-ray imager clearly identified the exact locations of the sources of radiation that gave rise to the elevated gamma dose rates measured by conventional health physics surveys of the area. In addition, the gamma-ray imager was able to characterise each hotspot as being either dominated by Cs-137 or by Co-60. The gamma imaging survey was undertaken with a RadScan gamma imaging system deployed on the walkways which run along the lengths of the ponds; this enabled the whole imaging survey to be performed with minimal dose uptake, demonstrating the ALARP principle within decommissioning. (authors)

Hughes, Karl; Shaw, Tracey [Babcock International, B14.1, Sellafield, Cumbria, CA20 1PG (United Kingdom)] [Babcock International, B14.1, Sellafield, Cumbria, CA20 1PG (United Kingdom)

2013-07-01T23:59:59.000Z

425

24.01.01.M5 Radiological Safety Page 1 of 3 UNIVERSITY RULE  

E-Print Network [OSTI]

Radiological Safety Page 3 of 3 1.5 Employees, visitors and students shall only work with radiation sources24.01.01.M5 Radiological Safety Page 1 of 3 UNIVERSITY RULE 24.01.01.M5 Radiological Safety 25, 2011 Next scheduled review: March 25, 2014 Rule Statement Environmental Health and Safety (EHS

426

Comment submitted by Hobart/ITW Food Equipment Group regarding the Energy Star Verification Testing Program  

Broader source: Energy.gov [DOE]

This document is a comment submitted by Hobart/ITW Food Equipment Group regarding the Energy Star Verification Testing Program

427

Comment submitted by BSH Home Appliances Corporation regarding the Energy Star Verification Testing Program  

Broader source: Energy.gov [DOE]

This document is a comment submitted by BSH Home Appliances Corporation regarding the Energy Star Verification Testing Program

428

Comment submitted by CertainTeed Corporation regarding the Energy Star Verification Testing Program  

Broader source: Energy.gov [DOE]

This document is a comment submitted by CertainTeed Corporation regarding the Energy Star Verification Testing Program

429

Comment submitted by the Natural Resources Defense Council (NRDC) regarding the Energy Star Verification Testing Program  

Broader source: Energy.gov [DOE]

This document is a comment submitted by the Natural Resources Defense Council (NRDC) regarding the Energy Star Verification Testing Program

430

Efficient Methods for Practical Fully-Homomorphic Symmetric-key Encryption, Randomization, and Verification  

E-Print Network [OSTI]

, and Verification Aviad Kipnis akipnis@nds.com; Eli Hibshoosh ehibshoo@nds.com Abstract We present high performance

431

E-Print Network 3.0 - attribute verification system Sample Search...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

systems for generation "attributes": those characteristics of a power plant's production... , electricity markets are devising accounting and verification systems for...

432

Comment submitted by Hoshizaki America, Inc. regarding the Energy Star Verification Testing Program  

Broader source: Energy.gov [DOE]

This document is a comment submitted by Hoshizaki America, Inc. regarding the Energy Star Verification Testing Program

433

EECLP Webinar #2: Quality Assurance and Evaluation Monitoring Verification-- Text Version  

Broader source: Energy.gov [DOE]

Below is the text version of the EECLP Webinar #2: Quality Assurance and Evaluation Monitoring Verification, presented in December 2014.

434

Comment submitted by Energizer Battery Manufacturing, Inc. regarding the Energy Star Verification Testing Program  

Broader source: Energy.gov [DOE]

This document is a comment submitted by Energizer Battery Manufacturing, Inc. regarding the Energy Star Verification Testing Program

435

Comment submitted by United Lighting, Inc. regarding the Energy Star Verification Testing Program  

Broader source: Energy.gov [DOE]

This document is a comment submitted by United Lighting, Inc. regarding the Energy Star Verification Testing Program

436

Comment submitted by A. O. Smith Corporation regarding the Energy Star Verification Testing Program  

Broader source: Energy.gov [DOE]

This document is a comment submitted by A. O. Smith Corporation regarding the Energy Star Verification Testing Program

437

Comment submitted by the Alliance for Water Efficiency (AWE) regarding the Energy Star Verification Testing Program  

Broader source: Energy.gov [DOE]

This document is a comment submitted by the Alliance for Water Efficiency (AWE) regarding the Energy Star Verification Testing Program

438

Evaluation of ANSI N42-17A by investigating the effects of temperature and humidity on the response of radiological instruments  

SciTech Connect (OSTI)

The American National Standards Institute (ANSI) N42.17A-1989 standard`s performance criteria and test methods has been evaluated by investigating the effects of temperature and humidity on the response of 105 portable direct-reading radiological instruments (45 beta-gamma survey meters, 32 neutron rem meters, 1O alpha contamination and 18 tritium-in-air monitors). The US Department of Energy (DOE) mandates the use of ANSI standards for the calibration and performance testing of radiological instruments, and requires that instruments be appropriate for existing environmental conditions. Random tests conducted in an environmental chamber determined the effects of temperatures ranging from {minus}10{degree}C to 50{degree}C and humidity at levels of 40% RH and 95% RH on the response of a cross section of instruments used in routine health physics operations at Los Alamos. The following instruments were tested: Eberline RO-2 and RO-C ionization chambers, Eberline E-530 survey meter with the Model HP-C stainless steel Geiger-Muller (G) wall probe, Eberline PIC-6A and PIC-6B ion chambers, Eberline ESP-1 survey meter with the Model HP-260 pancake G detector, Ludlum 3 survey meter with the Model 44-6 stainless steel G wall probe, Eberline ESP-1, ESP-2 and PAR-4 survey meters with the neutron rem detector, Health Physics Instruments 2080 survey meter with the moderator detector, Ludlum 139 survey meter with the Model 43-32 air-proportional alpha detector, and the Overhoff 394-C, Johnston J-111 and J-110 tritium monitors. Experimental results encompass 1128 temperature tests (1269-hours exposure in the chamber) and 735 humidity tests (1890-hours exposure in the chamber). The study shows the standard`s test requirement for temperature at or near the extreme conditions, and the standard`s test requirement for humidity at 95% RH may be too restrictive for instruments used in the work environment.

Clement, R.S.

1995-06-01T23:59:59.000Z

439

COMMENTARY/COMMENTAIRE The radiological consequences of the Chernobyl  

E-Print Network [OSTI]

COMMENTARY/COMMENTAIRE The radiological consequences of the Chernobyl accident The First­22 March 1996 Eric Voice Abstract: The human health consequences of the Chernobyl accident in 1986 have are discussed with particular focus on thyroid cancers and exposures to iodine-131. Key words: Chernobyl

Shlyakhter, Ilya

440

Radiology utilizing a gas multiwire detector with resolution enhancement  

DOE Patents [OSTI]

This invention relates to a process and apparatus for obtaining filmless, radiological, digital images utilizing a gas multiwire detector. Resolution is enhanced through projection geometry. This invention further relates to imaging systems for X-ray examination of patients or objects, and is particularly suited for mammography.

Majewski, Stanislaw (Grafton, VA); Majewski, Lucasz A. (Grafton, VA)

1999-09-28T23:59:59.000Z

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

DOE Radiological Calibrations Intercomparison Program: Results of fiscal year 1987  

SciTech Connect (OSTI)

This report presents the FY 1987 results of the radiological calibrations intercomparison program. The intercomparison operation is discussed, and the equipment is described, particularly the instrument set, the beta source set, and relevant calculations. Solutions to problems and improvements in the program are suggested, and conclusions are then introduced. 9 refs., 3 figs., 8 tabs.

Cummings, F.M.; McDonald, J.C.

1988-06-01T23:59:59.000Z

442

Radiological Laboratory, Utility, Office Building LEED Strategy & Achievement  

SciTech Connect (OSTI)

Missions that the Radiological Laboratory, utility, Office Building (RLUOB) supports are: (1) Nuclear Materials Handling, Processing, and Fabrication; (2) Stockpile Management; (3) Materials and Manufacturing Technologies; (4) Nonproliferation Programs; (5) Waste Management Activities - Environmental Programs; and (6) Materials Disposition. The key capabilities are actinide analytical chemistry and material characterization.

Seguin, Nicole R. [Los Alamos National Laboratory

2012-07-18T23:59:59.000Z

443

EM-Led Radiological Incident Response Program Receives Honors  

Broader source: Energy.gov [DOE]

A program led by EM’s Carlsbad Field Office (CBFO) that coordinates analytical capabilities throughout DOE for response to potential national radiological incidents recently received recognition for the best-in-track poster at a waste management conference earlier this year.

444

EA-1919: Recycle of Scrap Metals Originating from Radiological Areas  

Broader source: Energy.gov [DOE]

This Programmatic EA evaluates alternatives for the management of scrap metal originating from DOE radiological control areas, including the proposed action to allow for the recycle of uncontaminated scrap metal that meets the requirements of DOE Order 458.1. (Metals with volumetric radioactive contamination are not included in the scope of this Programmatic EA.)

445

Nuclear and Radiological Engineering and Medical Physics Programs  

E-Print Network [OSTI]

Nuclear and Radiological Engineering and Medical Physics Programs The George W. Woodruff School #12 Engineering Industry Graduate School DOE National Labs Nuclear Navy #12; 104 Operating Nuclear Power plants one of the highest among all engineers #12;Westinghouse AP1000 Areva EPR GE Nuclear ESBWR B&W m

Weber, Rodney

446

Verification and validation of RADMODL Version 1.0  

SciTech Connect (OSTI)

RADMODL is a system of linked computer codes designed to calculate the radiation environment following an accident in which nuclear materials are released. The RADMODL code and the corresponding Verification and Validation (V&V) calculations (Appendix A), were developed for Westinghouse Savannah River Company (WSRC) by EGS Corporation (EGS). Each module of RADMODL is an independent code and was verified separately. The full system was validated by comparing the output of the various modules with the corresponding output of a previously verified version of the modules. The results of the verification and validation tests show that RADMODL correctly calculates the transport of radionuclides and radiation doses. As a result of this verification and validation effort, RADMODL Version 1.0 is certified for use in calculating the radiation environment following an accident.

Kimball, K.D.

1993-03-01T23:59:59.000Z

447

A Zero Knowledge Protocol For Nuclear Warhead Verification  

SciTech Connect (OSTI)

The verification of nuclear warheads for arms control faces a paradox: International inspectors must gain high confidence in the authenticity of submitted items while learning nothing about them. Conventional inspection systems featuring ''information barriers'', designed to hide measurments stored in electronic systems, are at risk of tampering and snooping. Here we show the viability of fundamentally new approach to nuclear warhead verification that incorporates a zero-knowledge protocol, designed such that sensitive information is never measured so does not need to be hidden. We interrogate submitted items with energetic neutrons, making in effect, differential measurements of neutron transmission and emission. Calculations of diversion scenarios show that a high degree of discrimination can be achieved while revealing zero information. Timely demonstration of the viability of such an approach could be critical for the nexxt round of arms-control negotiations, which will likely require verification of individual warheads, rather than whole delivery systems.

Glaser, Alexander [Princeton, Univ., NJ (United States). Program on Science and Global Security] [Princeton, Univ., NJ (United States). Program on Science and Global Security; Goldston, Robert J. [Princeton Plasma Physics Lab., Princeton, NJ (United States)] [Princeton Plasma Physics Lab., Princeton, NJ (United States)

2014-03-14T23:59:59.000Z

448

Converter performance TFE Verification Program. Final test report  

SciTech Connect (OSTI)

This report details TFE Verification Program, the objective, of which 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 TFE Verification Program built directly on the technology and data base developed in the 1960s and early 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 features of thermionic power conversion technology were recognized but concern was expressed over the lack of fast reactor irradiation data. The TFE Verification Program addressed that concern.

Not Available

1994-03-01T23:59:59.000Z

449

Bibliography for Verification and Validation in Computational Simulations  

SciTech Connect (OSTI)

A bibliography has been compiled dealing with the verification and validation of computational simulations. The references listed in this bibliography are concentrated in the field of computational fluid dynamics (CFD). However, references from the following fields are also included: operations research, heat transfer, solid dynamics, software quality assurance, software accreditation, military systems, and nuclear reactor safety. This bibliography, containing 221 references, is not meant to be comprehensive. It was compiled during the last ten years in response to the author's interest and research in the methodology for verification and validation. The emphasis in the bibliography is in the following areas: philosophy of science underpinnings, development of terminology and methodology, high accuracy solutions for CFD verification, experimental datasets for CFD validation, and the statistical quantification of model validation. This bibliography should provide a starting point for individual researchers in many fields of computational simulation in science and engineering.

Oberkampf, W.L.

1998-10-01T23:59:59.000Z

450

Formal verification of complex properties on PLC programs  

E-Print Network [OSTI]

Formal verification has become a recommended practice in the safety-critical application areas. However, due to the complexity of practical control and safety systems, the state space explosion often prevents the use of formal analysis. In this paper we extend our former verification methodology with effective property preserving reduction techniques. For this purpose we developed general rule-based reductions and a customized version of the Cone of Influence (COI) reduction. Using these methods, the verification of complex requirements formalised with temporal logics (e.g. CTL, LTL) can be orders of magnitude faster. We use the NuSMV model checker on a real-life PLC program from CERN to demonstrate the performance of our reduction techniques.

Darvas, D; Voros, A; Bartha, T; Blanco Vinuela, E; Gonzalez Suarez, V M

2014-01-01T23:59:59.000Z

451

"CONFIRMATORY SURVEY RESULTS FOR THE ABB COMBUSTION ENGINEERING SITE WINDSOR, CONNECTICUT DCN 5158-SR-02-2  

SciTech Connect (OSTI)

The objectives of the confirmatory activities 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 contractor?s procedures and FSS results. ORAU reviewed ABB CE?s decommissioning plan, final status survey plan, and the applicable soil DCGLs, which were developed based on an NRC-approved radiation dose assessment. The surveys include gamma surface scans, gamma direct measurements, and soil sampling.

ADAMS, WADE C

2013-03-25T23:59:59.000Z

452

Under consideration for publication in Formal Aspects of Computing Specification and verification challenges for  

E-Print Network [OSTI]

and verification challenges as we see them today. We draw on our experience with specifying and verifying code], and static checking and verification tools for these [BCD+ 06, FLL+ 02, CK05]. While we do not claim in ESC/Java [FLL+ 02, LSS99, CK05] and other tools geared to the verification of Java-like programs [BCD

Leino, K. Rustan M.

453

Verification and Uncertainty Reduction of Amchitka Underground Nuclear Testing Models  

SciTech Connect (OSTI)

The modeling of Amchitka underground nuclear tests conducted in 2002 is verified and uncertainty in model input parameters, as well as predictions, has been reduced using newly collected data obtained by the summer 2004 field expedition of CRESP. Newly collected data that pertain to the groundwater model include magnetotelluric (MT) surveys conducted on the island to determine the subsurface salinity and porosity structure of the subsurface, and bathymetric surveys to determine the bathymetric maps of the areas offshore from the Long Shot and Cannikin Sites. Analysis and interpretation of the MT data yielded information on the location of the transition zone, and porosity profiles showing porosity values decaying with depth. These new data sets are used to verify the original model in terms of model parameters, model structure, and model output verification. In addition, by using the new data along with the existing data (chemistry and head data), the uncertainty in model input and output is decreased by conditioning on all the available data. A Markov Chain Monte Carlo (MCMC) approach is adapted for developing new input parameter distributions conditioned on prior knowledge and new data. The MCMC approach is a form of Bayesian conditioning that is constructed in such a way that it produces samples of the model parameters that eventually converge to a stationary posterior distribution. The Bayesian MCMC approach enhances probabilistic assessment. Instead of simply propagating uncertainty forward from input parameters into model predictions (i.e., traditional Monte Carlo approach), MCMC propagates uncertainty backward from data onto parameters, and then forward from parameters into predictions. Comparisons between new data and the original model, and conditioning on all available data using MCMC method, yield the following results and conclusions: (1) Model structure is verified at Long Shot and Cannikin where the high-resolution bathymetric data collected by CRESP yield profiles matching those used to construct the Long Shot and Cannikin model cross sections in 2002. (2) Distributions of model input parameters (recharge, conductivity, and recharge-conductivity ratio) used in 2002 for the three sites are verified where the new data indicate distributions with narrower ranges (smaller uncertainty) but within the range employed in the 2002 model. (3) As a conservative approach, distribution of fracture porosity used in 2002 was deliberately skewed toward lower values. New CRESP data indicate that the selected porosity range was overly conservative. In addition, the range of porosity values obtained from the analysis of the MT data is found to generally be about three orders of magnitude lower than range of values used in the 2002 model, though the values themselves are much larger from the MT data. (4) Distributions of the flow model output (head distribution, salinity distribution, groundwater fluxes) resulting from the 2002 model for the three sites are verified where the new model output after conditioning on the data lie within the range of the 2002 model output. (5) Cannikin model output at location of well UAe-1 is not fully verified where the new model results for small salinity values are not fully enclosed by the uncertainty bounds of the original model output. (6) With the new porosities developed from the analysis of MT data, radionuclides require thousands of years to reach the seafloor. No breakthrough resulted for any of the three sites within the 2000 year model timeframe, despite ignoring all retardation mechanisms (sorption, radionuclide trapping in glass, matrix diffusion, and radioactive decay). (7) The no-breakthrough results verify the original model in the sense that this result lies within the uncertainty bounds of the 2002 model expressed as + 2 {sigma}{sub Q} and - 2 {sigma}{sub Q}. The lower bound, - 2 {sigma}{sub Q}, in the 2002 model gave negative values implying that the bound is essentially zero. The current results of no-breakthrough match this lower bound. (8) Si

Ahmed Hassan; Jenny Chapman

2006-02-01T23:59:59.000Z

454

Verification for measurement-only blind quantum computing  

E-Print Network [OSTI]

Blind quantum computing is a new secure quantum computing protocol where a client who does not have any sophisticated quantum technlogy can delegate her quantum computing to a server without leaking any privacy. It is known that a client who has only a measurement device can perform blind quantum computing [T. Morimae and K. Fujii, Phys. Rev. A {\\bf87}, 050301(R) (2013)]. It has been an open problem whether the protocol can enjoy the verification, i.e., the ability of client to check the correctness of the computing. In this paper, we propose a protocol of verification for the measurement-only blind quantum computing.

Tomoyuki Morimae

2014-06-19T23:59:59.000Z

455

Supporting the President's Arms Control and Nonproliferation Agenda: Transparency and Verification for Nuclear Arms Reductions  

SciTech Connect (OSTI)

The President's arms control and nonproliferation agenda is still evolving and the details of initiatives supporting it remain undefined. This means that DOE, NNSA, NA-20, NA-24 and the national laboratories can help define the agenda, and the policies and the initiatives to support it. This will require effective internal and interagency coordination. The arms control and nonproliferation agenda is broad and includes the path-breaking goal of creating conditions for the elimination of nuclear weapons. Responsibility for various elements of the agenda will be widely scattered across the interagency. Therefore an interagency mapping exercise should be performed to identify the key points of engagement within NNSA and other agencies for creating effective policy coordination mechanisms. These can include informal networks, working groups, coordinating committees, interagency task forces, etc. It will be important for NA-20 and NA-24 to get a seat at the table and a functional role in many of these coordinating bodies. The arms control and nonproliferation agenda comprises both mature and developing policy initiatives. The more mature elements such as CTBT ratification and a follow-on strategic nuclear arms treaty with Russia have defined milestones. However, recent press reports indicate that even the START follow-on strategic arms pact that is planned to be complete by the end of 2009 may take significantly longer and be more expansive in scope. The Russians called for proposals to count non-deployed as well as deployed warheads. Other elements of the agenda such as FMCT, future bilateral nuclear arms reductions following a START follow-on treaty, nuclear posture changes, preparations for an international nuclear security summit, strengthened international safeguards and multilateral verification are in much earlier stages of development. For this reason any survey of arms control capabilities within the USG should be structured to address potential needs across the near-term (1-4) years and longer-term (5-10) years planning horizons. Some final observations include acknowledging the enduring nature of several key objectives on the Obama Administration's arms control and nonproliferation agenda. The CTBT, FMCT, bilateral nuclear arms reductions and strengthening the NPT have been sought by successive U.S. Administrations for nearly thirty years. Efforts towards negotiated arms control, although de-emphasized by the G.W. Bush Administration, have remained a pillar of U.S. national security strategy for decades and are likely to be of enduring if not increasing importance for decades to come. Therefore revitalization and expansion of USG capabilities in this area can be a positive legacy no matter what near-term arms control goals are achieved over the next four years. This is why it is important to reconstruct integrated bureaucratic, legislative, budgetary and diplomatic strategies to sustain the arms control and nonproliferation agenda. In this endeavor some past lessons must be taken to heart to avoid bureaucratic overkill and keep interagency policy-making and implementation structures lean and effective. On the Technical side a serious, sustained multilateral program to develop, down select and performance test nuclear weapons dismantlement verification technologies and procedures should be immediately initiated. In order to make this happen the United States and Russia should join with the UK and other interested states in creating a sustained, full-scale research and development program for verification at their respective nuc1ear weapons and defense establishments. The goals include development of effective technologies and procedures for: (1) Attribute measurement systems to certify nuclear warheads and military fissile materials; (2) Chain-of-custody methods to track items after they are authenticated and enter accountability; (3) Transportation monitoring; (4) Storage monitoring; (5) Fissile materials conversion verification. The remainder of this paper focuses on transparency and verification for nuclear arms a

Doyle, James E [Los Alamos National Laboratory; Meek, Elizabeth [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

456

Wide-Field Lensing Mass Maps from DES Science Verification Data  

E-Print Network [OSTI]

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 deg^2 area from the Dark Energy Survey (DES) Science Verification (SV) data overlapping with the South Pole Telescope survey. 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. Cross-correlating the mass map with the foreground galaxies from the same DES SV data gives results consistent with mock catalogs 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 sigma level with 20 arcminute smoothing. A maj...

Vikram, V; Jain, B; Bacon, D; Amara, A; Becker, M; Bernstein, G; Bonnett, C; Bridle, S; Brout, D; Busha, M; Frieman, J; Gaztanaga, E; Hartley, W; Jarvis, M; Kacprzak, T; Lahav, O; Leistedt, B; Lin, H; Melchior, P; Peiris, H; Rozo, E; Rykoff, E; Sanchez, C; Sheldon, E; Troxel, M; 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; Rosell, A Carnero; Kind, M Carrasco; Castander, F J; Crocce, M; D'Andrea, C B; da Costa, L N; DePoy, D L; Desai, S; Diehl, H T; Dietrich, J P; Cunha, C E; Estrada, J; Evrard, A E; Neto, A Fausti; Fernandez, E; Flaugher, B; Fosalba, P; Gerdes, D; Gruen, D; Gruendl, R A; Honscheid, K; James, D; Kent, S; Kuehn, K; Kuropatkin, N; Li, T S; Maia, M A G; Makler, M; March, M; Marshall, J; Martini, Paul; Merritt, K W; Miller, C J; Miquel, R; Neilsen, E; Nichol, R C; Nord, B; Ogando, R; Plazas, A A; Romer, A K; Roodman, A; Sanchez, E; Scarpine, V; Sevilla, I; Smith, R C; Soares-Santos, M; Sobreira, F; Suchyta, E; Swanson, M E C; Tarle, G; Thaler, J; Thomas, D; Walker, A R; Weller, J

2015-01-01T23:59:59.000Z

457

A Survey on Compositional Verification Hong Peng and Sofi`ene Tahar  

E-Print Network [OSTI]

tangoute we2 mji1 (#2339 et #1903 dans Li 1998). Bien que cette équation semble possible pour la première'on prend au sérieux la glose donnée dans le texte. En effet, en tangoute, le nom `vache' se dit we2 (#395

Tahar, Sofiène

458

Final Report - Independent Verification Survey Activities at the Seperations Process Research Unit Sites, Niskayuna, New York  

SciTech Connect (OSTI)

The Separations Process Research Unit (SPRU) complex located on the Knolls Atomic Power Laboratory (KAPL) site in Niskayuna, New York, was constructed in the late 1940s to research the chemical separation of plutonium and uranium (Figure A-1). SPRU operated as a laboratory scale research facility between February 1950 and October 1953. The research activities ceased following the successful development of the reduction oxidation and plutonium/uranium extraction processes. The oxidation and extraction processes were subsequently developed for large scale use by the Hanford and Savannah River sites (aRc 2008a). Decommissioning of the SPRU facilities began in October 1953 and continued through the 1990s.

Evan Harpenau

2011-03-15T23:59:59.000Z

459

Final Report - Verification Survey of the Hot Cell Facility Site, General Atomics, San Diego, California.  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C. 20545*. . : '* FEB1f\l p :.;LIST OF

460

Aerial vehicle with paint for detection of radiological and chemical warfare agents  

DOE Patents [OSTI]

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.

Farmer, Joseph C.; Brunk, James L.; Day, S. Daniel

2013-04-02T23:59:59.000Z

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


461

Method for warning of radiological and chemical agents using detection paints on a vehicle surface  

DOE Patents [OSTI]

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.

Farmer, Joseph C. (Tracy, CA); Brunk, James L. (Martinez, CA); Day, S. Daniel (Danville, CA)

2012-03-27T23:59:59.000Z

462

Surface Radiation Survey at the Shepley’s Hill Remediation Site, Devens, Massachusettes  

SciTech Connect (OSTI)

The Idaho National Laboratory (INL) provided technical support for ongoing environmental remediation activities at the Shepley’s Hill remediation site, near Devens, MA. The technical support included the completion of a radiation survey of naturally occurring radioactive materials (NORM) at Shepley’s Hill, Shepley’s Hill landfill cover, and Red Cove areas. The objective of the radiation survey was to assess the ability of the INL backpack sodium iodide spectroscopy (BaSIS) system to detect elevated levels of NORM that may be associated with radon-222 emanation from near surface and subsurface fractures in the area. It is postulated that these fracture zones provide subsurface conduits for the transport of environmental contaminants. As such, location of these fracture sets will proved EPA Region 1 with the means for completing the development of an accurate site conceptual model. The results of the radiological survey show that some of the radiological anomalies correlate with currently mapped rock outcrops; however, not all of the rock outcrops in the surveyed area have been mapped. As such, it is not conclusive that all of the radiological anomalies correspond with surface rock outcrops. EPA Region 1 intends to perform a more comprehensive correlation of the radiation data collected with the BaSIS system with additional data sets such as detailed bedrock structural mapping, 2-dimensional resistivity profiling, and high-resolution topographic mapping. The results of this effort will be used in consideration of designing a potential follow-on effort for mapping of radon.

J. R. Giles; C. P. Oertel; L. G. Roybal

2009-09-01T23:59:59.000Z

463

MACCS2 development and verification efforts  

SciTech Connect (OSTI)

MACCS2 represents a major enhancement of the capabilities of its predecessor MACCS, the MELCOR Accident Consequence Code System. MACCS, released in 1987, was developed to estimate the potential impacts to the surrounding public of severe accidents at nuclear power plants. The principal phenomena considered in MACCS/MACCS2 are atmospheric transport and deposition under time-variant meteorology, short-term and long-term mitigative actions and exposure pathways, deterministic and stochastic health effects, and economic costs. MACCS2 was developed as a general-purpose analytical tool applicable to diverse reactor and nonreactor facilities. The MACCS2 package includes three primary enhancements: (1) a more flexible emergency response model, (2) an expanded library of radionuclides, and (3) a semidynamic food-chain model. In addition, errors that had been identified in MACCS version1.5.11.1 were corrected, including an error that prevented the code from providing intermediate-phase results. MACCS2 version 1.10 beta test was released to the beta-test group in May, 1995. In addition, the University of New Mexico (UNM) has completed an independent verification study of the code package. Since the beta-test release of MACCS2 version 1.10, a number of minor errors have been identified and corrected, and a number of enhancements have been added to the code package. The code enhancements added since the beta-test release of version 1.10 include: (1) an option to allow the user to input the {sigma}{sub y} and {sigma}{sub z} plume expansion parameters in a table-lookup form for incremental downwind distances, (2) an option to define different initial dimensions for up to four segments of a release, (3) an enhancement to the COMIDA2 food-chain model preprocessor to allow the user to supply externally calculated tables of tritium food-chain dose per unit deposition on farmland to support analyses of tritium releases, and (4) the capability to calculate direction-dependent doses.

Young, M.; Chanin, D.

1997-03-01T23:59:59.000Z

464

INDEPENDENT CONFIRMATORY SURVEY OF THE NUCLEAR RESEARCH LABORATORY AT THE UNIVERSITY OF ILLINOIS URBANA-CHAMPAIGN, ILLINOIS  

SciTech Connect (OSTI)

ORAU conducted confirmatory survey activities within the NRL at the University during the week of May 7, 2012. The survey activities included visual inspections/ assessments, surface activity measurements, and volumetric concrete sampling activities. During the course of the confirmatory activities, ORAU noted several issues with the survey-for-release activities performed at the University. Issues included inconsistencies with: survey unit classifications were not designated according to Multi-Agency Radiation Survey and Site Investigation Manual guidance; survey instrument calibrations were not representative of the radionuclides of concern; calculations for instrumentation detection capabilities did not align with the release criteria discussed in the licensee’s survey guidance documents; total surface activity measurements were in excess of the release criteria; and Co-60 and Eu-152 concentrations in the confirmatory concrete samples were above their respective guidelines. Based on the significant programmatic issues identified, ORAU cannot independently conclude that the NRL satisfied the requirements and limits for release of materials without radiological restrictions.

EVAN M. HARPENAU

2012-06-28T23:59:59.000Z

465

Precise Dynamic Verification of Noninterference Gurvan Le Guernic  

E-Print Network [OSTI]

Precise Dynamic Verification of Noninterference Gurvan Le Guernic INRIA-MSR - Parc Orsay Universit analysis is used to analyze some un- executed pieces of code in order to take into account all types is that nowadays it is nearly impossible for consumers to prevent the execution of "bad" code on their devices

Paris-Sud XI, Université de

466

A STROKE BASED ALGORITHM FOR DYNAMIC SIGNATURE VERIFICATION  

E-Print Network [OSTI]

A STROKE BASED ALGORITHM FOR DYNAMIC SIGNATURE VERIFICATION Tong Qu, Abdulmotaleb El Saddik, Andy a novel stroke-based algorithm for DSV. An algorithm is developed to convert sample signatures of individual strokes. Individual strokes are identified by finding the points where there is a 1) decrease

Adler, Andy

467

Exploring Reliability for Automatic Identity Verification with Statistical Shape Models  

E-Print Network [OSTI]

Exploring Reliability for Automatic Identity Verification with Statistical Shape Models Federico M reliability measure of the result. In fact, the segmentation process is One ofthe drawbacks ofstatistical to a wrong result [4]. generic reliability measure for statistical shape models. It This problem

Frangi, Alejandro

468

Cleanup Verification Package for the 118-F-6 Burial Ground  

SciTech Connect (OSTI)

This cleanup verification package documents completion of remedial action for the 118-F-6 Burial Ground located in the 100-FR-2 Operable Unit of the 100-F Area on the Hanford Site. The trenches received waste from the 100-F Experimental Animal Farm, including animal manure, animal carcasses, laboratory waste, plastic, cardboard, metal, and concrete debris as well as a railroad tank car.

H. M. Sulloway

2008-10-02T23:59:59.000Z

469

Contracts for Model Execution Verification Eric Cariou1  

E-Print Network [OSTI]

Contracts for Model Execution Verification Eric Cariou1 , Cyril Ballagny2 , Alexandre Feugas3 a contract-based approach to specify an execution semantics for a meta-model. We show that an execution model transformation contracts for controlling the dynamic con- sistent evolution of a model during its

Paris-Sud XI, Université de

470

Getting Out of the Way Safety Verification without Compromise  

E-Print Network [OSTI]

verification of adaptive cruise control algorithms require both discrete braking modes and overly conservative conditions for adaptive cruise control algorithms that do not require discontinuous braking and also allow · Assume global upper and lower braking bounds · Assume worst-case scenario (WCS) ­ Leader uses strongest

Sivilotti, Paul

471

STATE OF CALIFORNIA LOW LEAKAGE AIR HANDLER VERIFICATION  

E-Print Network [OSTI]

or heat pump fan and inside coil) must be certified to the Commission to leak 2 percent or less of its in the dwelling as applicable. System Name or Identification/Tag System Location or Area Served LLAH Unit Make LLAH Unit Model The LLAH must be connected to a New Duct System that meets the HERS verification

472

Self-adaptive software needs quantitative verification at Radu Calinescu  

E-Print Network [OSTI]

, performance and operating cost (e.g., energy consumption) of software. These techniques include model checkingSelf-adaptive software needs quantitative verification at runtime Radu Calinescu Department 1: The world and the machine. [19, 30]. In contrast, several mathematically-based modelling

Oxford, University of

473

Self-adaptive software needs quantitative verification at Radu Calinescu  

E-Print Network [OSTI]

, performance and operating cost (e.g., energy consumption) of software. These techniques include model checkingSelf-adaptive software needs quantitative verification at runtime Radu Calinescu Department"#.&*#.+$ Figure 1: The world and the machine. [19, 30]. In contrast, several mathematically-based modelling

Paris-Sud XI, Université de

474

Verification of Network Management System Configurations David L. Cohrs  

E-Print Network [OSTI]

, with the use of simple, ad hoc tools. However in a large network, managing the net- work management system the amount of sharing and coordination possible in configuring the net- work management system. EachVerification of Network Management System Configurations David L. Cohrs (608) 262-6617 dave

Miller, Barton P.

475

3D Scanning for Biometric Identification and Verification  

E-Print Network [OSTI]

June 2010 3D Scanning for Biometric Identification and Verification Project Leads Anselmo Lastra visibility, cannot be controlled. A relatively new biometric, 3D facial recognition, holds great promise performance using 3D shape and texture matched that of the much more mature technologies of high

McShea, Daniel W.

476

Automated Verification of Practical Garbage Collectors Chris Hawblitzel  

E-Print Network [OSTI]

Automated Verification of Practical Garbage Collectors Chris Hawblitzel Microsoft Research One Technion Haifa 32000 Israel erez@cs.technion.ac.il Abstract Garbage collectors are notoriously hard in reasoning about reachability in graphs. Several papers have presented verified collectors, but either

Petrank, Erez

477

Verification of Data-Aware Commitment-Based Multiagent System  

E-Print Network [OSTI]

on the dynamics of such systems, and on the evolution of their commitments. This requires to lift the commitment I.2.11 [Artificial Intelligence]: Distributed Artificial Intelligence--Multiagent Systems; D.2Verification of Data-Aware Commitment-Based Multiagent System Marco Montali Diego Calvanese KRDB

De Giacomo, Giuseppe

478

Neptunium flow-sheet verification at reprocessing plants  

SciTech Connect (OSTI)

Due to their fissile nature, neptunium and americium have at least a theoretical potential application as nuclear explosives and their proliferation potential was considered by the IAEA in studies in the late 1990's. This work was motivated by an increased awareness of the proliferation potential of americium and neptunium and a number of emerging projects in peaceful nuclear programmes which could result in an increase in the available quantities of these minor actinides. The studies culminated in proposals for various voluntary measures including the reporting of international transfers of separated americium and neptunium, declarations concerning the amount of separated neptunium and americium held by states and the application of flow-sheet verification to ensure that facilities capable of separating americium or neptunium are operated in a manner consistent with that declared. This paper discusses the issue of neptunium flowsheet verification in reprocessing plants. The proliferation potential of neptunium is first briefly discussed and then the chemistry of neptunium relevant to reprocessing plants described with a view to indicating a number of issues relevant to the verification of neptunium flow-sheets. Finally, the scope of verification activities is discussed including analysis of process and engineering design information, plant monitoring and sampling and the potential application of containment and surveillance measures. (authors)

Rance, P.; Chesnay, B.; Killeen, T.; Murray, M.; Nikkinen, M.; Petoe, A.; Plumb, J.; Saukkonen, H. [International Atomic Energy Agency, Wagramer Strasse 5, P.O. Box 100, A-1400 Vienna (Austria)

2007-07-01T23:59:59.000Z

479

Verification of Parallel Garbage Collection by Abstract Model Checking  

E-Print Network [OSTI]

have a finite state space provided that the abstraction mapping is powerful. M¨uller and Nipkow's work working on abstract model checking. In Section 4, the abstractions we defined on garbage #12; collectionVerification of Parallel Garbage Collection by Abstract Model Checking (Extended Abstract) Masami

Hagiya, Masami

480

Fast Verification of Wind Turbine Power Summary of Project Results  

E-Print Network [OSTI]

Fast Verification of Wind Turbine Power Curves: Summary of Project Results by: Cameron Brown ­ s equation on high frequency wind turbine measurement data sampled at one sample per second or more. The aim's Nordtank wind turbine at the Risø site, the practical application of this new method was tested

Note: This page contains sample records for the topic "radiological verification survey" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


481

Department of Computing CSP||B modelling for railway verification  

E-Print Network [OSTI]

University of Surrey Department of Computing Computing Sciences Report CS-12-03 CSP||B modelling Schneider Helen Treharne March 30th 2012 #12;CSP||B modelling for railway verification: the double junction work in verifying railway systems through CSP k B modelling and analysis. In particular we consider

Doran, Simon J.

482

Combining Tools for the Verification of FaultTolerant Systems  

E-Print Network [OSTI]

and verification of fault­tolerant systems according to the invent&verify paradigm. Our method is based on the CSP specifications (CSP process terms), refinement relations or combinations of these three description formalisms specification paradigms ac­ cording to the specific needs of each development step is essential to cope

Peleska, Jan - Fachbereich 3

483

2012 -2013 BIRTH DATE VERIFICATION STUDENT NAME: SPU ID  

E-Print Network [OSTI]

an official copy of your Birth Certificate, Passport, or Driver's License with this form and we will update2012 - 2013 BIRTH DATE VERIFICATION STUDENT NAME: SPU ID: The date of birth reported on your Free Application for Federal Student Aid (FAFSA) does not match the date of birth reported in one of the following

Nelson, Tim

484

2013 -2014 BIRTH DATE VERIFICATION STUDENT NAME: SPU ID  

E-Print Network [OSTI]

an official copy of your Birth Certificate, Passport, or Driver's License with this form and we will update2013 - 2014 BIRTH DATE VERIFICATION STUDENT NAME: SPU ID: The date of birth reported on your Free Application for Federal Student Aid (FAFSA) does not match the date of birth reported in one of the following

Nelson, Tim

485

Parameterized Specification and Verification of PLC Systems in Coq  

E-Print Network [OSTI]

Parameterized Specification and Verification of PLC Systems in Coq Hai Wan D.CST, Tsinghua and verify PLC software systems with the theorem proving system Coq. Dependent inductive data types are har to cope with this situation, modular development of PLC software is adopted. During the modular

Boyer, Edmond

486

Improving large-sized PLC programs verification using abstractions  

E-Print Network [OSTI]

Improving large-sized PLC programs verification using abstractions V. Gourcuff O. de Smet J [2005]) models of PLC programs, which can be verified with well- known model-checkers, like UPPAAL the development of industrial PLC programs up to now (John- son [2007]). Several reasons can explain

Paris-Sud XI, Université de

487

Venus: Verification for Untrusted Cloud Storage Alexander Shraer  

E-Print Network [OSTI]

Venus: Verification for Untrusted Cloud Storage Alexander Shraer Dept. of Electrical Engineering, Switzerland cca@zurich.ibm.com Asaf Cidon Dept. of Electrical Engineering Technion, Haifa, Israel asaf@cidon.com Idit Keidar Dept. of Electrical Engineering Technion, Haifa, Israel idish@ee.technion.ac.il Yan

Keidar, Idit

488

HEALTH AND ACCIDENT INSURANCE VERIFICATION ******************** TO BE COMPLETED BY STUDENT ********************  

E-Print Network [OSTI]

HEALTH AND ACCIDENT INSURANCE VERIFICATION ******************** TO BE COMPLETED BY STUDENT Services Office of the university of Florida requires that s/he has health and accident insurance with your participating in study abroad activate hold health and accident insurance with a minimum coverage of $200

Jawitz, James W.

489

FORECAST VERIFICATION OF EXTREMES: USE OF EXTREME VALUE THEORY  

E-Print Network [OSTI]

1 FORECAST VERIFICATION OF EXTREMES: USE OF EXTREME VALUE THEORY Rick Katz Institute for Study on Extremes · Emil Gumbel (1891 ­ 1966) -- Pioneer in application of statistics of extremes "Il est impossible que l'improbable n'arrive jamais." #12;3 OUTLINE (1) Motivation (2) Conventional Methods (3) Extreme

Katz, Richard

490

FORECAST VERIFICATION OF EXTREMES: USE OF EXTREME VALUE THEORY  

E-Print Network [OSTI]

1 FORECAST VERIFICATION OF EXTREMES: USE OF EXTREME VALUE THEORY Rick Katz Institute for Study ON EXTREMES · Emil Gumbel (1891 ­ 1966) -- Pioneer in application of statistics of extremes "Il est impossible que l'improbable n'arrive jamais." #12;3 OUTLINE (1) Motivation (2) Conventional Methods (3) Extreme

Katz, Richard

491

Multi-canister overpack project -- verification and validation, MCNP 4A  

SciTech Connect (OSTI)

This supporting document contains the software verification and validation (V and V) package used for Phase 2 design of the Spent Nuclear Fuel Multi-Canister Overpack. V and V packages for both ANSYS and MCNP are included. Description of Verification Run(s): This software requires that it be compiled specifically for the machine it is to be used on. Therefore to facilitate ease in the verification process the software automatically runs 25 sample problems to ensure proper installation and compilation. Once the runs are completed the software checks for verification by performing a file comparison on the new output file and the old output file. Any differences between any of the files will cause a verification error. Due to the manner in which the verification is completed a verification error does not necessarily indicate a problem. This indicates that a closer look at the output files is needed to determine the cause of the error.

Goldmann, L.H.

1997-11-10T23:59:59.000Z

492

Aerial Measuring System (AMS) Baseline Surveys for Emergency Planning  

SciTech Connect (OSTI)

Originally established in the 1960s to support the Nuclear Test Program, the AMS mission is to provide a rapid and comprehensive worldwide aerial measurement, analysis, and interpretation capability in response to a nuclear/radiological emergency. AMS provides a responsive team of individuals whose processes allow for a mission to be conducted and completed with results available within hours. This presentation slide-show reviews some of the history of the AMS, summarizes present capabilities and methods, and addresses the value of the surveys.

Lyons, C

2012-06-04T23:59:59.000Z

493