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1

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

SciTech Connect

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

2

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

SciTech Connect

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

3

I COMPREHENSIVE RADIOLOGICAL SURVEY I  

Office of Legacy Management (LM)

im im I COMPREHENSIVE RADIOLOGICAL SURVEY I Prepared by Oak Ridge Associated Universities Prprd* OFF-SITE PROPERTY H' | Prepared for Office of Operational FORMER LAKE ONTARIO ORDNANCE WORKS SITE Safety U.S. Department LEWISTON, NEW YORK I of Energy i J.D. BERGER i Radiological Site Assessment Program Manpower Education, Research, and Training Division I l*~~~~~~ ~~~~DRAFT REPORT January 1983 I I I ------- COMPREHENSIVE RADIOLOGICAL SURVEY OFF-SITE PROPERTY H' FORMER LAKE ONTARIO ORDNANCE WORKS SITE LEWISTON, NEW YORK Prepared for U.S. Department of Energy as part of the Formerly Utilized Sites -- Remedial Action Program J. D. Berger Project Staff L.W. Cole W.O. Helton R.D. Condra T.J. Sowell P.R. Cotten C.F. Weaver G.R. Foltz T.S. Yoo R.C. Gosslee Prepared by Radiological Site Assessment Program

4

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

SciTech Connect

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

5

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

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

6

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

7

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

SciTech Connect

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

W. C. Adams

2007-05-25T23:59:59.000Z

8

Survey of radiologic practices among dental practitioners  

SciTech Connect

The purpose of this study was to determine the factors that influence and contribute to patient exposure in radiologic procedures performed in the offices of 132 staff members within the dental department of a teaching hospital. A questionnaire was prepared in which data were requested on brands of film used, type of x-ray unit used, processing, and use of leaded apron, cervical shield, and film holder. Offices were also visited to evaluate performance of existing dental x-ray equipment. Both the Dental Radiographic Normalizing and Monitoring Device and the Dental Quality Control Test Tool were evaluated. The average exposure was equivalent to the class D film (220 mR), but only 13% of those surveyed used the faster class E film, which would reduce patient exposure in half. The survey indicates that dentists are not using the newer low-exposure class E film in their practices.

Goren, A.D.; Sciubba, J.J.; Friedman, R.; Malamud, H. (Long Island Jewish Medical Center, New Hyde Park, NY (USA))

1989-04-01T23:59:59.000Z

9

Autonomous mobile robot for radiologic surveys  

SciTech Connect

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

10

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

SciTech Connect

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

11

A mobile autonomous robot for radiological surveys  

SciTech Connect

The Robotics Development Group at the Savannah River Site is developing an autonomous robot (SIMON) to perform radiological surveys of potentially contaminated floors. The robot scans floors at a speed of one-inch/second and stops, sounds an alarm, and flashes lights when contamination in a certain area is detected. The contamination of interest here is primarily alpha and beta-gamma. The robot, a Cybermotion K2A base, is radio controlled, uses dead reckoning to determine vehicle position, and docks with a charging station to replenish its batteries and calibrate its position. It uses an ultrasonic ranging system for collision avoidance. In addition, two safety bumpers located in the front and the back of the robot will stop the robots motion when they are depressed. Paths for the robot are preprogrammed and the robots motion can be monitored on a remote screen which shows a graphical map of the environment. The radiation instrument being used is an Eberline RM22A monitor. This monitor is microcomputer based with a serial I/0 interface for remote operation. Up to 30 detectors may be configured with the RM22A.

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

1992-01-01T23:59:59.000Z

12

A mobile autonomous robot for radiological surveys  

SciTech Connect

The Robotics Development Group at the Savannah River Site is developing an autonomous robot (SIMON) to perform radiological surveys of potentially contaminated floors. The robot scans floors at a speed of one-inch/second and stops, sounds an alarm, and flashes lights when contamination in a certain area is detected. The contamination of interest here is primarily alpha and beta-gamma. The robot, a Cybermotion K2A base, is radio controlled, uses dead reckoning to determine vehicle position, and docks with a charging station to replenish its batteries and calibrate its position. It uses an ultrasonic ranging system for collision avoidance. In addition, two safety bumpers located in the front and the back of the robot will stop the robots motion when they are depressed. Paths for the robot are preprogrammed and the robots motion can be monitored on a remote screen which shows a graphical map of the environment. The radiation instrument being used is an Eberline RM22A monitor. This monitor is microcomputer based with a serial I/0 interface for remote operation. Up to 30 detectors may be configured with the RM22A.

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

1992-10-01T23:59:59.000Z

13

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

14

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

SciTech Connect

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

15

OAK RIDGE NATIONAL LABORATORY RESULTS OF THE INDEPENDENT RADIOLOGICAL  

Office of Legacy Management (LM)

ornl< ORNLRASA-8664 (MJ18V) orni OAK RIDGE NATIONAL LABORATORY RESULTS OF THE INDEPENDENT RADIOLOGICAL EZ-BBBB - *VERIFICATION SURVEY AT THE BALLOD ASSOCIATES PROPERTY,...

16

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

SciTech Connect

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

17

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

SciTech Connect

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

18

Survey of Existing Tools for Formal Verification.  

SciTech Connect

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

19

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

Office of Legacy Management (LM)

K e l l e r , D i r e c t o r T e c h n i c a l S e r v i c e s D i v i s i o n 0ak Ridge Operations 0ffice The radiological survey data for the subject vicinity property has been...

20

VERIFICATION SURVEY OF THE BAKER AND WILLIAMS WAREHOUSES  

Office of Legacy Management (LM)

~ *-,-' .r_~, ~ *-,-' .r_~, VERIFICATION SURVEY OF THE BAKER AND WILLIAMS WAREHOUSES BUILDING 513-519 NEW YORK, NEW YORK Prepared by W. C. Adams Environmental Survey and Site Assessment Program Energy/Environment Systems Division Oak Ridge Institute for Science and Education Oak Ridge, Tennessee 37831-0117 Prepared for the Office of Environmental Restoration U.S. Department of Energy FINAL REPORT JUNE 1994 This report is based on work performed under contract number DE-AC05-760R00033 with the U.S. Department of Energy. Baker arId Wi,,iMI Wsrchouwl-Vcrification June 28, ,994 - ,I I_ ..I .- VERIFICATION SURVEY OF THE BAKER AND W ILLIAMS WAREHOUSES BUILDING 513-519 NEW YORK, NEW YORK Prepared by: ' J .,,,~ ' . W . C. Adams, Project Leader Date: Environmental Survey and Site Assessment 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.


21

Oak Ridge Associated VERIFICATION SURVEY Universities OF THE  

Office of Legacy Management (LM)

ORAU 89/K-79 ORAU 89/K-79 Prepared by ERIFICATION Oak Ridge Associated VERIFICATION SURVEY Universities OF THE Drepared of SHIPPINGPORT ATOMIC POWER STATION Facility and Site Decommissioning SHIPPINGPORT, PENNSYLVANIA I Projects U.S. Department R LANDIS ot Energy M. R. LANDIS ot Energy Environmental Survey and Site Assessment Program Energy/Environment Systems Division FINAL REPORT .i~ ~~ . ~NOVEMBER 1989 .Ii_- ORAU 89/K-79 VERIFICATION SURVEY OF THE SHIPPINGPORT ATOMIC POWER STATION SHIPPINGPORT, PENNSYLVANIA Prepared by M. R. Landis Environmental Survey and Site Assessment Program Energy/Environment Systems Division Oak Ridge Associated Universities 3*P~~~ ~~Oak Ridge, Tennessee 37831-0117 U~~~~~~~~1 ~Project Staff S. F. Barnett F. A. Payne J. D. Berger J. L. Payne G. R. Foltz E. A. Powell

22

Photometric redshift analysis in the Dark Energy Survey Science Verification data  

Science Journals Connector (OSTI)

......Photometric redshift analysis in the Dark Energy Survey Science Verification data C...redshift performance of the Dark Energy Survey (DES), using the early data...the photometric survey. The Dark Energy Survey (DES; Flaugher 2005) is one......

C. Sánchez; M. Carrasco Kind; H. Lin; R. Miquel; F. B. Abdalla; A. Amara; M. Banerji; C. Bonnett; R. Brunner; D. Capozzi; A. Carnero; F. J. Castander; L. A. N. da Costa; C. Cunha; A. Fausti; D. Gerdes; N. Greisel; J. Gschwend; W. Hartley; S. Jouvel; O. Lahav; M. Lima; M. A. G. Maia; P. Martí; R. L. C. Ogando; F. Ostrovski; P. Pellegrini; M. M. Rau; I. Sadeh; S. Seitz; I. Sevilla-Noarbe; A. Sypniewski; J. de Vicente; T. Abbot; S. S. Allam; D. Atlee; G. Bernstein; J. P. Bernstein; E. Buckley-Geer; D. Burke; M. J. Childress; T. Davis; D. L. DePoy; A. Dey; S. Desai; H. T. Diehl; P. Doel; J. Estrada; A. Evrard; E. Fernández; D. Finley; B. Flaugher; J. Frieman; E. Gaztanaga; K. Glazebrook; K. Honscheid; A. Kim; K. Kuehn; N. Kuropatkin; C. Lidman; M. Makler; J. L. Marshall; R. C. Nichol; A. Roodman; E. Sánchez; B. X. Santiago; M. Sako; R. Scalzo; R. C. Smith; M. E. C. Swanson; G. Tarle; D. Thomas; D. L. Tucker; S. A. Uddin; F. Valdés; A. Walker; F. Yuan; J. Zuntz

2014-01-01T23:59:59.000Z

23

An aerial radiological survey of the Nevada Test Site  

SciTech Connect

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

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

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

25

I RADIOLOGICAL SCOPING SURVEY OF FO,RMER MONSANTO' FACILITIES  

Office of Legacy Management (LM)

-I a.d *4dk *-f--l- -I a.d *4dk *-f--l- --- I. ,e-- - .- --_ -- -. ;,. -* " . I . RADIOLOGICAL SCOPING SURVEY OF FO,RMER MONSANTO' FACILITIES (Unit XII and W a rehouse) DAYTON, OHIO Report Date: 4 September 1997 Survey Dak 27 Aitgust 1991 Prepared by: Mark L. Mays, Chief Radiation Safety Branch Sponsored by: M iamisburg Environmental Matigement Reject Office Ohio FTekl Ofice U.S.. Department of Energy Conducted by: %diation Safety Branch Of&e of Environmental Management ggtb Air Base W ing U.S. Departmtnt of the Air Force In Cooperation W ith: Southwest District Office Ohio Environmental Protection Agency - O h io Cnvironmwhl Protection Agenty Bureau of Radiological Health Ohio Department of Health. I Lb ^U .L*-u i-.-r- --- , .., II ,.--(_ ~_ -_- --- -_ _.. ;

26

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

SciTech Connect

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

Northern Marshall Islands radiological survey: sampling and analysis summary  

SciTech Connect

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

28

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

SciTech Connect

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

29

The Northern Marshall Islands radiological survey: Data and dose assessments  

SciTech Connect

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

30

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

SciTech Connect

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

31

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

SciTech Connect

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

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

1993-09-01T23:59:59.000Z

32

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

SciTech Connect

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

33

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

SciTech Connect

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

34

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

SciTech Connect

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

35

Lessons Learned from Independent Verification Activities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Demonstration Demonstration Oak Ridge Institute for Science and Education - Independent Verification Lessons Learned IV - performed at nine DOE sites from 2004 to 2008 Page 1 of 2 Oak Ridge Institute for Science and Education Multiple Sites Lessons Learned from Independent Verification Activities Challenge The Department of Energy clears property from radiological control after the property has been demonstrated to meet the Department's stringent radiation protection requirements. Radiological surveys are used to demonstrate compliance with the requirements. Independent verification (IV) activities are conducted by an independent third party as a quality check on radiological surveys procedures and practices. The Oak Ridge Institute for Science and Education (ORISE) performs independent verification for the Department. In this lessons learned report, ORISE summarizes their

36

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

SciTech Connect

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

37

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

SciTech Connect

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

38

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

SciTech Connect

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

39

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

Office of Legacy Management (LM)

Environmental Survey and Site Assessment Program EnergyEnvironment Systems Division Oak Ridge Associated Universities Oak Ridge, TN 37831-0117 Project Staff E. A. Powell R....

40

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

Office of Legacy Management (LM)

RADIOLOGICAL SURVEY RADIOLOGICAL SURVEY AT 5823/5849 NORTH RAVENSWOOD AVEXJE CHICAGO, ILLINOIS Prepared by M.R. LANDIS Environmental Survey and Site Assessment Program Energy/Environment Systems Division Oak Ridge Associated Universities Oak Ridge, TN 37831-0117 Project Staff J.D. Berger R.C. Gosslee E.A. Powell G.R. Foltz M.J. Laudeman A. Wallo* C.F. Weaver Prepared for U.S. Department of Energy as part of the Formerly Utilized Sites - Remedial Action Program FINAL REPORT OCTOBER 1989 This report is based on work performed under contract number DE-AC05-760RC0033 with the U.S. Department of Energy. *with the U.S. Department of Energy, Division of Facility and Site Decommissioning -- LIST OF FIGURES Page FIGURE 1: Map of Chicago, Illinois Indicating the Location of the Facility at

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

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

42

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

SciTech Connect

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

43

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

Office of Legacy Management (LM)

Health and Safety Research Division Health and Safety Research Division RESULTS FROM A RADIOLOGICAL SURVEY ON YARDEORO AVENUE, ALBANY, AND CENTRAL AVENUE,, COLONIE, NEW YORK PROPERTIES AL013 - AL028 July 1984 Work performed as part of the RADIOLOGICAL SURVEY ACTIVITIES PROGRAM OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37831 operated by MARTIN MARIETTA ENERGY SYSTEMS, INC. for the U.S. DEPARTMENT OF ENERGY under Contract No. DE-AC05840R21400 _- _^." .-. ..-.- _---.--_ -... .- Fk. 3 ,=. Y)*cx gs 1 XEC @ d +I? ,%r $ g .&- _-.. .iTL--- d= m k m t Y iT 5 tn + a UT + t- 7 T? Y 0 + z cd (f c 0 W -7 0 9 0 oc !. __ g b a is d oJ F ig. 1. G a m m a exposure rates measured at the surface at grid points at 50 Yardboro Avenue, Albany, New York (AL013). . EE ?I 0 Es . m: 4 a I .r

44

PRELIMINqRY RADIOLOGICAL SURVEY REPORT OF THE FORMER STATEN ISLAND WAREHOUSE SITE  

Office of Legacy Management (LM)

pJ y, 22/4 pJ y, 22/4 PRELIMINqRY RADIOLOGICAL SURVEY REPORT OF THE FORMER STATEN ISLAND WAREHOUSE SITE (ARCHER-DANIELS MIOLANO COMPANY) AT PORT RICHMOND, NEW YORK ./ Work performed by the Health and Safety Research Division Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 . . ' October 1980 OAK RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPORATION for the DEPARTMENT OF ENERGY as part of the Former1 y Uti 1 i ted Sites-- Remedial Action Program PRELIMINARY RADIOLOGICAL SURVEY REPORT OF THE FORMER STATEN ISLANI I WAREHOUSE SITE (ARCHER-OANIELS MIDLAND COMPANY) AT PORT RICHMOND, NEW YORK B. A. Berven and C. Clark Introduction A number of buildings located at the site of the former Staten Island Warehouse in Port Richmond, New York, were used by Union Minie're

45

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

Office of Legacy Management (LM)

A" 917 A" 917 RADIOLOGICAL SURVEY OF A PORTION OF PROPERTY OWNED BY MODERN LANDFILL, INC. - FORMER LOOW SITE Summary Report Work performed by the Health and Safety Research Division Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 March 1981 OAK RIDGE NATIONAL LABORATORY operated by UNION. CARBIDE CORPORATION for the DEPARTMENT OF ENERGY as part of the Formerly Utilized Sites-- Remedial Action Program CONTENTS Page LIST OF FIGURES .. .. . .. . . . . . . . ......... iii LIST OF TABLES ......... .. iv INTRODUCTION .. ......... 1 OBJECTIVE .................... 1 SURVEY TECHNIQUES . . ............. ...... 1 RESULTS ..... 2 Gamma-Ray Exposure Rates . . . . . . 2 Beta-Gamma Dose Rate ............. 2 226Ra in Soil ............ 3 CONCLUSIONS .. . . . . . . . . . . . .. .. . .. .. 3 REFERENCES . . . . . . . . .

46

RADIOLOGICAL SURVEY OF THE GUN FORGING MACHINE BUILDING ITHACA GUN COMPANY  

Office of Legacy Management (LM)

SURVEY SURVEY OF THE GUN FORGING MACHINE BUILDING ITHACA GUN COMPANY ITHACA, NEW YORK T. J. VITKUS AND J. L. PAYNE Prepared for the Office of Erivironmental Restoration U.S.' Department of Energy ORISE 95/K-1 3 RADIOLOGICAL SURVEY OF THE GUN FORGING MACHINE BUILDING ITHACA GUN COMPANY ITHACA, NEW YORK Prepared by T. J. Vi&us and J. L. Payne Environme& Survey and Site Assessment Program Envirotiental and Health Sciences Group Oak Ridge Institute for Science and Education Oak Ridge, Tennessee 37831-0117 Prepared for the U.S. Department of Energy Offke of Environmental Restoration FINAL REPORT OCTOBER 1995 This report is based on work performed under contract number DE-AC05-760R00033 with the U.S. Department of Energy. .I I I I I I I I 1 I I I ' I

47

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

SciTech Connect

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

48

An aerial radiological survey of the Pilgrim Station Nuclear Power Plant and surrounding area, Plymouth, Massachusetts  

SciTech Connect

Terrestrial radioactivity surrounding the Pilgrim Station Nuclear Power Plant was measured using aerial radiolog- ical survey techniques. The purpose of this survey was to document exposure rates near the plant and to identify unexpected, man-made radiation sources within the survey area. The surveyed area included land areas within a three-mile radius of the plant site. Data were acquired using an airborne detection system that employs sodium iodide, thallium-activated detectors. Exposure rate and photopeak counts were computed from these data and plotted on aerial photographs of the survey area. Several ground-based exposure measurements were made for comparison with the,aerial survey results. Exposure rates in areas surrounding the plant site varied from 6 to 10 microroentgens per hour, with exposure rates below 6 microroentgens per hour occurring over bogs and marshy areas. Man-made radiation was found to be higher than background levels at the plant site. Radation due to nitrogen-1 6, which is produced in the steam cycle of a boiling-water reactor, was the primaty source of activity found at the plant site. Cesium-137 activity at levels slightly above those expected from natural fallout was found at isolated locations inland from the plant site. No other detectable sources of man-made radioactivity were found.

Proctor, A.E.

1997-06-01T23:59:59.000Z

49

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

Office of Legacy Management (LM)

COT"IPREITENS IVE RADIOLOGICAL COT"IPREITENS IVE RADIOLOGICAL SURVEY OFF-SITE PROPERTY P NIAGARA FALIS STORAGE SITE LEWISTON, NEW YORK Prepared for U.S. DePartment of EnergY as part of the Formerly Utilized Sites - Remedial ActLon Program J . D . B e r g e r P r o j e c t S t a f f J. Burden* w.L. Smlth* R.D. Condra T.J. Sowell J.S . Epler* G.M. S tePhens P.Iil. Frame L.B. Taus* W . 0 . H e l t o n C . F . W e a v e r R . C . G o s s l e e B . S . Z a c h a r e k d I I Prepared bY Radiological Slte Assessoent Progran Manpower Educailon Research, and Training Dlvision Oak Ridge Assoclated Universlties Oak Ridge, Tennessee 3783f-0117 I FINAL REPORT March 1984 Thts report ls based on work performed under contract number DE-AC05-760R00033 wiLh the DePartment of EnergY. *Evaluatlon Research Corporatlon, Oak Ridge, Tennessee TABLE OF CONTENTS L i s t o f F i g u

50

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

SciTech Connect

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

51

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

SciTech Connect

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

52

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

SciTech Connect

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

53

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

SciTech Connect

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

54

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

Office of Legacy Management (LM)

luSA-85/6 luSA-85/6 Health and Safety Research Division PRELIMINARY RADIOLOGICAL SURVEY OF TEE FORMER HAVENS PLANT OF TEE BRIDGEPORT BRASS COMPANY, BRIDGEPORT, CONNECTICUT May 1985 Work performed as part of the RADIOLOGICAL SURVEY ACCIVITIES PROGRAM OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37831 operated by MARTIN MARIETTA ENERGY SYSTEMS, INC. for the U. S. DEPARTMENT OF ENERGY under Contract No. DE-AC05-840R21400 \ .-l__--.-- -- PRELIMINARY RADIOLOGICAL SURVEY OF THE FORMER HAVENS PLAEJT OF THE BRIDGEPORT BRASS COMPANY, BRIDGEPORT, CONNECTICUT INTRODUCI' ION The Bridgeport Brass Company' s Havens plant located at Kossath and Pulaski Streets, Bridgeport, Connecticut. was used under contract with the Atomic Energy Commission (AEC) to process uranium during the period

55

An Aerial Radiological Survey of Selected Areas of the City of North Las Vegas  

SciTech Connect

As part of the proficiency training for the Radiological Mapping mission of the Aerial Measuring System (AMS), a survey team from the Remote Sensing Laboratory-Nellis (RSL-Nellis) conducted an aerial radiological survey of selected areas of the city of North Las Vegas for the purpose of mapping natural radiation background and locating any man-made radioactive sources. Survey areas were selected in collaboration with the City Manager's office and included four separate areas: (1) Las Vegas Motor Speedway (10.6 square miles); (2) North Las Vegas Downtown Area (9.2 square miles); (3) I-15 Industrial Corridor (7.4 square miles); and (4) Future site of University of Nevada Las Vegas campus (17.4 square miles). The survey was conducted in three phases: Phase 1 on December 11-12, 2007 (Areas 1 and 2), Phase 2 on February 28, 2008 (Area 3), and Phase 3 on March 19, 2008 (Area 4). The total completed survey covered a total of 44.6 square miles. The flight lines (without the turns) over the surveyed areas are presented in Figures 1, 2, 3, and 4. A total of eight 2.5-hour-long flights were performed at an altitude of 150 ft above ground level (AGL) with 300 feet of flight-line spacing. Water line and test line flights were conducted over the Lake Mead and Government Wash areas to ensure quality control of the data. The data were collected by the AMS data acquisition system (REDAR V) using an array of twelve 2-inch x 4-inch x 16-inch sodium iodide (NaI) detectors flown on-board a twin-engine Bell 412 helicopter. Data, in the form of gamma energy spectra, were collected continually (every second) over the course of the survey and were geo-referenced using a differential Global Positioning System. Collection of spectral data allows the system to distinguish between ordinary fluctuations in natural background radiation levels and the signature produced by man-made radioisotopes. Spectral data can also be used to identify specific radioactive isotopes. As a courtesy service, with the approval of the U.S. Department of Energy, National Nuclear Security Administration, Nevada Site Office, RSL-Nellis is providing this summary to the office of the Mayor of the City of North Las Vegas along with the gross-count-based exposure rate and man-made count contour maps and GIS shape files in electronic format on a compact disk.

Piotr Wasiolek

2008-06-01T23:59:59.000Z

56

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

SciTech Connect

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

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

1986-10-01T23:59:59.000Z

57

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

SciTech Connect

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

58

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

SciTech Connect

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

59

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

SciTech Connect

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

60

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

SciTech Connect

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

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
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61

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

SciTech Connect

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

62

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

SciTech Connect

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

63

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

SciTech Connect

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

64

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

SciTech Connect

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

65

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

SciTech Connect

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

66

Photometric redshift analysis in the Dark Energy Survey Science Verification data  

E-Print Network (OSTI)

We present results from a study of the photometric redshift performance of the Dark Energy Survey (DES), using the early data from a Science Verification (SV) period of observations in late 2012 and early 2013 that provided science-quality images for almost 200 sq.~deg.~at the nominal depth of the survey. We assess the photometric redshift performance using about 15000 galaxies with spectroscopic redshifts available from other surveys. These galaxies are used, in different configurations, as a calibration sample, and photo-$z$'s are obtained and studied using most of the existing photo-$z$ codes. A weighting method in a multi-dimensional color-magnitude space is applied to the spectroscopic sample in order to evaluate the photo-$z$ performance with sets that mimic the full DES photometric sample, which is on average significantly deeper than the calibration sample due to the limited depth of spectroscopic surveys. Empirical photo-$z$ methods using, for instance, Artificial Neural Networks or Random Forests, y...

Sánchez, C; Lin, H; Miquel, R; Abdalla, F B; Amara, A; Banerji, M; Bonnett, C; Brunner, R; Capozzi, D; Carnero, A; Castander, F J; da Costa, L A N; Cunha, C; Fausti, A; Gerdes, D; Greisel, N; Gschwend, J; Hartley, W; Jouvel, S; Lahav, O; Lima, M; Maia, M A G; Martí, P; Ogando, R L C; Ostrovski, F; Pellegrini, P; Rau, M M; Sadeh, I; Seitz, S; Sevilla-Noarbe, I; Sypniewski, A; de Vicente, J; Abbot, T; Allam, S S; Atlee, D; Bernstein, G; Bernstein, J P; Buckley-Geer, E; Burke, D; Childress, M J; Davis, T; DePoy, D L; Dey, A; Desai, S; Diehl, H T; Doel, P; Estrada, J; Evrard, A; Fernández, E; Finley, D; Flaugher, B; Gaztanaga, E; Glazebrook, K; Honscheid, K; Kim, A; Kuehn, K; Kuropatkin, N; Lidman, C; Makler, M; Marshall, J L; Nichol, R C; Roodman, A; Sánchez, E; Santiago, B X; Sako, M; Scalzo, R; Smith, R C; Swanson, M E C; Tarle, G; Thomas, D; Tucker, D L; Uddin, S A; Valdés, F; Walker, A; Yuan, F; Zuntz, J

2014-01-01T23:59:59.000Z

67

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

Office of Legacy Management (LM)

TM-11118 TM-11118 RESULTS OF THE RADIOLOGICAL SURVEY AT METPATH INCORPORATED, 1 MALCOLM AVENUE, TETERBORO, NEW JERSEY (TJOO3) FL D. Foley L. M. Floyd, Printed in the United States of America. Available from National Technical Information Serwce U.S. Department of Commerce I 5265 Port Royal Road. Springfield, Virginia 22161 NTIS price codes-Printed Copy:A03 Microfiche A01 This report was prepared as an account of work sponsored by an 8ge"cy of the UnitedSlaterGovernmenl.NeithertheUnitedStatesGovernmen~no,anyagency thereof. nor any 01 their employees. makes any warranty. express 0, implied. 0, assumes any legal liabhty or responsibility lo, the accuracy. completeness. 0, UJB~U~WSJ of any information. apparatus. product. or process disClosed. or represents that its use would not infringe privately owned rights. Reference herein

68

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

SciTech Connect

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

69

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

SciTech Connect

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

70

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

SciTech Connect

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

71

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

E-Print Network (OSTI)

We measure the weak-lensing masses and galaxy distributions of four massive galaxy clusters observed during the Science Verification phase of the Dark Energy Survey with the purpose of 1) validating the DECam imager for the task of measuring weak-lensing shapes, and 2) utilizing DECam's large field of view to map out the clusters and their environments over 90 arcmin. We conduct a series of rigorous tests on astrometry, photometry, image quality, PSF modeling, and shear measurement accuracy to single out flaws in the data and also to identify the optimal data processing steps and parameters. We find Science Verification data from DECam to be suitable for lensing analyses. The PSF is generally well-behaved, but the modeling is rendered difficult by a flux-dependent PSF width. We employ photometric redshifts to distinguish between foreground and background galaxies, and a red-sequence cluster finder to provide cluster richness estimates and cluster-galaxy distributions. By fitting NFW profiles to the clusters i...

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

2014-01-01T23:59:59.000Z

72

RADIOLOGICAL SURVEY STATION DEVELOPMENT FOR THE PIT DISASSEMBLY AND CONVERSION PROJECT  

SciTech Connect

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

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

2011-05-22T23:59:59.000Z

73

An aerial radiological survey of the neutron products company and surrounding area  

SciTech Connect

An aerial radiological survey was conducted from November 1-10, 1993, over the Neutron Products Company and neighboring areas. The company, located in Dickerson, Maryland, has two major operations involving the radioisotope cobalt-60 ({sup 60}Co)-the manufacture of commercial {sup 60}Co sources and the sterilization of medical products by exposure to radiation. The sterilization facility consists of two {sup 60}Co sources with activities of approximately 500,000 and 1,500,000 Ci, respectively. The purpose of the aerial survey was to detect and document any anomalous gamma-emitting radionuclides in the environment which may have resulted from operations of the Neutron Products Company. The survey covered two areas: the first was a 6.5- by 6.5-kilometer area centered over the Neutron Products facility; the second area was a 2- by 2.5-kilometer region surrounding a waste pumping station on Muddy Branch in Gaithersburg, Maryland. This site is approximately fifteen kilometers southeast of the Neutron Products facility and was included because sanitary and other liquid waste materials from the plant site are being disposed of at the pumping station. Contour maps showing gamma radiation exposure rates at 1 meter above ground level, overlaid on an aerial photo of the area, were constructed from the data measured during the flights. The exposure rates measured within the survey regions were generally uniform and typical of rates resulting from natural background radiation. Only one area showed an enhanced exposure rate not attributable to natural background. This area, located directly over the Neutron Products facility, was analyzed and identified as {sup 60}Co, the radioisotope used in the irradiation and source production operations conducted at the Neutron Products Company. The measurements over the Muddy Branch area in Gaithersburg were typical of natural background radiation and showed no evidence of {sup 60}Co or any other man-made radionuclide.

Vojtech, R.J.

1994-12-01T23:59:59.000Z

74

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

SciTech Connect

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

75

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

SciTech Connect

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

76

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

SciTech Connect

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

77

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

SciTech Connect

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

78

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

SciTech Connect

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

79

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

SciTech Connect

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

80

Results of the radiological survey at the Niagara-Mohawk property, Railroad Avenue, Colonie, New York (AL218)  

SciTech Connect

A number of properties in the Albany/Colonie area have been identified as being potentially contaminated with uranium originating from the former National Lead Company's uranium forming plant in Colonie, New York. The Niagara-Mohawk property on Railroad Avenue in Colonie, New York, was the subject of a radiological investigation initiated June 11, 1987. This commercial property is an irregularly shaped lot partially occupied by an electric power substation and associated transmission lines. Portions of the property that were swampy and heavily vegetated were inaccessible to the survey team. There are no buildings on the property. A diagram showing the approximate boundaries and the 15-m grid network established for measurements on the property is shown. The lot included in the radiological survey was /approximately/45 m wide by 246 m deep. Two views of the property are shown. 13 refs., 6 figs., 4 tabs.

Marley, J.L.; Carrier, R.F.

1987-12-01T23:59:59.000Z

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

An aerial radiological survey of the Kennedy Space Center and Cape Canaveral Air Force Station and surrounding area, Titusville, Florida: Date of survey: October 1985  

SciTech Connect

An aerial radiological survey of the entire Kennedy Space Center (KSC) and Cape Canaveral Air Force Station (CCAFS) was performed during the period 9 through 23 October 1985. This survey was conducted in three parts. First, a low resolution, low sensitivity background survey was performed that encompassed the entire KSC and CCAFS area. Next, two smaller, high resolution, high sensitivity surveys were conducted: the first focused on Launch Complexes 39A and 39B, and the second on the Shuttle Landing Facility. The areas encompassed by the surveys were 200, 5.5, and 8.5 square miles (500, 14, and 22 sq km), respectively. The purpose of these surveys was to provide information useful for an emergency response to a radiological accident. Results of the background survey are presented as isoradiation contour maps of both total exposure rate and man-made gross count superimposed on a mosaic of recent aerial photographs. Results of the two small, detailed surveys are also presented as an isoradiation contour map of exposure rate on the aerial photograph base. These data were evaluated to establish sensitivity limits for mapping the presence of plutonium-238. Natural background exposure rates at the Kennedy Space Center and Cape Canaveral Air Force Station are very low, generally ranging from 4 to 6.5 microroentgens per hour (..mu..R/h) and less than 4 ..mu..R/h in wet areas. However, exposure rates in developed areas were observed to be higher due to the importation of construction materials not characteristic of the area. 8 refs., 3 figs., 4 tabs.

Not Available

1988-01-01T23:59:59.000Z

82

Verification of Model Transformations: A Survey of the State-of-the-Art  

Science Journals Connector (OSTI)

Within the Model-Driven Engineering paradigm, software development is based on the definition of models providing different views of the system to be constructed and model transformations supporting a (semi)automatic development process. The verification of models and model transformations is crucial in order to improve the quality and the reliability of the products developed using this paradigm. In this context, the verification of a model transformation has three main components: the transformation itself, the properties of interest addressed, and the verification techniques used to establish the properties. In this paper we present an exhaustive review of the literature on the verification of model transformations analyzing these three components. We also take a problem-based approach exemplifying those aspects of interest that could be verified on a model transformation and show how this can be done. Finally, we conclude the need of an integrated environment for addressing the heterogeneous verification of model transformations.

Daniel Calegari; Nora Szasz

2013-01-01T23:59:59.000Z

83

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

SciTech Connect

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

84

Aerial radiological survey of the area surrounding the UNC Recovery Systems Facility, Wood River Junction, Rhode Island  

SciTech Connect

An aerial radiological survey to measure terrestrial gamma radiation was carried out over the United Nuclear Corporation (UNC) Recovery Systems Facility located near Wood River Junction, Rhode Island. At the time of the survey (August 1979) materials were being processed at the facility. Gamma ray data were collected over a 3.28 km/sup 2/ area centered on the facility by flying north-south lines spaced 60 m apart. Processed data indicated that detected radioisotopes and their associated gamma ray exposure rates were consistent with those expected from normal background emitters, except directly over the UNC Facility. Average exposure rates 1 m above the ground, as calculated from the aerial data, are presented in the form of an isopleth map. No ground sample data were taken at the time of the aerial survey.

Bluitt, C.M.

1981-05-01T23:59:59.000Z

85

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

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

86

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

SciTech Connect

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

87

An aerial radiological survey of Project Gasbuggy and surrounding area, Rio Arriba County, New Mexico. Date of survey: October 27, 1994  

SciTech Connect

An aerial radiological survey was conducted over the Project Gasbuggy site, 55 miles (89 kilometers) east of Farmington, New Mexico, on October 27, 1994. Parallel lines were flown at intervals of 300 feet (91 meters) over a 16-square-mile (41-square-kilometer) area at a 150-foot (46-meter) altitude centered on the Gasbuggy site. The gamma energy spectra obtained were reduced to an exposure rate contour map overlaid on a high altitude aerial photograph of the area. The terrestrial exposure rate varied from 14 to 20 {micro}R/h at 1 meter above ground level. No anomalous or man-made isotopes were found.

NONE

1995-08-01T23:59:59.000Z

88

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

SciTech Connect

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

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

1989-06-01T23:59:59.000Z

89

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

SciTech Connect

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

90

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

SciTech Connect

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

91

ORISE: Independent verification  

NLE Websites -- All DOE Office Websites (Extended Search)

Independent verification Independent verification ORISE techinician performs environmental scanning The Oak Ridge Institute for Science and Education (ORISE) performs independent environmental assessments and verification to determine the effectiveness of radiological cleanup at decontamination and decommissioning (D&D) projects across the United States. Since 1980, ORISE has performed independent verification at more than 500 sites in 42 states and the District of Columbia. As the primary independent verification contractor for all U.S. Department of Energy (DOE) cleanup projects and the only verification contractor for the U.S. Nuclear Regulatory Commission (NRC), we validate that soil, water and structures are within established state and federal release criteria, and can be safely designated for public use.

92

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

SciTech Connect

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

93

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

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

94

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

SciTech Connect

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

95

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

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

96

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

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

97

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

SciTech Connect

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

98

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

SciTech Connect

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

99

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

SciTech Connect

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

100

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

SciTech Connect

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

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101

A survey on contrast radiography and adverse reaction in the radiology departments of university dental hospitals in Japan  

Science Journals Connector (OSTI)

We analyzed the results of a questionnaire regarding the use of contrast radiography and computed tomography (CT), and the reactions to contrast media during 1993, which was sent to 28 Radiology Departments of Un...

Kenji Yuasa D.D.S.; Ph.D.; Koichi Yonetsu D.D.S. Ph.D.…

1996-12-01T23:59:59.000Z

102

ORNL-5680 Radiological Surveys  

Office of Legacy Management (LM)

These guidelines recommend the following graded action levels for remedial action in terms of external gamma radiation level (EGR) and indoor radon daughter concentration level...

103

Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Radiological Control Technician Training Facility Practical Training Attachment Phase IV Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy DOE-HDBK-1122-2009 ii This page intentionally left blank DOE-HDBK-1122-2009 iii Table of Contents Page Introduction................................................................................................................................1 Facility Job Performance Measures ........................................................................................2 Final Verification Signatures ....................................................................................................3 DOE-HDBK-1122-2009 iv

104

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

SciTech Connect

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

ADAMS, WADE C

2013-04-18T23:59:59.000Z

105

EMSL - radiological  

NLE Websites -- All DOE Office Websites (Extended Search)

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

106

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

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

107

Radiological Assistance Program (RAP)- Nuclear Engineering Division  

NLE Websites -- All DOE Office Websites (Extended Search)

Major Programs > Radiological Major Programs > Radiological Assistance Program Radiological Assistance Program Overview Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Radiological Assistance Program Bookmark and Share Survey equipment is used to detect and measure radiation Survey equipment is used to detect and measure radiation. Click on image to view larger image. The Radiological Assistance Program (RAP) team at Argonne can provide assistance in the event of a radiological accident or incident. Support ranges from giving technical information or advice over the telephone, to sending highly trained team members and state-of-the-art equipment to the accident site to help identify and minimize any radiological hazards. The

108

"What's New with Independent Verification at Department of Energy Sites"  

Energy.gov (U.S. Department of Energy (DOE))

"What's New with Independent Verification at Department of Energy Sites" Sarah Roberts*, Oak Ridge Associated Universities ; Edward Regnier, U.S. Department of Energy; Tim Vitkus, Oak Ridge Associated Universities; Alexander Williams, U.S. Department of Energy Abstract: Recent rulemaking by the U.S. Department of Energy (DOE) has formalized the requirements for independent verification (IV) of both real and personal property at DOE and National Nuclear Security Administration (NNSA) sites. DOE Order 458.1, Radiation Protection of the Public and the Environment, provides a more detailed framework for radiological clearance and IV than its predecessor DOE Order 5400.5, and emphasizes application of the “graded approach” for property clearance. The Order also incorporates recommendations for property release methodologies including the well-known Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) and the more recently issued guidance document for the release of materials and equipment (the Multi-Agency Radiation Survey and Assessments of Materials and Equipment Manual or MARSAME). The new Order has resulted in many discussions related to the application of requirements at both the headquarters and field site levels. This is not completely unexpected given that one of the major objectives of the document, to allow for a graded approach, allows for flexibility in application. There are trends in lessons learned that should be considered when evaluating the applicability of IV requirements in the Order. Some of those lessons learned include the reduction of overall project risk by early engagement of IV personnel (prior to commencement of the final status surveys), consideration of verification requirements prior to backfilling excavated (remediated) areas, and interpretation of the gray area for what constitutes a “graded approach”.

109

Radiological Control  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE-STD-1098-2008 October 2008 DOE STANDARD RADIOLOGICAL CONTROL U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. ii DOE-STD-1098-2008 This document is available on the Department of Energy Technical Standards Program Website at http://www.standards.doe.gov/ DOE-STD-1098-2008 Radiological Control DOE Policy October 2008 iii Foreword 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

110

Measuring Verification Coverage  

Science Journals Connector (OSTI)

In order to measure verification progress, we measure verification converage because verification coverage defines the extent of the verification problem. In order to measure anything however, we need metrics....

2008-01-01T23:59:59.000Z

111

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

112

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

113

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

114

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

115

Radiological Control  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE-STD-1098-2008 October 2008 ------------------------------------- Change Notice 1 May 2009 DOE STANDARD RADIOLOGICAL CONTROL U.S. Department of Energy SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1098-2008 ii This document is available on the Department of Energy Technical Standards Program Website at http://www.standards.doe.gov/ iii DOE-STD-1098-2008 Change Notice 1: DOE-STD-1098-2008, Radiological Control Standard Section/page/paragraph Change Section 211, page 2-3, paragraph 1 Add new paragraph 1: "Approval by the appropriate Secretarial Officer or designee should be required

116

Industrial Radiology  

Science Journals Connector (OSTI)

... chief application of industrial radiology in Norway is in the examination of pipe welds in hydroelectric plant. H. Vinter (Denmark), director of the Akademiet for de Technische Videns ... and to compare various methods of non-destructive testing. He gave results of tests on turbine disk forgings of austenitic steel which showed satisfactory agreement between radiography, ultrasonic examination and ...

1950-11-18T23:59:59.000Z

117

Radiological health aspects of uranium milling  

SciTech Connect

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

118

Radiological Areas  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Revision to Clearance Policy Associated with Recycle of Scrap Metals Originating from Revision to Clearance Policy Associated with Recycle of Scrap Metals Originating from Radiological Areas On July 13, 2000, the Secretary of Energy imposed an agency-wide suspension on the unrestricted release of scrap metal originating from radiological areas at Department of Energy (DOE) facilities for the purpose of recycling. The suspension was imposed in response to concerns from the general public and industry groups about the potential effects of radioactivity in or on material released in accordance with requirements established in DOE Order 5400.5, Radiation Protection of the Public and Environment. The suspension was to remain in force until DOE developed and implemented improvements in, and better informed the public about, its release process. In addition, in 2001 the DOE announced its intention to prepare a

119

Dental Radiology  

Science Journals Connector (OSTI)

Dental radiology is the core diagnostic modality of veterinary dentistry. Dental radiographs assist in detecting hidden painful pathology, estimating the severity of dental conditions, assessing treatment options, providing intraoperative guidance, and also serve to monitor success of prior treatments. Unfortunately, most professional veterinary training programs provide little or no training in veterinary dentistry in general or dental radiology in particular. Although a technical learning curve does exist, the techniques required for producing diagnostic films are not difficult to master. Regular use of dental x-rays will increase the amount of pathology detected, leading to healthier patients and happier clients who notice a difference in how their pet feels. This article covers equipment and materials needed to produce diagnostic intraoral dental films. A simplified guide for positioning will be presented, including a positioning “cheat sheet” to be placed next to the dental x-ray machine in the operatory. Additionally, digital dental radiograph systems will be described and trends for their future discussed.

Tony M. Woodward

2009-01-01T23:59:59.000Z

120

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

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

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

Estimating radiological background using imaging spectroscopy  

SciTech Connect

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

122

RADIOLOGICAL SURWY  

Office of Legacy Management (LM)

111 111 j -,~ ' - et- -*\. _(a v - r\lfs+8 plY 45+ c iill I r\l&; p) :;!I..; .: .. :,, ,m -,< :' - ' ec-. :-*% ". _(.*- ~ . . : : : ' .. : : : .. ..:, . . . :. : : ,, :;I;:~~:; :.:.!,;;y ' 1;: .: 1. .., ; ' . :. : c :...: .;: .: RADIOLOGICAL SURWY - RADIoL~BI~L.::.~~~y:- : ::: 1 ,: . . : : :: :. :..." - OFi~:,~~~~:poRTI~~~ 0J-g ,m_ ,. :. y.;,:. ,.:I; .:. F~~~~~~as~~~ ~~~~~~~:~~~~ :co~~~:~~~~~; ;, .. ; I : : ::.. :.. :. - ,B~~Lo,.~-~~~. ..; .:I ,,,, :--:.;:I:: ;' #I Y' i ' 11". .. .. ; :;: ;I, ' . 1::. J;,;. ~;_:y,;:::::; - T.J..:+~uS~~ .' .:' : : . . .. ...: .:.. : OFTHE EXCERIORPORTIONS O F THE FORIMER BLISS ANT3 LAUGHLIN STEEL COMPANY FAC' KJTy - BUFFALO,NEw YORK - T. J.VITKUS I : . . : : ' . .:. : I : : .. :. Prepaied for.:the:' 6ffice.iibfiEnvir~nmenfal Re$o&idn z . . :

123

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

124

For S Radiological  

Office of Legacy Management (LM)

? . ? . -. .- * -* (\/If.r.-5- .* , d- For S Radiological ' mer Bridgepo pecial Metals Adrian, Survey of the Irt Brass Company Extrusion Plant, Michigan / /f?t' . ( F. F. Haywood H. W. Dickson W. D. Cottrell W. H. Shinpaugh _ : I., _-. .I ( ._ rc/ DOE/EV-0005128 ORNL-57 13 / J. E. Burden 0. R. Stone R. W. Doane W. A. Goldsmith 4 , Printed in the United States of America. Available from National Technical Information Service U.S. Department of Commerce 5285 Port Royal Road, Springfield, Virginia 22161 NTIS price codes-Printed Copy: A06 Microfiche A01 This report was prepared as an account of work sponsored by an agency of the UnitedStatesGovernment. Neither theUnitedStatesGovernment noranyagency thereof, nor any of their employees, makes any warranty, express or implied, or

125

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

SciTech Connect

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

126

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

SciTech Connect

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

127

Roadmap: Radiologic Imaging Sciences -Nuclear Medicine (with AAS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology) - Bachelor Safety 3 C #12;Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-NMRT] Regional College Catalog Year: 2013-2014 Page 1

Sheridan, Scott

128

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

SciTech Connect

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

129

Verification Challenges at Low Numbers  

SciTech Connect

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

130

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Radiological Work Coverage Radiological Work Coverage Instructor's Guide 2.11-1 Course Title: Radiological Control Technician Module Title: Radiological Work Coverage Module Number: 2.11 Objectives: 2.11.01 List four purposes of job coverage. 2.11.02 Explain the differences between continuous and intermittent job coverage. 2.11.03 Given example conditions, identify those that should require job coverage. 2.11.04 Identify items that should be considered in planning job coverage. 2.11.05 Identify examples of information that should be discussed with workers during pre-job briefings. 2.11.06 Describe exposure control techniques that can be used to control worker and technician radiation exposures. L 2.11.07 Describe the in-progress radiological surveys that should be performed, at your site, under various radiological conditions.

131

DOE-HDBK-1122-99; Radiological Control Technican Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Radiological Work Coverage Radiological Work Coverage Study Guide 2.11-1 Course Title: Radiological Control Technician Module Title: Radiological Work Coverage Module Number: 2.11 Objectives: 2.11.01 List four purposes of job coverage. 2.11.02 Explain the differences between continuous and intermittent job coverage. 2.11.03 Given example conditions, identify those that should require job coverage. 2.11.04 Identify items that should be considered in planning job coverage. 2.11.05 Identify examples of information that should be discussed with workers during pre-job briefings. 2.11.06 Describe exposure control techniques that can be used to control worker and technician radiation exposures. i 2.11.07 Describe the in-progress radiological surveys that should be performed, at your site, under various radiological conditions.

132

Radiological Worker Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

MEASUREMENT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 Appendix B December 2008 Reaffirmed 2013 DOE HANDBOOK RADIOLOGICAL WORKER TRAINING RADIOLOGICAL CONTAMINATION CONTROL TRAINING FOR LABORATORY RESEARCH U.S. Department of Energy FSC 6910 Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Radiological Worker Training Appendix B Radiological Contamination Control for Laboratory Research DOE-HDBK-1130-2008 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ . ii Radiological Worker Training Appendix B Radiological Contamination Control for Laboratory Research DOE-HDBK-1130-2008 Foreword This Handbook describes a recommended implementation process for core training as outlined in

133

Radiological Worker Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NOT MEASUREMENT NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 Appendix A Change Notice 2 Reaffirmed 2013 DOE HANDBOOK Radiological Worker Training Radiological Control Training for Supervisors U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Radiological Worker Training - Appendix A Radiological Control Training for Supervisors DOE-HDBK-1130-2008 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ ii Radiological Worker Training - Appendix A Radiological Control Training for Supervisors DOE-HDBK-1130-2008 Foreword This Handbook describes an implementation process for training as recommended in

134

Radiological Worker Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NOT MEASUREMENT NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 Appendix A Change Notice 2 Reaffirmed 2013 DOE HANDBOOK Radiological Worker Training Radiological Control Training for Supervisors U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Radiological Worker Training - Appendix A Radiological Control Training for Supervisors DOE-HDBK-1130-2008 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ ii Radiological Worker Training - Appendix A Radiological Control Training for Supervisors DOE-HDBK-1130-2008 Foreword This Handbook describes an implementation process for training as recommended in

135

Radiological Worker Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 Appendix C December 2008 Reaffirmed 2013 DOE HANDBOOK Radiological Worker Training Radiological Safety Training for Radiation Producing (X-Ray) Devices U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Radiological Worker Training - Appendix C Radiological Safety Training for Radiation-Producing (X-Ray) Devices DOE-HDBK-1130-2008 Program Management This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ ii Radiological Worker Training - Appendix C Radiological Safety Training for Radiation-Producing (X-Ray) Devices DOE-HDBK-1130-2008

136

Radiological Worker Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 Appendix C December 2008 Reaffirmed 2013 DOE HANDBOOK Radiological Worker Training Radiological Safety Training for Radiation Producing (X-Ray) Devices U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Radiological Worker Training - Appendix C Radiological Safety Training for Radiation-Producing (X-Ray) Devices DOE-HDBK-1130-2008 Program Management This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ ii Radiological Worker Training - Appendix C Radiological Safety Training for Radiation-Producing (X-Ray) Devices DOE-HDBK-1130-2008

137

Panoramic Radiology: Endodontic Considerations  

Science Journals Connector (OSTI)

Endodontics is concerned with the morphology, physiology, and pathology of the human dental pulp and periradicular tissues. Radiology is especially important for diagnosis in the...

2007-01-01T23:59:59.000Z

138

Radiological Assistance Program  

Directives, Delegations, and Requirements

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

139

Microsoft Word - Berger Radiological Conditions.doc  

Office of Legacy Management (LM)

Dec. Dec. 2, 2009 1 Summary of Information Regarding Radiological Conditions of NFSS Vicinity Properties J. D. Berger, CHP DeNuke Contracting Services, Inc. Oak Ridge, TN The following is a summary of the information obtained from reviews of radiological survey reports, prepared by ORAU in support of the DOE Formerly Utilized Sites Remedial Action Program. These reports were obtained for review from the IVEA Program at ORAU/ORISE. A list of the reports, reviewed for this summary, is included at the end of this report. Hard copies of reports for ORAU survey activities of NFSS and NFSS Vicinity Properties are available at the South Campus Site of ORAU (these reports are not available in electronic form). In addition, there are 12 - 14 boxes of hard-copy supporting data and information, pertinent to the surveys. I inspected the contents of Box 54. That box contained records for NFSS Vicinity

140

Treaty Verification | ornl.gov  

NLE Websites -- All DOE Office Websites (Extended Search)

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

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

ORISE: Characterization surveys  

NLE Websites -- All DOE Office Websites (Extended Search)

Characterization surveys Characterization surveys An ORISE technicians performs a characterization survey The Oak Ridge Institute for Science and Education (ORISE) performs independent, objective characterization surveys to define the extent of radiological contamination at sites scheduled for decontamination and decommissioning (D&D). A fundamental aspect of all D&D projects, characterization surveys provide guidance to determine the best remediation procedures and are a cost-effective method of ensuring a site meets preliminary regulatory standards. ORISE designs characterization surveys using the data quality objectives process. This approach focuses on the particular objective of characterization, and ensures that only the data needed to address the characterization decisions are collected. Data collection efforts are

142

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

143

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

144

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

145

Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

7of 9 7of 9 Radiological Control Technician Training Practical Training Phase II Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy DOE-HDBK-1122-2009 ii Table of Contents Page Introduction.............................................................................. ......1 Development of Job Performance Measures (JPMs)............................ .....1 Conduct Job Performance Evaluation...................................................3 Qualification Area: Radiological Instrumentation.......................................5 Task 2-1.................. ..................................................................... 5 Objective.............................................................................. 5

146

SQA_CodeVerification_Survey_FINAL  

NLE Websites -- All DOE Office Websites (Extended Search)

of the MMS source term or evaluation of the analytic solution must be provided. A code fragment showing the implementation should also be provided. c. Output value(s) being...

147

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...

148

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

149

Monitoring, verification, and accounting  

NLE Websites -- All DOE Office Websites (Extended Search)

verification, and accounting (MVA) activities are underway verification, and accounting (MVA) activities are underway to ensure the injected CO 2 remains in the geologic formation. The first plant has been capturing CO 2 since December 2012, while the second plant completed construction in February and began carbon capture operations in March. Both units are now operating at full capacity. More than 222,000 tons of CO 2 have been captured and provided for storage

150

Radiological Worker Training - Radiological Control Training for Supervisors  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

A A December 2008 DOE HANDBOOK Radiological Worker Training Radiological Control Training for Supervisors U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE Radiological Worker Training - Appendix A Radiological Control Training for Supervisors DOE-HDBK-1130-2008 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Radiological Worker Training - Appendix A Radiological Control Training for Supervisors DOE-HDBK-1130-2008 iii Foreword This Handbook describes an implementation process for training as recommended in

151

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

152

Radiological Assessor Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1-2008 1-2008 August 2008 DOE HANDBOOK Radiological Assessor Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document is available on the Department of Energy Technical Standards Program Web site at http://tis.eh.doe.gov/techs\ Foreword This Handbook describes an implementation process for training as recommended in Implementation Guide G441.1-1B, Radiation Protection Programs, March 2007, and as outlined in DOE- STD- 1098-99, CN1, March 2005, DOE Radiological Control (the Radiological Control Standard - RCS). The Handbook is meant to assist those individuals within the Department of

153

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...

154

Radiological worker training  

SciTech Connect

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

155

Roadmap: Radiologic Imaging Sciences -Computed Tomography (with AAS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Computed Tomography (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-CTRT] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 30-Apr-13/LNHD This roadmap is a recommended semester

Sheridan, Scott

156

Roadmap: Radiologic Imaging Sciences -Computed Tomography (with AAS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Computed Tomography (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-CTRT] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 25-Oct-12/LNHD This roadmap is a recommended semester

Sheridan, Scott

157

Roadmap: Radiologic Imaging Sciences -Radiation Therapy (with AAS Radiologic Technology)  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Radiation Therapy (with AAS Radiologic Technology) ­ Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-RTAA] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 1-May-13/LNHD This roadmap is a recommended semester

Sheridan, Scott

158

Roadmap: Radiologic Imaging Sciences -Radiation Therapy (with AAS Radiologic Technology)  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Radiation Therapy (with AAS Radiologic Technology) ­ Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-RTAA] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 21-May-12/LNHD This roadmap is a recommended semester

Sheridan, Scott

159

Roadmap: Radiologic Imaging Sciences -Nuclear Medicine (with AAS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-NMRT] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 21-May-12/LNHD This roadmap is a recommended semester-by-semester plan of study

Sheridan, Scott

160

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

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

Radiology of thoracic diseases  

SciTech Connect

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

162

Verification and validation benchmarks.  

SciTech Connect

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

163

OAK RIDGE NATIONAL LABORATORY RESULTS OF RADIOLOGICAL  

Office of Legacy Management (LM)

2 7% 2 7% d &y / 7 ORNL/TM- 10076 OAK RIDGE NATIONAL LABORATORY RESULTS OF RADIOLOGICAL ~-T-m -~=- -~ w-~- -"" * ,<.~- ~w&$UREMENTs: TAKEN IN THE NIAGARA FALLS, NEW YORK, AREA (NF002) J. K. Williams B. A. Berven ~.~~;:;-~~~ ~. -,' - ~~ 7, OPERATED BY MARTIN MARIDTA ENERGY SYSTEMS, INC, FOR THE UNITED STATES DEPARTMENT OF ENERGY --... ORNL/TM-10076 HEALTH AND SAFETY RESEARCH DIVISION Nuclear and Chemical Waste Programs (Activity No. AH 10 05 00 0; ONLWCOI) RESULTS OF RADIOLOGICAL MEASUREMENTS TAKEN IN THE NIAGARA FALLS, NEW YORK, AREA (NFOO2) J. K. Williams* and B. A. Berven *Biology Division Date Published November 1986 Investigation Team B. A. Berven - RASA Program Manager W. D. Cottrell - FUSRAP Project Director W. H. Shinpaugh - Field Survey Supervisor

164

Independent Verification and Validation  

E-Print Network (OSTI)

&V works best when incorporated into the entire software and hardware development life cycle -- fromIndependent Verification and Validation Evaluating integrity and quality of hardware and software&V must be applied at the systems level to include hardware and software interactions. High

Kemner, Ken

165

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

SciTech Connect

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

Lambert, K.A.; Mitchell, M.M. [Brown and Root Environmental, Albuquerque, NM (United States); Jean, D. [MDM/Lamb, Inc., Albuquerque, NM (United States); Brown, C. [Environmental Dimensions, Inc., Albuquerque, NM 87109 (United States); Byrd, C.S. [Sandia National Labs., Albuquerque, NM (United States)

1997-09-01T23:59:59.000Z

166

General Employee Radiological Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE HANDBOOK GENERAL EMPLOYEE RADIOLOGICAL TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-HDBK-1131-2007 iii Foreword This Handbook describes an implementation process for core training as recommended in chapter 14, Radiation Safety Training, of Implementation Guide G44.1B, Radiation Protection Programs Guide, and as outlined in the DOE Radiological Control Standard [RCS - DOE-STD-1098-99, Ch. 1]. The Handbook is meant to assist those individuals

167

Radiological Assessor Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

141-2001 141-2001 April 2001 Change Notice No. 1 and Reaffirmation January 2007 DOE HANDBOOK Radiological Assessor Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Radiological Assessor Training DOE-HDBK-1141-2001 iii

168

Radiological Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Part 2 of 9 Radiological Control Technician Training Technician Qualification Standard Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy DOE-HDBK-1122-2009 ii This page intentionally left blank. DOE-HDBK-1122-2009 iii Table of Contents Page Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Purpose of Qualification Standard . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Phase I: RCT Academics Training . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . 1 Phase II: RCT Core Practical (JPMs) Training . . . . . . . . . . . . . . . . . .. . . . . . . 1

169

Radiological Worker Training - Radiological Contamination Control for Laboratory Research  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

B B December 2008 DOE HANDBOOK RADIOLOGICAL WORKER TRAINING RADIOLOGICAL CONTAMINATION CONTROL TRAINING FOR LABORATORY RESEARCH U.S. Department of Energy FSC 6910 Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE Radiological Worker Training Appendix B Radiological Contamination Control for Laboratory Research DOE-HDBK-1130-2008 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ . Radiological Worker Training Appendix B Radiological Contamination Control for Laboratory Research DOE-HDBK-1130-2008 iii Foreword This Handbook describes a recommended implementation process for core training as outlined in

170

Spherical coverage verification  

E-Print Network (OSTI)

We consider the problem of covering hypersphere by a set of spherical hypercaps. This sort of problem has numerous practical applications such as error correcting codes and reverse k-nearest neighbor problem. Using the reduction of non degenerated concave quadratic programming (QP) problem, we demonstrate that spherical coverage verification is NP hard. We propose a recursive algorithm based on reducing the problem to several lower dimension subproblems. We test the performance of the proposed algorithm on a number of generated constellations. We demonstrate that the proposed algorithm, in spite of its exponential worst-case complexity, is applicable in practice. In contrast, our results indicate that spherical coverage verification using QP solvers that utilize heuristics, due to numerical instability, may produce false positives.

Petkovic, Marko D; Latecki, Longin Jan

2011-01-01T23:59:59.000Z

171

Nuclear & Radiological Activity Center (NRAC)  

NLE Websites -- All DOE Office Websites (Extended Search)

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

172

Panoramic Radiology: Oncologic Dentistry Considerations  

Science Journals Connector (OSTI)

Panoramic radiology can serve as an important input supporting ... they are also important (1) for planning dental treatment in preparation of the oral cavity...

2007-01-01T23:59:59.000Z

173

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

174

Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Change Notice No. 1 2009 Change Notice No. 2 2011 DOE HANDBOOK RADIOLOGICAL CONTROL TECHNICIAN TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive DOE-HDBK-1122-2009 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1122-2009 Original Change Part 3 1.05-1 NCRP Report No. 93 "Ionizing Radiation Exposure of the Population of the United States". NCRP Report No. 160 "Ionizing Radiation Exposure of the Population

175

Radiological Worker Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

98 98 October 1998 Change Notice No. 1 June 2001 Change Notice No. 2 December 2003 Reaffirmation with Errata May 2004 DOE HANDBOOK Radiological Worker Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-98 ii This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration,

176

Nuclear Safeguards Verification Measurement Techniques  

Science Journals Connector (OSTI)

This chapter deals with the “nuclear safeguards” verification system and describes procedures and measurement methods that allow the safeguards inspectorates/authorities...

M. Zendel; D. L. Donohue; E. Kuhn; S. Deron; T. Bíró

2011-01-01T23:59:59.000Z

177

Ensemble Forecasts and their Verification  

E-Print Network (OSTI)

· Ensemble forecast verification ­ Performance metrics: Brier Score, CRPSS · New concepts and developments of weather Sources: Insufficient spatial resolution, truncation errors in the dynamical equations

Maryland at College Park, University of

178

Femtocell Coverage Optimisation Using Statistical Verification  

E-Print Network (OSTI)

Femtocell Coverage Optimisation Using Statistical Verification Tiejun Ma and Peter Pietzuch and coverage holes and ensure a balanced traffic workload among them. We use statistical verification the cost of self-optimisation. Keywords: Femtocell, Self-Optimisation, Statistical Verification 1

Pietzuch, Peter

179

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...

180

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

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

MULTIVESSEL BATCH DISTILLATION EXPERIMENTAL VERIFICATION  

E-Print Network (OSTI)

MULTIVESSEL BATCH DISTILLATION ­ EXPERIMENTAL VERIFICATION Bernd Wittgens and Sigurd Skogestad 1 The experimental verification of the operation of a multivessel batch distillation column, operated under total vessels, provides a generalization of previously proposed batch distillation schemes. We propose a simple

Skogestad, Sigurd

182

Handling and Packaging a Potentially Radiologically Contaminated...  

Office of Environmental Management (EM)

Radiologically Contaminated Patient.docx More Documents & Publications Pre-Hospital Practices for Handling a Radiologically Contaminated Patient Medical ExaminerCoroner...

183

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Environmental Monitoring Environmental Monitoring Study Guide 2.09-1 Course Title: Radiological Control Technician Module Title: Environmental Monitoring Module Number: 2.09 Objectives: 2.09.01 State the goals of an environmental monitoring program. 2.09.02 State the exposure limits to the general public as they apply to environmental monitoring. 2.09.03 Define the term "critical nuclide." 2.09.04 Define the term "critical pathway." i 2.09.05 State locations frequently surveyed for radiological contamination at outdoor waste sites associated with your site and the reasons for each. 2.09.06 Define the term "suspect waste site," and how they can be identified. i 2.09.07 Describe the methods used for environmental monitoring at your site. INTRODUCTION Environmental monitoring plays a large role in the field of radiological control.

184

Radiological Worker Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

TS TS NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 December 2008 Change Notice 2 Reaffirmed 2013 DOE HANDBOOK Radiological Worker Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1130-2008 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 2 DOE-HDBK-1130-2008 Original Change Throughout Program Management Guide Instructor's Guide Student's Guide "Shall" and "Must" statements Program Management Instructor's Material Student's Material Reworded to non-mandatory language unless associated with a requirement document.

185

General Employee Radiological Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Not Measurement Not Measurement Sensitive DOE-HDBK-1131-2007 December 2007_______ Change Notice 1 Reaffirmed 2013 DOE HANDBOOK GENERAL EMPLOYEE RADIOLOGICAL TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1131-2007 Original Change Part 2 page 5 The average annual radiation dose to a member of the general population is about 360 millirem/year. The average annual radiation dose to a member of the general population is about 620 millirem/year. Part 2 page 5 Natural background radiation is by far the

186

General Employee Radiological Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

_______ _______ Change Notice 1 June 2009 DOE HANDBOOK GENERAL EMPLOYEE RADIOLOGICAL TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1131-2007 Original Change Part 2 page 5 The average annual radiation dose to a member of the general population is about 360 millirem/year. The average annual radiation dose to a member of the general population is about 620 millirem/year. Part 2 page 5 Natural background radiation is by far the

187

Radiological Worker Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

8 8 December 2008 Change Notice 1 June 2009 DOE HANDBOOK Radiological Worker Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1130-2008 Original Change Part 2 Module 2 page 17 Medical radiation sources (total average dose ~ 54 mrem/yr) 1) X rays (total average dose ~ 40mrem/yr) a) X rays are similar to gamma rays; however, they originate outside the nucleus.

188

Radiological Worker Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

TS TS NOT MEASUREMENT SENSITIVE DOE-HDBK-1130-2008 December 2008 Change Notice 2 Reaffirmed 2013 DOE HANDBOOK Radiological Worker Training U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1130-2008 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 2 DOE-HDBK-1130-2008 Original Change Throughout Program Management Guide Instructor's Guide Student's Guide "Shall" and "Must" statements Program Management Instructor's Material Student's Material Reworded to non-mandatory language unless associated with a requirement document.

189

Case Based Dental Radiology  

Science Journals Connector (OSTI)

Dental radiology is quickly becoming integral to the standard of care in veterinary dentistry. This is not only because it is critical for proper patient care, but also because client expectations have increased. Furthermore, providing dental radiographs as a routine service can create significant practice income. This article details numerous conditions that are indications for dental radiographs. As you will see, dental radiographs are often critical for proper diagnosis and treatment. These conditions should not be viewed as unusual; they are present within all of our practices. When you choose not to radiograph these teeth, you leave behind painful pathology. Utilizing the knowledge gained from dental radiographs will both improve patient care and increase acceptance of treatment recommendations. Consequently, this leads to increased numbers of dental procedures performed at your practice.

Brook A. Niemiec

2009-01-01T23:59:59.000Z

190

Standardized radiological dose evaluations  

SciTech Connect

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

191

Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

_______ _______ Change Notice 1 June 2009 DOE HANDBOOK RADIOLOGICAL CONTROL TECHNICIAN TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive DOE-HDBK-1122-2009 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1122-2009 Original Change Part 3 1.05-1 NCRP Report No. 93 "Ionizing Radiation Exposure of the Population of the United States". NCRP Report No. 160 "Ionizing Radiation Exposure of the Population of the United States". Part 3 1.05-9 4) U.S. national average from diagnostic

192

TFE Verification Program  

SciTech Connect

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

193

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

6 Radiation Survey Instrumentation 6 Radiation Survey Instrumentation Instructor's Guide 2.16-1 Course Title: Radiological Control Technician Module Title: Radiation Survey Instrumentation Module Number: 2.16 Objectives: 2.16.01 List the factors which affect an RCT's selection of a portable radiation survey instrument, and identify appropriate instruments for external radiation surveys. L 2.16.02 Identify the following features and specifications for ion chamber instruments used at your facility: a. Detector type b. Instrument operating range c. Detector shielding d. Detector window e. Types of radiation detected/measured f. Operator-adjustable controls g. Markings for detector effective center h. Specific limitations/characteristics. L 2.16.03 Identify the following features and specifications for high range

194

ESPC ENABLE Measurement and Verification Plan Template  

Energy.gov (U.S. Department of Energy (DOE))

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

195

Radiological-dose assessments of atolls in the northern Marshall Islands  

SciTech Connect

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

196

Become an SEP Verification Body  

Energy.gov (U.S. Department of Energy (DOE))

Superior Energy Performance® (SEP™) establishes a high standard in energy management and performance, and SEP certification validates your commitment to energy efficiency by verifying your achieved energy performance improvement using an ANSI-ANAB Accredited Verification body. This third-party verification provides independent confirmation of energy performance achievements and commitment to managing energy use. Currently, SEP is the only national certification program offering this level of rigor and credibility to industrial facilities through accredited third-party verification of sustained energy performance improvements.

197

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

198

Radiological Source Registry and Tracking  

NLE Websites -- All DOE Office Websites (Extended Search)

Radiological Source Registry and Tracking (RSRT) Radiological Source Registry and Tracking (RSRT) Home HSS Logo Radiological Source Registry and Tracking (RSRT) Department of Energy (DOE) Notice N 234.1 Reporting of Radioactive Sealed Sources has been superseded by DOE Order O 231.1B Environment, Safety and Health Reporting. O 231.1B identifies the requirements for centralized inventory and transaction reporting for radioactive sealed sources. Each DOE site/facility operator that owns, possesses, uses or maintains in custody those accountable radioactive sealed sources identified in Title 10 Code of Federal Regulation Part 835, Occupational Radiation Protection (10 CFR 835), Appendix E, and International Atomic Energy Agency (IAEA) Categories 1 and 2 radioactive sealed sources identified in Attachment 5, Appendix A of O 321.1B, will submit information to the DOE Radiological Source Registry and Tracking (RSRT) System.

199

Radiological Emergency Response Plan (Vermont)  

Energy.gov (U.S. Department of Energy (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...

200

Radiological cleanup of Enewetak Atoll  

SciTech Connect

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

Not Available

1981-01-01T23:59:59.000Z

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.


201

Radiological training for tritium facilities  

SciTech Connect

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

NONE

1996-12-01T23:59:59.000Z

202

Radiological Protection for DOE Activities  

Directives, Delegations, and Requirements

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

203

International performance measurement and verification protocol for new construction  

E-Print Network (OSTI)

Performance Measurement and Verification Protocol for New1. INTRODUCTION Measurement and Verification (M&V) of energyPerformance Measurement & Verification Protocol.

2002-01-01T23:59:59.000Z

204

AHAM DOE Verification Test Agreement | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE Verification Test Agreement AHAM DOE Verification Test Agreement This letter is to inform AHAM that DOE is adopting a new policy regarding DOE ENERGY STAR verification testing...

205

DOE-HDBK-1141-2001; Radiological Assessor Training, Instructor's Guide  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

8-1 8-1 DEPARTMENT OF ENERGY LESSON PLAN Course Material Topic: Radiological Aspects of Plutonium Objectives: Upon completion of this lesson, the participant will be able to: 1. Identify the radiological properties of plutonium. 2. Identify the biological effects of plutonium. 3. Identify special controls and considerations required for plutonium operations. 4. Describe appropriate instruments, measurement techniques, and special radiological survey methods for plutonium. 5. Describe personnel protection requirements and dose control techniques for plutonium. Training Aids: Overhead Transparencies (OTs): OT 8.1 - OT 8.12 (may be supplemented or substituted with updated or site-specific information) Equipment Needs: Overhead projector Screen

206

Purity verification and measurement uncertainty  

Science Journals Connector (OSTI)

In chemical analysis, laboratories are required to verify the purity of reference material being used. Also, the contributions from the verification procedure, where significant, have to be included in the estima...

Siu Kay Wong

2010-06-01T23:59:59.000Z

207

DOE standard: Radiological control  

SciTech Connect

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

208

E-Print Network 3.0 - areas surveys program Sample Search Results  

NLE Websites -- All DOE Office Websites (Extended Search)

search results for: areas surveys program Page: << < 1 2 3 4 5 > >> 1 Physics Division ESH Bulletin 2007-03 Radiological Survey Requirements Summary: to be an activated ion...

209

LANL responds to radiological incident  

NLE Websites -- All DOE Office Websites (Extended Search)

LANL responds to radiological incident LANL responds to radiological incident LANL responds to radiological incident Multiple tests indicate no health risks to public or employees. August 27, 2012 Aerial view of the Los Alamos Neutron Science Center(LANSCE). Aerial view of the Los Alamos Neutron Science Center (LANSCE). The contamination poses no danger to the public. The Laboratory is investigating the inadvertent spread of Technetium 99 by employees and contractors at the Lujan Neutron Scattering Center August 27, 2012-The Laboratory is investigating the inadvertent spread of Technetium 99 by employees and contractors at the Lujan Neutron Scattering Center at the Los Alamos Neutron Science Center (LANSCE), a multidisciplinary accelerator facility used for both civilian and national security research. The Laboratory has determined that about a dozen people

210

Radiological Training for Tritium Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Change Notice No. 2 Change Notice No. 2 May 2007 DOE HANDBOOK RADIOLOGICAL TRAINING FOR TRITIUM FACILITIES U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Change Notice 2. Radiological Safety Training for Tritium Facilities DOE-HDBK-1105-2002 Page/Section Change Part 1, page 14 Change: U.S. Department of Energy, Radiological Control

211

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

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

212

An overview of dental radiology: a primer on dental radiology  

SciTech Connect

To provide medical and scientific background on certain selected technologies generally considered to be of particular significance, the National Center for Health Care Technology (NCHCT) has commissioned a series of overview papers. This is one of several projects entered into jointly by the Bureau of Radiological Health (BRH) and NCHCT relating to the use of radiation for health care. Dental radiation protection has been a long-time interest of BRH. Both past and on-going efforts to minimize population radiation exposure from electronic products have included specific action programs directed at minimizing unnecessary radiation exposure to the population from dental radiology. Current efforts in quality assurance and referral criteria are two aspects of NCHCT's own assessment of this technology which are described within the larger picture presented in this overview. The issues considered in this document go beyond the radiation exposure aspects of dental x-ray procedures. To be responsive to the informational needs of NCHCT, the assessment includes various other factors that influence the practice of dental radiology. It is hoped this analysis will serve as the basis for planning and conducting future programs to improve the practice of dental radiology.

Manny, E.F.; Carlson, K.C.; McClean, P.M.; Ra1hlin, J.A.; Segal, P.

1980-11-07T23:59:59.000Z

213

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

2012-06-07T23:59:59.000Z

214

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

215

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

216

Nuclear Radiological Threat Task Force Established | National...  

National Nuclear Security Administration (NNSA)

Radiological Threat Task Force Established | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy...

217

Operational Guidelines/Radiological Emergency Response  

Energy.gov (U.S. Department of Energy (DOE))

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

218

International Approaches to Measurement and Verification of  

E-Print Network (OSTI)

LBNL-6419E International Approaches to Measurement and Verification of Continual ImprovementKane, Lawrence Berkeley Laboratory, and Julia Vetromile, DNV KEMA ABSTRACT Effective measurement and verification.S. Department of Energy under Contract No. DE-AC02-05CH11231. #12;International Approaches to Measurement

219

Verification, Validation and Testing OSMAN BALCI  

E-Print Network (OSTI)

1 CHAPTER 10 Verification, Validation and Testing OSMAN BALCI Virginia Tech 10.1 INTRODUCTION involves the measurement and assessment of a variety of quality char- acteristics such as accuracy is assessed by conducting verification, validation and testing (VV&T). #12;2 Model Verification

Tesfatsion, Leigh

220

Runtime verification of microcontroller binary code  

Science Journals Connector (OSTI)

Runtime verification bridges the gap between formal verification and testing by providing techniques and tools that connect executions of a software to its specification without trying to prove the absence of errors. This article presents a framework ... Keywords: Embedded real-time systems, Past time LTL, Runtime verification

Thomas Reinbacher; Jörg Brauer; Martin Horauer; Andreas Steininger; Stefan Kowalewski

2014-02-01T23:59:59.000Z

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.


221

Departmental Radiological Emergency Response Assets  

Directives, Delegations, and Requirements

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

222

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

223

Robotic Surveying  

SciTech Connect

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

224

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Environmental Monitoring Environmental Monitoring Instructor's Guide 2.09-1 Course Title: Radiological Control Technician Module Title: Environmental Monitoring Module Number: 2.09 Objectives: 2.09.01 State the goals of an environmental monitoring program. 2.09.02 State the exposure limits to the general public as they apply to environmental monitoring. 2.09.03 Define the term "critical nuclide." 2.09.04 Define the term "critical pathway." L 2.09.05 State locations frequently surveyed for radiological contamination at outdoor waste sites associated with your site and the reasons for each. 2.09.06 Define the term "suspect waste site," and how they can be identified. L 2.09.07 Describe the methods used for environmental monitoring at your site. References: 1. Gollnick, Daniel, Basic Radiation Protection Technology, 2nd Edition, Pacific

225

Release criteria and pathway analysis for radiological remediation  

SciTech Connect

Site-specific activity concentrations were derived for soils contaminated with mixed fission products (MFP), or uranium-processing residues, using the Department of Energy (DOE) pathway analysis computer code RESRAD at four different sites. The concentrations and other radiological parameters, such as limits on background-subtracted gamma exposure rate were used as the basis to arrive at release criteria for two of the sites. Valid statistical parameters, calculated for the distribution of radiological data obtained from site surveys, were then compared with the criteria to determine releasability or need for further decontamination. For the other two sites, RESRAD has been used as a preremediation planning tool to derive residual material guidelines for uranium. 11 refs., 4 figs., 3 tabs.

Subbaraman, G.; Tuttle, R.J.; Oliver, B.M. (Rockwell International Corp., Canoga Park, CA (United States). Rocketdyne Div.); Devgun, J.S. (Argonne National Lab., IL (United States))

1991-01-01T23:59:59.000Z

226

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Instrumentation Study Guide Instrumentation Study Guide 2.16-1 Course Title: Radiological Control Technician Module Title: Radiation Survey Instrumentation Module Number: 2.16 Objectives: 2.16.01 List the factors which affect an RCT's selection of a portable radiation survey instrument, and identify appropriate instruments for external radiation surveys. i 2.16.02 Identify the following features and specifications for ion chamber instruments used at your facility: a. Detector type b. Instrument operating range c. Detector shielding d. Detector window e. Types of radiation detected/measured f. Operator-adjustable controls g. Markings for detector effective center h. Specific limitations/characteristics i 2.16.03 Identify the following features and specifications for high range instruments used at your facility:

227

Carbon Storage Monitoring, Verification and Accounting Research |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Monitoring, Verification and Accounting Research Monitoring, Verification and Accounting Research Carbon Storage Monitoring, Verification and Accounting Research Reliable and cost-effective monitoring, verification and accounting (MVA) techniques are an important part of making geologic sequestration a safe, effective, and acceptable method for greenhouse gas control. MVA of geologic storage sites is expected to serve several purposes, including addressing safety and environmental concerns; inventory verification; project and national accounting of greenhouse gas emissions reductions at geologic storage sites; and evaluating potential regional, national, and international greenhouse gas reduction goals. The goal of our program area is to develop and demonstrate a broad portfolio of technologies, applications, and accounting requirements that

228

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

229

Nuclear / Radiological Advisory Team | National Nuclear Security  

NLE Websites -- All DOE Office Websites (Extended Search)

/ Radiological Advisory Team | National Nuclear Security / Radiological Advisory Team | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Nuclear / Radiological Advisory Team Home > About Us > Our Programs > Emergency Response > Responding to Emergencies > Operations > Nuclear / Radiological Advisory Team Nuclear / Radiological Advisory Team

230

Radiological Training for Accelerator Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

8-2002 8-2002 May 2002 Change Notice No 1. with Reaffirmation January 2007 DOE HANDBOOK RADIOLOGICAL TRAINING FOR ACCELERATOR FACILITIES U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Change Notice 1. Radiological Safety Training for Accelerator Facilities

231

Radiological Training for Tritium Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE HANDBOOK DOE HANDBOOK RADIOLOGICAL TRAINING FOR TRITIUM FACILITIES U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Change Notice 1. Radiological Safety Training for Tritium Facilities DOE-HDBK-1105-2002 Page/Section Change Cover sheets parts 1, 2, 3, and 4 Change: Office of Environment, Safety & Health

232

Radiological Control Training for Supervisors  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3-2001 3-2001 August 2001 Change Notice No 1. with Reaffirmation January 2007 DOE HANDBOOK Radiological Control Training for Supervisors U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Radiological Control Training for Supervisors

233

Understanding Mechanisms of Radiological Contamination  

SciTech Connect

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

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

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

236

Nuclear Data Verification and Standardization  

SciTech Connect

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

237

5 - Medical Considerations for Radiological Terrorism  

Science Journals Connector (OSTI)

Publisher Summary This chapter discusses the medical considerations for radiological terrorism. Radiological warfare (RW) attack is the deliberate use of radiological materials to cause injury and death. The explosion of a radiological weapon causes damage by the heat and blast liberated at the time of detonation. The proliferation of nuclear material and technology has made the acquisition and terrorist use of ionizing radiation more probable than ever. Currently, there are three threat scenarios for radiological terrorism. The most probable scenario for the near future would be a radiological dispersion device. Such a weapon can be developed and used by any terrorist with conventional weapons and access to radionuclides. This is an expedient weapon in that the radioactive waste material is easy to obtain from any location that uses radioactive sources. These sites can include a nuclear-waste processor, a nuclear power plant, a university research facility, a medical radiotherapy clinic, or an industrial complex.

James Winkley; Paul D. Mongan

2006-01-01T23:59:59.000Z

238

Radiological Assistance Program | National Nuclear Security Administration  

NLE Websites -- All DOE Office Websites (Extended Search)

Assistance Program | National Nuclear Security Administration Assistance Program | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Radiological Assistance Program Home > About Us > Our Programs > Emergency Response > Responding to Emergencies > First Responders > Radiological Assistance Program Radiological Assistance Program RAP Logo NNSA's Radiological Assistance Program (RAP) is the nation's

239

TEPP Training - Modular Emergency Response Radiological Transportation  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Services » Waste Management » Packaging and Transportation » Services » Waste Management » Packaging and Transportation » Transportation Emergency Preparedness Program » TEPP Training - Modular Emergency Response Radiological Transportation Training (MERRTT) TEPP Training - Modular Emergency Response Radiological Transportation Training (MERRTT) Once the jurisdiction has completed an evaluation of their plans and procedures, they will need to address any gaps in training. To assist, TEPP has developed the Modular Emergency Response Radiological Transportation Training (MERRTT) program. MERRTT provides fundamental knowledge for responding to transportation incidents involving radiological material and builds on training in existing hazardous materials curricula. MERRTT satisfies the training requirements outlined in the Waste Isolation Pilot

240

US, UK, Kazakhstan Secure Radiological Transportation Vehicles...  

National Nuclear Security Administration (NNSA)

place them in secure storage, and improve radiological transportation security and site security. The United Kingdom-funded projects provide an immediate security and safety...

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

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...

242

Implementation of a Radiological Safety Coach program  

SciTech Connect

The Safe Sites of Colorado Radiological Safety program has implemented a Safety Coach position, responsible for mentoring workers and line management by providing effective on-the-job radiological skills training and explanation of the rational for radiological safety requirements. This position is significantly different from a traditional classroom instructor or a facility health physicist, and provides workers with a level of radiological safety guidance not routinely provided by typical training programs. Implementation of this position presents a challenge in providing effective instruction, requiring rapport with the radiological worker not typically developed in the routine radiological training environment. The value of this unique training is discussed in perspective with cost-savings through better radiological control. Measures of success were developed to quantify program performance and providing a realistic picture of the benefits of providing one-on-one or small group training. This paper provides a description of the unique features of the program, measures of success for the program, a formula for implementing this program at other facilities, and a strong argument for the success (or failure) of the program in a time of increased radiological safety emphasis and reduced radiological safety budgets.

Konzen, K.K. [Safe Sites of Colorado, Golden, CO (United States). Rocky Flats Environmental Technology Site; Langsted, J.M. [M.H. Chew and Associates, Golden, CO (United States)

1998-02-01T23:59:59.000Z

243

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...

244

Radiological Safety Training for Accelerator Facilities  

Office of Environmental Management (EM)

HANDBOOK RADIOLOGICAL SAFETY TRAINING FOR ACCELERATOR FACILITIES U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public...

245

Radiological Assistance Program | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Assistance Program | National Nuclear Security Administration Assistance Program | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Radiological Assistance Program Home > About Us > Our Programs > Emergency Response > Responding to Emergencies > First Responders > Radiological Assistance Program Radiological Assistance Program RAP Logo NNSA's Radiological Assistance Program (RAP) is the nation's

246

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Measurement and Verification Plan for Your Energy Efficiency ProjectProgram A Primer on EM&V, Data Collection, Tracking and Reporting of Efficiency Savings, and Supporting...

247

Guide to good practices for independent verification  

SciTech Connect

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

248

Guide to good practices for independent verification  

SciTech Connect

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

249

Guide to good practices for independent verification  

SciTech Connect

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

250

ESPC ENABLE Measurement and Verification Protocol  

Energy.gov (U.S. Department of Energy (DOE))

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

251

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...

252

DOE Zero Energy Ready Home Verification | Department of Energy  

Energy Savers (EERE)

Verification DOE Zero Energy Ready Home Verification DOE Zero Energy Ready Homes Verification, a publication of the U.S. Department of Energy Zero Energy Ready Homes program. DOE...

253

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites (Waste Management Conference 2011) Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites (Waste Management Conference 2011) More Documents & Publications

254

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites (Waste Management Conference 2011) Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites (Waste Management Conference 2011) More Documents & Publications

255

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Instructor's Guide Instructor's Guide 2.12-1 Course Title: Radiological Control Technician Module Title: Shipment/Receipt of Radioactive Material Module Number: 2.12 Objectives: 2.12.01 List the applicable agencies which have regulations that govern the transport of radioactive material. 2.12.02 Define terms used in DOT regulations. 2.12.03 Describe methods that may be used to determine the radionuclide contents of a package. 2.12.04 Describe the necessary radiation and contamination surveys to be performed on packages and state the applicable limits. 2.12.05 Describe the necessary radiation and contamination surveys to be performed on exclusive use vehicles and state the applicable limits. 2.12.06 Identify the proper placement of placards on a transport vehicle. L 2.12.07 Identify inspection criteria that should be checked prior to releasing a

256

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Study Guide Study Guide 2.12-1 Course Title: Radiological Control Technician Module Title: Shipment/Receipt of Radioactive Material Module Number: 2.12 Objectives: 2.12.01 List the applicable agencies which have regulations that govern the transport of radioactive material. 2.12.02 Define terms used in DOT regulations. 2.12.03 Describe methods that may be used to determine the radionuclide contents of a package. 2.12.04 Describe the necessary radiation and contamination surveys to be performed on packages and state the applicable limits. 2.12.05 Describe the necessary radiation and contamination surveys to be performed on exclusive use vehicles and state the applicable limits. 2.12.06 Identify the proper placement of placards on a transport vehicle. i 2.12.07 Identify inspection criteria that should be checked prior to releasing a

257

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

SciTech Connect

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

NONE

1999-06-01T23:59:59.000Z

258

Roadmap: Radiologic Imaging Sciences Magnetic Resonance Imaging (with certification and ATS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences ­ Magnetic Resonance Imaging (with certification and ATS Radiologic Technology) - Bachelor of Radiologic Imaging Sciences Technology [RE-BRIT-RIS-MRHA] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 1-May-13/LNHD This roadmap is a recommended

Sheridan, Scott

259

Roadmap: Radiologic Imaging Sciences Diagnostic Medical Sonography (with AAS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences ­ Diagnostic Medical Sonography (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-RTAS] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 11-Apr-12/LNHD This roadmap is a recommended semester

Sheridan, Scott

260

Roadmap: Radiologic Imaging Sciences -Magnetic Resonance Imaging (with AAS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Magnetic Resonance Imaging (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-MRRT] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 1-May-13/LNHD This roadmap is a recommended semester

Sheridan, Scott

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

Roadmap: Radiologic Imaging Sciences Magnetic Resonance Imaging (with certification and ATS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences ­ Magnetic Resonance Imaging (with certification and ATS Radiologic Technology) - Bachelor of Radiologic Imaging Sciences Technology [RE-BRIT-RIS-MRHA] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 11-Apr-12/LNHD This roadmap is a recommended

Sheridan, Scott

262

Roadmap: Radiologic Imaging Sciences Nuclear Medicine (with certification and ATS Radiologic Technology)  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences ­ Nuclear Medicine (with certification and ATS Radiologic Technology) ­ Bachelor of Radiologic Imaging Sciences Technology [RE-BRIT-RIS-NMHO] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 1-May 13/LNHD This roadmap is a recommended semester

Sheridan, Scott

263

Roadmap: Radiologic Imaging Sciences -Magnetic Resonance Imaging (with AAS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Magnetic Resonance Imaging (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-MRRT] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 21-May-12/LNHD This roadmap is a recommended semester

Sheridan, Scott

264

Roadmap: Radiologic Imaging Sciences Nuclear Medicine (with certification and ATS Radiologic Technology)  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences ­ Nuclear Medicine (with certification and ATS Radiologic Technology) ­ Bachelor of Radiologic Imaging Sciences Technology [RE-BRIT-RIS-NMHO] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 11-Apr-12/LNHD This roadmap is a recommended semester

Sheridan, Scott

265

Roadmap: Radiologic Imaging Sciences -Computed Tomography (with certification and ATS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Computed Tomography (with certification and ATS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-CTHA] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 30-Apr-13/LNHD This roadmap is a recommended semester

Sheridan, Scott

266

Roadmap: Radiologic Imaging Sciences-Diagnostic Medical Sonography (with certification and ATS Radiologic Technology)  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences- Diagnostic Medical Sonography (with certification and ATS Radiologic Technology) Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-HATS] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 30-Apr-13/LNHD This roadmap is a recommended

Sheridan, Scott

267

Roadmap: Radiologic Imaging Sciences Diagnostic Medical Sonography (with AAS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences ­ Diagnostic Medical Sonography (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-RTAS] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 30-Apr-2013/LNHD This roadmap is a recommended

Sheridan, Scott

268

Roadmap: Radiologic Imaging Sciences Radiation Therapy (with certification and ATS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences ­ Radiation Therapy ­ (with certification and ATS Radiologic Technology) - Bachelor of Radiologic Imaging Sciences Technology [RE-BRIT-RIS-RTHB] Regional College Catalog Year: 2013-2014 Page 1 of 2 | Last Updated: 1-May-13/LNHD This roadmap is a recommended semester

Sheridan, Scott

269

Roadmap: Radiologic Imaging Sciences-Diagnostic Medical Sonography (with certification and ATS Radiologic Technology)  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences- Diagnostic Medical Sonography (with certification and ATS Radiologic Technology) Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-HATS] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 21-May-12/LNHD This roadmap is a recommended

Sheridan, Scott

270

Roadmap: Radiologic Imaging Sciences -Computed Tomography (with certification and ATS Radiologic Technology) -  

E-Print Network (OSTI)

Roadmap: Radiologic Imaging Sciences - Computed Tomography (with certification and ATS Radiologic Technology) - Bachelor of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-CTHA] Regional College Catalog Year: 2012-2013 Page 1 of 2 | Last Updated: 25-Oct-12/LNHD This roadmap is a recommended semester

Sheridan, Scott

271

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...

272

Introduction to Measurement and Verification for DOE Super ESPC...  

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

Introduction to Measurement and Verification for DOE Super ESPC Projects Introduction to Measurement and Verification for DOE Super ESPC Projects Document offers an overview of why...

273

Example Measurement & Verification Plan for a Super ESPC Project...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Example Measurement & Verification Plan for a Super ESPC Project Example Measurement & Verification Plan for a Super ESPC Project Report features a comprehensive measurement and...

274

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

M&V Guidelines: Measurement and Verification for Federal Energy Projects M&V Guidelines: Measurement and Verification for Federal Energy Projects Document describes the Federal...

275

Reviewing Measurement and Verification Plans for Federal ESPC...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Reviewing Measurement and Verification Plans for Federal ESPC Projects Reviewing Measurement and Verification Plans for Federal ESPC Projects Document provides a framework for...

276

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

M&V Guidelines: Measurement and Verification for Federal Energy Projects M&V Guidelines: Measurement and Verification for Federal Energy Projects FEMP's standard procedures and...

277

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

Office of Environmental Management (EM)

Waste Management Now Available as Accredited SEP Verification Body Advanced Waste Management Now Available as Accredited SEP Verification Body October 24, 2014 - 2:58pm Addthis The...

278

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

279

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Verification Testing in Support of ENERGY STAR, April 22, 2011 DOE Verification Testing in Support of ENERGY STAR, April 22, 2011 This document describes ENERGY STAR verificaion...

280

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

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

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

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

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

Energy Savers (EERE)

Appliance & Equipment Standards ENERGY STAR ENERGY STAR Test Procedures and Verification ENERGY STAR Test Procedures and Verification The Department of Energy (DOE) is the...

282

Verification of Shell GTL Fuel as CARB Alternative Diesel | Department...  

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

Verification of Shell GTL Fuel as CARB Alternative Diesel Verification of Shell GTL Fuel as CARB Alternative Diesel Presentation given at the 2007 Diesel Engine-Efficiency &...

283

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.

284

Nevada Test Site Radiological Control Manual  

SciTech Connect

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

285

Nevada Test Site Radiological Control Manual  

SciTech Connect

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

286

Federal Radiological Monitoring and Assessment Center  

Directives, Delegations, and Requirements

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

287

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

288

Memorandum, Reporting of Radiological Sealed Sources Transactions  

Energy.gov (U.S. Department of Energy (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.

289

Functional Verification through Operation Diagnostics  

E-Print Network (OSTI)

ICEBO'11 Abstract Burgoyne 110328.docx Page 1 of 1 ? Ebert & Baumann Consulting Engineers, Inc. A B S T R A C T ICEBO 2011 New York City March 28, 2011 Functional Verification through Operation Diagnostics One of the core objectives... throughout occupancy. In this paper, Operation Diagnostics is applied in a case study. Ben Burgoyne, LEED? AP Mechanical Engineer Ebert & Baumann Consulting Engineers, Inc. A n E n t e r p r i s e o f t h e E b e r t - C o n s u l t i n g G r...

Burgoyne, B.

290

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

291

Additional Verification Bodies Now Available for SEP  

Energy.gov (U.S. Department of Energy (DOE))

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

292

The monitoring and verification of nuclear weapons  

SciTech Connect

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

293

CFE verification: The decision to inspect  

SciTech Connect

Verification of compliance with the provisions of the treaty on Conventional Forces-Europe (CFE) is subject to inspection quotas of various kinds. Thus the decision to carry out a specific inspection or verification activity must be prudently made. This decision process is outlined, and means for conserving quotas'' are suggested. 4 refs., 1 fig.

Allentuck, J.

1990-01-01T23:59:59.000Z

294

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

295

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...

296

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

Office of Environmental Management (EM)

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

297

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

Office of Environmental Management (EM)

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

298

Lessons Learned from Independent Verification Activities  

Energy.gov (U.S. Department of Energy (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.

299

Review of Evaluation, Measurement and Verification Approaches Used to Estimate the Load Impacts and Effectiveness of Energy Efficiency Programs  

E-Print Network (OSTI)

of Evaluation, Measurement and Verification Approaches Usedof Evaluation, Measurement and Verification Approaches UsedEvaluation, measurement, and verification National Action

Messenger, Mike

2010-01-01T23:59:59.000Z

300

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

SciTech Connect

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

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

STATE OF CALIFORNIA VERIFICATION OF HIGH EER EQUIPMENT  

E-Print Network (OSTI)

STATE OF CALIFORNIA VERIFICATION OF HIGH EER EQUIPMENT CEC-CF-6R-MECH-23-HERS (Revised 08/09) CALIFORNIA ENERGY COMMISSION INSTALLATION CERTIFICATE CF-6R-MECH-23-HERS Verification of High EER Equipment 2009 Verification of High EER Equipment Procedures for verification of High EER Equipment are described

302

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

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

303

verification  

National Nuclear Security Administration (NNSA)

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

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

304

Attributes and practices of oral and maxillofacial radiology departments in US and Canadian dental schools  

Science Journals Connector (OSTI)

Abstract Objective: To assess the actual state of oral and maxillofacial radiology departments in US and Canadian dental schools against the ideal characteristics defined by the American Academy of Oral and Maxillofacial Radiology (AAOMR) 1997 position paper. Study Design: Cross-sectional survey of all 65 US and Canadian dental schools. Results: Sixty-four surveys were returned (98%). At most schools, oral and maxillofacial radiology (OMR) was an identifiable division of a department, established policies, and had operational authority for radiographic practices in the primary radiology clinic. The majority of full-time faculty (72%) had formal training in OMR; the majority of part-time faculty (86%) did not. Full-time faculty spent approximately 60% of their time teaching, with the remainder of their time divided among research and scholarship, faculty practice, and service. Routine x-ray equipment was universally available; advanced imaging technologies were not. OMR faculty involvement in the interpretation of radiographs varied across diseases and conditions. Most published scholarship (85%+) was produced by full-time faculty. Average output was 1 paper per person per year, but a relatively small cadre of OMR faculty generated most papers. Conclusions: In some attributes, the status of OMR closely approximated the ideal characteristics established in the AAOMR report. Among the remaining attributes, bridging the difference between the actual and the ideal will be the challenge for the next 5 years. (Oral Surg Oral Med Oral Pathol Oral Radiol Endod 2001;91:101-8)

Mel L. Kantor; Dona Schneider; M.Kevin O Carroll

2001-01-01T23:59:59.000Z

305

EOSO ENERGY MEASUREMENTS GROUP THE REMOT SENSIN EG&G SURVEY REPORT LABORATO  

Office of Legacy Management (LM)

Oe. 1-G Oe. 1-G l/ZL=q n EOSO ENERGY MEASUREMENTS GROUP THE REMOT SENSIN EG&G SURVEY REPORT LABORATO EP-F-002 Of THE UNITED STATES DECEMBER 1981 DEPARTMENT OF ENERGY AN AERIAL RADIOLOGICAL SURVEY OF THE AREA SURROUNDING THE BUREAU OF MINES SITE ALBANY, OREGON DATE OF SURVEY: FEBRUARY 1980 AN AERIAL RADIOLOGICAL SURVEY OF THE BUREAU OF MINES SITE ALBANY, OREGON I I I . t I 1 I I I I I I I t PROJECT SCIENTIST: E. FEIMSTER EG&G, INC. LAS VEGAS, NEVADA 1.0 SUMMARY OF RESULTS An aerial radiological measuring system was used to survey areas surrounding the Bureau of Mines Site near Albany, Oregon in February 1980. The survey was conducted for the U.S. Department of Energy's Office of Operational Safety by the Department's Remote Sensing Laboratory of Las

306

Radiological Triage | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Triage | National Nuclear Security Administration Triage | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Radiological Triage Home > About Us > Our Programs > Emergency Response > Responding to Emergencies > Render Safe > Radiological Triage Radiological Triage Triage Logo NNSA's Triage is a non-deployable, secure, on-line capability

307

Radiological Worker Training - Radiological Safety Training for Radiation Producing (X-Ray) Devices  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

C C December 2008 DOE HANDBOOK Radiological Worker Training Radiological Safety Training for Radiation Producing (X-Ray) Devices U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE Radiological Worker Training - Appendix C Radiological Safety Training for Radiation-Producing (X-Ray) Devices DOE-HDBK-1130-2008 Program Management ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Radiological Worker Training - Appendix C Radiological Safety Training for Radiation-Producing (X-Ray) Devices DOE-HDBK-1130-2008 Program Management

308

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

SciTech Connect

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

309

Seismic verification of underground explosions  

SciTech Connect

The first nuclear test agreement, the test moratorium, was made in 1958 and lasted until the Soviet Union unilaterally resumed testing in the atmosphere in 1961. It was followed by the Limited Test Ban Treaty of 1963, which prohibited nuclear tests in the atmosphere, in outer space, and underwater. In 1974 the Threshold Test Ban Treaty (TTBT) was signed, limiting underground tests after March 1976 to a maximum yield of 250 kt. The TTBT was followed by a treaty limiting peaceful nuclear explosions and both the United States and the Soviet Union claim to be abiding by the 150-kt yield limit. A comprehensive test ban treaty (CTBT), prohibiting all testing of nuclear weapons, has also been discussed. However, a verifiable CTBT is a contradiction in terms. No monitoring technology can offer absolute assurance that very-low-yield illicit explosions have not occurred. The verification process, evasion opportunities, and cavity decoupling are discussed in this paper.

Glenn, L.A.

1985-06-01T23:59:59.000Z

310

Entanglement verification via nonlinear witnesses  

E-Print Network (OSTI)

The controlled generation of entangled states and their subsequent detection are integral aspects of quantum information science. In this work, we analyse the application of nonlinear witnesses to the verification of entanglement, and we demonstrate experimentally that nonlinear witnesses perform significantly better than linear witnesses. Specifically, we demonstrate that a single non- linear entanglement witness is able to determine to a high degree of certainty that a mixed state containing orbital angular momentum (OAM) entanglement of specific forms is entangled for any relative phase and sufficient fidelity. This is a significant improvement over linear witnesses, which cannot provide the same level of performance. We envisage that nonlinear witnesses and our method of state preparation will have further uses in areas of quantum science such as superdense coding and quantum key distribution.

Megan Agnew; Jeff Z. Salvail; Jonathan Leach; Robert W. Boyd

2012-10-03T23:59:59.000Z

311

NUMERICAL VERIFICATION OF EQUILIBRIUM CHEMISTRY  

SciTech Connect

A numerical tool is in an advanced state of development to compute the equilibrium compositions of phases and their proportions in multi-component systems of importance to the nuclear industry. The resulting software is being conceived for direct integration into large multi-physics fuel performance codes, particularly for providing boundary conditions in heat and mass transport modules. However, any numerical errors produced in equilibrium chemistry computations will be propagated in subsequent heat and mass transport calculations, thus falsely predicting nuclear fuel behaviour. The necessity for a reliable method to numerically verify chemical equilibrium computations is emphasized by the requirement to handle the very large number of elements necessary to capture the entire fission product inventory. A simple, reliable and comprehensive numerical verification method is presented which can be invoked by any equilibrium chemistry solver for quality assurance purposes.

Piro, Markus [Royal Military College of Canada; Lewis, Brent [Royal Military College of Canada; Thompson, Dr. William T. [Royal Military College of Canada; Simunovic, Srdjan [ORNL; Besmann, Theodore M [ORNL

2010-01-01T23:59:59.000Z

312

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

313

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

314

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

315

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

316

2.04 - Oral and Maxillofacial Radiology  

Science Journals Connector (OSTI)

Abstract This chapter addresses the technologies and the applications of radiology used in the field of oral (or dental) and maxillofacial imaging. While the basic science and x-ray technology are the same as in general radiology, there are here important specialized differentiations that lead to very distinct equipment and procedures compared to general medical imaging. Four major subcategories are discussed: Dedicated x-ray sources for dental intraoral radiology, that is, radiography where the detector is located inside the oral cavity, and the radiographic object consisting of a few teeth Intraoral detectors: (classic) radiographic film, photostimulated-phosphor imaging plates, and solid-state digital detectors (that produce an image immediately) Equipment for panoramic and for cephalometric extraoral radiology Cone beam volumetric imaging (3D x-ray) of the head (aka CBCT)

R. Molteni

2014-01-01T23:59:59.000Z

317

Educational strategies in oral and maxillofacial radiology  

Science Journals Connector (OSTI)

In this paper, we interpret a trend in higher education in terms of its relation to oral and maxillofacial radiology education. Specifically, we describe an “evidence-based dental education” – borrowing from the ...

Madeleine Rohlin; Koji Shinoda; Yumi Takano

2004-06-01T23:59:59.000Z

318

Radiological safety training for uranium facilities  

SciTech Connect

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

319

DOE Issues WIPP Radiological Release Investigation Report  

Energy.gov (U.S. Department of Energy (DOE))

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

320

Measurement & verification reality check: A yawning gap between theory and practice  

E-Print Network (OSTI)

Kumar Satish. 2000. “Measurement and Verification of Energystandard measurement and verification (M&V) terminology andPerformance Measurement and Verification Protocol (IPMVP

2002-01-01T23:59:59.000Z

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.


321

International Approaches to Measurement and Verification of Continual Improvement in Industrial Facilities  

E-Print Network (OSTI)

US DOE 2012b. SEP Measurement and Verification Protocol forAnalysis of Measurement and Verification Practices in GlobalPerformance, Measurement and Verification Protocol for

McKane, Aimee T.

2014-01-01T23:59:59.000Z

322

Calculation and Verification of Blood Ethanol Measurement Uncertainty for Headspace Gas Chromatography  

Science Journals Connector (OSTI)

......Calculation and Verification of Blood Ethanol Measurement Uncertainty for...Calculation and verification of blood ethanol measurement uncertainty for...2% of the BAC measurement. Verification of the estimate......

Jason H. Sklerov; Fiona J. Couper

2011-09-01T23:59:59.000Z

323

Handling and Packaging a Potentially Radiologically Contaminated Patient |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Handling and Packaging a Potentially Radiologically Contaminated Handling and Packaging a Potentially Radiologically Contaminated Patient Handling and Packaging a Potentially Radiologically Contaminated Patient The purpose of this procedure is to provide guidance to EMS care providers for properly handling and packaging potentially radiologically contaminated patients. This procedure applies to Emergency Medical Service care providers who respond to a radioactive material transportation incident that involves potentially contaminated injuries. Handling and Packaging a Potentially Radiologically Contaminated Patient.docx More Documents & Publications Pre-Hospital Practices for Handling a Radiologically Contaminated Patient Medical Examiner/Coroner on the Handling of a Body/Human Remains that are Potentially Radiologically Contaminated

324

Radiological Contamination Control Training for Laboratory Research  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3 of 3) 3 of 3) RADIOLOGICAL CONTAMINATION CONTROL TRAINING FOR LABORATORY RESEARCH Student's Guide Office of Environment, Safety & Health U.S. Department of Energy February 1997 DOE-HDBK-1106-97 ii This page intentionally left blank. DOE-HDBK-1106-97 iii Table of Contents Page TERMINAL OBJECTIVE............................................................................1 ENABLING OBJECTIVES...........................................................................1 I. RADIOLOGICAL CONTAMINATION................................................. 2 A. Comparison of Radiation and Radioactive Contamination ..................... 2 B. Types of Contamination.............................................................. 2

325

Environmental/Radiological Assistance Directory (ERAD)  

Energy.gov (U.S. Department of Energy (DOE))

The Environmental Radiological Assistance Directory or ERAD, developed by HS-22, serves as an assistance tool to the DOE complex for protection of the public and environment from radiation. The ERAD is a combination webinar/conference call, designed to provide DOE and its contractors a forum to share information, lessons-learned, best practices, emerging trends, compliance issues, etc. in support of radiological protection programs developed in accordance with DOE O 458.1. ERAD Presentations, Questions and Answers ERAD

326

A radiological evaluation of phosphogypsum  

SciTech Connect

Phosphogypsum is the by-product resulting from phosphoric acid or phosphate fertilizer production. The phosphate used in these chemical processes contains the naturally occurring radioactive material U and all its subsequent decay products. During processing, the U generally remains in the phosphoric acid product, while the daughter, {sup 226}Ra, tends to be concentrated in the phosphogypsum. Phosphogypsum has physical properties that make it useful as a sub-base for roadways, parking lots, and similar construction. A radiological evaluation, to determine exposures to workers mixing this material with a stabilizing agent (portland cement), was performed at a South Louisiana phosphoric acid chemical plant. Measurements of the {sup 226}Ra content of the phosphogypsum showed an average of 1.1 +/- 0.3 Bq g-1 (0.7-1.7 Bq g-1). The average measured gross gamma exposure rate on the phosphogypsum pile corresponded to a dose equivalent rate of 0.368 +/- 0.006 mu Sv h-1 (0.32-0.42 mu Sv h-1). Radon daughter concentrations measured on top of the phosphogypsum pile ranged from 0.0006 to 0.001 working levels. An analysis of the airborne {sup 226}Ra concentrations showed only background levels.

Laiche, T.P.; Scott, L.M. (Louisiana State Univ., Baton Rouge (USA))

1991-05-01T23:59:59.000Z

327

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

328

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

329

NREL: Wind Research - Field Verification Project  

NLE Websites -- All DOE Office Websites (Extended Search)

Field Verification Project Field Verification Project The mission of the Field Verification Project (FVP) was to enable U.S. industry to complete the research, testing, and field verification needed to fully develop advanced wind energy technologies that lead the world in cost-effectiveness and reliability. The project, completed in 2003, included cost-shared research with industry partners to lead to the development of advanced technology wind turbines and support for projects that verify performance of wind turbine technologies in actual operational applications. FVP provided small wind turbine (<=100 kW) manufacturers with opportunities to operate and monitor their turbines under a range of distributed power applications and environments throughout the United States. This experience helped U.S. companies validate and improve the

330

Measurement and Verification for Demand Response  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Measurement and Verification for Measurement and Verification for Demand Response Prepared for the National Forum on the National Action Plan on Demand Response: Measurement and Verification Working Group AUTHORS: Miriam L. Goldberg & G. Kennedy Agnew-DNV KEMA Energy and Sustainability National Forum of the National Action Plan on Demand Response Measurement and Verification for Demand Response was developed to fulfill part of the Implementation Proposal for The National Action Plan on Demand Response, a report to Congress jointly issued by the U.S. Department of Energy (DOE) and the Federal Energy Regulatory Commission (FERC) in June 2011. Part of that implementation proposal called for a "National Forum" on demand response to be conducted by DOE and FERC. Given that demand response has matured, DOE and FERC decided that a "virtual" project

331

Measurement and Verification | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Measurement and Verification Measurement and Verification Measurement and Verification October 16, 2013 - 4:43pm Addthis Photo of a man with a clipboard and measuring tools standing in front of an open energy panel box. A National Park Service energy manager checks an energy management system at the Zion National Park Visitor Center. Measurement and verification (M&V) play a vital role in renewable energy projects. M&V verifies verify that renewable energy technologies successfully meet the energy generation or savings requirements as specified by the agency and the system design. Federal sustainable building guidelines require M&V systems for sustainable building projects and the use of M&V data for benchmarking systems. However, these systems deliver value well beyond regulatory compliance.

332

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

333

Microsoft Word - Preliminary Solution Verification of Denovo...  

NLE Websites -- All DOE Office Websites (Extended Search)

for which the code verification will be performed. Each problem is run using the code's standard modeling interface as for any physical problem that would be modeled. It c an be...

334

Doses to patients from dental radiology in France  

SciTech Connect

In France, a national study was undertaken to estimate both dental radiology practices (equipment and activity) and the associated population collective dose. This study was done in two steps: A nationwide survey was conducted on the practitioner categories involved in dental radiology, and dosimetric measurements were performed on patients and on an anthropomorphic phantom by using conventional dental x-ray machines and pantomographic units. A total of 27.5 x 10(6) films were estimated to have been performed in 1984; 6% of them were pantomographic and 94% were conventional. Most of the organ doses measured for one intra-oral film were lower than 1 mGy (100 mrad); pantomogram dose values were generally higher than intra-oral ones. The collective effective dose equivalent figure was 2,000 person-Sv (2 x 10(5) person rem) leading to a per head dose equivalent of 0.037 mSv (3.7 mrem). The study allowed authors to identify ways to reduce the patient dose in France (e.g., implementing the use of long cone devices and controlling darkroom practices).

Benedittini, M.; Maccia, C.; Lefaure, C.; Fagnani, F. (Centre d'etude sur l'Evaluation de la Protection dans le domaine Nucleaire, Fontenay aux Roses (France))

1989-06-01T23:59:59.000Z

335

ENERGY MEASUREMENTS GROUP EG&G Survey Report  

Office of Legacy Management (LM)

kL2' kL2' . ",- - &j EGG0 ENERGY MEASUREMENTS GROUP EG&G Survey Report NRC-81 09 April 1981 . AN AERIAL RADIOLOGIC SURVEY OF THE STEPAN CHEMCIAL COMPANY AND SURROUNDING AREA MAYWOOD, N E W JERSEY DATE OF SURVEY: 26 JANUARY 1981 J.R. Mueller Project Director S.A. Gunn Project Scientist APPROVED FOR DISTRIBUTION W . John Tipton, Head Radiation Sciences Section This Document is UNCLASSIFIED G. P. Stobie Classification Officer This work was performed by EG&G for the United States Nuclear Regulatory Commission through an EAO transfer of funds to Contract No. DE-AC08-76NV01183 with the United States Department of Energy. 3 ABSTRACT An aerial radiologic survey to measure terrestrial gamma radiation was performed in Maywood, New Jersey over the Stepan Chemical Company and thesurrounding area. This survey was conducted by EG&G for the

336

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Instructor's Guide Instructor's Guide 2.17-1 Course Title: Radiological Control Technician Module Title: Contamination Monitoring Instrumentation Module Number: 2.17 Objectives: 2.17.01 List the factors which affects an RCT's selection of a portable contamination monitoring instrument. L 2.17.02 Describe the following features and specifications for commonly used count rate meter probes used at your site for beta/gamma and/or alpha surveys: a. Detector type b. Detector shielding and window c. Types of radiation detected/measured d. Energy response for measured radiation e. Specific limitations/characteristics L 2.17.03 Describe the following features and specifications for commonly used count rate instruments used at your site: a. Types of detectors available for use b. Operator-adjustable controls

337

RADIOLOGICAL ASSESSMENT OF BALLOD AND ASSOCIATES PROPERTY  

Office of Legacy Management (LM)

and Quality Assurance With the exception of the exposure- and dose-rate conversion factors for portable survey gamma and beta-gamma meters, all survey and laboratory...

338

Survey Statisticians  

U.S. Energy Information Administration (EIA) Indexed Site

Survey Statisticians Survey Statisticians The U.S.Energy Information Administration (EIA) within the Department of Energy has forged a world-class information program that stresses quality, teamwork, and employee growth. In support of our program, we offer a variety of profes- sional positions, including the Survey Statistician, who measures the amounts of energy produced and consumed in the United States. Responsibilities: Survey Statisticians perform or participate in one or more of the following important functions: * Design energy surveys by writing questions, creating layouts and testing questions for clarity and accuracy. * Conduct energy surveys to include sending out and tracking survey responses, editing and analyzing data submis- sions and communicating with respondents to verify data.

339

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 technology, housed at the Salem Campus. Course Subject and Title Credit Hours Min. Grade Major GPA Important

Sheridan, Scott

340

Digital Surveying Directional Surveying Specialists | Open Energy  

Open Energy Info (EERE)

Digital Surveying Directional Surveying Specialists Digital Surveying Directional Surveying Specialists Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Digital Surveying Directional Surveying Specialists Author Directional Surveying Specialists Published Publisher Not Provided, 2012 DOI Not Provided Check for DOI availability: http://crossref.org Online Internet link for Digital Surveying Directional Surveying Specialists Citation Directional Surveying Specialists. Digital Surveying Directional Surveying Specialists [Internet]. 2012. [cited 2013/10/08]. Available from: http://www.digitalsurveying.co.za/services/geophysical-borehole-surveying/overview/optical-televiewer/ Retrieved from "http://en.openei.org/w/index.php?title=Digital_Surveying_Directional_Surveying_Specialists&oldid=690244"

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

Monitoring and verification R&D  

SciTech Connect

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

342

Handling and Packaging a Potentially Radiologically Contaminated Patient |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Handling and Packaging a Potentially Radiologically Contaminated Handling and Packaging a Potentially Radiologically Contaminated Patient Handling and Packaging a Potentially Radiologically Contaminated Patient The purpose of this procedure is to provide guidance to EMS care providers for properly handling and packaging potentially radiologically contaminated patients. This procedure applies to Emergency Medical Service care providers who respond to a radioactive material transportation incident that involves potentially contaminated injuries. Handling and Packaging a Potentially Radiologically Contaminated Patient.docx More Documents & Publications Pre-Hospital Practices for Handling a Radiologically Contaminated Patient Emergency Response to a Transportation Accident Involving Radioactive Material Radioactive Materials Transportation and Incident Response

343

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

SciTech Connect

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

344

PRELIMINARY SURVEY OF VITRO CORPORATION  

Office of Legacy Management (LM)

PRELIMINARY SURVEY OF VITRO CORPORATION (VITRO LABORATORIES) WEST ORANGE, NEW JERSEY Work performed by the Health and Safety Research Division Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 March 1980 OAK RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPORATION for the DEPARTMENT OF ENERGY as part of the Formerly Utilized Sites-- Remedial Actton Program VITRO CORPORATION (VITRO LABORATORIES) WEST ORANGE, NEW JERSEY At the request of the Department of Energy (DOE), a preliminary survey was performed at the former Vitro Corporation Laboratory in West Orange, New Jersey (see Fig 1), on November 30, 1977, to assess the radiological status of those facilities utilized under Atomic Energy Commission (AEC) contract during the late 1950s and early 1960s. This

345

Functional Verification of Class Invariants in CleanJava  

Science Journals Connector (OSTI)

In Cleanroom-style functional program verification, a program is ... a formal annotation language for Java to support Cleanroom-style functional program verification. We propose a ... to use class invariants in t...

Carmen Avila; Yoonsik Cheon

2013-01-01T23:59:59.000Z

346

ESPC Measurement and Verification (M&V) Planning Tool | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

ESPC Measurement and Verification (M&V) Planning Tool ESPC Measurement and Verification (M&V) Planning Tool Document provides instructions for Federal agencies on how to use a...

347

Recommendation 165: Recommendation on Conducting Future Verifications of Cleanup  

Energy.gov (U.S. Department of Energy (DOE))

The ORSSAB commends the DOE policy of obtaining independent verification of DOE Environmental Management-related activities.

348

NREL: Wind Research - Regional Field Verification  

NLE Websites -- All DOE Office Websites (Extended Search)

Field Verification Field Verification The Regional Field Verification (RFV) project, completed in 2007, focused on regional issues and opportunities and tested turbines to gain operational knowledge that could be applied nationwide. The RFV objectives were to: Support industry needs for gaining initial field operation experience with small wind turbines, and verify the performance, reliability, maintainability, and cost of small wind turbines in diverse applications. Expand opportunities for wind energy in new regions of the United States by tailoring projects to meet unique regional requirements, and document and communicate the experience from these projects for the benefit of others in the wind power development community and rural utilities. Through a competitive solicitation in 2001-2002, NREL selected one

349

Survey Consumption  

Gasoline and Diesel Fuel Update (EIA)

fsidentoi fsidentoi Survey Consumption and 'Expenditures, April 1981 March 1982 Energy Information Administration Wasningtoa D '" N """"*"""*"Nlwr. . *'.;***** -. Mik>. I This publication is available from ihe your COr : 20585 Residential Energy Consumption Survey: Consum ption and Expendi tures, April 1981 Through March 1982 Part 2: Regional Data Prepared by: Bruce Egan This report was prepared by the Energy Information Administra tion, the independent statistical

350

Incremental Partitioning-Based Vectorless Power Grid Verification  

E-Print Network (OSTI)

Incremental Partitioning-Based Vectorless Power Grid Verification Dionysios Kouroussis Department performance of a chip, design verification of the power grid is of critical importance. This paper builds the efficient verification of local power grid sections or blocks, enabling incremen- tal design analysis

Najm, Farid N.

351

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 of the circuit attached to the grid, thereby precluding early verification of the grid. We propose a power grid

Najm, Farid N.

352

Power Grid Verification Using Node and Branch Nahi Abdul Ghani  

E-Print Network (OSTI)

Power Grid Verification Using Node and Branch Dominance Nahi Abdul Ghani ECE Department University Toronto, Ontario, Canada f.najm@utoronto.ca ABSTRACT The verification of power grids in modern integrated, Verification Keywords Power grid, voltage drop, dominance 1. INTRODUCTION The rising demand for low

Najm, Farid N.

353

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

354

STATE OF CALIFORNIA VERIFICATION OF HIGH EER EQUIPMENT  

E-Print Network (OSTI)

STATE OF CALIFORNIA VERIFICATION OF HIGH EER EQUIPMENT CEC-CF-4R-MECH-23 (Revised 08/09) CALIFORNIA of High EER Equipment (Page 1 of 2) Site Address: Enforcement Agency: Permit Number: Registration Number 2009 Verification of High EER Equipment Procedures for verification of High EER Equipment are described

355

EM-Led Radiological Incident Response Program Receives Honors...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EM-Led Radiological Incident Response Program Receives Honors EM-Led Radiological Incident Response Program Receives Honors May 29, 2014 - 12:00pm Addthis Jessie Welch performs...

356

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 Year Enrollment - Fall Semester Undergraduate Graduate #12; Nuclear Power Industry Radiological Engineering Industry Graduate School DOE National Labs Nuclear Navy #12; 104 Operating Nuclear Power plants

Weber, Rodney

357

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

NLE Websites -- All DOE Office Websites (Extended Search)

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

358

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.

359

Feminist theoretical perspectives on ethics in radiology  

Science Journals Connector (OSTI)

......about the substantive public health issues? In the Western world...female cancer, and yet public health systems come under serious...accorded the best education, health care, nutrition or technology...unwanted food or inferior or even dangerous radiological or other technical......

Mary Condren

2009-07-01T23:59:59.000Z

360

Measurement of radiation dose in dental radiology  

Science Journals Connector (OSTI)

......product to effective dose and energy imparted to the patient. Phys...C. A. and Persliden, J. Energy imparted to the patient in diagnostic...factors for determining the energy imparted from measurements of...dental radiology. | Patient dose audit is an important tool for quality......

Ebba Helmrot; Gudrun Alm Carlsson

2005-05-01T23:59:59.000Z

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.


361

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.

362

Development of radiological concentrations and unit liter doses for TWRS FSAR radiological consequence calculations  

SciTech Connect

The analysis described in this report develops the Unit Liter Doses for use in the TWRS FSAR. The Unit Liter Doses provide a practical way to calculate conservative radiological consequences for a variety of potential accidents for the tank farms.

Cowley, W.L.

1996-04-25T23:59:59.000Z

363

THE RABIT: A RAPID AUTOMATED BIODOSIMETRY TOOL FOR RADIOLOGICAL TRIAGE  

E-Print Network (OSTI)

-priority need in an environment of heightened concern over possible radiological or nuclear terrorist attacks (Pellmar and Rockwell 2005). The detonation of even a small dirty bomb (radiological dispersal device of radiological injuries. A small improvised nuclear device (IND) would produce a major health emergency

364

Radiological safety at Argonne national laboratory's heavy ion research facility  

Science Journals Connector (OSTI)

This paper discusses the radiological safety system to be employed at the Argonne tandem—linac accelerator system (ATLAS). The design parameters of ATLAS that affect safety have remained unchanged since ATLAS construction began in 1982. The specialized radiological safety considerations of ATLAS were discussed in 1982 [1]. This paper will present the details of the hardware, the administrative controls, and the radiation monitoring that will be in effect when beam is produced in April 1985. The experimental hall utilizing the maximum energy beam ( ? 27 MeV per nucleon) from the completed ATLAS has been partitioned with shielding blocks into its final configuration. Because scientists want access to some of the partitioned-off areas while beam is present in other areas, an interlock and logic system allowing such occupancy has been designed. The rationale and hardware of the system will be discussed. Since one of the potential radiation hazards is high-energy forward-directed neutrons from any location where the beam impinges (such as collimators, bending and focussing systems, experimental targets, and beam stops), radiation surveys and hazard assessments are necessary for the administrative controls that allow occupancy of various areas. Because of the various uses of ATLAS, neutrons (the dominant beam hazard) will be non-existent in some experiments and will be of energies ? 10 MeV for a few experiments. These conditions may exist at specific locations during beam preparation but may change rapidly when beam is finally delivered to an experimental area. Monitoring and assessing such time varying and geographically changing hazards will be a challenge since little data will be available on source terms until various beams are produced of sufficient intensity and energy to make measurements. How the operating division for ATLAS and the Argonne safety division are addressing this aspect through administrative controls will also be discussed.

R.H. Cooke; R.A. Wynveen

1985-01-01T23:59:59.000Z

365

Monitoring, Verification and Reporting: Improving Compliance Within Energy  

Open Energy Info (EERE)

Monitoring, Verification and Reporting: Improving Compliance Within Energy Monitoring, Verification and Reporting: Improving Compliance Within Energy Efficient Programs Jump to: navigation, search Tool Summary Name: Monitoring, Verification and Reporting: Improving Compliance Within Energy Efficient Programs Agency/Company /Organization: International Energy Agency Sector: Energy Focus Area: Energy Efficiency Topics: GHG inventory, Policies/deployment programs Resource Type: Guide/manual Website: www.iea.org/papers/pathways/monitoring.pdf Monitoring, Verification and Reporting: Improving Compliance Within Energy Efficient Programs Screenshot References: Monitoring, Verification and Reporting: Improving Compliance Within Energy Efficient Programs[1] This document includes: A brief overview of MVE in the context of S&L programmes.

366

The Office of Nuclear Verification | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Nuclear Verification | National Nuclear Security Nuclear Verification | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog The Office of Nuclear Verification Home > About Us > Our Programs > Nonproliferation > Nonproliferation & International Security > The Office of Nuclear Verification The Office of Nuclear Verification

367

UN-REDD Workshop: Monitoring, Assessment and Verification | Open Energy  

Open Energy Info (EERE)

UN-REDD Workshop: Monitoring, Assessment and Verification UN-REDD Workshop: Monitoring, Assessment and Verification Jump to: navigation, search Tool Summary LAUNCH TOOL Name: UN-REDD Workshop: Monitoring, Assessment and Verification Agency/Company /Organization: United Nations Environment Programme, Food and Agriculture Organization of the United Nations, United Nations Development Programme Sector: Land Focus Area: Forestry Topics: GHG inventory, Policies/deployment programs, Resource assessment Resource Type: Workshop Website: www.un-redd.org/UNREDDProgramme/InternationalSupport/MeasurementReport UN-REDD Workshop: Monitoring, Assessment and Verification Screenshot References: UN-REDD Workshop: Monitoring, Assessment and Verification[1] Background "The specific objectives of the workshop were to develop a roadmap with

368

Climate Survey  

NLE Websites -- All DOE Office Websites (Extended Search)

Operations Employee Operations Employee Climate Survey March 2009 Acknowledgements The Berkeley Lab Survey Team consisted of the following: Jim Krupnick, Sponsor Vera Potapenko, Project Lead Karen Ramorino, Project Manager Chris Paquette, MOR Associates Alexis Bywater, MOR Associates MOR Associates, an external consulting firm, acted as project manager for this effort, analyzing the data and preparing this report. MOR Associates specializes in continuous improve- ment, strategic thinking and leadership development. MOR Associates has conducted a number of large-scale surveys for organizations in higher education, including MIT, Stanford, the University of Chicago, and others. MOR Associates, Inc. 462 Main Street, Suite 300 Watertown, MA 02472 tel: 617.924.4501

369

Mechanical Verification of Clock Synchronization Algorithms ?  

E-Print Network (OSTI)

functions, in addition to averaging algorithms. The generic theory is presented as a set of param­ eterizedMechanical Verification of Clock Synchronization Algorithms ? D. Schwier and F. von Henke schwier,vhenke@informatik.uni­ulm.de Universit¨at Ulm, Fakult¨at f¨ur Informatik, D­89069 Ulm, Germany Abstract. Clock synchronization algorithms

Biundo, Susanne

370

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

371

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.

372

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.

373

Uncertainty and Inference for Verification Measures  

Science Journals Connector (OSTI)

When a forecast is assessed, a single value for a verification measure is often quoted. This is of limited use, as it needs to be complemented by some idea of the uncertainty associated with the value. If this uncertainty can be quantified, it is ...

Ian T. Jolliffe

2007-06-01T23:59:59.000Z

374

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

375

RELAP-7 SOFTWARE VERIFICATION AND VALIDATION PLAN  

SciTech Connect

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

376

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

SciTech Connect

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

377

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Radiological Protection Standards Radiological Protection Standards Instructor's Guide 1.09-1 Course Title: Radiological Control Technician Module Title: Radiological Protection Standards Module Number: 1.09 Objectives: 1.09.01 Identify the role of advisory agencies in the development of recommendations for radiological control. 1.09.02 Identify the role of regulatory agencies in the development of standards and regulations for radiological control. 1.09.03 Identify the scope of the 10 CFR Part 835. References: 1. ANL-88-26 (1988) "Operational Health Physics Training"; Moe, Harold; Argonne National Laboratory, Chicago 2. U.S. Department of Energy, DOE-STD-1098-99, "Radiological Control Standard" 3. 10 CFR Part 835 (1998) "Occupational Radiation Protection" Instructional Aids:

378

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Radiological Considerations for First Aid Radiological Considerations for First Aid Study Guide 2.15-1 Course Title: Radiological Control Technician Module Title: Radiological Considerations for First Aid Module Number: 2.15 Objectives: 2.15.01 List the proper steps for the treatment of minor injuries occurring in various radiological areas. 2.15.02 List the requirements for responding to major injuries or illnesses in radiological areas. 2.15.03 State the RCT's responsibility at the scene of a major injury in a radiological area after medical personnel have arrived at the scene. i 2.15.04 List the requirements for treatment and transport of contaminated injured personnel at your facility. INTRODUCTION "Standard first aid is applied prior to contamination control whenever it is considered to have life-saving value, or is important to the patient for relief of pain or prevention of

379

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

5 Radiological Considerations for First Aid 5 Radiological Considerations for First Aid Instructor's Guide 2.15-1 Course Number: Radiological Control Technicians Module Title: Radiological Considerations for First Aid Module Number: 2.15 Objectives: 2.15.01 List the proper steps for the treatment of minor injuries occurring in various radiological areas. 2.15.02 List the requirements for responding to major injuries or illnesses in radiological areas. 2.15.03 State the RCT's responsibility at the scene of a major injury in a radiological area after medical personnel have arrived at the scene. L 2.15.04 List the requirements for treatment and transport of contaminated injured personnel at your facility. References: 1. Basic Radiation Protection Technology (2nd edition) - Daniel A. Gollnick 2. Operational Health Physics Training - H. J. Moe

380

SURVEY OF ROLLING MILL USED BY BETHLEHEM STEEL CORPORATION LACKAWANNA, NEW YORK  

Office of Legacy Management (LM)

SURVEY OF ROLLING MILL USED BY SURVEY OF ROLLING MILL USED BY BETHLEHEM STEEL CORPORATION LACKAWANNA, NEW YORK Work performed by the Health and Safety Research Division Gak Ridge fiational Laboratory Oak Ridge, Tennessee 37830 September 1980 OAK RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPORATION for the DEPARTMENT OF ENERGY as part of the Formerly Utilized Sites!- Remedial Action Program SURVEY OF ROLLING MILL USED BY BETHLEHEM STEEL CORPORATION LACKAWANNA, NEW YORK A radiological survey was conducted at the Bethelem Steel Corporation Plant in Lackawanna, New York, on September 23, 1980, by representatives of Oak Ridge National Laboratory (ORNL). The subject of the radiological survey was a portion of the original 25.4-cm (lo-inch) bar mill used in converting uranium billets into 3.8-cm rods. All radiation survey

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

National Energy Efficiency Evaluation, Measurement and Verification (EM&V) Standard: Scoping Study of Issues and Implementation Requirements  

E-Print Network (OSTI)

of Evaluation, Measurement and Verification Approaches Usedan Update of BPA's Measurement and Verification Protocols,Performance Measurement and Verification Protocol (IPMVP):

Schiller, Steven R.

2011-01-01T23:59:59.000Z

382

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

383

Radiological Contamination Control Training for Laboratory Research  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

06-97 06-97 February 1997 CHANGE NOTICE NO. 1 March 2002 Reaffirmation with Errata August 2002 DOE HANDBOOK RADIOLOGICAL CONTAMINATION CONTROL TRAINING FOR LABORATORY RESEARCH U.S. Department of Energy FSC 6910 Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Reaffirmation with Errata DOE-HDBK-1106-97 Radiological Contamination Control for Laboratory Research

384

Radiological Safety Training for Accelerator Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

TS TS NOT MEASUREMENT SENSITIVE DOE-HDBK-1108-2002 May 2002 Reaffirmation with Change Notice 2 July 2013 DOE HANDBOOK RADIOLOGICAL SAFETY TRAINING FOR ACCELERATOR FACILITIES U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change Notice No.2 Radiological Training for Accelerator Facilities Page/Section Change Throughout the document: Program Management Guide Instructor's Guide Student's Guide "Shall" and "Must" statements Revised to: Program Management Instructor's Material Student's Material Reworded to non-mandatory language unless associated with a requirement

385

Radiological Safety Training for Plutonium Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

145-2008 145-2008 April 2008 DOE HANDBOOK Radiological Safety Training for Plutonium Facilities U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. Radiological Safety Training for Plutonium Facilities DOE-HDBK-1145-2008 Program Management Guide

386

Radiological Safety Training for Uranium Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE HDBK-1113-2008 DOE HDBK-1113-2008 April 2008 DOE HANDBOOK RADIOLOGICAL SAFETY TRAINING FOR URANIUM FACILITIES U.S. Department of Energy FSC 6910 Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-HDBK-1113-2008 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-HDBK-1113-2008 iii Foreword This Handbook describes a recommended implementation process for additional training as outlined in DOE-STD-1098-99, Radiological Control (RCS). Its purpose is to assist those individuals, Department of Energy (DOE) employees, Managing and Operating (M&O) contractors, and Managing and Integrating

387

Radiological Dispersion Devices and Basic Radiation Science  

Science Journals Connector (OSTI)

Introductory physics courses present the basic concepts of radioactivity and an overview of nuclear physics that emphasizes the basic decay relationship and the various types of emitted radiation. Although this presentation provides insight into radiological science it often fails to interest students to explore these concepts in a more rigorous manner. One reason for limited student interest is the failure to link the discussion to topics of current interest. The author has found that presenting this material with a link to radiological dispersion devices (RDDs) or dirty bombs and their associated health effects provides added motivation for students. The events of Sept. 11 2001 and periodic media focus on RDDs heighten student interest from both a scientific curiosity as well as a personal protection perspective. This article presents a framework for a more interesting discussion of the basics of radiation science and their associated health effects. The presentation can be integrated with existing radioactivitylectures or added as a supplementary or enrichment activity.

Joseph John Bevelacqua

2010-01-01T23:59:59.000Z

388

Radiological Safety Training for Plutonium Facilities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NOT MEASUREMENT NOT MEASUREMENT SENSITIVE DOE-HDBK-1145-2013 March 2013 DOE HANDBOOK Radiological Safety Training for Plutonium Facilities U.S. Department of Energy TRNG-0061 Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. ii Radiological Safety Training for Plutonium Facilities DOE-HDBK-1145-2013 Program Management Foreword

389

ORISE: Multi-Agency Radiation Survey and Site Investigation Manual  

NLE Websites -- All DOE Office Websites (Extended Search)

Site Investigation Manual (MARSSIM) Site Investigation Manual (MARSSIM) As greater attention is being directed toward the decontamination and decommissioning (D&D) of nuclear facilities, the need for a standardized approach for implementing the necessary radiological surveys has become increasingly important. A multi-agency committee representing the U.S. Department of Defense (DOD), U.S. Department of Energy (DOE), U.S. Environmental Protection Agency (EPA), and U.S. Nuclear Regulatory Commission (NRC) has addressed this need by producing a guidance document known as the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM). Published in December 1997, MARSSIM provides detailed guidance for planning, implementing and evaluating environmental and facility radiological surveys to demonstrate compliance with a dose- or risk-based

390

Radiological Contamination Control Training for Laboratory Research  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

2 of 3) 2 of 3) Radiological Contamination Control Training for Laboratory Research Instructor's Guide Office of Environment, Safety & Health U.S. Department of Energy February 1997 DOE-HDBK-1106-97 ii This page intentionally left blank. DOE-HDBK-1106-97 iii Table of Contents Page DEPARTMENT OF ENERGY - Course/Lesson Plan.............................. 1 Standardized Core Course Materials................................................... 1 Course Goal.........................................................................1 Target Audience.................................................................. 1 Course Description............................................................... 1 Prerequisites...................................................................... 1

391

Nevada National Security Site Radiological Control Manual  

SciTech Connect

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

392

Radiological standards and calibration laboratory capabilities  

SciTech Connect

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

393

Conceptual design. Final report: TFE Verification Program  

SciTech Connect

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

394

The deployment of an innovative real-time radiological soil characterization system  

SciTech Connect

Fluor Fernald Inc., in conjunction with partners from Argonne National Laboratory, the Department of Energy's Environmental Measurements Laboratory, and Idaho National Engineering and Environmental Laboratory, has developed a program for characterizing radiological contaminants in soil in real time. The soil characterization system in use at the Fernald Environmental Management Project (FEMP) for over three years combines gamma ray spectrometry equipment with other technologies to produce a system that can scan large areas of ground and produce color coded maps which display quantitative information regarding isotopic contamination patterns. Software running on a battery powered lap-top computer, is used to control acquisition of gamma spectral data to link the spectral Information with precise detector position measurements from Global Positioning System (GPS) satellites, and to control transmission of data to a central station or van via a wireless Ethernet link where Surfer6 mapping software is used to produce maps showing the position and amount of each target analyte. Either sodium iodide (NaI) gamma ray detectors mounted on three different vehicles for mobile measurements or stationary tripod-mounted hyper-pure germanium (HPGe) detectors can be used in this system to radiologically characterize soil. The operational and performance characteristics, as well as the strengths and limitations of each of these units, will be described. The isotopic information generated by this system can be made available to remediation project mangers within an hour after the completion of a scan to aid in determination of excavation footprints, segregation of contaminated soil and verification of contamination removal. The immediate availability of radiological characterization data made possible by this real-time scanning system has allowed Fluor Fernald to accelerate remediation schedules and reduce costs by avoiding excavation delays and expensive and time consuming laboratory analyses. Obtaining actual radiological characterization data from a much greater percentage of the soil under characterization than would be possible with the collection of physical samples has also resulted in more effective remediation of the site. The regulatory climate under which these realtime measurements are performed is briefly discussed.

David Allen; Raymond Danahy; Gregory Laird; Dale Seiller; Joan White; Robert Janke

2000-09-29T23:59:59.000Z

395

Tags and seals for arms control verification  

SciTech Connect

Tags and seals have long been recognized as important tools in arms control. The trend in control of armaments is to limit militarily significant equipment that is capable of being verified through direct and cooperative means, chiefly on-site inspection or monitoring. Although this paper will focus on the CFE treaty, the role of tags and seals for other treaties will also be addressed. Published technology and concepts will be reviewed, based on open sources. Arms control verification tags are defined as unique identifiers designed to be tamper-revealing; in that respect, seals are similar, being used as indicators of unauthorized access. Tamper-revealing tags might be considered as single-point markers, seals as two-point couplings, and nets as volume containment. The functions of an arms control tag can be considered to be two-fold: to provide field verification of the identity of a treaty-limited item (TLI), and to have a means of authentication of the tag and its tamper-revealing features. Authentication could take place in the field or be completed elsewhere. For CFE, the goal of tags and seals can be to reduce the overall cost of the entire verification system.

DeVolpi, A.

1990-09-18T23:59:59.000Z

396

Verification of conventional arms-control agreements in Europe  

SciTech Connect

This study focuses on the verification conundrum and its manifestation in the European context - the CFE talks and agreement. It is based on the assumption that, in the foreseeable future, various types of verification regimes will be part of arms-control agreements all over the world: In Europe, where the Cold War has ended, but peace has yet to be established, and in volatile areas like Africa and the Middle East, where acute crises still rage. The main findings of the analysis are as follows: First, the puzzles of verification have to be addressed simultaneously within the prevailing political environment. In that way, the verification regime is able to handle the puzzles successfully. Second, the three main hypotheses of the dissertation, asserting the subordination of verification regimes to political environments, were supported by the analysis. Third, the theory was found helpful in explaining and predicting verification regimes of different political environments.

Lederman, I.I.

1991-01-01T23:59:59.000Z

397

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...&V—with publication of documents such as the International Performance Measurement and Verification Protocol (IPMVP) and ASHRAE’s “Guideline for Measurement of Energy and Demand Savings”—the continuing evolution of innovative energy saving technologies, processes...

Heinemeier, K.

2005-01-01T23:59:59.000Z

398

Logic verification using recursive learning, ATPG and transformations  

E-Print Network (OSTI)

Implications . Types of Indirect Implications 1. Controllability Implications and Equivalences Introduction to Conditional Don't Cares 1. CD: Conditional Don't Care Condition . 2. Example: Derivation of a Conditional Don't Care . 3. Multiple Conditional... 1. Similarity Enhancing Transformations Equivalent Node Identification . Proposed Verification Procedure 1. New Techniques Used in Our Verification Tool 39 43 44 49 51 fii1 vn CHAPTER Page E F G Algorithm for Verification Results...

Paul, Debjyoti

1996-01-01T23:59:59.000Z

399

Surveillance Guides - RPS 11.2 Radiological Work Practices  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

RADIOLOGICAL WORK PRACTICES RADIOLOGICAL WORK PRACTICES 1.0 Objective The objective of this surveillance is to evaluate the practices of workers performing tasks in radiological controlled areas to ensure that these practices protect the safety and health of the workers and comply with DOE requirements. 2.0 References 2.1 10 CFR 835, Occupational Radiation Protection 2.2 DOE/EH-0256T, rev. 1, Radiological Control Manual 3.0 Requirements Implemented This surveillance is conducted to implement requirement RP-0024 from the RL S/RID. This requirement comes from the Radiological Control Manual. 4.0 Surveillance Activities The Facility Representative performs the following activities to evaluate the effectiveness of work practices by contractor personnel in minimizing exposure to radiological hazards.

400

A golden anniversary for space-based treaty verification  

NLE Websites -- All DOE Office Websites (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...

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

Reviewing Measurement and Verification Plans for Federal ESPC Projects  

Energy.gov (U.S. Department of Energy (DOE))

Document provides a framework for implementing uniform and consistent reviews of measurement and verification (M&V) plans for Federal energy savings performance contract (ESPC) projects.

402

Microsoft Word - Advanced Solution Verification of CFD Solutions...  

NLE Websites -- All DOE Office Websites (Extended Search)

of a software implementation of a numerical algorithm is evaluated, typically by comparison against an exact solution. For t he p urpose o f comparison, the new verification...

403

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

404

NEMVP: North American energy measurement and verification protocol  

SciTech Connect

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

405

Measurement and Verification of Low Income Energy Efficiency Programs in  

Open Energy Info (EERE)

Measurement and Verification of Low Income Energy Efficiency Programs in Measurement and Verification of Low Income Energy Efficiency Programs in Brazil: Methodological Challenges Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Measurement and Verification of Low Income Energy Efficiency Programs in Brazil: Methodological Challenges Focus Area: Energy Efficiency Topics: Socio-Economic Website: www.eceee.org/conference_proceedings/eceee/2009/Panel_3/3.049/ Equivalent URI: cleanenergysolutions.org/content/measurement-and-verification-low-inco Language: English Policies: "Regulations,Financial Incentives" is not in the list of possible values (Deployment Programs, Financial Incentives, Regulations) for this property. Regulations: Feebates This report presents results from Brazilian electric utilities evaluation

406

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

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

faqfinaldecember-2010.pdf More Documents & Publications Comment submitted by the Alliance for Water Efficiency (AWE) regarding the Energy Star Verification Testing Program DOE...

407

Verification Method for SSI Problems with Extended Parameter Ranges  

Energy.gov (U.S. Department of Energy (DOE))

Verification Method for SSI Problems with Extended Parameter Ranges 2014 U.S. DOE Natural Phenomena Hazards Meeting Carl J. Costantino and Associates www.cjcassoc.com

408

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

409

GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material |  

National Nuclear Security Administration (NNSA)

Removing Vulnerable Civilian Nuclear and Radiological Material | Removing Vulnerable Civilian Nuclear and Radiological Material | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material Fact Sheet GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material

410

NNSA Helps Vietnam Establish Nuclear, Radiological Emergency Management  

National Nuclear Security Administration (NNSA)

Helps Vietnam Establish Nuclear, Radiological Emergency Management Helps Vietnam Establish Nuclear, Radiological Emergency Management System | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Press Releases > NNSA Helps Vietnam Establish Nuclear, Radiological Emergency ... Press Release NNSA Helps Vietnam Establish Nuclear, Radiological Emergency Management

411

GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material |  

NLE Websites -- All DOE Office Websites (Extended Search)

Removing Vulnerable Civilian Nuclear and Radiological Material | Removing Vulnerable Civilian Nuclear and Radiological Material | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material Fact Sheet GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material

412

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

Office of Environmental Management (EM)

of Radiological Incidents Carlos Corredor*, Department of Energy; Charley Yu, Argonne National Labs Abstract: Since September 11, 2001, there has been a large effort by...

413

Analysis of nuclear test TRINITY radiological and meteorological data  

SciTech Connect

This report describes the Weather Service Nuclear Support Office (WSNSO) analyses of the radiological and meteorological data collected for the TRINITY nuclear test. Inconsistencies in the radiological data and their resolution are discussed. The methods of normalizing the radiological data to a standard time and estimating fallout-arrival times are presented. The meteorological situations on event day and the following day are described. Comparisons of the WSNSO fallout analyses with analyses performed in the 1940s are presented. The radiological data used to derive the WSNSO 1987 fallout patterns are tabulated in appendices.

Quinn, V.E.

1987-09-01T23:59:59.000Z

414

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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...

415

DOE, Westinghouse to Partner with NMJC To Train Radiological...  

NLE Websites -- All DOE Office Websites (Extended Search)

to Partner with NMJC To Train Radiological and Waste Handling Technicians Hobbs, NM, December 5, 2001 -- Representatives of the Waste Isolation Pilot Plant (WIPP) yesterday...

416

Trending and root cause analysis of TWRS radiological problem reports  

SciTech Connect

This document provides a uniform method for trending and performing root cause analysis for radiological problem reports at Tank Waste Remediation System (TWRS).

Brown, R.L.

1997-07-31T23:59:59.000Z

417

Hospital Triage in First Hours After Nuclear or Radiological...  

NLE Websites -- All DOE Office Websites (Extended Search)

Hospital Triage in the First 24 Hours after a Nuclear or Radiological Disaster Medical professionals with the Radiation Emergency Assistance CenterTraining Site (REACTS) at the...

418

DOE Subpart H Report. Annual NESHAPS Meeting on Radiological...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NESHAPS Meeting on Radiological Emissions Gustavo Vazquez*, DOE; Sandra Snyder, PNNL Abstract: The National Emissions Standards for Hazardous Air Pollutants, Subpart H,...

419

Radiological hazards of alpha-contaminated waste  

SciTech Connect

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

420

OPS 9.10 Independent Verification 8/24/98 | Department of Energy  

Energy Savers (EERE)

Independent Verification 82498 The objective of this surveillance is to evaluate the conduct of selected independent verification activities. This surveillance provides a...

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

The First Hundred Brown Dwarfs Discovered by the Wide-field Infrared Survey Explorer (WISE)  

E-Print Network (OSTI)

We present ground-based spectroscopic verification of 6 Y dwarfs (see also Cushing et al.), 89 T dwarfs, 8 L dwarfs, and 1 M dwarf identified by the Wide-field Infrared Survey Explorer (WISE). Eighty of these are cold brown ...

Bochanski, John J.

422

Radiological Conditions at Bikini Atoll: Prospects for ResettlementRadiological Conditions at the Semipalatinsk Test Site, Kazakhstan: Preliminary assessment and recommendations for further study  

Science Journals Connector (OSTI)

Radiological Conditions at the Semipalatinsk Test Site, Kazakhstan: Preliminary assessment and recommendations for further study Radiological Assessment Reports Series 1998 (Vienna: IAEA) 43 pp 200 Austr. Sch. ISBN 92 0 104098 9 These two reports stem from requests to the IAEA, from the local Government Authorities, for help and advice in assessing the radiological situations at two former nuclear weapons testing sites. Both reports have similar general structures - a discussion of the geographical context of the sites; a summary of the weapon tests, and their continuing impacts on the local populations; the basis for the IAEA programme; radiological concepts and criteria in the context of the residual contamination arising from the tests, and specifically the bases for intervention and remediation; assessments of the present and future radiation exposures of the actual/potential residents of the areas; and conclusions and recommendations. Because the indigenous Bikinian population is at present relocated elsewhere in the Marshall Islands archipelago, the report for Bikini Atoll is essentially concerned with an assessment of the current radiological situation, the prospects for resettlement, and the justification and available strategies for remedial action to reassure the Bikinians that it would be safe to return. Since the cessation of testing at the atoll in July 1958, there have been continuing radiological surveys of the local environment - the latest being the Marshall Islands Nationwide Radiological Study under an International Scientific Advisory Panel. The Panel report was not accepted by the Marshall Islands Government, who then requested the IAEA to carry out an independent peer review. The IAEA assessment (with some corroboratory data from a monitoring mission) confirmed the estimate of 15 mSv a-1 for the total potential dose rate to individuals relying entirely on locally produced foodstuffs, mainly from 137Cs in coconuts and other fruits. An examination of existing guidelines and practice concluded that 10 mSv a-1 is an appropriate generic action level to trigger consideration of remediation strategies prior to resettlement. From five potential remedial measures, two were considered in more detail - removal and disposal of the surface 40 cm of the topsoil, and treatment of the soil with high potassium fertilizers. It was concluded that the former, although reducing the dose rate from the residual contamination to less than 0.1 mSv a-1, would entail unacceptable environmental and social consequences. Experimental investigation of the latter showed that it would reduce the uptake of 137Cs significantly, with the total dose rate rapidly declining to about 1.2 mSv a-1; it was also found that the application of fertilizer would have to be repeated every 4-5 years to sustain the reduction. The latter was, therefore, the preferred option together with some localised soil removal in the living areas of the village to reduce both the external exposure and the inhalation pathway. The sole remaining concern of the Bikinians appears to relate to the identification of a reliable authority to assume responsibility for maintaining the implementation of the countermeasure to reduce the 137Cs uptake into foodstuffs for the foreseeable future. If this concern can be resolved, it appears that the way is open for the resettlement of the Bikinian people on the atoll. The situation at Semipalatinsk is somewhat different in one respect - the site, although large, has unrestricted access and small numbers of people already live within the boundaries. After the request to the IAEA from the Kazakhstan Government for assistance, the initial objective was to determine the magnitude of the problem. This was achieved on the first mission to the site when the main areas of contamination were identified using information available from the local authorities, and radiation measurements and sample collections were made at identified places both within, and external to, the site. A second mission extended the range of measurements and sample

Dennis Woodhead

1999-01-01T23:59:59.000Z

423

Efficient RC Power Grid Verification Using Node Elimination  

E-Print Network (OSTI)

Efficient RC Power Grid Verification Using Node Elimination Ankit Goyal Department of ECE to reduce the size of power grids but their fo- cus is more on simulation. In verification, we are concerned. This paper pro- poses a novel approach to systematically reduce the power grid and accurately compute

Najm, Farid N.

424

Fast Vectorless Power Grid Verification Using an Approximate Inverse Technique  

E-Print Network (OSTI)

Fast Vectorless Power Grid Verification Using an Approximate Inverse Technique Nahi H. Abdul Ghani Department of ECE University of Toronto Toronto, Ontario, Canada f.najm@utoronto.ca ABSTRACT Power grid Aids General Terms Performance, Algorithms, Verification Keywords Power grid, voltage drop, approximate

Najm, Farid N.

425

SPPV: A NEW FORMAL VERIFICATION ENVIRONMENT Lubomir Ivanov Michael Shute  

E-Print Network (OSTI)

are extremely powerful, but cannot be fully automated (e.g. Theorem Proving). Others such as Model Checking [1 ­ based on series-parallel poset verification. SPPV allows fast, automated verification of event sequencing in complex systems. The system model and properties can be expressed as series-parallel poset

Ivanov, Lubomir

426

Modeling and Verification of Embedded Systems using Cadence SMV  

E-Print Network (OSTI)

in the designs obtained by simulation is rapidly diminishing. However, verification has the promise of reducing1 Modeling and Verification of Embedded Systems using Cadence SMV Ali Abbas Mir, Subhashini on a technique called ``symbolic model checking''. It uses an OBDD (Ordered Binary Decision Diagram) algorithm

Tahar, Sofiène

427

Modeling and Verification of Embedded Systems using Cadence SMV  

E-Print Network (OSTI)

in the designs obtained by simulation is rapidly diminishing. However, verification has the promise of reducing1 Modeling and Verification of Embedded Systems using Cadence SMV Ali Abbas Mir, Subhashini on a technique called "symbolic model checking". It uses an OBDD (Ordered Binary Decision Diagram) algorithm

Tahar, Sofiène

428

Modeling and Verification of Embedded Systems Using Cadence SMV  

E-Print Network (OSTI)

the confidence in the de- signs obtained by simulation is rapidly diminishing. How- ever, verification hasModeling and Verification of Embedded Systems Using Cadence SMV Ali Abbas Mir, Subhashini, based on a tech- nique called "symbolic model checking". In this paper we investigate the modeling

Tahar, Sofiène

429

AHAM Letter Acknowledging DOE Letter on Verification Program  

Energy.gov (U.S. Department of Energy (DOE))

This document is a response to the letter dated April 26, 2013, in which DOE adopted a new policy regarding DOE ENERGY STAR verification testing of models that are part of the AHAM verification program for clothes washers, dishwashers, and residential refrigerator/freezers.

430

Advanced Waste Management Now Available as Accredited SEP Verification Body  

Energy.gov (U.S. Department of Energy (DOE))

The U.S. Department of Energy is pleased to announce that Advanced Waste Management Systems Inc. (AWM) is now a fully accredited Verification Body for Superior Energy Performance™ (SEP). This ANSI-ANAB accreditation enables AWM to provide third-party verification for industrial facilities that wish to demonstrate energy management excellence and sustained energy savings to earn SEP certification.

431

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.

432

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

433

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

434

The Present Role of Radiological Methods in Engineering  

Science Journals Connector (OSTI)

...Present Role of Radiological Methods in Engineering R. Halmshaw A brief outline of the history of industrial radiology is given. Major...of metals and metal thicknesses used in engineering, X-ray energies from 20 keV to 30 MeV...

1979-01-01T23:59:59.000Z

435

Surveillance Guide - OPS 9.10 Independent Verification  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

INDEPENDENT VERIFICATION INDEPENDENT VERIFICATION 1.0 Objective The objective of this surveillance is to evaluate the conduct of selected independent verification activities. This surveillance provides a basis for evaluating the effectiveness of the contractor's independent verifications programs and for establishing compliance with DOE requirements. 2.0 References 2.1 DOE 5480.19, Conduct of Operations Requirements for DOE Facilities 2.2 DOE-STD-1036-93, Guide to Good Practices for Independent Verification 3.0 Requirements Implemented This surveillance is conducted to implement requirements of the Functions, Responsibilities and Authorities Manual, Section 20, Operations, FRAM #s 4253, 4258, and 4261. These requirements are drawn from DOE 5480.19.

436

CRAD, Implementation Verification Review - July 20, 2011 | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Implementation Verification Review - July 20, 2011 Implementation Verification Review - July 20, 2011 CRAD, Implementation Verification Review - July 20, 2011 July 20, 2011 Implementation Verification Review of Safety Basis Hazard Controls (HSS CRAD 45-39, Rev. 1) The Implementation Verification Review (IVR) inspection will evaluate the effectiveness of processes for independently verifying and re-verifying implementation of the safety basis hazard controls at the site's nuclear facilities and associated site office oversight methodology. The inspection will consist of an evaluation of the procedures and processes that establish the IVR or similar process, as well as an evaluation of IVR or similar processes implementation and oversight. Review of implementation at a site may include any or all of the following activities:

437

Pre-Hospital Practices for Handling a Radiologically Contaminated Patient |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Pre-Hospital Practices for Handling a Radiologically Contaminated Pre-Hospital Practices for Handling a Radiologically Contaminated Patient Pre-Hospital Practices for Handling a Radiologically Contaminated Patient The purpose of this User's Guide is to provide instructors with an overview of the key points covered in the video. The Student Handout portion of this Guide is designed to assist the instructor in reviewing those points with students. The Student Handout should be distributed to students after the video is shown and the instructor should use the Guide to facilitate a discussion on key activities and duties at the scene. PRE-HOSPITAL PRACTICES FOR HANDLING A RADIOLOGICALLY CONTAMINATED PATIENT More Documents & Publications Emergency Response to a Transportation Accident Involving Radioactive Material Handling and Packaging a Potentially Radiologically Contaminated Patient

438

Nuclear Radiological Threat Task Force Established | National Nuclear  

NLE Websites -- All DOE Office Websites (Extended Search)

Radiological Threat Task Force Established | National Nuclear Radiological Threat Task Force Established | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > Nuclear Radiological Threat Task Force Established Nuclear Radiological Threat Task Force Established November 03, 2003 Washington, DC Nuclear Radiological Threat Task Force Established

439

How ORISE is Making a Difference: Radiological Assessment and Monitoring  

NLE Websites -- All DOE Office Websites (Extended Search)

Develops Paperless Tool to Assist with Data Input Into Radiological Develops Paperless Tool to Assist with Data Input Into Radiological Assessment and Monitoring System During the Empire 09 exercise, the Oak Ridge Institute for Science and Education (ORISE) tested (for the first time) a paperless system of data management to support the operations of the Federal Radiological Monitoring and Assessment Center (FRMAC). The paperless FRMAC (pFRMAC) provides tools that enables the FRMAC to collect and process field measurements and samples following a radiological or nuclear event. The process allows field data to be entered into specialized electronic tablets that are then sent to the Radiological Assessment and Monitoring System (RAMS). RAMS is the hub of pFRMAC that provides data analysis to the consequence management home team and

440

NNSA Conducts Radiological Training in Slovenia | National Nuclear Security  

National Nuclear Security Administration (NNSA)

NNSA Blog > NNSA Conducts Radiological Training in Slovenia NNSA Blog > NNSA Conducts Radiological Training in Slovenia NNSA Conducts Radiological Training in Slovenia Posted By Office of Public Affairs NNSA Blog NNSA today concluded International Radiological Assistance Program Training for Emergency Response (I-RAPTER) in Slovenia. The training, co-sponsored by the International Atomic Energy Agency, was provided to 36 nuclear/radiological emergency responders, which included 15 participants from Slovenia and 21 students from 20 other countries. The training was conducted with involvement of personnel from Sandia National Laboratories, the Remote Sensing Laboratory and Idaho National Laboratory. To read more about the training see: http://www.nnsa.energy.gov/mediaroom/pressreleases/slovenia Posted on March 22, 2012 at 4:13 pm ET

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-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Radiation Protection Standards Radiation Protection Standards Study Guide 1.09-1 Course Title: Radiological Control Technician Module Title: Radiological Protection Standards Module Number: 1.09 Objectives: 1.09.01 Identify the role of advisory agencies in the development of recommendations for radiological control. 1.09.02 Identify the role of regulatory agencies in the development of standards and regulations for radiological control. 1.09.03 Identify the scope of 10 CFR Part 835. References: 1. ANL-88-26 (1988) "Operational Health Physics Training"; Moe, Harold; Argonne National Laboratory, Chicago 2. U.S. Department of Energy, DOE-STD-1098-99, "Radiological Control Standard" 3. 10 CFR Part 835 (1998) "Occupational Radiation Protection" DOE-HDBK-1122-99 Module 1.09 Radiation Protection Standards

442

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EA-1919: Recycle of Scrap Metals Originating from Radiological EA-1919: Recycle of Scrap Metals Originating from Radiological Areas EA-1919: Recycle of Scrap Metals Originating from Radiological Areas Summary 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.) PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD December 28, 2012 EA-1919: Notice of Public Comment Period Extension Recycling of Scrap Metals Originating from Radiological Areas December 12, 2012 EA-1919: Notice of Availability of a Draft Programmatic Environmental

443

PRE-HOSPITAL PRACTICES FOR HANDLING A RADIOLOGICALLY CONTAMINATED PATIENT  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Pre-hospital Practices for Handling a Pre-hospital Practices for Handling a Pre-hospital Practices for Handling a Pre-hospital Practices for Handling a Pre-hospital Practices for Handling a Pre-hospital Practices for Handling a Radiologically Contaminated Patient Radiologically Contaminated Patient Radiologically Contaminated Patient Radiologically Contaminated Patient Radiologically Contaminated Patient DISCLAIMER DISCLAIMER DISCLAIMER DISCLAIMER DISCLAIMER Viewing this video and completing the enclosed printed study material do not by themselves provide sufficient skills to safely engage in or perform duties related to emergency response to a transportation accident involving radioactive material. Meeting that goal is beyond the scope of this video and requires either additional specific areas of competency or more hours of training

444

CONSENT FOR PROGRAM ACCESS SURVEYS AND ENGINEERING STUDIES  

Office of Legacy Management (LM)

^_. . _ .." ^_. . _ .." -. . -.. --__ .-._-4 .I.. -. . _ ,.. ' 1,. .k -e I %..a, *a' i.J t 7 . .L 0 - ' f: . CONSENT FOR PROGRAM ACCESS SURVEYS AND ENGINEERING STUDIES The undersigned persons (hereinafter individually and collectively referred to as "Owner") represent that they own the following property: THE B b T METALS COMPANY 425 WEST T O W N STREET COLUMBUS, OHIO 43215 The following matters are understood by the Owner: The United States of America (the "Government"), acting through the U.S. Department of Energy (DOE), will provide or contract for radiological surveys and engineering assessments for the following purposes: (1) DESIGNATION - determining if there is radiological contamination on the property for which DOE has authority and

445

Formal Verification of the SeVeCom HSM API with the Applied -calculus and the ProVerif tool  

E-Print Network (OSTI)

Formal Verification of the SeVeCom HSM API with the Applied -calculus and the ProVerif tool Ta Vinh Programming Interface (API) of the HSM. Besides the physical protection provided by the hardware of the HSM, its API must also be secure and resistant against attempts of logical break-ins. Unfortunately

Bencsáth, Boldizsár

446

Radiological aspects of in situ uranium recovery  

SciTech Connect

In the last few years, there has been a significant increase in the demand for Uranium as historical inventories have been consumed and new reactor orders are being placed. Numerous mineralized properties around the world are being evaluated for Uranium recovery and new mining / milling projects are being evaluated and developed. Ore bodies which are considered uneconomical to mine by conventional methods such as tunneling or open pits, can be candidates for non-conventional recovery techniques, involving considerably less capital expenditure. Technologies such as Uranium in situ leaching in situ recovery (ISL / ISR), have enabled commercial scale mining and milling of relatively small ore pockets of lower grade, and may make a significant contribution to overall world wide uranium supplies over the next ten years. Commercial size solution mining production facilities have operated in the US since 1975. Solution mining involves the pumping of groundwater, fortified with oxidizing and complexing agents into an ore body, solubilizing the uranium in situ, and then pumping the solutions to the surface where they are fed to a processing plant. Processing involves ion exchange and may also include precipitation, drying or calcining and packaging operations depending on facility specifics. This paper presents an overview of the ISR process and the health physics monitoring programs developed at a number of commercial scale ISL / ISR Uranium recovery and production facilities as a result of the radiological character of these processes. Although many radiological aspects of the process are similar to that of conventional mills, conventional-type tailings as such are not generated. However, liquid and solid byproduct materials may be generated and impounded. The quantity and radiological character of these by products are related to facility specifics. Some special monitoring considerations are presented which are required due to the manner in which Radon gas is evolved in the process and the unique aspects of controlling solution flow patterns underground. An overview of the major aspects of the health physics and radiation protection programs that were developed at these facilities are discussed and contrasted to circumstances of the current generation and state of the art of Uranium ISR technologies and facilities. (authors)

BROWN, STEVEN H. [SHB INC., 7505 S. Xanthia Place, Centennial, Colorado (United States)

2007-07-01T23:59:59.000Z

447

Enhancing Diagnostic Accuracy in Oral Radiology: A Case for the Basic Sciences.  

E-Print Network (OSTI)

??Background: Cognitive processing in diagnostic oral radiology requires a solid foundation in the basic sciences as well as knowledge of the radiologic changes associated with… (more)

Baghdady, Mariam

2014-01-01T23:59:59.000Z

448

E-Print Network 3.0 - aids radiological findings Sample Search...  

NLE Websites -- All DOE Office Websites (Extended Search)

pulmonary edema... administrative codes that will aid in billing and quality assurance. The radiology report should record... of Radiology. ACR prac- tice guideline for...

449

Safeguards for spent fuels: Verification problems  

SciTech Connect

The accumulation of large quantities of spent nuclear fuels world-wide is a serious problem for international safeguards. A number of International Atomic Energy Agency (IAEA) member states, including the US, consider spent fuel to be a material form for which safeguards cannot be terminated, even after permanent disposal in a geologic repository. Because safeguards requirements for spent fuels are different from those of conventional bulk-handling and item-accounting facilities, there is room for innovation to design a unique safeguards regime for spent fuels that satisfies the goals of the nuclear nonproliferation treaty at a reasonable cost to both the facility and the IAEA. Various strategies being pursued for long-term management of spent fuels are examined with a realistic example to illustrate the problems of verifying safeguards under the present regime. Verification of a safeguards regime for spent fuels requires a mix of standard safeguards approaches, such as quantitative verification and use of seals, with other measures that are unique to spent fuels. 17 refs.

Pillay, K.K.S.; Picard, R.R.

1991-01-01T23:59:59.000Z

450

CTBT integrated verification system evaluation model supplement  

SciTech Connect

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 U.S. 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, in sound, radionuclide, and hydroacoustic) and allows the user to investigate synergy among the technologies. Specifically, IVSEM estimates the detection effectiveness (probability of detection), location accuracy, and identification capability 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. The original IVSEM report, CTBT Integrated Verification System Evaluation Model, SAND97-25 18, described version 1.2 of IVSEM. This report describes the changes made to IVSEM version 1.2 and the addition of identification capability estimates that have been incorporated into IVSEM version 2.0.

EDENBURN,MICHAEL W.; BUNTING,MARCUS; PAYNE JR.,ARTHUR C.; TROST,LAWRENCE C.

2000-03-02T23:59:59.000Z

451

Radiological Control Programs for Special Tritium Compounds  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

84-2004 84-2004 SEPTEMBER 2004 CHANGE NOTICE NO. 1 Date June 2006 DOE HANDBOOK RADIOLOGICAL CONTROL PROGRAMS FOR SPECIAL TRITIUM COMPOUNDS U.S. Department of Energy AREA OCSH Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE ii Table of Changes Page Change 67 (near bottom) In row 1, column 2 of the table titled "dosimetric properties" 6 mrem was changed to 6 x 10 -2 mrem Available on the Department of Energy Technical Standards Program Web site at http://tis.eh.doe.gov/techstds/ DOE-HDBK-1184-2004 iii Foreword The Department of Energy (DOE) and its predecessor agencies have undertaken a wide variety

452

Radiological Control Programs for Special Tritium Compounds  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

F 1325.8 F 1325.8 (08-93) United States Government Department of Energy memorandum DATE: May 11, 2006 REPLY TO EH-52:JRabovsky:3-2 135 ATTN OF: APPROVAL OF CHANGE NOTICE 1 TO DEPARTMENT OF ENERGY (DOE) SUBJECT. HANDBOOK 1184-2004, RADIOLOGICAL CONTROL PROGRAMS FOR SPECIAL TRITIUM COMPOUNDS TO: Dennis Kubicki, EH-24 Technical Standards Manager This memorandum forwards the subject Change Notice 1 to DOE Handbook, DOE- HDBK- 1184-2004, which has approved for publication and distribution. The change to this handbook consists of a correction to the rule of thumb, listed in Appendix A, for converting the uptake of tritium oxide into radiation dose. A factor of 1/100 was inadvertently omitted from this rule of thumb when this DOE Handbook was originally published. This change does not affect the references, is not of a technical nature, and

453

Radiological Contamination Control Training for Laboratory Research  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Change Notice 2 Change Notice 2 with Reaffirmation January 2007 DOE HANDBOOK RADIOLOGICAL CONTAMINATION CONTROL TRAINING FOR LABORATORY RESEARCH U.S. Department of Energy FSC 6910 Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-HDBK-1106-97 ii This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. DOE-HDBK-1106-97 iii Page/Section Change

454

Radiological Contamination Control Training for Laboratory Research  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Reaffirmation Reaffirmation August 2002 Change Notice 1 December 2004 DOE HANDBOOK RADIOLOGICAL CONTAMINATION CONTROL TRAINING FOR LABORATORY RESEARCH U.S. Department of Energy FSC 6910 Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-HDBK-1106-97 ii This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. DOE-HDBK-1106-97 iii Page/Section Change

455

Radiological assessment of BWR recirculatory pipe replacement  

SciTech Connect

Replacement of primary recirculating coolant pipe in BWRs is a major effort that has been carried out at a number of nuclear generating stations. This report reviews the planned or actual pipe replacement projects at six sites: Nine Mile Point-1, Monticello, Cooper, Peach Bottom-2, Vermont Yankee, and Browns Ferry-1. It covers the radiological issues of the pipe replacement, measures taken to reduce doses to ALARA, estimated and actual occupational doses, and lessons learned during the various replacements. The basis for the decisions to replace the pipes, the methods used for preparation and decontamination, the removal of old pipe, and the installation of the new pipe are briefly described. Methods for reducing occupational radiation dose during pipe repairs/replacements are recommended. 32 refs., 12 figs., 17 tabs.

Parkhurst, M.A.; Hadlock, D.E.; Harty, R.; Pappin, J.L.

1986-02-01T23:59:59.000Z

456

Radiological Control Change Notice 1 Memorandum  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DATE: May DATE: May 20, 2004 REPLY TO EH-52:Judith D. Foulke:301 :903-5865 ATTN OF: CHANGE NOTICE TO DEPARTMENT OF ENERGY (DOE) HANDBOOK, DOE-STD- SUBJECT. 1098-99, RADIOLOGICAL CONTROL TO: George Detsis, EH-3 1 This memorandum forwards Change Notice Number 1 to subject DOE Technical Standard, DOE-STD-1098-99. The changes are being made as part of the 5-year review of the standard. The table inserted into the document details the changes. After the changes are made, a notice of intent to reaffirm memorandum will be issued. A compact disk (CD) of the revised document in MS Word and in PDF format is attached. If there are any questions, please contact Dr. Judith Foulke of my staff on 3-5865 or electronic mail (Judy.Foulke@eh.doe.gov). ill R. McArthur, PhD, C1}T Office Director Office of Worker Protection Policy

457

Comment submitted by Traulsen regarding the Energy Star Verification Testing Program  

Energy.gov (U.S. Department of Energy (DOE))

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

458

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

Energy.gov (U.S. Department of Energy (DOE))

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

459

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

Energy.gov (U.S. Department of Energy (DOE))

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

460

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

Energy.gov (U.S. Department of Energy (DOE))

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


461

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

Energy.gov (U.S. Department of Energy (DOE))

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

462

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

Energy.gov (U.S. Department of Energy (DOE))

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

463

Supplement No. 2 to the FUSRAP Summary Protocol – Verification and Certification Protocol  

Energy.gov (U.S. Department of Energy (DOE))

Supplement No. 2 to the FUSRAP Summary Protocol – Verification and Certification Protocol (November 1985, Rev. 1)

464

Pretreatment verification of dose calculation and delivery by means of measurements with PLEXITOM™ phantom  

Science Journals Connector (OSTI)

Aim To validate a pretreatment verification method of dose calculation and dose delivery based on measurements with Metaplex PTW phantom. Background The dose-response relationships for local tumor control and radiosensitive tissue complications are strong. It is widely accepted that an accuracy of dose delivery of about 3.5% (one standard deviation) is required in modern radiotherapy. This goal is difficult to achieve. This paper describes our experience with the control of dose delivery and calculations at the ICRU reference point. Materials and methods The calculations of dose at the ICRU reference point performed with the treatment planning system CMS XiO were checked by measurements carried out in the PLEXITOM™ phantom. All measurements were performed with the ion chamber positioned in the phantom, at the central axis of the beam, at depth equivalent to the radiological depth (at gantry zero position). The source-to-phantom surface distance was always set to keep the source-to-detector distance equal to the reference point depth defined in the ICRU Report 50 (generally, 100 cm). The dose was measured according to IAEA TRS 398 report for measurements in solid phantoms. The measurement results were corrected with the actual accelerator's output factor and for the non-full scatter conditions. Measurements were made for 111 patients and 327 fields. Results The average differences between measurements and calculations were 0.03% (SD = 1.4%), 0.3% (SD = 1.0%), 0.1% (SD = 1.1%), 0.6% (SD = 1.8%), 0.3% (SD = 1.5%) for all measurements, for total dose, for pelvis, thorax and H&N patients, respectively. Only in 15 cases (4.6%), the difference between the measured and the calculated dose was greater than 3%. For these fields, a detailed analysis was undertaken. Conclusion The verification method provides an instantaneous verification of dose calculations before the beginning of a patient's treatment. It allows to detect differences smaller than 3.5%.

Pawe? Wo?owiec; Pawe? Kuko?owicz; Krzysztof Lis

2013-01-01T23:59:59.000Z

465

MCNP Techniques for Modeling Sodium Iodide Spectra of Kiwi Surveys  

SciTech Connect

This work demonstrates how MCNP can be used to predict the response of mobile search and survey equipment from base principles. The instrumentation evaluated comes from the U.S. Department of Energy’s Aerial Measurement Systems. Through reconstructing detector responses to various point-source measurements, detector responses to distributed sources can be estimated through superposition. Use of this methodology for currently deployed systems allows predictive determinations of activity levels and distributions for common configurations of interest. This work helps determine the quality and efficacy of certain surveys in fully characterizing an effected site following a radiological event of national interest.

Robert B. Hayes

2007-11-01T23:59:59.000Z

466

Idaho National Laboratory Radiological Response Training Range draft  

NLE Websites -- All DOE Office Websites (Extended Search)

Idaho National Laboratory Radiological Response Training Range draft environmental assessment available for public review and comment Idaho National Laboratory Radiological Response Training Range draft environmental assessment available for public review and comment August 4, 2010 Media contact: Brad Bugger, 208-526-0833 The public is invited to read and comment on a draft environmental assessment that the U.S. Department of Energy has published for a proposed radiological response training range at the Idaho National Laboratory (INL). At the range, INL experts would train personnel, conduct exercises, and perform technology evaluation and demonstrations in support of national technical nuclear forensic and radiological emergency response programs. �The Radiological Response Training Range will allow emergency responders to prepare for a major radiological incident by training in an environment that safely simulates scenarios they might encounter,� said Vic Pearson, DOE�s document manager for the environmental assessment. �Activities at the range would directly support the nation�s readiness to respond to a radiological incident, but more importantly, would enable responders to develop proficiency in characterizing the scene in support of determining the origins of the incident.�

467

Status Report on REC Verification, Tracking and Associated Issues  

NLE Websites -- All DOE Office Websites (Extended Search)

REC REC Verification, Tracking Systems and Associated Issues DOE Workshop on REC Markets and Challenges September 11, 2007 Meredith Wingate Director of Clean Energy Policy Design and Implementation Center for Resource Solutions Main Points * Think National - Verification issues are getting more complicated with the intersection of RECs and emissions markets - Market needs more rigorous verification * More coordination is needed Role of Tracking Systems * Primary tool for implementing state RPS programs * Produce data for environmental disclosure programs * Facilitate REC transactions Certificate-based Tracking Programs * ERCOT RECs Program (2001) * NEPOOL GIS (2002) * WI RRC Program (2003-2007) * PJM GATS (2005) * NJ SRECS (2005) * WREGIS (2007) * M-RETS (2007) * New York State (2008?)

468

Reviewing Measurement and Verification Plans for Federal ESPC Projects  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Reviewing Measurement & Verification Plans Reviewing Measurement & Verification Plans for Federal ESPC Projects February 2007 Federal Energy Management Program (FEMP) Office of Energy Efficiency and Renewable Energy U.S. Department of Energy This document was developed for the U.S. Department of Energy's Federal Energy Management Program by Nexant, Inc., and Lawrence Berkeley National Laboratory. This document is posted on FEMP's web site at www.eere.energy.gov/femp/financing/ . [Headers and footers only revised 12/08] Reviewing M&V Plans Contents REVIEWING MEASUREMENT AND VERIFICATION PLANS FOR FEDERAL ESPC PROJECTS ............................................................................................................ 1 STEP 1 - PREPARE CUSTOM REPORT AND CHECKLIST FROM TEMPLATE .......................... 1

469

GTRI's Nuclear and Radiological Material Protection | National Nuclear  

NLE Websites -- All DOE Office Websites (Extended Search)

Protection | National Nuclear Protection | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog GTRI's Nuclear and Radiological Material Protection Home > About Us > Our Programs > Nonproliferation > Global Threat Reduction Initiative > GTRI's Nuclear and Radiological Material Protection GTRI's Nuclear and Radiological Material Protection

470

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

9 9 Radiological Control Technician Training Fundamental Academic Training Instructor's Guide Phase I Coordinated and Conducted for Office of Environment, Safety & Health U.S. Department of Energy DOE-HDBK-1122-99 Radiological Control Technician Instructor's Guide ii This page intentionally left blank. DOE-HDBK-1122-99 Radiological Control Technician Instructor's Guide iii Course Developers William Egbert Lawrence Livermore National Laboratory Dave Lent Coleman Research Michael McNaughton Los Alamos National Laboratory Bobby Oliver Lockheed Martin Energy Systems Richard Cooke Argonne National Laboratory Brian Thomson Sandia National Laboratory Michael McGough Westinghouse Savannah River Company Brian Killand Fluor Daniel Hanford Corporation Course Reviewers Technical Standards Managers

471

Verification Checklist Home Address: City: State: Zip:  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Indoor airPLUS Version 1 (Rev. 01) Verification Checklist Home Address: City: State: Zip: Section Requirements (Refer to full Indoor airPLUS Construction Specifications for details) Must Correct Builder Verified Rater Verified N/A Note: The Rev. 01 checklist has been modified to reflect only the additional Indoor airPLUS requirements and their corresponding section numbers that must be met after completing the ENERGY STAR checklists. ENERGY STAR remains a prerequisite for Indoor airPLUS certification. ENERGY STAR V3 Checklists Thermal Enclosure System Rater Checklist completed. o o Water Management System Builder Checklist completed. o o HVAC System Quality Installation Contractor Checklist completed. o o HVAC System Quality Installation Rater Checklist completed. o o

472

2014 NERSC User Survey  

NLE Websites -- All DOE Office Websites (Extended Search)

2014 NERSC User Survey 2014 NERSC User Survey December 17, 2014 by Francesca Verdier (0 Comments) Please take a few minutes to fill out NERSC's annual user survey. Your feedback is...

473

DOE-HDBK-1122-99; Radiological Control Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Radiological Incidents and Emergencies Radiological Incidents and Emergencies Instructor's Guide 2.13-1 Course Title: Radiological Control Technician Module Title: Radiological Incidents and Emergencies Module Number: 2.13 Objectives: 2.13.01 Describe the general response and responsibilities of an RCT during any incident. L 2.13.02 Identify any emergency equipment and facilities that are available, including the location and contents of emergency equipment kits. L 2.13.03 Describe the RCT response to a Continuous Air Monitor (CAM) alarm. L 2.13.04 Describe the RCT response to a personnel contamination monitor alarm. L 2.13.05 Describe the RCT response to off scale or lost dosimetry. L 2.13.06 Describe the RCT response to rapidly increasing, unanticipated radiation levels or an area radiation monitor alarm. L

474

DOE-HDBK-1141-2001; Radiological Assessor Training, Overheads  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

13.1 13.1 Overhead 13.1 DOE-HDBK-1141-2001 Radiological Aspects of Accelerators Objectives: * Identify the general characteristics of accelerators. * Identify the types of particles accelerated. * Identify the two basic types of accelerators. * Identify uses for accelerators. * Define prompt radiation. * Identify prompt radiation sources. OT 13.2 Overhead 13.2 DOE-HDBK-1141-2001 Radiological Aspects of Accelerators (cont.) Objectives: * Define radioactivation. * Explain how contaminated material differs from activated material with regard to radiological concerns. * Identify activation sources. OT 13.3 Overhead 13.3 DOE-HDBK-1141-2001 Radiological Aspects of Accelerators (cont.) Objectives: * Identify engineered and administrative controls at accelerator facilities. * Identify the special

475

GTRI commended for work to secure radiological sources | National Nuclear  

National Nuclear Security Administration (NNSA)

GTRI commended for work to secure radiological sources | National Nuclear GTRI commended for work to secure radiological sources | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > GTRI commended for work to secure radiological sources GTRI commended for work to secure radiological sources Posted By Office of Public Affairs Container NNSA's Global Threat Reduction Initiative (GTRI) was recently commended

476

Radiological Worker Training Power Point Slides for App. A  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

30-2008 30-2008 DOE HANDBOOK Radiological Worker Training DOE-HDBK-1130-2008 Overheads December 2008 Reaffirmed 2013 OT 1.1 DOE-HDBK-1130-2008 Overhead 1.1 Regulatory Documents Objectives: * Identify the hierarchy of regulatory documents. * Define the purposes of 10 CFR Parts 820, 830 and 835. * Define the purpose of the DOE Radiological Control Standard. OT 1.2 DOE-HDBK-1130-2008 Overhead 1.2 Regulatory Documents (cont.) Objectives: * Define the terms "shall" and "should" as used in the above documents. * Describe the role of the Defense Nuclear Facilities Safety Board (DNFSB) at DOE sites and facilities. OT 1.3 DOE-HDBK-1130-2008 Overhead 1.3 DOE Radiological Health and Safety Policy * Conduct oversight to ensure compliance and that appropriate radiological work

477

GTRI commended for work to secure radiological sources | National Nuclear  

NLE Websites -- All DOE Office Websites (Extended Search)

GTRI commended for work to secure radiological sources | National Nuclear GTRI commended for work to secure radiological sources | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > GTRI commended for work to secure radiological sources GTRI commended for work to secure radiological sources Posted By Office of Public Affairs Container NNSA's Global Threat Reduction Initiative (GTRI) was recently commended

478

ORISE: REAC/TS Radiological Incident Medical Consultation  

NLE Websites -- All DOE Office Websites (Extended Search)

Radiological Incident Medical Consultation Radiological Incident Medical Consultation Radiological Incident Medical Consultation The Oak Ridge Institute for Science and Education (ORISE) provides the U.S. Department of Energy (DOE) with a comprehensive capability to respond effectively to medical emergencies involving radiological or nuclear materials. Through the management of the Radiation Emergency Assistance Center/Training Site (REAC/TS), ORISE provides advice and consultation to emergency personnel responsible for the medical management of radiation accidents. REAC/TS strengthens hospital preparedness for radiation emergencies by preparing and educating first responders, medical personnel and occupational health professionals who will provide care to patients with a radiation injury or illness. REAC/TS staff provide medical advice,

479

DOE-HDBK-1122-99; Radiological Technician Training  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Radiological Incidents and Emergencies Radiological Incidents and Emergencies Study Guide 2.13-1 Course Title: Radiological Control Technician Module Title: Radiological Incidents and Emergencies Module Number: 2.13 Objectives: 2.13.01 Describe the general response and responsibilities of an RCT during any incident. i 2.13.02 Identify any emergency equipment and facilities that are available, including the location and contents of emergency equipment kits. i 2.13.03 Describe the RCT response to a Continuous Air Monitor (CAM) alarm. i 2.13.04 Describe the RCT response to a personnel contamination monitor alarm. i 2.13.05 Describe the RCT response to off scale or lost dosimetry. i 2.13.06 Describe the RCT response to rapidly increasing, unanticipated radiation levels or an area radiation monitor alarm. i 2.13.07

480

CRAD, Radiological Controls - Los Alamos National Laboratory Waste  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Radiological Controls - Los Alamos National Laboratory Waste Radiological Controls - Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility CRAD, Radiological Controls - Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for an assessment of the Radiation Protection Program portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Radiological Controls - Los Alamos National Laboratory Waste

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

A comparative study of quality control in diagnostic radiology  

Science Journals Connector (OSTI)

......effective National Regulatory Authority in Syria...radiological and Nuclear Regulatory Office, for his...2 Atomic Energy Regulatory Board. Atlas of Reference Plans for Medical Diagnostic...Burkhart R. L. A review of the experience......

M. H. Kharita; M. S. Khedr; K. M. Wannus

2008-07-01T23:59:59.000Z

482

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

483

An external dose reconstruction involving a radiological dispersal device  

E-Print Network (OSTI)

emergency situation. In response, the Department of Homeland Security has published Protective Action Guides (DHS 2006) to help minimize these exposures and associated risks. This research attempts to provide some additional radiological exposure knowledge...

Hearnsberger, David Wayne

2007-04-25T23:59:59.000Z

484

Radiological Worker Training Power Point Slides for App. A  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

30-2008 30-2008 DOE HANDBOOK Radiological Worker Training DOE-HDBK-1130-2008 Overheads December 2008 Reaffirmed 2013 OT 1.1 DOE-HDBK-1130-2008 Overhead 1.1 Regulatory Documents Objectives: * Identify the hierarchy of regulatory documents. * Define the purposes of 10 CFR Parts 820, 830 and 835. * Define the purpose of the DOE Radiological Control Standard. OT 1.2 DOE-HDBK-1130-2008 Overhead 1.2 Regulatory Documents (cont.) Objectives: * Define the terms "shall" and "should" as used in the above documents. * Describe the role of the Defense Nuclear Facilities Safety Board (DNFSB) at DOE sites and facilities. OT 1.3 DOE-HDBK-1130-2008 Overhead 1.3 DOE Radiological Health and Safety Policy * Conduct oversight to ensure compliance and that appropriate radiological work

485

Insider Threat to Nuclear and Radiological Materials: Fact Sheet | National  

National Nuclear Security Administration (NNSA)

Insider Threat to Nuclear and Radiological Materials: Fact Sheet | National Insider Threat to Nuclear and Radiological Materials: Fact Sheet | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > Insider Threat to Nuclear and Radiological Materials: ... Fact Sheet Insider Threat to Nuclear and Radiological Materials: Fact Sheet

486

V-073: IBM Tivoli Federated Identity Manager Signature Verification Flaw  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3: IBM Tivoli Federated Identity Manager Signature Verification 3: IBM Tivoli Federated Identity Manager Signature Verification Flaw Lets Remote Users Modify Attributes V-073: IBM Tivoli Federated Identity Manager Signature Verification Flaw Lets Remote Users Modify Attributes January 21, 2013 - 12:15am Addthis PROBLEM: IBM Tivoli Federated Identity Manager Signature Verification Flaw Lets Remote Users Modify Attributes PLATFORM: Tivoli Federated Identity Manager versions 6.2.0, 6.2.1, 6.2.2 ABSTRACT: A vulnerability was reported in IBM Tivoli Federated Identity Manager. REFERENCE LINKS: IBM Security Bulletin: 1615744 SecurityTracker Alert ID: 1028011 CVE-2012-6359 IMPACT ASSESSMENT: Medium DISCUSSION: The system does not check that all attributes have been signed. A remote user with the ability to conduct a man-in-the-middle attack can modify

487

Measurement & Verification with Green Button Data | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Measurement & Verification with Green Button Data Measurement & Verification with Green Button Data Measurement & Verification with Green Button Data April 13, 2012 - 4:15pm Addthis Shankar Earni Program Manager at Lawrence Berkeley National Laboratory Measurement and verification (M&V) focuses on ensuring that the savings from energy efficiency projects are being realized with a certain degree of confidence. M&V involves understanding how energy savings arebeing realized from a project; designing a cost-effective assessment strategy that addresses how to ensure the savings can be measured; and implementing the designed strategy by gathering the key data followed by analysis and reporting of the actual savings. In some cases, data from the Green Button program can be used to assess the energy savings from new efficiency

488

Verification of Quantitative Precipitation Reforecasts over the Southeastern United States  

Science Journals Connector (OSTI)

NOAA’s second-generation reforecasts are approximately consistent with the operational version of the 2012 NOAA Global Ensemble Forecast System (GEFS). The reforecasts allow verification to be performed across a multidecadal time period using a ...

Martin A. Baxter; Gary M. Lackmann; Kelly M. Mahoney; Thomas E. Workoff; Thomas M. Hamill

2014-10-01T23:59:59.000Z

489

Similarity Measurement for Off-Line Signature Verification  

Science Journals Connector (OSTI)

Existing methods to deal with off-line signature verification usually adopt the feature representation based approaches ... . Experimental results showed that the computed similarity measurement was able to provi...

Xinge You; Bin Fang; Zhenyu He; Yuanyan Tang

2005-01-01T23:59:59.000Z

490

Verification of three-dimensional laser Doppler velocimeter measurements  

Science Journals Connector (OSTI)

An experimental comparison method is proposed for the verification of mean flow and turbulence measurements obtained with a three-dimensional laser Doppler velocimeter system. Such measurements can include large ...

R. D. Mehta

1990-03-01T23:59:59.000Z

491

Introduction to Measurement and Verification for DOE Super ESPC Projects  

Energy.gov (U.S. Department of Energy (DOE))

Document offers an overview of why and how measurement and verification is conducted in super energy savings performance contracts (ESPC) projects. Topics include allocating project risk, steps to verify savings, and M&V plans and reports.

492

Summary Verification Measures and Their Interpretation for Ensemble Forecasts  

Science Journals Connector (OSTI)

Ensemble prediction systems produce forecasts that represent the probability distribution of a continuous forecast variable. Most often, the verification problem is simplified by transforming the ensemble forecast into probability forecasts for ...

A. Allen Bradley; Stuart S. Schwartz

2011-09-01T23:59:59.000Z

493

Multi Modal Verification for Teleservices and Security Applications (MZVTS)  

Science Journals Connector (OSTI)

This paper presents the European ACTS project ( MZVTS ), which stands for Multi Modal Verification for Teleservices and Security Applications. The primar) goal of this project is to address the issue of secured access to local and centralised services ...

G. Richard; Y. Menguy; 1. Guis; N. Suaudeau; J. Boudy; P. Lockwood; C. Fernandez; F. Fernández; C. Kotropoulos; A. Tefas; Pitas; R. Heimgartner; P. Ryser; C. Beumier; P. Verlinde; S. Pigeon; G. Matas; J. Kittler; J. Bigün; Y. Abdeljaoued; E. Meurville; L. Besacier; M. Ansorge; G. Maitre; J. Luettin; S. Ben-Yacoub; B. Ruiz; K. Aldama; J. Cortes

1999-06-01T23:59:59.000Z

494

Hanford Site Assessment & Characterization/Verification of Buildings...  

NLE Websites -- All DOE Office Websites (Extended Search)

Assessment & CharacterizationVerification of Buildings Procedure Published Date: 09-19-2013 Effective Date: 05-14-2014 Change Summary Page 1 of 1 Change Summary Revision Date...

495

Hanford Site Assessment & Characterization/Verification of Structures...  

NLE Websites -- All DOE Office Websites (Extended Search)

Verification of Structures and Conex Boxes Procedure Published Date: 09-19-2013 Effective Date: 05-14-2014 Signature Page 1 of 1 DOE-0342-004, Rev. 0 Hanford Site...

496

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

497

Low-Level Code Verification Based on CSP Models  

Science Journals Connector (OSTI)

This paper contributes to the broad field of software verification by proposing a methodology that uses CSP to verify implementations of real-life multithreaded applications. We therefore use CSP to formalize the...

Moritz Kleine; Steffen Helke

2009-01-01T23:59:59.000Z

498

DRAFT Measurement & Verification Guidelines Version 4.0  

Energy.gov (U.S. Department of Energy (DOE))

Document describes the Federal Energy Management Program's (FEMP) standard procedures and guidelines for measurement and verification (M&V) for federal energy managers, procurement officials, and energy service providers.

499

Verification of a technical system model with linear temporal logic  

Science Journals Connector (OSTI)

We consider the verification problem for an electromechanical device with a variable number of connectors and solve it with the modal logic LTL (Linear Temporal Logic). In the course of the analysis, we prove continuity and unambiguity theorems for the ...

A. N. Nepeivoda

2012-09-01T23:59:59.000Z

500

NICTA Advanced Course Advanced Topics in Software Verification  

E-Print Network (OSTI)

.g. c) § Have syntax 'a :: c for: type 'a supports the operations of c § Can write abstract polymorphicCOMP 4161 NICTA Advanced Course Advanced Topics in Software Verification Gerwin Klein, June

Klein, Gerwin