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1

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

2

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

3

AERIAL RADIOLOGICAL SURVEYS  

SciTech Connect

Measuring terrestrial gamma radiation from airborne platforms has proved to be a useful method for characterizing radiation levels over large areas. Over 300 aerial radiological surveys have been carried out over the past 25 years including U.S. Department of Energy (DOE) sites, commercial nuclear power plants, Formerly Utilized Sites Remedial Action Program/Uranium Mine Tailing Remedial Action Program (FUSRAP/UMTRAP) sites, nuclear weapons test sites, contaminated industrial areas, and nuclear accident sites. This paper describes the aerial measurement technology currently in use by the Remote Sensing Laboratory (RSL) for routine environmental surveys and emergency response activities. Equipment, data-collection and -analysis methods, and examples of survey results are described.

Proctor, A.E.

1997-06-09T23:59:59.000Z

4

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

5

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

6

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

7

Radiological Habits Survey: Bradwell, 2007  

E-Print Network (OSTI)

.2 Comparisons with previous surveys 55 Table A Comparison between 1999 and 2007 aquatic internal exposure 56 3. METHODS FOR DATA ANALYSIS 19 3.1 Data recording 19 3.2 Data analysis 21 4. AQUATIC RADIATION RADIATION PATHWAYS 41 5.1 Terrestrial survey area 41 5.2 Unusual pathways 42 5.3 Retailers 43 5.4 Food

8

Radiological Habits Survey: Wylfa, 2004  

E-Print Network (OSTI)

.7 Internal exposure 28 4.8 External exposure 31 4.9 Water based activities 33 5. TERRESTRIAL RADIATION PATHWAYS 34 5.1 Terrestrial survey area 34 5.2 Wholesalers and retailers 36 5.3 Internal exposure 36 6 analysis 21 4. AQUATIC RADIATION PATHWAYS 23 4.1 Aquatic survey area 23 4.2 Commercial fisheries 25 4

9

Radiological Habits Survey: Winfrith, 2003  

E-Print Network (OSTI)

.7 Internal exposure 26 4.8 External exposure 30 4.9 Water based activities 31 5 TERRESTRIAL RADIATION exposure 37 6 DIRECT RADIATION PATHWAYS 40 6.1 Direct radiation survey area 40 6.2 Residential activities analysis 19 4 AQUATIC RADIATION PATHWAYS 21 4.1 Aquatic survey area 21 4.2 Commercial fisheries 23 4

10

Radiological Habits Survey: Amersham, 2004  

E-Print Network (OSTI)

.4 Wholesalers and retailers 29 4.5 Internal exposure 29 4.6 External exposure 30 4.7 Water based activities 32 5. TERRESTRIAL RADIATION PATHWAYS 35 5.1 Terrestrial survey area 35 5.2 Wholesalers and retailers 39 5.3 Internal exposure 39 6. DIRECT RADIATION PATHWAYS 43 6.1 Direct radiation survey area 43 6.2 Residential activities

11

Radiological Habits Survey, Dounreay, 2003  

E-Print Network (OSTI)

.5 Internal exposure 25 4.6 External exposure 28 5. TERRESTRIAL RADIATION PATHWAYS 32 5.1 Terrestrial survey area and local produce 32 5.2 Novel radiation pathways 33 5.3 Land cover 33 5.4 Internal exposure 34 5 conversion 14 3.2 Determination of critical groups 14 4. AQUATIC RADIATION PATHWAYS 18 4.1 Aquatic survey

12

Radiological Habits Survey: Hartlepool, 2002  

E-Print Network (OSTI)

.4 Seafood wholesalers and retailers 27 4.5 Wildfowl 28 4.6 Other food pathways 28 4.7 Internal exposure 29 4.8 External exposure 32 4.9 Water based activities 35 5. TERRESTRIAL RADIATION PATHWAYS 36 5.1 Terrestrial survey area 36 5.2 Terrestrial food wholesalers and retailers 38 5.3 Internal exposure 38 6. DIRECT

13

Radiological Habits Survey: Cardiff, 2003  

E-Print Network (OSTI)

.4 Seafood wholesalers and retailers 26 4.5 Wildfowl 26 4.6 Internal exposure 27 4.7 External exposure 29 4.2 Terrestrial food wholesalers and retailers 37 5.3 Internal exposure 37 6. COMBINED PATHWAYS 41 7. CONCLUSIONS of the survey 15 3. METHODS FOR DATA ANALYSIS 18 3.1 Data recording 18 3.2 Data analysis 20 4. AQUATIC RADIATION

14

Radiological Habits Survey, Faslane, 2006  

E-Print Network (OSTI)

.3 Land cover 24 5.4 Internal exposure 25 6. DIRECT RADIATION 26 7. COMBINED PATHWAYS 28 8. CONCLUSIONS.5 Wildfowling 18 4.6 Internal exposure 19 4.7 External exposure 21 4.8 Water based activities 22 5. TERRESTRIAL.2 Determination of critical groups 11 3.3 Data analysis 11 4. AQUATIC RADIATION PATHWAYS 15 4.1 Aquatic survey

15

Radiological Habits Survey: Devonport, 2004  

E-Print Network (OSTI)

36 5.2 Wholesalers and retailers 38 5.3 Internal exposure 38 6. DIRECT RADIATION PATHWAYS 42 6.4 Wholesalers and retailers 28 4.5 Wildfowl 28 4.6 Other pathways 28 4.7 Internal exposure 29 4.8 External exposure 31 4.9 Water based activities 34 5. TERRESTRIAL RADIATION PATHWAYS 36 5.1 Terrestrial survey area

16

Radiological Habits Survey: Dungeness, 2005  

E-Print Network (OSTI)

44 5.2 Wholesalers and retailers 47 5.3 Internal exposure 47 6. DIRECT RADIATION PATHWAYS 50 6.4 Wholesalers and retailers 34 4.5 Wildfowl 35 4.6 Other pathways 35 4.7 Internal exposure 36 4.8 External exposure 39 4.9 Water based activities 42 5. TERRESTRIAL RADIATION PATHWAYS 44 5.1 Terrestrial survey area

17

Radiological Habits Survey: Trawsfynydd, 2005  

E-Print Network (OSTI)

5.2 Wholesalers and retailers 36 5.3 Internal exposure 36 6. DIRECT RADIATION PATHWAYS 40 6.1 Direct.3 Angling 28 4.4 Wholesalers and retailers 28 4.5 Wildfowl 28 4.6 Internal exposure 29 4.7 External exposure analysis 22 4. AQUATIC RADIATION PATHWAYS 25 4.1 Aquatic survey area 25 4.2 Commercial fisheries 27 4

18

Radiological Habits Survey, Chapelcross, 2005  

E-Print Network (OSTI)

and local produce 25 5.2 Novel radiation pathways 26 5.3 Land cover 26 5.4 Internal exposure 27 6. DIRECT fisheries 18 4.3 Angling 19 4.4 Seafood wholesalers and retailers 19 4.5 Internal exposure 20 4.6 External exposure 22 4.7 Water based activities 23 5. TERRESTRIAL RADIATION PATHWAYS 25 5.1 Terrestrial survey area

19

Radiological Habits Survey, Hunterston 2001  

E-Print Network (OSTI)

and local produce 25 5.2 Novel radiation pathways 26 5.3 Land cover 26 5.4 Internal exposure 27 5.5 External fisheries 18 4.3 Angling and hobby fishing 19 4.4 Seafood wholesalers and retailers 19 4.5 Internal exposure 19 4.6 External exposure 23 5. TERRESTRIAL RADIATION PATHWAYS 25 5.1 Terrestrial survey area

20

Radiological Habits Survey: Sizewell, 2005  

E-Print Network (OSTI)

.1 Terrestrial survey area 38 5.2 Wholesalers and retailers 40 5.3 Internal exposure 40 6. DIRECT RADIATION fishing 29 4.4 Wholesalers and retailers 30 4.5 Wildfowl 30 4.6 Other pathways 30 4.7 Internal exposure 31 4.8 External exposure 34 4.9 Water based activities 36 5. TERRESTRIAL RADIATION PATHWAYS 38 5

Note: This page contains sample records for the topic "handled radiological surveys" 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

Radiological Habits Survey: Sellafield, 2003  

E-Print Network (OSTI)

.4 Seafood wholesalers and retailers 28 4.5 Wildfowl 28 4.6 Other pathways 29 4.7 Internal exposure 29 4.8 External exposure 33 4.9 Water based activities 36 5. TERRESTRIAL RADIATION PATHWAYS 38 5.1 Terrestrial survey area 38 5.2 Terrestrial food wholesalers and retailers 41 5.3 Internal exposure 41 6. DIRECT

22

Autonomous mobile robot for radiologic surveys  

DOE Patents (OSTI)

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

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

1994-06-28T23:59:59.000Z

23

Autonomous mobile robot for radiologic surveys  

DOE Patents (OSTI)

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

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

1994-01-01T23:59:59.000Z

24

Anticipated Radiological Dose to Worker for Plutonium Stabilization and Handling at PFP - Project W-460  

E-Print Network (OSTI)

This report provides estimates of the expected whole body and extremity radiological dose, expressed as dose equivalent (DE), to workers conducting planned plutonium (Pu) stabilization processes at the Hanford Site Plutonium Finishing Plant (PFP). The report is based on a time and motion dose study commissioned for Project W-460, Plutonium Stabilization and Handling, to provide personnel exposure estimates for construction work in the PFP storage vault area plus operation of stabilization and packaging equipment at PFP.

Weiss, E V

2000-01-01T23:59:59.000Z

25

Radiological Habits Survey: Berkeley and Oldbury, 2007  

E-Print Network (OSTI)

aquatic internal exposure 63 pathways at Berkeley and Oldbury Table B Comparison between 2001 and 2007 of the survey 18 3. METHODS FOR DATA ANALYSIS 22 3.1 Data recording 22 3.2 Data analysis 24 4. AQUATIC RADIATION. TERRESTRIAL RADIATION PATHWAYS 45 5.1 Terrestrial survey area 45 5.2 Unusual pathways 48 5.3 Wholesalers

26

Radiological Habits Survey: Sellafield Review, 2005  

E-Print Network (OSTI)

2. Survey area 3 3. Conduct of survey 3 4. Data analysis 4 4.1 Internal exposure 4 Figure 2 Critical;3 1. Introduction This report describes a review of public radiation exposure pathways due to liquid 1996-2005 5 4.2 External exposure 6 5. Conclusions 7 6. Recommendations 7 7. References 7 Figure 1

27

Radiological Habits Survey: Aldermaston/Burghfield, 2002  

E-Print Network (OSTI)

.3 Internal exposure 30 6 ALDERMASTON DIRECT RADIATION 33 6.1 Direct radiation survey area 33 6.2 Residential pathways 22 4.5 Internal exposure 23 4.6 External exposure 25 4.7 Water based activities 26 5 TERRESTRIAL 3 METHODS FOR DATA ANALYSIS 16 3.1 Data recording 16 3.2 Data analysis 18 4 AQUATIC RADIATION

28

Radiological Habits Survey, Rosyth Business Park, 2005  

E-Print Network (OSTI)

.3 Land cover 17 5.4 Internal exposure 17 6. DIRECT RADIATION 18 7. COMBINED PATHWAYS 19 8. CONCLUSIONS.5 Wildfowling 14 4.6 Internal exposure 14 4.7 External exposure 15 4.8 Water based activities 16 5. TERRESTRIAL 3.2 Determination of critical groups 8 4. AQUATIC RADIATION PATHWAYS 9 4.1 Aquatic survey area 9 4

29

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

30

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 ,.--(_ ~_ -_- --- -_ _.. ;

31

An aerial radiological survey of Naturita, Colorado and surrounding area  

SciTech Connect

An aerial radiological survey of four areas in the vicinity of the inactive uranium mill tailings site at Naturita, Colorado was conducted in September 1981. The average background radiation exposure rate (normalized to 3 feet above the ground) was about 10 to 16 microroentgens per hour ({mu}R/h). Uranium ore or tailings were detected at Naturita, Nucla, East Vancorum, and the general region downriver and downwind from the former mill tailings site.

Jaffe, R.J.

1982-09-01T23:59:59.000Z

32

Radiological decontamination, survey, and statistical release method for vehicles  

SciTech Connect

Earth-moving vehicles (e.g., dump trucks, belly dumps) commonly haul radiologically contaminated materials from a site being remediated to a disposal site. Traditionally, each vehicle must be surveyed before being released. The logistical difficulties of implementing the traditional approach on a large scale demand that an alternative be devised. A statistical method for assessing product quality from a continuous process was adapted to the vehicle decontamination process. This method produced a sampling scheme that automatically compensates and accommodates fluctuating batch sizes and changing conditions without the need to modify or rectify the sampling scheme in the field. Vehicles are randomly selected (sampled) upon completion of the decontamination process to be surveyed for residual radioactive surface contamination. The frequency of sampling is based on the expected number of vehicles passing through the decontamination process in a given period and the confidence level desired. This process has been successfully used for 1 year at the former uranium millsite in Monticello, Utah (a cleanup site regulated under the Comprehensive Environmental Response, Compensation, and Liability Act). The method forces improvement in the quality of the decontamination process and results in a lower likelihood that vehicles exceeding the surface contamination standards are offered for survey. Implementation of this statistical sampling method on Monticello projects has resulted in more efficient processing of vehicles through decontamination and radiological release, saved hundreds of hours of processing time, provided a high level of confidence that release limits are met, and improved the radiological cleanliness of vehicles leaving the controlled site.

Goodwill, M.E.; Lively, J.W.; Morris, R.L.

1996-06-01T23:59:59.000Z

33

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

34

A Mobile High Resolution Gamma Ray Spectrometry System for Radiological Surveys  

Science Conference Proceedings (OSTI)

Surveying nuclear power plant sites for radioactive contamination is an expensive part of the overall decommissioning process. This report details a mobile radiological survey system designed to produce a rapid and cost effective radiological characterization of outdoor land areas. The system combines high resolution gamma ray spectrometry with modern automated surveying techniques to precisely locate areas of contamination.

1998-12-04T23:59:59.000Z

35

An aerial radiological survey of Naturita, Colorado and surrounding area. Date of survey: September 1981  

SciTech Connect

An aerial radiological survey of four areas in the vicinity of the inactive uranium mill tailings site at Naturita, Colorado was conducted in September 1981. The average background radiation exposure rate (normalized to 3 feet above the ground) was about 10 to 16 microroentgens per hour ({mu}R/h). Uranium ore or tailings were detected at Naturita, Nucla, East Vancorum, and the general region downriver and downwind from the former mill tailings site.

Jaffe, R.J.

1982-09-01T23:59:59.000Z

36

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

Science Conference Proceedings (OSTI)

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

37

Confirmatory radiological survey of portions of the former A. H. Robins Research Center, Richmond, Virginia  

SciTech Connect

The former A.H. Robins Research Center, in Richmond, VA, was devoted primarily to the research and development of pharmaceuticals. The use of radionuclides at the A.H. Robins Research Center was first begun in the early 1960s and the facility is now operating under Nuclear Regulatory Commission (NRC) License No. 45-09042-01. A. H. Robins' Drug Metabolism Department used radioactive material (H-3, C-14, Na-22, P-32, S-35, CI-36, Ca-45, Cr-51, Ni-63, Rb-86, I-125, I-129, I-131, and Cs-137) in laboratory tracer studies on animals, for calibration of instrumentation, and for research analyses. The radionuclides were used in various,rooms throughout the facility. Following its acquisition by American Home Products in 1990, radionuclide activities were discontinued at this facility. The process for the termination of the material license for A.H. Robins (AHR) was initiated by the Corporate Radiation Health Safety Officer of Wyeth-Ayerst Research (WAR), another wholly owned subsidiary of American Home Products (AHP). In June 1990, WAR developed and submitted a decommissioning plan to the NRC. A radiological survey of the areas in which radionuclides were known to have been handled was performed to determine the extent of the contamination. During the cleanup and survey of the facility, the licensee identified H-3 and C-14 as the major

Adams, W.C.

1992-05-01T23:59:59.000Z

38

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

SciTech Connect

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

W.C. Adams

2007-03-13T23:59:59.000Z

39

Nevada Test Site Area 25. Radiological survey and cleanup project, 1974-1983. Final report  

SciTech Connect

This report describes radiological survey, decontamination and decommissioning of the Nevada Test Site (NTS) Area 25 facilities and land areas incorporated in the Nuclear Rocket Development Station (NRDS). Buildings, facilities and support systems used after 1959 for nuclear reactor and engine testing were surveyed for the presence of radioactive contamination. The cleanup was part of the Surplus Facilities Management Program funded by the Department of Energy's Richland Operations Office. The radiological survey portion of the project encompassed portable instrument surveys and removable contamination surveys (swipe) for alpha and beta plus gamma radiation contamination of facilities, equipment and land areas. Soil sampling was also accomplished. The majority of Area 25 facilities and land areas have been returned to unrestricted use. Remaining radiologically contaminated areas are posted with warning signs and barricades. 12 figures.

McKnight, R.K.; Rosenberry, C.E.; Orcutt, J.A.

1984-01-01T23:59:59.000Z

40

An aerial radiological survey of the Central Savannah River Site, Aiken, South Carolina  

Science Conference Proceedings (OSTI)

An aerial radiological survey was conducted over a 194-square- kilometer (75-square-mile) area encompassing the central portion of the Savannah River Site (SRS). The survey was flown during February 10--27, 1987. These radiological measurements were used as baseline data for the central area and for determining the extent of man-made radionuclide distribution. Previous SRS surveys included small portions of the area; the 1987 survey was covered during the site- wide survey conducted in 1979. Man-made radionuclides (including cobalt-60, cesium-137, protactinium-234m, and elevated levels of uranium-238 progeny) that were detected during the survey were typical of those produced by the reactor operations and material processing activities being conducted in the area. The natural terrestrial radiation levels were consistent with those measured during prior surveys of other SRS areas. 1 refs., 4 figs.

Feimster, E.L.

1991-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "handled radiological surveys" 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

Results of the radiological survey at 136 West Central Avenue (MJ030), Maywood, New Jersey  

SciTech Connect

As a result of the Energy and Water Appropriations Act of Fiscal Year 1984, the property discussed in this report and properties in its vicinity contaminated with residues from the former Maywood Chemical Works (MCW) were included as a decontamination research and development project under the DOE Formerly Utilized Sites Remedial Action Program. As part of this project, DOE is conducting radiological surveys in the vicinity of the site to identify properties contaminated with residues derived from the MCW. The principal radionuclide of concern is thorium-232. The radiological survey discussed in this report is part of that effort and was conducted, at the request of DOE by members of the Measurement Applications and Development Group of Oak Ridge National Laboratory. A radiological survey of the private, residential property at 136 West Central Avenue, Maywood, New Jersey, was conducted during 1987. The survey and sampling of the ground surface and subsurface were carried out on April 29, 1987.

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

1989-02-01T23:59:59.000Z

42

Radiological Surveys Performed in Support of the Demolition and Bulk Disposal Decommissioning Method  

SciTech Connect

Connecticut Yankee Atomic Power Company is decommissioning the Haddam Neck Plant using the 'Demolition and Bulk Disposal' method, or commonly referred to as 'Rip and Ship'. In general, completing the project using this method entails the removal of all irradiated fuel and highly contaminated systems and components, and the subsequent demolition of the above ground portions of most site structures. Since most structures are removed from site, cost and time savings are realized by virtually eliminating the need for remediation. However, this method of decommissioning creates more waste, both radiological and non-radiological, which must be segregated, packaged and disposed of properly. Prior to demolition, various types of radiological surveys must be performed and work controls put into place to minimize the spread of contamination to other areas of the site, and to prevent the inadvertent release of radioactive materials from the site. This paper will discuss the various types of radiological surveys performed, and controls implemented, in support of the demolition and bulk material disposal decommissioning method, with the emphasis on pre-demolition surveys. Details will be provided on the release criteria, survey design, survey implementation and data analysis on each of the various surveys, as well as a discussion on the controls implemented to prevent the various wastes from inadvertently being shipped to an inappropriate disposal facility. This paper will also strive to provide lessons learned for future projects that utilize the demolition and bulk disposal decommissioning method. (authors)

Yetter, R.F. [Babcock Services, Inc., 1840 Terminal Drive, Richland, WA 99352 (United States); Newson, C.T. [Connecticut Yankee Atomic Power Company, 362 Injun Hollow Road, East Hampton, CT 06424 (United States)

2006-07-01T23:59:59.000Z

43

An aerial radiological survey of the southwest drainage basin area of the Savannah River Site  

SciTech Connect

An aerial radiological survey was conducted over a 106-square-mile area of the Savannah River Site (SRS), formerly the Savannah River Plant. The survey was conducted from August 24 through September 8, 1988, to collect baseline radiological data over the area. Both natural and man-made gamma emitting radionuclides were detected in the area. The detected man-made sources were confined to creeks, branches, and SRS facilities in the surveyed area and were a result of SRS operations. Naturally-occurring radiation levels were consistent with those levels detected in adjacent areas during previous surveys. The annual dose levels were within the range of levels found throughout the United States.

Feimster, E.L.

1994-04-01T23:59:59.000Z

44

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

Science Conference Proceedings (OSTI)

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

T.J. Vitkus

2008-04-07T23:59:59.000Z

45

Quarterly environmental radiological survey summary second quarter 1996 100, 200, 300 and 600 areas  

Science Conference Proceedings (OSTI)

This report provides a summary of the radiological surveys performed in support of the operational environmental monitoring program at the Hanford Site. The Second Quarter 1996 survey results and the status of actions required from current and past reports are summarized below: All the routine environmental radiological surveys scheduled during April, May, and June 1996 were completed. One Hundred twenty- five environmental radiological surveys were performed during the second quarter of 1996, twenty nine at the active waste sites and ninety six at the inactive waste sites. Contamination above background levels Wag found at three of the active waste sites and fifteen of the inactive waste sites. Contamination levels as high as 65,000 disintegrations per minute (dpm) were reported. Of these contaminated surveys seven were in Underground Radioactive Material (URM) areas and one was in an unposted area. The contamination found within three of the URM areas was immediately cleaned up and no further action was required. In the remaining four sites the areas were posted and will require decontamination. At the site where there was no posting, the contamination was below action levels, however, Site Support Services was notified. Radiological Problem Reports (RPR`s) were issued and the sites were turned over to the landlord for further action if required. During the second quarter 1996, 0. 7 hectares (1.7 acres) were stabilized and radiologically down posted from Surface Contamination (SC) to URM. No Compliance Assessment Reports (CARS) were issued for sites found out of compliance with standards identified in WHC-CM-7-5, Environmental Compliance. No Surveillance Compliance/Inspection Reports (SCIR) were closed during the Second Quarter of 1996. Five open SCIRB had not been resolved.

Dorian, J.J., Westinghouse Hanford

1996-07-26T23:59:59.000Z

46

Radiological Habits Survey, Dumfries and Galloway Coast, 2002  

E-Print Network (OSTI)

-washed pasture 19 4.6 Internal exposure 19 4.7 External exposure 24 5. COMBINED PATHWAYS 26 6. MATERIALS.2 Determination of critical groups 10 4. AQUATIC RADIATION PATHWAYS 13 4.1 Aquatic survey area 13 4.2 Commercial of radioactivity in the Irish Sea. Potential exposure pathways include con

47

Radiological Habits Survey, HM Naval Base Clyde, Faslane 2000  

E-Print Network (OSTI)

wholesalers and retailers 17 4.5 Internal exposure 17 4.6 External exposure 19 5. TERRESTRIAL RADIATION pathways 22 5.3 Land cover 22 5.4 Internal exposure 23 5.5 External radiation 25 6. COMBINED PATHWAYS 26 7 conversion 10 3.2 Determination of critical groups 11 4. AQUATIC RADIATION PATHWAYS 14 4.1 Aquatic survey

48

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

49

An aerial radiological survey of the Ames Laboratory and surrounding area, Ames, Iowa. Date of survey: July 1991  

Science Conference Proceedings (OSTI)

An aerial radiological survey of the Ames Laboratory and surrounding area in Ames, Iowa, was conducted during the period July 15--25, 1991. The purpose of the survey was to measure and document the terrestrial radiological environment at the Ames Laboratory and the surrounding area for use in effective environmental management and emergency response planning. The aerial survey was flown at an altitude of 200 feet (61 meters) along a series of parallel lines 350 feet (107 meters) apart. The survey encompassed an area of 36 square miles (93 square kilometers) and included the city of Ames, Iowa, and the Iowa State University. The results are reported as exposure rates at 1 meter above ground level (inferred from the aerial data) in the form of a gamma radiation contour map. Typical background exposure rates were found to vary from 7 to 9 microroentgens per hour ({mu}R/h). No anomalous radiation levels were detected at the Ames Laboratory. However, one anomalous radiation source was detected at an industrial storage yard in the city of Ames. In support of the aerial survey, ground-based exposure rate and soil sample measurements were obtained at several sites within the survey perimeter. The results of the aerial and ground-based measurements were found to agree within the expected uncertainty of {+-}15%.

Maurer, R.J.

1993-04-01T23:59:59.000Z

50

Results of the radiological survey at Diebold Safe Company, 1550 Grand Boulevard, Hamilton, Ohio (HO001)  

SciTech Connect

At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducted investigative radiological surveys at Diebold Safe Company, 1550 Grand Boulevard, Hamilton, Ohio in 1988 and 1989. The purpose of the surveys was to determine whether the property was contaminated with radioactive residues, principally {sup 238}U. The surveys included gamma scans; direct and transferable measurements of alpha, beta, and gamma radiation levels; and dust, debris, air, and soil sampling for radionuclide analyses. 6 refs., 6 figs., 5 tabs.

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

1990-02-01T23:59:59.000Z

51

Results of the radiological survey at 266 East Spring Valley Avenue (MJ024), Hackensack, New Jersey  

SciTech Connect

As a result of the Energy and Water Appropriations Act of Fiscal Year 1984, the property discussed in this report and properties in its vicinity contaminated with residues from the former Maywood Chemical Works (MCW) were included as a decontamination research and development project under the DOE Formerly Utilized Sites Remedial Action Program. As part of this project, DOE is conducting radiological surveys in the vicinity of the site to identify properties contaminated with residues derived from the MCW. The principal radionuclide of concern is thorium-232. The radiological survey discussed in this report is part of that effort and was conducted, at the request of DOE, by members of the Measurement Applications and Development Group of Oak Ridge National Laboratory. A radiological survey of the private, residential property at 266 East Spring Valley Avenue, Hackensack, New Jersey, was conducted during 1987. The survey and sampling of the ground surface and subsurface were carried out on April 23, 1987. 4 refs., 2 figs., 3 tabs.

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

1989-02-01T23:59:59.000Z

52

An Aerial Radiological Survey of the Yucca Mountain Project Proposed Land Withdrawal and Adjacent Areas  

SciTech Connect

An aerial radiological survey of the Yucca Mountain Project (YMP) proposed land withdrawal was conducted from January to April 2006, and encompassed a total area of approximately 284 square miles (73,556 hectares). The aerial radiological survey was conducted to provide a sound technical basis and rigorous statistical approach for determining the potential presence of radiological contaminants in the Yucca Mountain proposed Land withdrawal area. The survey site included land areas currently managed by the Bureau of Land Management, the U.S. Air Force as part of the Nevada Test and Training Range or the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) as part of the Nevada Test Site (NTS). The survey was flown at an approximate ground speed of 70 knots (36 meters per second), at a nominal altitude of 150 ft (46 m) above ground level, along a set of parallel flight lines spaced 250 ft (76 m) apart. The flight lines were oriented in a north-south trajectory. The survey was conducted by the DOE NNSA/NSO Remote Sensing Laboratory-Nellis, which is located in Las Vegas, Nevada. The aerial survey was conducted at the request of the DOE Office of Civilian Radioactive Waste Management. The primary contaminant of concern was identified by YMP personnel as cesium-137 ({sup 137}Cs). Due to the proposed land withdrawal area's proximity to the historical Nuclear Rocket Development Station (NRDS) facilities located on the NTS, the aerial survey system required sufficient sensitivity to discriminate between dispersed but elevated {sup 137}Cs levels from those normally encountered from worldwide fallout. As part of that process, the survey also measured and mapped the exposure-rate levels that currently existed within the survey area. The inferred aerial exposure rates of the natural terrestrial background radiation varied from less than 3 to 22 microroentgens per hour. This range of exposure rates was primarily due to the surface geological features within the survey area. The survey area has extensive areas of desert valleys, mountain ranges, extinct volcanic cones, and old lava flows. With the exception of five areas identified within the NRDS boundaries (discussed later in this report), there were no areas within the survey that exceeded aerial survey minimum detectable concentration levels of 0.4 through 0.7 picocuries per gram (pCi/g). The {sup 137}Cs levels do not exceed typical worldwide fallout levels for the continental United States.

Craig Lyons, Thane Hendricks

2006-07-01T23:59:59.000Z

53

Confirmatory radiological survey of portions of the former A. H. Robins Research Center, Richmond, Virginia. Final report  

SciTech Connect

The former A.H. Robins Research Center, in Richmond, VA, was devoted primarily to the research and development of pharmaceuticals. The use of radionuclides at the A.H. Robins Research Center was first begun in the early 1960s and the facility is now operating under Nuclear Regulatory Commission (NRC) License No. 45-09042-01. A. H. Robins` Drug Metabolism Department used radioactive material (H-3, C-14, Na-22, P-32, S-35, CI-36, Ca-45, Cr-51, Ni-63, Rb-86, I-125, I-129, I-131, and Cs-137) in laboratory tracer studies on animals, for calibration of instrumentation, and for research analyses. The radionuclides were used in various,rooms throughout the facility. Following its acquisition by American Home Products in 1990, radionuclide activities were discontinued at this facility. The process for the termination of the material license for A.H. Robins (AHR) was initiated by the Corporate Radiation Health Safety Officer of Wyeth-Ayerst Research (WAR), another wholly owned subsidiary of American Home Products (AHP). In June 1990, WAR developed and submitted a decommissioning plan to the NRC. A radiological survey of the areas in which radionuclides were known to have been handled was performed to determine the extent of the contamination. During the cleanup and survey of the facility, the licensee identified H-3 and C-14 as the major

Adams, W.C.

1992-05-01T23:59:59.000Z

54

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

SciTech Connect

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

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

1996-09-01T23:59:59.000Z

55

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

56

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

57

An aerial radiological survey of the Oak Ridge Reservation, Oak Ridge, Tennessee. Date of survey: April 1992  

Science Conference Proceedings (OSTI)

An aerial radiological survey of the Oak Ridge Reservation (ORR) and surrounding area in Oak Ridge, Tennessee, was conducted during the period March 30 to April 14,1992. The purpose of the survey was to measure and document the terrestrial radiological environment of the Oak Ridge Reservation for use in environmental management programs and emergency response planning. The aerial survey was flown at an altitude of 150 feet (46 meters) along a series of parallel lines 250 feet (76 meters) apart and included X-10 (Oak Ridge National Laboratory), K-25 (former Gaseous Diffusion Plant), Y-12 (Weapons Production Plant), the Freels Bend Area and Oak Ridge Institute for Science and Education, the East Fork Poplar Creek (100-year floodplain extending from K-25 to Y-12), Elza Gate (former uranium ore storage site located in the city of Oak Ridge), Parcel A, the Clinch River (river banks extending from Melton Hill Dam to the city of Kingston), and the CSX Railroad Tracks (extending from Y-12 to the city of Oak Ridge). The survey encompassed approximately 55 square miles (1 41 square kilometers) of the Oak Ridge Reservation and surrounding area.

Maurer, R.J.

1993-04-01T23:59:59.000Z

58

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

SciTech Connect

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

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

1996-09-01T23:59:59.000Z

59

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

SciTech Connect

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

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

1996-09-01T23:59:59.000Z

60

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 . . . . . . . . .

Note: This page contains sample records for the topic "handled radiological surveys" from the National Library of EnergyBeta (NLEBeta).
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61

Radiological verification survey results at the Pompton Plains Railroad Spur, Pequannock, New Jersey (PJ008V)  

SciTech Connect

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

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

1995-05-01T23:59:59.000Z

62

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

SciTech Connect

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

Namdoo Moon

2007-12-01T23:59:59.000Z

63

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

64

An aerial radiological survey of the Durango, Colorado uranium mill tailings site and surrounding area. Date of survey: August 1980  

Science Conference Proceedings (OSTI)

An aerial radiological survey of Durango, Colorado, including the inactive uranium mill tailings piles located southwest of the town, was conducted during August 25--29, 1980, for the Department of Energy`s Environmental and Safety Engineering Division. Areas of radiation exposure rates higher than the local background, which was about 15 microrentgens per hour ({mu}R/h), were observed directly over and to the south of the mill tailings piles, over a cemetery, and at two spots near the fairgrounds. The rapidly changing radiation exposure rates at the boundaries of the piles preclude accurate extrapolation of aerial radiological data to ground level exposure rates in their immediate vicinity. Estimated radiation exposure rates close to the piles, however, approached 30 times background, or about 450 {mu}R/h. Radiation exposure rates in a long area extending south from the tailings piles were about 25 {mu}R/h.

Hilton, L.K.

1981-06-01T23:59:59.000Z

65

Medical Examiner/Coroner on the Handling of a Body/Human Remains that are Potentially Radiologically Contaminated  

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

The purpose of this Model Procedure is to identify precautions and provide guidance to Medical Examiners/Coroners on the handling of a body or human remains that are potentially contaminated with...

66

Workshop on Radiological Surveys in Support of the Edgemont Clean-up Action Program  

Science Conference Proceedings (OSTI)

The Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, has given Pacific Northwest Laboratory (PNL) the responsibility for the development of procedures for the identification of offsite structures and properties in the vicinity of Edgemont, South Dakota, that require remedial action because of elevated radiation levels caused by residual radioactivity as defined in the Uranium Mill Tailings Radiation Control Act of 1978. In order to acquaint interested investigators with the procedures PNL has developed and the measurements that have been performed at Edgemont using these procedures, and also to obtain suggestions for the improvement of these procedures, PNL organized a "Workshop on Radiological Surveys in Support of the Edgemont Clean-up Action Program" on behalf of the Nuclear Regulatory Commission. This workshop was held in Denver on January 21 and 22, 1981. On the first day of the workshop an in-depth discussion of the procedures employed in the entire radiological survey program at Edgemont was held. It included a description of the equipment, techniques and procedures employed in radon daughter measurements within structures, indoor and outdoor gamma radiation surveys, and 226Ra measurements in surface and sub-surface soil samples. On the second day, the results of the measurements that have been conducted at Edgemont were presented. During the afternoon an open discussion of the radiological survey procedures used at Edgemont was held for the purpose of obtaining suggestions for the possible improvement of these procedures. Many useful suggestions were made and a few modifications in the survey procedures at Edgemont have been made in response to these suggestions.

Perkins, R. W.; Young, J. A.; Jackson, P. O.; Thomas, V. W.; Schwendiman, L. C.

1981-10-01T23:59:59.000Z

67

An Aerial Radiological Survey of Selected Areas of Area 18 - Nevada Test Site  

Science Conference Proceedings (OSTI)

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 Area 18 of the Nevada Test Site (NTS) for the purpose of mapping man-made radiation deposited as a result of the Johnnie Boy and Little Feller I tests. The survey area centered over the Johnnie Boy ground zero but also included the ground zero and deposition area of the Little Feller I test, approximately 7,000 feet (2133 meters) southeast of the Johnnie Boy site. The survey was conducted in one flight. The completed survey covered a total of 4.0 square miles. The flight lines (with the turns) over the surveyed areas are presented in Figure 1. One 2.5-hour-long flight was performed at an altitude of 100 ft above ground level (AGL) with 200 foot flight-line spacing. A test-line flight was conducted near the Desert Rock Airstrip to ensure quality control of the data. The test line is not shown in Figure 1. However, Figure 1 does include the flight lines for a ''perimeter'' flight. The path traced by the helicopter flying over distinct roads within the survey area can be used to overlay the survey data on a base map or image. The flight survey lines were flown in an east-west orientation perpendicular to the deposition patterns for both sites. This technique provides better spatial resolution when contouring 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 every second over the course of the survey and were geo-referenced using a differential Global Positioning System. 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 identify specific radioactive isotopes. Based on the results of the RSL NTS 1994 surveys, this area was chosen for a resurvey to improve the spatial resolution of the reported depositions for the Johnnie Boy and Little Feller I events. In addition, the survey was expected to confirm the absence of detectable concentrations of Americium-241 (Am-241) at the Johnnie Boy site and attempt to confirm the presence of Uranium-235 (U-235).

Craig Lyons

2009-07-31T23:59:59.000Z

68

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

Science Conference Proceedings (OSTI)

Results of a radiological survey of the inactive uranium-mill site a Naturita, Colorado, conducted in May 1976, are presented. The spread of tailings was detected in the area surrounding the site by means of direct above ground gamma measurements and analysis of surface and subsurface soil samples. Radiochemical analyses of water samples in the vicinity of the tailings pile indicate local surface water contamination immediately downstream from the pile, although the /sup 226/Ra concentration in the water at that point as well below the concentration guide for drinking water. The calculated subsoil distribution of /sup 226/Ra in onsite holes is presented graphically. The tailings at this site were removed and reprocessed at another location. This operation was completed and reclamation of the site was conducted in 1978. Consequently the information in this report documents radiological conditions that no longer exist.

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

1980-03-01T23:59:59.000Z

69

An aerial radiological survey of the Durango, Colorado uranium mill tailings site and surrounding area  

SciTech Connect

An aerial radiological survey of Durango, Colorado, including the inactive uranium mill tailings piles located southwest of the town, was conducted during August 25--29, 1980, for the Department of Energy's Environmental and Safety Engineering Division. Areas of radiation exposure rates higher than the local background, which was about 15 microrentgens per hour ({mu}R/h), were observed directly over and to the south of the mill tailings piles, over a cemetery, and at two spots near the fairgrounds. The rapidly changing radiation exposure rates at the boundaries of the piles preclude accurate extrapolation of aerial radiological data to ground level exposure rates in their immediate vicinity. Estimated radiation exposure rates close to the piles, however, approached 30 times background, or about 450 {mu}R/h. Radiation exposure rates in a long area extending south from the tailings piles were about 25 {mu}R/h.

Hilton, L.K.

1981-06-01T23:59:59.000Z

70

Radiological survey support activities for the decommissioning of the Ames Laboratory Research Reactor Facility, Ames, Iowa  

SciTech Connect

At the request of the Engineering Support Division of the US Department of Energy-Chicago Operations Office and in accordance with the programmatic overview/certification responsibilities of the Department of Energy Environmental and Safety Engineering Division, the Argonne National Laboratory Radiological Survey Group conducted a series of radiological measurements and tests at the Ames Laboratory Research Reactor located in Ames, Iowa. These measurements and tests were conducted during 1980 and 1981 while the reactor building was being decontaminated and decommissioned for the purpose of returning the building to general use. The results of these evaluations are included in this report. Although the surface contamination within the reactor building could presumably be reduced to negligible levels, the potential for airborne contamination from tritiated water vapor remains. This vapor emmanates from contamination within the concrete of the building and should be monitored until such time as it is reduced to background levels. 2 references, 8 figures, 6 tables.

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

1984-09-01T23:59:59.000Z

71

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

72

Survey of the State-of-the-Art of Coal Handling During Freezing Weather  

Science Conference Proceedings (OSTI)

This report presents a state-of-the-art review of coal-handling procedures and programs used by electric utilities, coal mines, and coal transfer stations during periods of freezing weather. The use of freeze-conditioning agents to reduce coal-handling problems is discussed, as well as the relative efficacy of various nonchemical techniques. Guidelines for handling frozen coal that reflect typical problems and solutions are given.

1981-04-04T23:59:59.000Z

73

An Aerial Radiological Survey of the City of North Las Vegas (Downtown) and the Motor Speedway  

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 on December 11-12, 2007, with the purpose of mapping natural radiation background and locating any man-made radioactive sources. The survey covered 19.4 square miles (9.2 square miles over the downtown area of the City of North Las Vegas and 10.2 square miles over the Las Vegas Motor Speedway [LVMS]). The flight lines over the surveyed areas are presented in Figures 1 and 2. A total of four 2.5-hour-long flights were performed at an altitude of 150 ft above ground level (AGL) with 300 ft 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 sources. 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 City of North Las Vegas and LVMS security along with the gross counts-based exposure rate and man-made counts maps.

Piotr Wasiolek

2007-12-01T23:59:59.000Z

74

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

75

Radiological survey of the inactive uranium-mill tailings at Riverton, Wyoming  

SciTech Connect

Results of a radiological survey performed at the Riverton, Wyoming site in July 1976, are presented. The average external gamma exposure rate at 1 m over the tailings pile was 56 ..mu..R/hr. The corresponding rate for the former mill area was 97 ..mu..R/hr. Movement of tailings particles in a dry wash is evident; but it appears that, in general, the earth cover over the tailings pile has been effective in limiting both wind and water erosion of the tailings. The calculated concentration of /sup 226/Ra as a function of depth in 15 augered holes is presented graphically. A survey of the Teton Division Lumber Company property in Riverton showed a maximum external gamma exposure rate of 270 ..mu..R/hr.

Haywood, F.F.; Lorenzo, D.; Christian, D.J.; Chou, K.D.; Ellis, B.S.; Shinpaugh, W.H.

1980-03-01T23:59:59.000Z

76

A Survey of Interventional Radiology Awareness Among Final-Year Medical Students in a European Country  

Science Conference Proceedings (OSTI)

Interventional radiology (IR) is a rapidly expanding specialty that is facing the challenges of turf wars and personnel shortages. Appropriate exposure of medical students to this field can be vital to recruitment of potential future trainees or referring physicians. The aim of this study was to determine the knowledge and views of final-year medical students in a single EU country regarding various aspects of IR. An electronic survey was sent via e-mail to all final-year medical students in a European country. The students were given a month to respond to the questionnaire. A total of 234 students of 675 (34.5%) replied to the survey. Of the respondents, 35% had previously completed an attachment to the radiology department. The majority of students (63%) thought their knowledge in radiology in general was poor. The percentage of students who correctly identified procedures performed by interventional radiologists was 69% for Hickman line insertion, 79% for fibroid embolization, and 67.5% for lower limb angioplasty. Sixty percent, 30%, and 47% thought that interventional radiologists perform cardiac angioplasties, perform arterial bypasses, and create AV fistulas, respectively. Forty-nine percent felt that interventional radiologists are surgically trained. Eighty-three percent of students were first made aware of angioplasty by a cardiologist. Thirty-one percent thought that interventional radiologists do ward rounds, 24% thought that interventional radiologists have admitting rights, and 26% felt that interventional radiologists run an outpatient practice. A significant number of students (76%) thought that the job prospects in IR are good or excellent but only 40.5% were willing to consider a career in IR. In conclusion, this study indicates that IR remains a nascent but attractive specialty to the majority of medical students. Further development of the existing informal undergraduate curriculum to address shortcomings will ensure that IR continues to attract the brightest talents to the field.

Leong, Sum; Keeling, Aoife N.; Lee, Michael J., E-mail: mlee@rcsi.i [Beaumont Hospital, Department of Academic Radiology (Ireland)

2009-07-15T23:59:59.000Z

77

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

SciTech Connect

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

Colin Okada

2010-09-16T23:59:59.000Z

78

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

79

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

80

Results of the radiological survey at Essex Street and State Route 17 (MJ036), Maywood, New Jersey  

SciTech Connect

As a result of the Energy and Water Appropriations Act of Fiscal Year 1984, the property discussed in this report and properties in its vicinity contaminated with residues from the former Maywood Chemical Works (MCW) were included as a decontamination research and development project under the DOE Formerly Utilized Sites Remedial Action Program. As part of this project, DOE is conducting radiological surveys in the vicinity of the site to identify properties contaminated with residues derived from the MCW. The principal radionuclide of concern is thorium-232. The radiological survey discussed in this report is part of that effort and was conducted, at the request of DOE, by members of the Measurement Applications and Development Group of the Oak Ridge National Laboratory. A radiological survey of the commercial property at Essex Street and State Route 17, Maywood, New Jersey, was conducted during 1987. 4 refs., 2 figs., 3 tabs.

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

1989-02-01T23:59:59.000Z

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81

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

82

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

SciTech Connect

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

Phoenix, K.A.

1997-04-01T23:59:59.000Z

83

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

Science Conference Proceedings (OSTI)

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

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

1997-09-01T23:59:59.000Z

84

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

Science Conference Proceedings (OSTI)

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

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

1997-09-01T23:59:59.000Z

85

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

Science Conference Proceedings (OSTI)

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

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

1997-09-01T23:59:59.000Z

86

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

87

An aerial radiological survey of Project Rulison and surrounding area, Battlement Creek Valley, Colorado  

SciTech Connect

An aerial radiological survey was conducted over the Project Rulison site, 40 miles (64 kilometers) northeast of Grand Junction, Colorado, from July 6 through July 12, 1993. Parallel lines were flown at intervals of 250 feet (76 meters) over a 6.5-square-mile (17-square-kilometer) area at a 200-foot (61-meter) altitude surrounding Battlement Creek Valley. 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 3.5 to 12.5 {mu}R/h (excluding cosmic) at 1 meter above ground level. No anomalous or man-made isotopes were found.

NONE

1995-08-01T23:59:59.000Z

88

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

Science Conference Proceedings (OSTI)

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

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

1980-10-01T23:59:59.000Z

89

Radiological survey of the inactive uranium-mill tailings at the Spook site, Converse County, Wyoming  

SciTech Connect

Results of a radiological survey performed at the Spook site in Converse County, Wyoming, in June 1976, are presented. The mill at this site was located a short distance from the open-pit mine where the ore was obtained and where part of the tailings was dumped into the mine. Several piles of overburden or low-grade ore in the vicinity were included in the measurements of above-ground gamma exposure rate. The average exposure rate over these piles varied from 14 ..mu..R/hr, the average background exposure rate for the area, to 140 ..mu..R/hr. The average exposure rate for the tailings and former mill area was 220 ..mu..R/hr. Movement of tailings particles down dry washes was evident. The calculated concentration of /sup 226/Ra in ten holes as a function of depth is presented graphically.

Haywood, F.F.; Christian, D.J.; Chou, K.D.; Ellis, B.S.; Lorenzo, D.; Shinpaugh, W.H.

1980-05-01T23:59:59.000Z

90

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

Science Conference Proceedings (OSTI)

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

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

1980-06-01T23:59:59.000Z

91

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

Science Conference Proceedings (OSTI)

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

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

1980-03-01T23:59:59.000Z

92

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

Science Conference Proceedings (OSTI)

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

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

1980-03-01T23:59:59.000Z

93

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

94

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

SciTech Connect

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

Berry, H.A.

1987-02-01T23:59:59.000Z

95

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

96

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

SciTech Connect

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

Berry, H.A.

1991-09-01T23:59:59.000Z

97

Survey and conceptual flow sheets for coal conversion plant handling-preparation and ash/slag removal operations  

Science Conference Proceedings (OSTI)

This study was undertaken at the request of the Fossil Fuel Processing Division of the Department of Energy. The report includes a compilation of conceptual flow sheets, including major equipment lists, and the results of an availability survey of potential suppliers of equipment associated with the coal and ash/slag operations that will be required by future large coal conversion plant complexes. Conversion plant flow sheet operations and related equipment requirements were based on two representative bituminous coals - Pittsburgh and Kentucky No. 9 - and on nine coal conversion processes. It appears that almost all coal handling and preparation and ash/slag removal equipment covered by this survey, with the exception of some coal comminution equipment, either is on hand or can readily be fabricated to meet coal conversion plant capacity requirements of up to 50,000 short tons per day. Equipment capable of handling even larger capacities can be developed. This approach appears to be unjustified, however, because in many cases a reasonable or optimum number of trains of equipment must be considered when designing a conversion plant complex. The actual number of trains of equipment selected will be influenced by the total requied capacity of the complex, the minimum on-line capacity that can be tolerated in case of equipment failure, reliability of specific equipment types, and the number of reactors and related feed injection stations needed for the specific conversion process.

Zapp, F.C.; Thomas, O.W.; Silverman, M.D.; Dyslin, D.A.; Holmes, J.M.

1980-03-01T23:59:59.000Z

98

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

Science Conference Proceedings (OSTI)

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

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

1994-10-01T23:59:59.000Z

99

Results of the independent radiological verification survey at the former Chapman Valve Manufacturing Company, Indian Orchard, Massachusetts (CIO001V)  

SciTech Connect

The Chapman Valve Manufacturing Company in Indian Orchard, Massachusetts was one of many companies performing work during the 1940s associated with the development of nuclear energy for defense-related projects for the Manhattan Engineer District (MED) and the Atomic Energy Commission (AEC). In 1991, a radiological survey was conducted at the site. The survey report indicated {sup 238}U contamination in excess of the DOE criteria for surface contamination, and some {sup 235}U residues in the west end of the building. Decontamination of the facility to supplemental guidelines, derived by a hazard assessment based on appropriate scenarios for this building, was conducted by subcontractor personnel in 1995 under the direction of Bechtel National Incorporated (BNI), the project management contractor for FUSRAP. The independent radiological verification survey detailed in this report was performed in July and August 1995 under the FUSRAP program by members of ORNL at the request of DOE. The radiological verification survey of the west end of the building included gamma, alpha, and beta-gamma scans for fixed contamination, smear sampling for transferable contamination, and radionuclide analysis of soil samples taken from outside the building and from excavations in the concrete floor inside the building.

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

1997-05-01T23:59:59.000Z

100

Radiological survey of the inactive uranium-mill tailings at Lakeview, Oregon  

Science Conference Proceedings (OSTI)

The results of the radiological survey of the inactive uranium-mill site at Lakeview, Oregon, show that the average gamma-ray exposure rate 1 m above the tailings pile and the evaporation pond area (now dry) is close to the average background level for the area (11 ..mu..R/hr). The /sup 226/Ra concentration in most of the surface soil and sediment samples is also at or below the average background value for surface soil samples in the area (0.8 pCi/g). Calculated /sup 226/Ra concentrations, based on gamma radiation measurements in shallow (1-m-deep) holes, are in agreement with the results of surface soil and sediment analyses and with gamma-ray exposure rate measurements. The tailings at this site have been stabilized by the addition of 46 to 60 cm (18 to 24 in.) of soil that supports vigorous growth of vegetation. This treatment, coupled with a low-level inventory of /sup 226/Ra in the tailings (50 Ci), has resulted in limited spread of tailings by wind and water.

Haywood, F.F.; Burden, J.E.; Ellis, B.S.; Loy, E.T.; Shinpaugh, W.H.

1980-06-01T23:59:59.000Z

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


101

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

SciTech Connect

Results of a radiological survey of two inactive mill sites near Slick Rock, Colorado, in April 1976 are presented. One mill, referred to in this report as North Continent (NC), was operated primarily for recovery of radium and vanadium and, only briefly, uranium. The Union Carbide Corporation (UCC) mill produced a uranium concentrate for processing elsewhere and, although low-level contamination with /sup 226/Ra was widespread at this site, the concentration of this nuclide in tailings was much lower than at the NC site. The latter site also has an area with a high above-ground gamma dose rate (2700 ..mu..R/hr) and a high-surface /sup 226/Ra concentration (5800 pCi/g). This area, which is believed to have been a liquid disposal location during plant operations, is contained within a fence. A solid disposal area outside the present fence contains miscellaneous contaminated debris. The estimated concentration of /sup 226/Ra as a function of depth, based on gamma hole-logging data, is presented for 27 holes drilled at the two sites.

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

1980-06-01T23:59:59.000Z

102

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

103

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  

Science Conference Proceedings (OSTI)

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

104

An aerial radiological survey of the Robert Emmett Ginna Nuclear Power Plant and surrounding area, Ontario, New York  

SciTech Connect

Terrestrial radioactivity surrounding the Robert Emmett Ginna Nuclear Power Plant was measured using aerial radiological surveying 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 employed 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 the area surrounding the plant site varied from 6 to 10 microroentgens per hour. Man-made radiation (cobalt-60 within the plant site and cesium-1 37 directly over the reactor) was found at the plant site. In addition, small areas of suspected cesium-137 activity were found within the survey areas. Other than these small sites, the survey area was free of man-made radioac- tivity.

Proctor, A.E.

1997-06-01T23:59:59.000Z

105

An aerial radiological survey of the Oyster Creek Nuclear Power Plant and surrounding area, Forked River, New Jersey. Date of survey: September 18--25, 1992  

SciTech Connect

An aerial radiological survey was conducted over the Oyster Creek Nuclear Power Plant in Forked River, New Jersey, during the period September 18 through September 24, 1992. The survey was conducted at an altitude of 150 feet (46 meters) over a 26-square-mile (67-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Oyster Creek Nuclear Power plant and surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 4 and 10 microroentgens per hour and were attributed to naturally-occurring uranium, thorium, and radioactive potassium gamma emitters. The aerial data were compared to ground-based benchmark exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system. A previous survey of the power plant was conducted in August 1969 during its initial startup phase. Exposure rates and radioactive isotopes revealed in both surveys were consistent and within normal terrestrial background levels.

Hopkins, H.A.; McCall, K.A.

1994-05-01T23:59:59.000Z

106

An aerial radiological survey of the Babcock and Wilcox Nuclear Facilities and surrounding area, Lynchburg, Virginia. Date of survey: July 1988  

SciTech Connect

An aerial radiological survey was conducted from July 18 through July 25, 1988, over a 41-square-kilometer (16-square-mile) area surrounding the Babcock and Wilcox nuclear facilities located near Lynchburg, Virginia. The survey was conducted at a nominal altitude of 61 meters (200 feet) with line spacings of 91 meters (300 feet). A contour map of the terrestrial gamma exposure rate extrapolated to 1 meter above ground level (AGL) was prepared and overlaid on an aerial photograph. The terrestrial exposure rates varied from 8 to 12 microroentgens per hour ({mu}R/h). A search of the data for man-made radiation sources revealed the presence of three areas of high count rates in the survey area. Spectra accumulated over the main plant showed the presence of cobalt-60 ({sup 60}Co) and cesium-137 ({sup 137}Cs). A second area near the main plant indicated the presence of uranium-235 ({sup 235}U). Protactinium-234m ({sup 234m}Pa) and {sup 60}Co were detected over a building to the east of the main plant. Soil samples and pressurized ion chamber measurements were obtained at four locations within the survey boundaries in support of the aerial data.

Guss, P.P.

1993-04-01T23:59:59.000Z

107

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

Science Conference Proceedings (OSTI)

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

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

1984-04-01T23:59:59.000Z

108

Radiological Habits Survey: Hunterston, 2007 This page has been intentionally left blank  

E-Print Network (OSTI)

..................................................................................................23 4.7 Internal exposure..... .................................................................15 Figure 2 The Hunterston terrestrial (outer ring) and direct radiation (inner ring) survey areas AQUATIC RADIATION PATHWAYS ...........................................................................21 4

109

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

Science Conference Proceedings (OSTI)

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

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

1997-09-01T23:59:59.000Z

110

Radiological survey of shoreline vegetation from the Hanford Reach of the Columbia River, 1990--1992  

Science Conference Proceedings (OSTI)

A great deal of interest exists concerning the seepage of radiologically contaminated groundwater into the Columbia River where it borders the US Department of Energy`s Hanford Site (Hanford Reach). Areas of particular interest include the 100-N Area, the Old Hanford Townsite, and the 300 Area springs. While the radiological character of the seeps and springs along the Hanford Site shoreline has been studied, less attention has been given to characterizing the radionuclides that may be present in shoreline vegetation. The objective of this study was to characterize radionuclide concentrations in shoreline plants along the Hanford Reach of the Columbia River that were usable by humans for food or other purposes. Vegetation in two areas was found to have elevated levels of radionuclides. Those areas were the 100-N Area and the Old Hanford Townsite. There was also some indication of uranium accumulation in milfoil and onions collected from the 300 Area. Tritium was elevated above background in all areas; {sup 60}Co and {sup 9O}Sr were found in highest concentrations in vegetation from the 100-N Area. Technetium-99 was found in 2 of 12 plants collected from the Old Hanford Townsite and 1 of 10 samples collected upstream from the Vernita Bridge. The concentrations of {sup 137}Cs, {sup 238}Pu, {sup 239,240}Pu, and isotopes of uranium were just above background in all three areas (100-N Area, Old Hanford Townsite, and 300 Area).

Antonio, E.J.; Poston, T.M.; Rickard, W.H. Jr.

1993-09-01T23:59:59.000Z

111

An aerial radiological survey of the project Rio Blanco and surrounding area  

SciTech Connect

A team from the Remote Sensing Laboratory in Las Vegas, Nevada, conducted an aerial radiation survey of the area surrounding ground zero of Project Rio Blanco in the northwestern section of Colorado in June 1993. The object of the survey was to determine if there were man-made radioisotopes on or near the surface resulting from a nuclear explosion in 1972. No indications of surface contamination were found. A search for the cesium-137 radioisotope was negative. The Minimum Detectable Activity for cesium-137 is presented for several detection probabilities. The natural terrestrial exposure rates in units of Roentgens per hour were mapped and are presented in the form of a contour map over-laid on an aerial photograph. A second team made independent ground-based measurements in four places within the survey area. The average agreement of the ground-based with aerial measurements was six percent.

Singman, L.V.

1994-11-01T23:59:59.000Z

112

An aerial radiological survey of the Davis-Monthan Air Force Base and surrounding area, Tucson, Arizona  

SciTech Connect

An aerial radiological survey, which was conducted from March 1 to 13, 1995, covered a 51-square-mile (132-square-kilometer) area centered on the Davis-Monthan Air Force Base (DMAFB) in Tucson, Arizona. The results of the survey are reported as contours of bismuth-214 ({sup 214}Bi) soil concentrations, which are characteristic of natural uranium and its progeny, and as contours of the total terrestrial exposure rates extrapolated to one meter above ground level. All data were scaled and overlaid on an aerial photograph of the DMAFB area. The terrestrial exposure rates varied from 9 to 20 microroentgens per hour at one meter above the ground. Elevated levels of terrestrial radiation due to increased concentrations of {sup 214}Bi (natural uranium) were observed over the Southern Pacific railroad yard and along portions of the railroad track bed areas residing both within and outside the base boundaries. No man-made, gamma ray-emitting radioactive material was observed by the aerial survey. High-purity germanium spectrometer and pressurized ionization chamber measurements at eight locations within the base boundaries were used to verify the integrity of the aerial results. The results of the aerial and ground-based measurements were found to be in agreement. However, the ground-based measurements were able to detect minute quantities of cesium-137 ({sup 137}Cs) at six of the eight locations examined. The presence of {sup 137}Cs is a remnant of fallout from foreign and domestic atmospheric nuclear weapons testing that occurred in the 1950s and early 1960s. Cesium-137 concentrations varied from 0.1 to 0.3 picocuries per gram, which is below the minimum detectable activity of the aerial system.

NONE

1995-09-01T23:59:59.000Z

113

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

E-Print Network (OSTI)

cover 25 5.3 Novel radiation pathways 25 5.4 Internal exposure 25 6. DIRECT RADIATION 27 6.1 Direct.5 Wildfowling 19 4.6 The use of seaweed as a fertiliser 19 4.7 Internal exposure 19 4.8 External exposure 22 4 ratios for use in dose assessments 13 4. AQUATIC RADIATION PATHWAYS 14 4.1 Aquatic survey area 14 4

114

Radiological surveys of properties contaminated by residual radioactive materials from uranium processing sites  

Science Conference Proceedings (OSTI)

This report examines methods for determining the extent and nature of contamination on properties contaminated by residual radioactive materials from uranium processing sites. Methods are also examined for verifying the success of remedial actions in removing the residual radioactive materials. Using literature review and practical experiences from the Edgemont, South Dakota survey program a critical review is made of sampling programs, instrumentation, analytical procedures, data reporting format, and statistical analyses of data. Protocols are recommended for measuring indoor and outdoor gamma-ray exposure rates, surface and subsurface Radium-226 concentrations in soil, and radon daughter concentrations.

Young, J.A.; Jackson, P.O.; Thomas, V.W.

1983-06-01T23:59:59.000Z

115

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

116

Radiological survey of the inactive uranium-mill tailings at Ambrosia Lake, New Mexico  

Science Conference Proceedings (OSTI)

The inactive uranium-mill tailings pile at Ambrosia Lake, New Mexico, contains approximately 1520 Ci of /sup 226/Ra in 2.4 million metric tons of tailings covering an area of 43 hectares. All of the former mill buildings were intact and, at the time of this survey, several were in use. The tailings have not been stabilized, but the crusty surface is reported to be resistant to wind erosion. The average gamma-ray exposure rate 1 m above the tailings is 720 ..mu..R/h while the average rate in the former mill area is 150 ..mu..R/h. The adjacent area, between the mill site, ponds, and tailings pile, has an average exposure rate of 230 ..mu..R/h. Gamma radiation measurements outside these areas, as well as the results of analyses of surface or near-surface sediment and soil samples, show fairly wide dispersion of contamination around the site. The subsurface distribution of /sup 226/Ra in 18 holes drilled at the site, calculated from gamma-ray monitoring data, is presented graphically and compared with measured concentrations in two holes.

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

1980-06-01T23:59:59.000Z

117

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

SciTech Connect

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

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

1995-08-01T23:59:59.000Z

118

Long-Term Overvoltage on Medical Radiology and Treatment Equipment Detected by First Power-Line Monitoring Survey  

Science Conference Proceedings (OSTI)

This case study describes an equipment-to-electromagnetic environment incompatibility that occurred in a cancer research and treatment center radiology laboratory that is part of a large teaching and research hospital.

2003-12-31T23:59:59.000Z

119

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...

120

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

Science Conference Proceedings (OSTI)

The former Associate Aircraft Tool and Manufacturing Company site is located at 3550 Dixie Highway, Fairfield, Ohio. Associate Aircraft Tool and Manufacturing Company produced hollow uranium slugs in a machine shop at the site in 1956. The work was performed for National Lead of Ohio in a contract with the Atomic Energy Commission to augment the capacity of the Feed Materials Production Center at Fernald in the development of nuclear energy for defense-related projects. The current occupant of the building, Force Control, operates a multipurpose machine shop. At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted an independent radiological verification survey at the former Associate Aircraft Tool and Manufacturing Company Site, Fairfield, Ohio. The survey was performed from February to May of 1995. The purpose of the survey was to verify that radioactivity from residues of {sup 238}U was remediated to a level below acceptable DOE guidelines levels.

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

1996-01-01T23:59:59.000Z

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


121

Results of the radiological survey at the former Herring-Hall-Marvin Safe Company (3rd floor), 1550 Grand Boulevard, Hamilton, Ohio (HO001)  

SciTech Connect

At the request of the US Department of Energy (DOE), a group from the Oak Ridge National Laboratory conducted a radiological survey at the former Herring-Hall-Marvin Safe Company (third floor), 1550 Grand Boulevard, Hamilton, Ohio (HO001) in August 1993. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, principally {sup 238}U, derived from the former Manhattan Engineer District project. The survey included gamma scans; direct and transferable measurements of alpha, beta, and gamma radiation levels; and debris sampling for radionuclide analyses. Results of the survey demonstrated {sup 238}U surface contamination in excess of the DOE criteria for surface contamination. The third floor was generally contaminated over 25 percent of its area with isolated spots in the remaining area. Although three isolated spots of contamination were found in areas other than on the third floor (in the same southeastern comer of the facility), they were remediated by sampling. Based on the survey results, this site is recommended for remediation.

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

1994-03-01T23:59:59.000Z

122

An aerial radiological survey of Technical Areas 2, 21, and 53 and surroundings, Los Alamos National Laboratory, Los Alamos, New Mexico  

SciTech Connect

An aerial radiological survey of the entire Los Alamos National Laboratory was flown in September 1982. The data from a part of the survey, Technical Areas 2, 21, and 53, are presented here along with pertinent data from an October 1975 survey of limited areas of Los Alamos. The data from Technical Area 15, another part of the survey, will be published in another report. Contour maps of the gamma survey data show some Cs-137 activity in Los Alamos Canyon as well as in DP Canyon beside TA-21. Some Be-7, Sb-124, and Co-58 apparently exist in the canyon immediately below the Los Alamos Meson Physics Facility (LAMPF) ponds. Estimates on the Cs-137 inventory in the canyons range from 210 mCi to 1270 mCi. An exposure rate contour map at 1 meter above ground level (AGL) was constructed from the gamma data and overlaid on an aerial photograph and map of the area. The terrestrial exposure rates ranged from 6{mu}R/h to about 18{mu}R/h. 25 figs., 3 tabs.

Fritzsche, A.E.

1990-09-01T23:59:59.000Z

123

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...

124

A series of low-altitude aerial radiological surveys of selected regions within Areas 3, 5, 8, 9, 11, 18, and 25 at the Nevada Test Site  

SciTech Connect

A series of low-altitude, aerial radiological surveys of selected regions within Areas 3, 5, 8, 9, 11, 18,and 25 of the Nevada Test Site was conducted from December 1996 through June 1999. The surveys were conducted for the US Department of Energy by the Remote Sensing Laboratory, located in Las Vegas, Nevada, and maintained and operated by Bechtel Nevada. The flights were conducted at a nominal altitude of 15 meters above ground level along a set of parallel flight lines spaced 23 meters apart. The purpose of these low-altitude surveys was to measure, map, and define the areas of americium-241 activity. The americium contamination will be used to determine the areas of plutonium contamination. Americium-241 activity was detected within 8 of the 11 regions. The three regions where americium-241 was not detected were in the inactive Nuclear Rocket Development Station complex in Area 25, which encompassed the Test Cell A and Test Cell C reactor test stands and the Reactor Maintenance Assembly and Disassembly facility.

Colton, D.P.

1999-12-01T23:59:59.000Z

125

Health and Safety Research Division RESULTS OF THE RADIOLOGICAL...  

Office of Legacy Management (LM)

Contaninated material was discovered in the area during an EG&G aerial radiological survey,l and confirmed by a ground-level radiological survey by the Nuclear Regulatory...

126

Health and Safety Research Divlsion RESULTS OF THE RADIOLOGICAL...  

Office of Legacy Management (LM)

Contaminated material was discovered in the area during an. EG&G aerial radiological survey,l and confirmed by a ground-level radiological survey by the Nuclear Regulatory...

127

Medical Examiner/Coroner on the Handling of a Body/Human Remains...  

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

Medical ExaminerCoroner on the Handling of a BodyHuman Remains that are Potentially Radiologically Contaminated Medical ExaminerCoroner on the Handling of a BodyHuman Remains...

128

OAK RIDGE NATIONAL LABORATORY RESULTS OF THE INDEPENDENT RADIOLOGICAL  

Office of Legacy Management (LM)

W. D. Cottrell - FUSRAP Project Director M. G. Yalcintas - Field Survey Supervisor Work performed as part of the RADIOLOGICAL SURVEY ACTIVITIES PROGRAM Prepared by the OAK...

129

Confirmatory radiological survey for the 190-C Main Pumphouse Facility decommissioning at the Hanford Site, Richland, Washington  

Science Conference Proceedings (OSTI)

An independent assessment of remedial action activities at the 190-C Main Pumphouse Facility at the Hanford Site, Richland, Washington has been accomplished by the Oak Ridge National Laboratory Environmental Assessments Group. The purpose of the assessment was to confirm the site`s compliance with DOE applicable guidelines and provide independent measurements of the activity levels in the 190-C trenches and 105-C process water tunnels. The assessment included reviews of the Decontamination and Decommissioning Plan and data provided in the pre- and post-remedial action surveys. An on-site independent verification survey of the facility was conducted during the period of November 19--21, 1996. The independent verification survey included beta and gamma scans, smears for removable contamination, and direct measurements for beta-gamma activity in the trenches and tunnels. The same measurements and scans, with the addition of alpha measurements, were performed on the floor in the filter repair confinement area. The facility was also spot-checked for direct alpha and beta-gamma activity.

Coleman, R.L. [Oak Ridge National Lab., TN (United States); Forbes, G.H. [Oak Ridge National Lab., Grand Junction, CO (United States). Environmental Technology Section

1997-06-01T23:59:59.000Z

130

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

131

Radiological characterization of Yankee Nuclear Power Station  

SciTech Connect

The Yankee nuclear power station located in Rowe, Massachusetts, permanently ceased power operations on February 26, 1992, after 31 yr of operation. Yankee has since initiated decommissioning planning activities. A significant component of these activities is the determination of the extent of radiological contamination of the Yankee site. This paper describes the site radiological characterization program that has been implemented for decommissioning the Yankee plant. Radiological scoping surveys were completed to support submittal of a decommissioning plan to the U.S. Nuclear Regulatory Commission (NRC) by October 1, 1993. These surveys were designed to provide sufficient detail to estimate the extent of contamination, volume of radiological waste, activity of radiological waste, and personnel dose estimates for removal activities. Surveys were conducted both inside and on the grounds outside of the Yankee plant buildings. Survey results were combined with analytical evaluations to characterize the Yankee site.

Bellini, F.X.; Cumming, E.R.; Hollenbeck, P. (Yankee Atomic Electric Co., Bolton, MA (United States))

1993-01-01T23:59:59.000Z

132

Radiological Habits Survey, Torness 2001  

E-Print Network (OSTI)

............................................................................ 30 4.5 Internal exposure................................................................................................................ 39 5.4 Internal Exposure ................................................................................ 12 4 AQUATIC RADIATION PATHWAYS

133

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

134

Incident Handling Activities  

Science Conference Proceedings (OSTI)

[an error occurred while processing this directive] Incident Handling Activities. Since 1989 the National Institute of Standards ...

135

ORISE: Characterization surveys  

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

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

136

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

137

Vacuum Vessel Remote Handling  

E-Print Network (OSTI)

FIRE Vacuum Vessel and Remote Handling Overview B. Nelson, T. Burgess, T. Brown, H-M Fan, G. Jones #12;13 July 2002 Snowmass Review: FIRE Vacuum Vessel and Remote Handling 2 Presentation Outline · Remote Handling - Maintenance Approach & Component Classification - In-Vessel Transporter - Component

138

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

SciTech Connect

In 1998, a portion of Bldg. K-1006 was leased to the Community Reuse Organization of East Tennessee (CROET) as part of the reindustrialization efforts at the East Tennessee Technology Park (ETTP). The facility was subleased and is being used as an analytical laboratory. The 1998 lease did not include rooms C107, C107-A, C107-B, C107-C, and C107-D. The lease of these rooms is now desired. These rooms comprise the area to be surveyed. The building was constructed as a laboratory facility to support the gaseous diffusion uranium enrichment process. It also contains offices and administrative spaces for laboratory personnel. After the gaseous diffusion process was shut down in the mid-1980s, the building was used to provide research and development support to ETTP environmental, safety, and health programs; the Toxic Substances Control Act Incinerator; the Central Neutralization Facility; and other multi-site waste treatment activities. It also served as the chemistry laboratory for the Environmental Technology Technical Services Organization. The activities currently conducted in Bldg. K-1006 utilize a variety of analytical techniques. Some of the major techniques being employed are X-ray analysis, electron microanalysis, and spectrochemical analysis. In 1998, a portion of Bldg. K-1006 was leased to CROET as part of the reindustrialization efforts at ETTP. The facility was subleased and is being used as an analytical laboratory. The 1998 lease did not include Rooms C107, C107-A, C107-B, C107-C, and C107-D. Some demolition of furniture and decontamination activities has taken place for Rooms C 107 and C 107-B since the last radiological survey of those rooms. In March 2009, a final remedial action (RA) was performed for the Bldg. K-1006 north basement sump. The Bldg. K-1006 north basement sump is a nominal 30-in.-diameter, 36-in.-deep concrete structure in the north corner of room C107B. The building receives groundwater in-leakage that is periodically pumped to the sewer system via this float-controlled pump. Solids in the bottom of the sump consisted of an estimated 1-ft{sup 3} coarse-grained material that varied in thickness from 0 to 4 in. with no suspended fraction. The RA consisted of removing the water in the sump and then removing and sampling the solids. The solids were mixed with grout after removal and allowed to set. The solids were then disposed off-site at an approved disposal facility. The building sump will remain until the K-1006 building is demolished. The actions for the K- 1006 sump are described in the revised Phased Construction Completion Report for Exposure Unit (EU) Z2-33, which received regulatory approval in December 2009.

Blevins M.F.

2010-09-01T23:59:59.000Z

139

Radiological Worker Training - Radiological Contamination Control...  

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

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....

140

Radiological Worker Training - Radiological Control Training...  

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

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...

Note: This page contains sample records for the topic "handled radiological surveys" 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

DOE handbook: Tritium handling and safe storage  

SciTech Connect

The DOE Handbook was developed as an educational supplement and reference for operations and maintenance personnel. Most of the tritium publications are written from a radiological protection perspective. This handbook provides more extensive guidance and advice on the null range of tritium operations. This handbook can be used by personnel involved in the full range of tritium handling from receipt to ultimate disposal. Compliance issues are addressed at each stage of handling. This handbook can also be used as a reference for those individuals involved in real time determination of bounding doses resulting from inadvertent tritium releases. This handbook provides useful information for establishing processes and procedures for the receipt, storage, assay, handling, packaging, and shipping of tritium and tritiated wastes. It includes discussions and advice on compliance-based issues and adds insight to those areas that currently possess unclear DOE guidance.

NONE

1999-03-01T23:59:59.000Z

142

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

143

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 . . :

144

Handling Pyrophoric Reagents  

SciTech Connect

Pyrophoric reagents are extremely hazardous. Special handling techniques are required to prevent contact with air and the resulting fire. This document provides several methods for working with pyrophoric reagents outside of an inert atmosphere.

Alnajjar, Mikhail S.; Haynie, Todd O.

2009-08-14T23:59:59.000Z

145

Radiological Control Manual  

Science Conference Proceedings (OSTI)

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

Not Available

1993-04-01T23:59:59.000Z

146

Transportation and handling environment  

SciTech Connect

The elements of the environment relating to transportation and handling include temperature, solar radiation, precipitation, humidity, pressure, shock, and vibration. While each of these deserves consideration, the latter two, shock and vibration, are perhaps the least understood. The report discusses all of these elements, but concentrates largely on shock and vibration. Emphasis is upon the necessity of understanding both the product and the environment. To that end, descriptions of the environment which have been derived statistically are discussed. Land, sea, and air transport are considered. Current knowledge of the handling environment is indicated.

Gens, M.B.

1972-09-01T23:59:59.000Z

147

FUEL HANDLING MECHANISM  

DOE Patents (OSTI)

A remotely operable handling device specifically adapted for the handling of vertically disposed fuel rods in a nuclear reactor was developed. The device consists essentially of an elongated tubular member having a gripping device at the lower end of the pivoted jaw type adapted to grip an enlarged head on the upper end of the workpiece. The device includes a sensing element which engages the enlarged head and is displaced to remotely indicate when the workpiece is in the proper position to be engaged by the jaws.

Koch, L.J.; Hutter, E.

1960-02-01T23:59:59.000Z

148

SLUG HANDLING DEVICES  

DOE Patents (OSTI)

A device is described for handling fuel elements of a neutronic reactor. The device consists of two concentric telescoped contalners that may fit about the fuel element. A number of ratchet members, equally spaced about the entrance to the containers, are pivoted on the inner container and spring biased to the outer container so thnt they are forced to hear against and hold the fuel element, the weight of which tends to force the ratchets tighter against the fuel element. The ratchets are released from their hold by raising the inner container relative to the outer memeber. This device reduces the radiation hazard to the personnel handling the fuel elements.

Gentry, J.R.

1958-09-16T23:59:59.000Z

149

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

150

WASTE HANDLING BUILDING VENTILATION SYSTEM DESCRIPTION DOCUMENT  

SciTech Connect

The Waste Handling Building Ventilation System provides heating, ventilation, and air conditioning (HVAC) for the contaminated, potentially contaminated, and uncontaminated areas of the Monitored Geologic Repository's (MGR) Waste Handling Building (WHB). In the uncontaminated areas, the non-confinement area ventilation system maintains the proper environmental conditions for equipment operation and personnel comfort. In the contaminated and potentially contaminated areas, in addition to maintaining the proper environmental conditions for equipment operation and personnel comfort, the contamination confinement area ventilation system directs potentially contaminated air away from personnel in the WHB and confines the contamination within high-efficiency particulate air (HEPA) filtration units. The contamination confinement areas ventilation system creates airflow paths and pressure zones to minimize the potential for spreading contamination within the building. The contamination confinement ventilation system also protects the environment and the public by limiting airborne releases of radioactive or other hazardous contaminants from the WHB. The Waste Handling Building Ventilation System is designed to perform its safety functions under accident conditions and other Design Basis Events (DBEs) (such as earthquakes, tornadoes, fires, and loss of the primary electric power). Additional system design features (such as compartmentalization with independent subsystems) limit the potential for cross-contamination within the WHB. The system provides status of important system parameters and equipment operation, and provides audible and/or visual indication of off-normal conditions and equipment failures. The Waste Handling Building Ventilation System confines the radioactive and hazardous material within the building such that the release rates comply with regulatory limits. The system design, operations, and maintenance activities incorporate ALARA (as low as is reasonably achievable) principles to maintain personnel radiation doses to all occupational workers below regulatory limits and as low as is reasonably achievable. The Waste Handling Building Ventilation System interfaces with the Waste Handling Building System by being located within the WHB and by maintaining specific pressures, temperatures, and humidity within the building. The system also depends on the WHB for water supply. The system interfaces with the Site Radiological Monitoring System for continuous monitoring of the exhaust air; the Waste Handling Building Fire Protection System for detection of fire and smoke; the Waste Handling Building Electrical System for normal, emergency, and standby power; and the Monitored Geologic Repository Operations Monitoring and Control System for monitoring and control of the system.

P.A. Kumar

2000-06-21T23:59:59.000Z

151

Radiological design guide  

SciTech Connect

The purpose of this design guide is to provide radiological safety requirements, standards, and information necessary for designing facilities that will operate without unacceptable risk to personnel, the public, or the environment as required by the US Department of Energy (DOE). This design guide, together with WHC-CM-4-29, Nuclear Criticality Safety, WHC-CM-4-46, Nonreactor Facility Safety Analysis, and WHC-CM-7-5, Environmental Compliance, covers the radiation safety design requirements at Westinghouse Hanford Company (WHC). This design guide applies to the design of all new facilities. The WHC organization with line responsibility for design shall determine to what extent this design guide shall apply to the modifications to existing facilities. In making this determination, consideration shall include a cost versus benefit study. Specifically, facilities that store, handle, or process radioactive materials will be covered. This design guide replaces WHC-CM-4-9 and is designated a living document. This design guide is intended for design purposes only. Design criteria are different from operational criteria and often more stringent. Criteria that might be acceptable for operations might not be adequate for design.

Evans, R.A.

1994-08-16T23:59:59.000Z

152

General Employee Radiological Training (GERT)  

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

General Employee Radiological Training (GERT) Radiological Training for NSLS Access has been replaced with BNL General Employee Radiological Training (GERT). Please read the...

153

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

Science Conference Proceedings (OSTI)

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

W. C. Adams

2007-10-30T23:59:59.000Z

154

Uranium hexafluoride handling. Proceedings  

SciTech Connect

The United States Department of Energy, Oak Ridge Field Office, and Martin Marietta Energy Systems, Inc., are co-sponsoring this Second International Conference on Uranium Hexafluoride Handling. The conference is offered as a forum for the exchange of information and concepts regarding the technical and regulatory issues and the safety aspects which relate to the handling of uranium hexafluoride. Through the papers presented here, we attempt not only to share technological advances and lessons learned, but also to demonstrate that we are concerned about the health and safety of our workers and the public, and are good stewards of the environment in which we all work and live. These proceedings are a compilation of the work of many experts in that phase of world-wide industry which comprises the nuclear fuel cycle. Their experience spans the entire range over which uranium hexafluoride is involved in the fuel cycle, from the production of UF{sub 6} from the naturally-occurring oxide to its re-conversion to oxide for reactor fuels. The papers furnish insights into the chemical, physical, and nuclear properties of uranium hexafluoride as they influence its transport, storage, and the design and operation of plant-scale facilities for production, processing, and conversion to oxide. The papers demonstrate, in an industry often cited for its excellent safety record, continuing efforts to further improve safety in all areas of handling uranium hexafluoride. Selected papers were processed separately for inclusion in the Energy Science and Technology Database.

Not Available

1991-12-31T23:59:59.000Z

155

Radiological Control Division  

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

Support personnel, an accredited Personnel Monitoring service, a fully functional Instrumentation & Calibration facility, expertise in Radiological Engineering and the...

156

Ash Handling System Maintenance Guide  

Science Conference Proceedings (OSTI)

This Ash Handling System Maintenance Guide provides fossil plant maintenance personnel with current maintenance information on this system. This guide will assist plant maintenance personnel in improving the reliability and reducing the maintenance costs for the ash handling system.

2005-12-23T23:59:59.000Z

157

December 2005 PREVENTING AND HANDLING  

E-Print Network (OSTI)

, and remote access servers. NIST SP 800-61, Computer Security Incident Handling Guide, describes the fourDecember 2005 PREVENTING AND HANDLING MALWARE INCIDENTS: HOW TO PROTECT INFORMATION TECHNOLOGY SYSTEMS FROM MALICIOUS CODE AND SOFTWARE PREVENTING AND HANDLING MALWARE INCIDENTS: HOW TO PROTECT

158

Solid handling valve  

DOE Patents (OSTI)

The present invention is directed to a solids handling valve for use in combination with lock hoppers utilized for conveying pulverized coal to a coal gasifier. The valve comprises a fluid-actuated flow control piston disposed within a housing and provided with a tapered primary seal having a recessed seat on the housing and a radially expandable fluid-actuated secondary seal. The valve seals are highly resistive to corrosion, erosion and abrasion by the solids, liquids, and gases associated with the gasification process so as to minimize valve failure.

Williams, William R. (Morgantown, WV)

1979-01-01T23:59:59.000Z

159

Sectional device handling tool  

DOE Patents (OSTI)

Apparatus for remotely handling a device in an irradiated underwater environment includes a plurality of tubular sections interconnected end-to-end to form a handling structure, the bottom section being adapted for connection to the device. A support section is connected to the top tubular section and is adapted to be suspended from an overhead crane. Each section is flanged at its opposite ends. Axially retractable bolts in each bottom flange are threadedly engageable with holes in the top flange of an adjacent section, each bolt being biased to its retracted position and retained in place on the bottom flange. Guide pins on each top flange cooperate with mating holes on adjacent bottom flanges to guide movement of the parts to the proper interconnection orientation. Each section carries two hydraulic line segments provided with quick-connect/disconnect fittings at their opposite ends for connection to the segments of adjacent tubular sections upon interconnection thereof to form control lines which are connectable to the device and to an associated control console.

Candee, Clark B. (Monroeville, PA)

1988-07-12T23:59:59.000Z

160

Status of ITER neutral beam cell remote handling system  

E-Print Network (OSTI)

The ITER neutral beam cell will contain up to three heating neutral beams and one diagnostic neutral beam, and four upper ports. Though manual maintenance work is envisaged within the cell, when containment is breached, or the radiological protection is removed the maintenance must be conducted remotely. This maintenance constitutes the removal and replacement of line replaceable units, and their transport to and from a cask docked to the cell. A design of the remote handling system has been prepared to concept level which this paper describes including the development of a beam line transporter, beam source remote handling equipment, upper port remote handling equipment and equipment for the maintenance of the neutral shield. This equipment has been developed complete the planned maintenance tasks for the components of the neutral beam cell and to have inherent flexibility to enable as yet unforeseen tasks and recovery operations to be performed.

Sykes, N; Choi, C-H; Crofts, O; Crowe, R; Damiani, C; Delavalle, S; Meredith, L; Mindham, T; Raimbach, J; Tesini, A; Van Uffelen, M

2013-01-01T23:59:59.000Z

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


161

Radiological Laboratory, Utility, Office Building LEED Strategy & Achievement  

SciTech Connect

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

Seguin, Nicole R. [Los Alamos National Laboratory

2012-07-18T23:59:59.000Z

162

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

163

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

164

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

165

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

166

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

167

Remote Inspection, Measurement and Handling for LHC  

E-Print Network (OSTI)

Personnel access to the LHC tunnel will be restricted to varying extents during the life of the machine due to radiation, cryogenic and pressure hazards. The ability to carry out visual inspection, measurement and handling activities remotely during periods when the LHC tunnel is potentially hazardous offers advantages in terms of safety, accelerator down time, and costs. The first applications identified were remote measurement of radiation levels at the start of shut-down, remote geometrical survey measurements in the collimation regions, and remote visual inspection during pressure testing and initial machine cool-down. In addition, for remote handling operations, it will be necessary to be able to transmit several real-time video images from the tunnel to the control room. The paper describes the design, development and use of a remotely controlled vehicle to demonstrate the feasibility of meeting the above requirements in the LHC tunnel. Design choices are explained along with operating experience to-dat...

Kershaw, K; Coin, A; Delsaux, F; Feniet, T; Grenard, J L; Valbuena, R

2007-01-01T23:59:59.000Z

168

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.

169

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.

170

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...

171

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

172

REMOTE HANDLING ARRANGEMENTS  

DOE Patents (OSTI)

A means for handling remotely a sample pellet to be irradiated in a nuclear reactor is proposed. It is comprised essentially of an inlet tube extending through the outer shield of the reactor and being inclined so that its outer end is at a higher elevation than its inner end, an outlet tube extending through the outer shield being inclined so that its inner end is at a higher elevation than its outer end, the inner ends of these two tubes being interconnected, and a straight tube extending through the outer shield and into the reactor core between the inlet and outlet tubes and passing through the juncture of said inner ends. A rod-like member is rotatably and slidely operated within the central straight tube and has a receptacle on its inner end for receiving a sample pellet from the inlet tube. The rod member is operated to pick up a sample pellet from the inlet tube, carry the sample pellet into the irradiating position within the core, and return to the receiving position where it is rotated to dump the irradiated pellet into the outlet tube by which it is conveyed by gravity to the outside of the reactor. Stop members are provided in the inlet tube, and electrical operating devices are provided to control the sequence of the operation automatically.

Ginns, D.W.

1958-04-01T23:59:59.000Z

173

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

174

Radiological assessment of the town of Edgemont  

SciTech Connect

Congress, in 1980, gave the Nuclear Regulatory Commission (NRC) the responsibility to coordinate and conduct a monitoring, engineering assessment, and remedial cleanup program in Edgemont, South Dakota. The Congressional intent was to locate public properties in Edgemont that had been contaminated by radioactive materials from a local uranium mill, and to clean up those properties. Because the Atomic Energy Act of 1954 gave NRC the authority to monitor for contamination but not to clean up contamination, Congress later assigned the remedial cleanup responsibility to the Department of Energy (DOE). NRC, through Battelle Pacific Northwest Laboratory (PNL), conducted a radiological survey of 96% of the properties in Edgemont and vicinity during the time period of September 1980 through April 1984. (Out of 976 total properties, 941 were surveyed.) The strategy of the survey was to screen properties for the possible presence of contamination by using short- and long-term radon progeny measurements, indoor and outdoor gamma exposure rate measurements, and soil radium-226 measurements. Properties that failed the screening surveys were measured more extensively to determine whether the elevated readings were due to residual radioactive materials from the uranium mill. This report contains the historical perspective of the Edgemont survey, explains the development and modifications of survey protocols, examines the problems encountered during the survey, and lists a summary of the results. The report also presents conclusions about the effectiveness of the survey techniques and about the rationale of a comprehensive survey of a whole community. The appendices section of this report contains all the protocols, a list of all the properties showing survey results for each, and reports on special studies conducted during the survey. These special studies contain many valuable insights that may prove beneficial to future radiological assessment surveys.

Jackson, P.O.; Thomas, V.W.; Young, J.A.

1985-01-01T23:59:59.000Z

175

FACT SHEET ERDA'S RADIOLOGICAL SURVEY PROGRAM INTRODUCTION  

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

New York; Site A, Cook County Forest Preserve, Palos Park, Illinois; Bridgeport Brass Metal Extfusion Plant (now property of General Motors Corporation), Adrian, Michigan;...

176

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

Science Conference Proceedings (OSTI)

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

Garcia-Bermejo, R.; Felipe, A.; Gutierrez, S.; Salas, E. [Iberdrola Ingenieria y Construccion (Spain); Martin, N. [ENRESA (Spain)

2008-01-15T23:59:59.000Z

177

Radiological Worker Training  

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

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...

178

Biodiesel Handling and Use Guidelines  

DOE Green Energy (OSTI)

This document is a field guide for end-users, distributors, and those involved in related activities. These guidelines cover fuel use and handling issues that could be anticipated or encountered in the field.

Tyson, S.

2001-09-05T23:59:59.000Z

179

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

180

DISPOSAL CONTAINER HANDLING SYSTEM DESCRIPTION DOCUMENT  

Science Conference Proceedings (OSTI)

The Disposal Container Handling System receives and prepares new disposal containers (DCs) and transfers them to the Assembly Transfer System (ATS) or Canister Transfer System (CTS) for loading. The system receives the loaded DCs from ATS or CTS and welds the lids. When the welds are accepted the DCs are termed waste packages (WPs). The system may stage the WP for later transfer or transfer the WP directly to the Waste Emplacement/Retrieval System. The system can also transfer DCs/WPs to/from the Waste Package Remediation System. The Disposal Container Handling System begins with new DC preparation, which includes installing collars, tilting the DC upright, and outfitting the container for the specific fuel it is to receive. DCs and their lids are staged in the receipt area for transfer to the needed location. When called for, a DC is put on a cart and sent through an airlock into a hot cell. From this point on, all processes are done remotely. The DC transfer operation moves the DC to the ATS or CTS for loading and then receives the DC for welding. The DC welding operation receives loaded DCs directly from the waste handling lines or from interim lag storage for welding of the lids. The welding operation includes mounting the DC on a turntable, removing lid seals, and installing and welding the inner and outer lids. After the weld process and non-destructive examination are successfully completed, the WP is either staged or transferred to a tilting station. At the tilting station, the WP is tilted horizontally onto a cart and the collars removed. The cart is taken through an air lock where the WP is lifted, surveyed, decontaminated if required, and then moved into the Waste Emplacement/Retrieval System. DCs that do not meet the welding non-destructive examination criteria are transferred to the Waste Package Remediation System for weld preparation or removal of the lids. The Disposal Container Handling System is contained within the Waste Handling Building System. This includes the primary hot cell bounded by the receiving area and WP transport exit air locks; and isolation doors at ATS, CTS, and Waste Package Remediation. The hot cell includes areas for welding, various staging, tilting, and WP transporter loading. There are associated operating galleries and equipment maintenance areas outside the hot cell. These areas operate concurrently to accommodate the DC/WP throughput rates and support system maintenance. The new DC preparation area is located in an unshielded structure. The handling equipment includes DC/WP bridge cranes, tilting stations, and horizontal transfer carts. The welding area includes DC/WP welders and staging stations. Welding operations are supported by remotely operated equipment including a bridge crane and hoists, welder jib cranes, welding turntables, and manipulators. WP transfer includes a transfer/decontamination and transporter load area. The transfer operations are supported by a remotely operated horizontal lifting system, decontamination system, decontamination and inspection manipulator, and a WP horizontal transfer cart. All handling operations are supported by a suite of fixtures including collars, yokes, lift beams, and lid attachments. Remote equipment is designed to facilitate decontamination and maintenance. Interchangeable components are provided where appropriate. Set-aside areas are included, as required, for fixtures and tooling to support off-normal and recovery operations. Semi-automatic, manual, and backup control methods support normal, maintenance, and recovery operations. The system interfaces with the ATS and CTS to provide empty and receive loaded DCs. The Waste Emplacement/Retrieval System interfaces are for loading/unloading WPs on/from the transporter. The system also interfaces with the Waste Package Remediation System for DC/WP repair. The system is housed, shielded, supported, and has ventilation boundaries by the Waste Handling Building (WHB). The system is ventilated by the WHB Ventilation System, which in conjunction with ventilation boundaries ensure that ai

E. F. Loros

2000-06-30T23:59:59.000Z

Note: This page contains sample records for the topic "handled radiological surveys" 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

Storage/Handling | Department of Energy  

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

StorageHandling StorageHandling Records Management Procedures for Storage, Transfer & Retrieval of Records from the Washington National Records Center (WNRC) or Legacy Management...

182

WEAR RESISTANT ALLOYS FOR COAL HANDLING EQUIPMENT  

E-Print Network (OSTI)

Proceedings of the Conference on Coal Feeding Systems, HeldWear Resistant Alloys for Coal Handling Equipment", proposalWear Resistant Alloys for Coal Handling Equi pment". The

Bhat, M.S.

2011-01-01T23:59:59.000Z

183

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

184

Propane gas: Handle with care  

SciTech Connect

Because of its chemical composition and combustion properties, this liquefied petroleum (LP) gas can be mixed with air and used as a direct replacement for natural gas with no burner or process equipment modifications. One major and growing use of propane is as a vehicle fuel. Growing industrial use of propane also has prompted the National Fire Protection Association (NFPA) to issue new codes. NFPA standard 58-95, Storing and Handling of Liquefied Petroleum Gases, stresses the need to adhere to safe work and handling practices whenever propane is involved. All employees directly handling the gas should be formally trained and certified, and recertified annually. Although the code applies only to those directly handling propane or operating propane equipment such as portable cylinder filling stations, all employees working around or with propane or other LP gases should understand the characteristics of LP gas and be aware of basic safe handling practices. The paper discusses what LP gas is, special safety concerns, the care required in refilling cylinders, and cylinder inspection.

Fernald, D. [Plant Systems, Inc., Berea, OH (United States)

1996-04-01T23:59:59.000Z

185

Aerial survey finds no increase in radioactivity for Los Alamos...  

National Nuclear Security Administration (NNSA)

Alamos County and Los Alamos National Laboratory. The radiological surveys, conducted in August 2011 and June 2012, found that radioisotopes and their associated exposure rates...

186

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

187

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

188

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

189

Bulk materials storage handling and transportation  

Science Conference Proceedings (OSTI)

This book contains papers on bulk materials storage, handling, and transportation. Topic areas covered include: mechanical handling; pneumatic conveying; transportation; freight pipeliners; storage and discharge systems; integrated handling systems; automation; environment and sampling; feeders and flow control; structural design; large mobile machines; and grain handling.

Not Available

1983-01-01T23:59:59.000Z

190

324 Building Baseline Radiological Characterization  

SciTech Connect

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

R.J. Reeder, J.C. Cooper

2010-06-24T23:59:59.000Z

191

Tritium Handling and Safe Storage  

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

SENSITIVE DOE-HDBK-1129-2007 March 2007 ____________________ DOE HANDBOOK TRITIUM HANDLING AND SAFE STORAGE U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1129-2007

192

Photon Sciences Material Handling Equipment  

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

Active Y Y Rhein Craig 20622 PSBC Active Y Y Page 3 of 80 List of Photon Sciences Mat'l Handling Equip 5242013 4:09:58 PM 725 UV East GE-56 PS-C01 Yale A-422-3749 2 ton...

193

Portable vacuum object handling device  

DOE Patents (OSTI)

The disclosure relates to a portable device adapted to handle objects which are not to be touched by hand. A piston and bore wall form a vacuum chamber communicating with an adaptor sealably engageable with an object to be lifted. The piston is manually moved and set to establish vacuum. A valve is manually actuable to apply the vacuum to lift the object.

Anderson, G.H.

1981-07-30T23:59:59.000Z

194

Portable vacuum object handling device  

SciTech Connect

The disclosure relates to a portable device adapted to handle objects which are not to be touched by hand. A piston and bore wall form a vacuum chamber communicating with an adaptor sealably engageable with an object to be lifted. The piston is manually moved and set to establish vacuum. A valve is manually actuatable to apply the vacuum to lift the object.

Anderson, Gordon H. (Los Alamos, NM)

1983-08-09T23:59:59.000Z

195

Arrival condition of spent fuel after storage, handling, and transportation  

Science Conference Proceedings (OSTI)

This report presents the results of a study conducted to determine the probable arrival condition of spent light-water reactor (LWR) fuel after handling and interim storage in spent fuel storage pools and subsequent handling and accident-free transport operations under normal or slightly abnormal conditions. The objective of this study was to provide information on the expected condition of spent LWR fuel upon arrival at interim storage or fuel reprocessing facilities or at disposal facilities if the fuel is declared a waste. Results of a literature survey and data evaluation effort are discussed. Preliminary threshold limits for storing, handling, and transporting unconsolidated spent LWR fuel are presented. The difficulty in trying to anticipate the amount of corrosion products (crud) that may be on spent fuel in future shipments is also discussed, and potential areas for future work are listed. 95 references, 3 figures, 17 tables.

Bailey, W.J.; Pankaskie, P.J.; Langstaff, D.C.; Gilbert, E.R.; Rising, K.H.; Schreiber, R.E.

1982-11-01T23:59:59.000Z

196

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

197

Appendix A: Handling of Federal  

Gasoline and Diesel Fuel Update (EIA)

and selected State legislation and regulation in the AEO This page inTenTionally lefT blank 177 U.S. Energy Information Administration | Assumptions to the Annual Energy Outlook 2012 Appendix A: Handling of Federal and selected State legislation and regulation in the AEO Legislation Brief description AEO handling Basis Residential sector A. National Appliance Energy Conservation Act of 1987 Requires Secretary of Energy to set minimum efficiency standards for 10 appliance categories with periodic updates Included for categories represented in the AEO residential sector forecast. Public Law 100-12. a. Room air conditioners Sets standards for room air conditioners in 2014. Require new purchases of room air conditioners to meet the standard. Federal Register Notice

198

Tritium Handling and Safe Storage  

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

DOE-HDBK-1129-2008 December 2008 DOE HANDBOOK TRITIUM HANDLING AND SAFE STORAGE U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS DOE-HDBK-1129-2008 ii This page is intentionally blank. DOE-HDBK-1129-2008 iii TABLE OF CONTENTS SECTION PAGE FOREWORD................................................................................................................................ ix ACRONYMS ................................................................................................................................ xi 1.0 INTRODUCTION ....................................................................................................................

199

Portable vacuum object handling device  

DOE Patents (OSTI)

The disclosure relates to a portable device adapted to handle objects which are not to be touched by hand. A piston and bore wall form a vacuum chamber communicating with an adaptor sealably engageable with an object to be lifted. The piston is manually moved and set to establish vacuum. A valve is manually actuatable to apply the vacuum to lift the object. 1 fig.

Anderson, G.H.

1983-08-09T23:59:59.000Z

200

Enhancing CIMOSA with Exception Handling  

E-Print Network (OSTI)

CIMOSA (Open System Architecture for CIM) [2], an architecture for the modelling of manufacturing applications, does not provide a facility for exception definition and handling. Exceptions, traditionally associated to programming language and operating systems, are necessary in all types of languages, including specification languages. Our contribution consists of the enhancement of the CIMOSA model with a complete facility and methodology for the specification of the system behaviour in case of exception.

Messina Pleinevaux Swiss; S. Messina; P. Pleinevaux

1996-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "handled radiological surveys" 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 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

202

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

203

DOE - Office of Legacy Management -- South Valley Superfund Site...  

Office of Legacy Management (LM)

Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The Department...

204

DOE - Office of Legacy Management -- Kerr McGee - 028  

Office of Legacy Management (LM)

Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The Kerr McGee...

205

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

206

Disabling Radiological Dispersal Terror  

SciTech Connect

Terror resulting from the use of a radiological dispersal device (RDD) relies upon an individual's lack of knowledge and understanding regarding its significance. Disabling this terror will depend upon realistic reviews of the current conservative radiation protection regulatory standards. It will also depend upon individuals being able to make their own informed decisions merging perceived risks with reality. Preparation in these areas will reduce the effectiveness of the RDD and may even reduce the possibility of its use.

Hart, M

2002-11-08T23:59:59.000Z

207

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

208

DOE N 435.1, Contact-Handled and Remote-Handled Transuranic Waste Packaging  

Directives, Delegations, and Requirements

Provides specific instructions for packaging and/or repackaging contact-handled transuranic (CH-TRU) and remote-handled transuranic (RH-TRU) waste in a manner ...

2011-08-15T23:59:59.000Z

209

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

210

FMAC: Coal-Handling Maintenance Guide  

Science Conference Proceedings (OSTI)

The Coal Handling System Maintenance Guide provides fossil plant maintenance personnel with current maintenance information on this system. This report will assist plant maintenance personnel in improving the reliability of and reducing the maintenance costs for the coal handling system.

2006-12-22T23:59:59.000Z

211

PRELIMINARY SURVEY OF TEXAS CITY CHEMICALS, INC.  

Office of Legacy Management (LM)

(DOE), a preliminary survey was performed at the Borden Chemical Division plant in Texas City, Texas (see Fig. l), on November 17, 1977, to assess the radiological status of those...

212

ENDTOEND REQUEST HANDLING IN DISTRIBUTED VIDEOONDEMAND SYSTEMS  

E-Print Network (OSTI)

that adequate storage and stream handling capacities are present at the servers in the remote clusters. In addition, the remote sites act as sources of supplemental request handling capacity minimizing overall service is delivered only when the local cluster can­ not handle the load. Between the two remote clusters

Mundur, Padma

213

PNNL: Available Technologies: Nuclear & Radiological  

PNNL has more than 40 years of experience in radiological science and radiochemical separations based on its activities at the U.S. Department of ...

214

Radiological Toolbox User's Manual  

Science Conference Proceedings (OSTI)

A toolbox of radiological data has been assembled to provide users access to the physical, chemical, anatomical, physiological and mathematical data relevant to the radiation protection of workers and member of the public. The software runs on a PC and provides users, through a single graphical interface, quick access to contemporary data and the means to extract these data for further computations and analysis. The numerical data, for the most part, are stored within databases in SI units. However, the user can display and extract values using non-SI units. This is the first release of the toolbox which was developed for the U.S. Nuclear Regulatory Commission.

Eckerman, KF

2004-07-01T23:59:59.000Z

215

Smart Radiological Dosimeter  

DOE Patents (OSTI)

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

Kosslow, William J.; Bandzuch, Gregory S.

2004-07-20T23:59:59.000Z

216

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

217

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,

218

Depleted UF6 Production and Handling Slide Presentation  

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

Production and Handling Depleted UF6 Production and Handling Slide Presentation An online slide presentation about production and handling of depleted UF6, from mining of uranium...

219

CANISTER HANDLING FACILITY DESCRIPTION DOCUMENT  

Science Conference Proceedings (OSTI)

The purpose of this facility description document (FDD) is to establish requirements and associated bases that drive the design of the Canister Handling Facility (CHF), which will allow the design effort to proceed to license application. This FDD will be revised at strategic points as the design matures. This FDD identifies the requirements and describes the facility design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This FDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This FDD is part of an iterative design process. It leads the design process with regard to the flowdown of upper tier requirements onto the facility. Knowledge of these requirements is essential in performing the design process. The FDD follows the design with regard to the description of the facility. The description provided in this FDD reflects the current results of the design process.

J.F. Beesley

2005-04-21T23:59:59.000Z

220

Cask system design guidance for robotic handling  

SciTech Connect

Remote automated cask handling has the potential to reduce both the occupational exposure and the time required to process a nuclear waste transport cask at a handling facility. The ongoing Advanced Handling Technologies Project (AHTP) at Sandia National Laboratories is described. AHTP was initiated to explore the use of advanced robotic systems to perform cask handling operations at handling facilities for radioactive waste, and to provide guidance to cask designers regarding the impact of robotic handling on cask design. The proof-of-concept robotic systems developed in AHTP are intended to extrapolate from currently available commercial systems to the systems that will be available by the time that a repository would be open for operation. The project investigates those cask handling operations that would be performed at a nuclear waste repository facility during cask receiving and handling. The ongoing AHTP indicates that design guidance, rather than design specification, is appropriate, since the requirements for robotic handling do not place severe restrictions on cask design but rather focus on attention to detail and design for limited dexterity. The cask system design features that facilitate robotic handling operations are discussed, and results obtained from AHTP design and operation experience are summarized. The application of these design considerations is illustrated by discussion of the robot systems and their operation on cask feature mock-ups used in the AHTP project. 11 refs., 11 figs.

Griesmeyer, J.M.; Drotning, W.D.; Morimoto, A.K.; Bennett, P.C.

1990-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "handled radiological surveys" 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

CARRIER/CASK HANDLING SYSTEM DESCRIPTION DOCUMENT  

Science Conference Proceedings (OSTI)

The Carrier/Cask Handling System receives casks on railcars and legal-weight trucks (LWTs) (transporters) that transport loaded casks and empty overpacks to the Monitored Geologic Repository (MGR) from the Carrier/Cask Transport System. Casks that come to the MGR on heavy-haul trucks (HHTs) are transferred onto railcars before being brought into the Carrier/Cask Handling System. The system is the interfacing system between the railcars and LWTs and the Assembly Transfer System (ATS) and Canister Transfer System (CTS). The Carrier/Cask Handling System removes loaded casks from the cask transporters and transfers the casks to a transfer cart for either the ATS or CTS, as appropriate, based on cask contents. The Carrier/Cask Handling System receives the returned empty casks from the ATS and CTS and mounts the casks back onto the transporters for reshipment. If necessary, the Carrier/Cask Handling System can also mount loaded casks back onto the transporters and remove empty casks from the transporters. The Carrier/Cask Handling System receives overpacks from the ATS loaded with canisters that have been cut open and emptied and mounts the overpacks back onto the transporters for disposal. If necessary, the Carrier/Cask Handling System can also mount empty overpacks back onto the transporters and remove loaded overpacks from them. The Carrier/Cask Handling System is located within the Carrier Bay of the Waste Handling Building System. The system consists of cranes, hoists, manipulators, and supporting equipment. The Carrier/Cask Handling System is designed with the tooling and fixtures necessary for handling a variety of casks. The Carrier/Cask Handling System performance and reliability are sufficient to support the shipping and emplacement schedules for the MGR. The Carrier/Cask Handling System interfaces with the Carrier/Cask Transport System, ATS, and CTS as noted above. The Carrier/Cask Handling System interfaces with the Waste Handling Building System for building structures and space allocations. The Carrier/Cask Handling System interfaces with the Waste Handling Building Electrical System for electrical power.

E.F. Loros

2000-06-23T23:59:59.000Z

222

EA-1900: Radiological Work and Storage Building at the Knolls Atomic Power  

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

0: Radiological Work and Storage Building at the Knolls 0: Radiological Work and Storage Building at the Knolls Atomic Power Laboratory Kesselring Site, West Milton, New York EA-1900: Radiological Work and Storage Building at the Knolls Atomic Power Laboratory Kesselring Site, West Milton, New York Summary The Naval Nuclear Propulsion Program (NNPP) intent to prepare an Environmental Assessment for a radiological work and storage building at the Knolls Atomic Power Laboratory (Kesselring Site in West Milton, New York. A new facility is needed to streamline radioactive material handling and storage operations, permit demolition of aging facilities, and accommodate efficient maintenance of existing nuclear reactors. Public Comment Opportunities None available at this time. Documents Available for Download July 16, 2012

223

Nuclear Radiological Threat Task Force Established | National...  

National Nuclear Security Administration (NNSA)

Force Established Nuclear Radiological Threat Task Force Established November 03, 2003 Washington, DC Nuclear Radiological Threat Task Force Established NNSA's Administrator...

224

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

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

Radiological Controls - Idaho Accelerated Retrieval Project Phase II CRAD, Radiological Controls - Idaho Accelerated Retrieval Project Phase II February 2006 A section of Appendix...

225

Concerns Regarding Lead Contamination and Radiological Controls...  

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

Home Concerns Regarding Lead Contamination and Radiological Controls at the Nevada Test Site, INS-O-06-02 Concerns Regarding Lead Contamination and Radiological Controls at...

226

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.

227

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.

228

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.

229

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

230

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

231

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

232

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

233

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.

234

Scheduling coal handling processes using metaheuristics.  

E-Print Network (OSTI)

??The operational scheduling at coal handling facilities is of the utmost importance to ensure that the coal consuming processes are supplied with a constant feed… (more)

Conradie, David Gideon

2008-01-01T23:59:59.000Z

235

Waste management handling in Benin City.  

E-Print Network (OSTI)

??The researcher was inspired by the topic “Waste management handling” due to the ugly situa-tion of waste being littered all over the city, which have… (more)

Oseghale, Peter

2011-01-01T23:59:59.000Z

236

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

237

WASTE HANDLING BUILDING ELECTRICAL SYSTEM DESCRIPTION DOCUMENT  

SciTech Connect

The Waste Handling Building Electrical System performs the function of receiving, distributing, transforming, monitoring, and controlling AC and DC power to all waste handling building electrical loads. The system distributes normal electrical power to support all loads that are within the Waste Handling Building (WHB). The system also generates and distributes emergency power to support designated emergency loads within the WHB within specified time limits. The system provides the capability to transfer between normal and emergency power. The system provides emergency power via independent and physically separated distribution feeds from the normal supply. The designated emergency electrical equipment will be designed to operate during and after design basis events (DBEs). The system also provides lighting, grounding, and lightning protection for the Waste Handling Building. The system is located in the Waste Handling Building System. The system consists of a diesel generator, power distribution cables, transformers, switch gear, motor controllers, power panel boards, lighting panel boards, lighting equipment, lightning protection equipment, control cabling, and grounding system. Emergency power is generated with a diesel generator located in a QL-2 structure and connected to the QL-2 bus. The Waste Handling Building Electrical System distributes and controls primary power to acceptable industry standards, and with a dependability compatible with waste handling building reliability objectives for non-safety electrical loads. It also generates and distributes emergency power to the designated emergency loads. The Waste Handling Building Electrical System receives power from the Site Electrical Power System. The primary material handling power interfaces include the Carrier/Cask Handling System, Canister Transfer System, Assembly Transfer System, Waste Package Remediation System, and Disposal Container Handling Systems. The system interfaces with the MGR Operations Monitoring and Control System for supervisory monitoring and control signals. The system interfaces with all facility support loads such as heating, ventilation, and air conditioning, office, fire protection, monitoring and control, safeguards and security, and communications subsystems.

S.C. Khamamkar

2000-06-23T23:59:59.000Z

238

Nuclear Maintenance Applications Center: Nuclear Fuel Handling Equipment Application and Maintenance Guide: Fuel Handling Equipment Guide  

Science Conference Proceedings (OSTI)

Fuel handling is a critical task during a nuclear power plant refueling outage. The proper operation of fuel handling equipment (such as fuel handling machines, fuel upending machines, fuel transfer carriages, and fuel elevators) is important to a successful refueling outage and to preparing fuel for eventual disposal.BackgroundThe fuel handling system contains the components used to move fuel from the time that the new fuel is received until the spent fuel ...

2013-12-13T23:59:59.000Z

239

Assessment of Coal Handling for Fuel Flexibility  

Science Conference Proceedings (OSTI)

To reduce total generating costs, power generators may use multiple solid fuels. This study is a preliminary investigation of the methods and costs of handling multiple solid fuels. An important byproduct of the study was some of the first-ever systematic comparisons of coal handling costs at a sample of plants.

1998-09-03T23:59:59.000Z

240

Constraint Handling in Particle Swarm Optimization  

Science Conference Proceedings (OSTI)

In this article, the authors propose a particle swarm optimization PSO for constrained optimization. The proposed PSO adopts a multiobjective approach to constraint handling. Procedures to update the feasible and infeasible personal best are designed ... Keywords: Constrained Optimization, Constraint Handling, Feasible Personal Best, Infeasible Personal Best, Multiobjective Optimization, Particle Swarm Optimization

Wen Fung Leong; Gary G. Yen

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "handled radiological surveys" 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

Preliminary assessment of radiological doses in alternative waste management systems without an MRS facility  

SciTech Connect

This report presents generic analyses of radiological dose impacts of nine hypothetical changes in the operation of a waste management system without a monitored retrievable storage (MRS) facility. The waste management activities examined in this study include those for handling commercial spent fuel at nuclear power reactors and at the surface facilities of a deep geologic repository, and the transportation of spent fuel by rail and truck between the reactors and the repository. In the reference study system, the radiological doses to the public and to the occupational workers are low, about 170 person-rem/1000 metric ton of uranium (MTU) handled with 70% of the fuel transported by rail and 30% by truck. The radiological doses to the public are almost entirely from transportation, whereas the doses to the occupational workers are highest at the reactors and the repository. Operating alternatives examined included using larger transportation casks, marshaling rail cars into multicar dedicated trains, consolidating spent fuel at the reactors, and wet or dry transfer options of spent fuel from dry storage casks. The largest contribution to radiological doses per unit of spent fuel for both the public and occupational workers would result from use of truck transportation casks, which are smaller than rail casks. Thus, reducing the number of shipments by increasing cask sizes and capacities (which also would reduce the number of casks to be handled at the terminals) would reduce the radiological doses in all cases. Consolidating spent fuel at the reactors would reduce the radiological doses to the public but would increase the doses to the occupational workers at the reactors.

Schneider, K.J.; Pelto, P.J.; Daling, P.M.; Lavender, J.C.; Fecht, B.A.

1986-06-01T23:59:59.000Z

242

Radiological Threat Reduction: Dealing with Dirty Bombs  

E-Print Network (OSTI)

Nonproliferation and National Security Department May 2, 2007 #12;Topics What is a Radiological Dispersal Device

Homes, Christopher C.

243

Homeland Security Chemical/Biological/Radiological/Nuclear ...  

Science Conference Proceedings (OSTI)

... Information at NIST. Homeland Security Chemical/Biological/Radiological/ Nuclear/Explosives (CBRNE) Information at NIST. ...

2010-09-24T23:59:59.000Z

244

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.

245

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...

246

Marshall Islands radiological followup  

SciTech Connect

In August, 1968, President Johnson announced that the people of Bikini Atoll would be able to return to their homeland. Thereafter, similar approval was given for the return of the peoples of Enewetak. These two regions, which comprised the Pacific Nuclear Testing Areas from 1946 to 1958, will probably be repopulated by the original inhabitants and their families within the next year. As part of its continuing responsibility to insure the public health and safety in connection with the nuclear programs under its sponsorship, ERDA (formerly AEC) has contracted Brookhaven National Laboratory to establish radiological safety and environmental monitoring programs for the returning Bikini and Enewetak peoples. These programs are described in the following paper. They are designed to define the external radiation environment, assess radiation doses from internal emitters in the human food chain, make long range predictions of total doses and dose commitments to individuals and to each population group, and to suggest actions which will minimize doses via the more significant pathways. (auth)

Greenhouse, N.A.; McCraw, T.F.

1976-04-30T23:59:59.000Z

247

Radiological-dose assessments of atolls in the northern Marshall Islands  

Science Conference Proceedings (OSTI)

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

Robison, W.L.

1983-04-01T23:59:59.000Z

248

Radiological training for tritium facilities  

Science Conference Proceedings (OSTI)

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

249

FDH radiological design review guidelines  

SciTech Connect

These guidelines discuss in more detail the radiological design review process used by the Project Hanford Management Contractors as described in HNF-PRO-1622, Radiological Design Review Process. They are intended to supplement the procedure by providing background information on the design review process and providing a ready source of information to design reviewers. The guidelines are not intended to contain all the information in the procedure, but at points, in order to maintain continuity, they contain some of the same information.

Millsap, W.J.

1998-09-29T23:59:59.000Z

250

METHODS OF HANDLING AND LAUNDERING BERYLLIUM-CONTAMINATED GARMENTS  

SciTech Connect

In beryllium industries, it has been the general practice to supply workers with protective clothing. Problems in handling and laundering this clothing were investigated. These problems include: potential hazard to laundry workers and subsequent wearers of the clothing, special laundering techniques, methods to determine the degree of contamination on garments, and determining the most desirable types of garments for the purpose. Four methods to determine the degree of contamination discussed include the shake test, the vacuum test, the rinse test, and the smear test. Assuming conventional laundering procedures have been used, the potential hazard to subsequent wearers of the garment is minimal. Standards for determining adequacy of laundry are suggested. These ar 0.1 mu g Be/cm/sup 2/ as determined by the vacuum test, or 200 mu g Be/garment as determined by the rinse test. Possible hazard to those handling contaminated garments could be significant. This hazard is best controlled simply by use of wet methods. Included in this report is the summary of a survey conducted to determine how these problems are handled in other beryllium industries. (auth)

Cohen, J.J.

1963-04-01T23:59:59.000Z

251

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

252

DOE standard: Radiological control  

Science Conference Proceedings (OSTI)

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

Not Available

1999-07-01T23:59:59.000Z

253

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

SciTech Connect

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

E.N. Bailey

2009-03-18T23:59:59.000Z

254

INTERNATIONAL SYMPOSIUM ON PROCESSING AND HANDLING ...  

Science Conference Proceedings (OSTI)

... Battle, DuPont White Pigments and Mineral Products, Edge Moor Plant, Edge Moor, ... PHYSICAL EXAMINATION AND HANDLING OF WET AND DRY C60: K. ... part of a modern ironmaking blast furnace with high pulverised coal injection, ...

255

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

256

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

257

Radiological control manual. Revision 1  

SciTech Connect

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

Kloepping, R.

1996-05-01T23:59:59.000Z

258

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

259

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

260

LM Records Handling System (LMRHS01) - Rocky Flats Environmental...  

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

here Home LM Records Handling System (LMRHS01) - Rocky Flats Environmental Records Database, Office of Legacy Management LM Records Handling System (LMRHS01) - Rocky Flats...

Note: This page contains sample records for the topic "handled radiological surveys" 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

LM Records Handling System (LMRHS01) - Electronic Records Keeping...  

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

Publications LM Records Handling System (LMRHS01) - Rocky Flats Environmental Records Database, Office of Legacy Management LM Records Handling System (LMRHS01) - Energy Employees...

262

T-656: Microsoft Office Visio DXF File Handling Arbitrary Code...  

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

6: Microsoft Office Visio DXF File Handling Arbitrary Code Execution Vulnerability T-656: Microsoft Office Visio DXF File Handling Arbitrary Code Execution Vulnerability June 28,...

263

Nuclear Radiological Threat Task Force Established | National...  

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

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

264

NNSA Conducts Radiological Response Training in Kazakhstan |...  

National Nuclear Security Administration (NNSA)

Radiological Response Training in Kazakhstan | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy...

265

NNSA Conducts International Radiological Response Training in...  

National Nuclear Security Administration (NNSA)

International Radiological Response Training in Vienna | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear...

266

International Data on Radiological Sources  

SciTech Connect

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

Martha Finck; Margaret Goldberg

2010-07-01T23:59:59.000Z

267

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

Science Conference Proceedings (OSTI)

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

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

1994-07-01T23:59:59.000Z

268

Evaluation of a Mobile Hot Cell Technology for Processing Idaho National Laboratory Remote-Handled Wastes  

SciTech Connect

The Idaho National Laboratory (INL) currently does not have the necessary capabilities to process all remote-handled wastes resulting from the Laboratory’s nuclear-related missions. Over the years, various U.S. Department of Energy (DOE)-sponsored programs undertaken at the INL have produced radioactive wastes and other materials that are categorized as remote-handled (contact radiological dose rate > 200 mR/hr). These materials include Spent Nuclear Fuel (SNF), transuranic (TRU) waste, waste requiring geological disposal, low-level waste (LLW), mixed waste (both radioactive and hazardous per the Resource Conservation and Recovery Act [RCRA]), and activated and/or radioactively-contaminated reactor components. The waste consists primarily of uranium, plutonium, other TRU isotopes, and shorter-lived isotopes such as cesium and cobalt with radiological dose rates up to 20,000 R/hr. The hazardous constituents in the waste consist primarily of reactive metals (i.e., sodium and sodium-potassium alloy [NaK]), which are reactive and ignitable per RCRA, making the waste difficult to handle and treat. A smaller portion of the waste is contaminated with other hazardous components (i.e., RCRA toxicity characteristic metals). Several analyses of alternatives to provide the required remote-handling and treatment capability to manage INL’s remote-handled waste have been conducted over the years and have included various options ranging from modification of existing hot cells to construction of new hot cells. Previous analyses have identified a mobile processing unit as an alternative for providing the required remote-handled waste processing capability; however, it was summarily dismissed as being a potentially viable alternative based on limitations of a specific design considered. In 2008 INL solicited expressions of interest from Vendors who could provide existing, demonstrated technology that could be applied to the retrieval, sorting, treatment (as required), and repackaging of INL remote-handled wastes. Based on review of the responses and the potential viability of a mobile hot cell technology, INL subsequently conducted a technology evaluation, including proof-of-process validation, to assess the feasibility of utilizing such a technology for processing INL’s remote-handled wastes to meet established regulatory milestones. The technology evaluation focused on specific application of a mobile hot cell technology to the conditions to be encountered at the INL and addressed details of previous technology deployment, required modifications to accommodate INL’s remote-handled waste, ability to meet DOE safety requirements, requirements for fabrication/construction/decontamination and dismantling, and risks and uncertainties associated with application of the technology to INL’s remote-handled waste. The large capital costs associated with establishing a fixed asset to process INL’s remote-handled waste, the relatively small total volume of waste to be processed when compared to other waste streams through the complex, and competing mission-related needs has made it extremely difficult to secure the necessary support to advance the project. Because of this constraint, alternative contract structures were also explored as part of the technology evaluation wherein the impact of a large capital investment could be lessened.

B.J. Orchard; L.A. Harvego; R.P. Miklos; F. Yapuncich; L. Care

2009-03-01T23:59:59.000Z

269

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

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

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

270

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

271

Release criteria and pathway analysis for radiological remediation  

Science Conference Proceedings (OSTI)

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

272

Storage and Handling | Department of Energy  

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

Storage and Handling Storage and Handling Storage and Handling Records Management Procedures for Storage, Transfer & Retrieval of Records from the Washington National Records Center (WNRC) or Legacy Management Business Center RETIREMENT OF RECORDS: 1. The Program Office is responsible for originating the Records Transmittal and Receipt Form SF-135 (PDF, 107KB), and sending it to IM-23 at doerha@hq.doe.gov for approval. 2. IM-23 reviews the SF-135 for completeness/correctness (Coordinates with the originating office by email if more information is required.). 3. IM-23 sends the SF-135 for approval to WNRC. PREPARING RECORDS FOR THE TRANSFER TO THE WNRC: 1. Use your organization's Records Information Disposition Schedule (RIDS) as a guide toward assessing records for storage. Refer to DOE O

273

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:

274

Recommendations for cask features for robotic handling from the Advanced Handling Technology Project  

SciTech Connect

This report describes the current status and recent progress in the Advanced Handling Technology Project (AHTP) initiated to explore the use of advanced robotic systems and handling technologies to perform automated cask handling operations at radioactive waste handling facilities, and to provide guidance to cask designers on the impact of robotic handling on cask design. Current AHTP tasks have developed system mock-ups to investigate robotic manipulation of impact limiters and cask tiedowns. In addition, cask uprighting and transport, using computer control of a bridge crane and robot, were performed to demonstrate the high speed cask transport operation possible under computer control. All of the current AHTP tasks involving manipulation of impact limiters and tiedowns require robotic operations using a torque wrench. To perform these operations, a pneumatic torque wrench and control system were integrated into the tool suite and control architecture of the gantry robot. The use of captured fasteners is briefly discussed as an area where alternative cask design preferences have resulted from the influence of guidance for robotic handling vs traditional operations experience. Specific robotic handling experiences with these system mock-ups highlight a number of continually recurring design principles: (1) robotic handling feasibility is improved by mechanical designs which emphasize operation with limited dexterity in constrained workspaces; (2) clearances, tolerances, and chamfers must allow for operations under actual conditions with consideration for misalignment and imprecise fixturing; (3) successful robotic handling is enhanced by including design detail in representations for model-based control; (4) robotic handling and overall quality assurance are improved by designs which eliminate the use of loose, disassembled parts. 8 refs., 15 figs.

Drotning, W.

1991-02-01T23:59:59.000Z

275

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

276

RADIOLOGICAL SURVEY OF SITE A AND PLOT M  

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

as the tritiated water source is depleted by both horizontal and vertical migration and radioactive decay. Since substantial amounts of tritium still remain below the surface of...

277

Radiological Habits Survey: Dumfries and Galloway Coast, 2007  

E-Print Network (OSTI)

....................................................25 4.8 Internal exposure................................................................. AQUATIC RADIATION PATHWAYS ...........................................................................17 4

278

Safe Handling Of Nuclear Substances Undergraduate Laboratories  

E-Print Network (OSTI)

Safe Handling Of Nuclear Substances Undergraduate Laboratories There are three main hazards associated with working with unsealed sources of nuclear substances. These are: 1. Skin contamination and/or deposition of the nuclear substance in the body 2. Spread of contamination 3. External radiation In teaching

Beaumont, Christopher

279

Water Management in Ash-Handling Systems  

Science Conference Proceedings (OSTI)

In 1980, EPA proposed revisions to the effluent standards and guidelines for fly ash and bottom ash transport systems. This review of utility practices provides a comprehensive account of the operation of and problems experienced in wet handling of bottom and fly ash and suggests areas for further research.

1987-08-24T23:59:59.000Z

280

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

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


281

Radiological 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

282

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

283

Good Practices for Ocupational Radiological Protection in Plutonium Facilities  

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

Not Measurement Not Measurement Sensitive DOE- STD-1128-2013 April 2013 DOE STANDARD GOOD PRACTICES FOR OCCUPATIONAL RADIOLOGICAL PROTECTION IN PLUTONIUM FACILITIES U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1128-2013 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ ii DOE-STD-1128-2013 Foreword This Technical Standard does not contain any new requirements. Its purpose is to provide information on good practices, update existing reference material, and discuss practical lessons learned relevant to the safe handling of plutonium. U.S. Department of Energy (DOE) health

284

NV/YMP radiological control manual, Revision 2  

Science Conference Proceedings (OSTI)

The Nevada Test Site (NTS) and the adjacent Yucca Mountain Project (YMP) are located in Nye County, Nevada. The NTS has been the primary location for testing nuclear explosives in the continental US since 1951. Current activities include operating low-level radioactive and mixed waste disposal facilities for US defense-generated waste, assembly/disassembly of special experiments, surface cleanup and site characterization of contaminated land areas, and non-nuclear test operations such as controlled spills of hazardous materials at the hazardous Materials (HAZMAT) Spill Center (HSC). Currently, the major potential for occupational radiation exposure is associated with the burial of low-level nuclear waste and the handling of radioactive sources. Planned future remediation of contaminated land areas may also result in radiological exposures. The NV/YMP Radiological Control Manual, Revision 2, represents DOE-accepted guidelines and best practices for implementing Nevada Test Site and Yucca Mountain Project Radiation Protection Programs in accordance with the requirements of Title 10 Code of Federal Regulations Part 835, Occupational Radiation Protection. These programs provide protection for approximately 3,000 employees and visitors annually and include coverage for the on-site activities for both personnel and the environment. The personnel protection effort includes a DOE Laboratory Accreditation Program accredited dosimetry and personnel bioassay programs including in-vivo counting, routine workplace air sampling, personnel monitoring, and programmatic and job-specific As Low as Reasonably Achievable considerations.

Gile, A.L. [comp.] [comp.

1996-11-01T23:59:59.000Z

285

Laundered protective clothing survey  

SciTech Connect

It is considered appropriate occasionally to make independent checks on the effectiveness of the plant laundry in removing radioactive contamination from plant-issue protective clothing. Previous surveys have offered constructive criticism resulting in improved handling of high level and soft beta contaminated clothing and incorporation in new designs of ventilating and air sampling recommendations. Recurrently the adequacy of laundry reject limits is questioned, and only recently an accurate, special study resulted in relaxed limits for Metal Preparation area clothing. A current question concerns the advisability of determining the reject level on the beta-gamma monitor more frequently than once a day. 2 tabs.

Clukey, H.V.

1952-10-15T23:59:59.000Z

286

DOE - Office of Legacy Management -- Lowman Mill Site - ID 01  

Office of Legacy Management (LM)

Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Lowman, Idaho, Disposal Site Documents Related to Lowman Mill Site Historical documents may contain...

287

DOE - Office of Legacy Management -- Falls City Mill Site - TX...  

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

Materials Handled: Radiological Survey(s): Site Status: Also see Falls City, Texas, Disposal Site Documents Related to Falls City Mill Site Data Validation Package for...

288

History of remote handling at LAMPF  

SciTech Connect

A portable remote-handling system (Monitor) has been developed for performing remote maintenance on radioactive experimental facilities at the Clinton P. Anderson Meson Physics Facility (LAMPF). This system has been continually improved since its implementation in 1976. The present system has performed highly sophisticated tasks in improving and maintaining the LAMPF experimental facility. Unlike conventional hot-cell remote-handling technology, the Monitor system is portable and highly flexible, thereby allowing quick response to unforeseen tasks with minimal planning and/or special tooling. In addition to performing routine maintenance and repairs, the Monitor system is capable of performing major revisions and improvements to current facilities, keeping pace with new experimental requirements.

Grisham, D.L.; Lambert, J.E.

1982-01-01T23:59:59.000Z

289

Fuel handling apparatus for a nuclear reactor  

DOE Patents (OSTI)

Fuel handling apparatus for transporting fuel elements into and out of a nuclear reactor and transporting them within the reactor vessel extends through a penetration in the side of the reactor vessel. A lateral transport device carries the fuel elements laterally within the vessel and through the opening in the side of the vessel, and a reversible lifting device raises and lowers the fuel elements. In the preferred embodiment, the lifting device is supported by a pair of pivot arms.

Hawke, Basil C. (Solana Beach, CA)

1987-01-01T23:59:59.000Z

290

Vestibule and Cask Preparation Mechanical Handling Calculation  

SciTech Connect

The scope of this document is to develop the size, operational envelopes, and major requirements of the equipment to be used in the vestibule, cask preparation area, and the crane maintenance area of the Fuel Handling Facility. This calculation is intended to support the License Application (LA) submittal of December 2004, in accordance with the directive given by DOE correspondence received on the 27th of January 2004 entitled: ''Authorization for Bechtel SAIC Company L.L.C. to Include a Bare Fuel Handling Facility and Increased Aging Capacity in the License Application, Contract Number DE-AC28-01R W12101'' (Ref. 167124). This correspondence was appended by further correspondence received on the 19th of February 2004 entitled: ''Technical Direction to Bechtel SAIC Company L.L. C. for Surface Facility Improvements, Contract Number DE-AC28-01R W12101; TDL No. 04-024'' (Ref. 16875 1). These documents give the authorization for a Fuel Handling Facility to be included in the baseline. The limitations of this preliminary calculation lie within the assumptions of section 5 , as this calculation is part of an evolutionary design process.

N. Ambre

2004-05-26T23:59:59.000Z

291

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

292

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

293

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

294

Nuclear and Radiological Material Security | National Nuclear...  

National Nuclear Security Administration (NNSA)

to intensive site security efforts, NNSA is also working to build international standards and criteria for nuclear and radiological security. This includes NNSA's work to...

295

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

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

The program concludes with an opportunity to apply new knowledge and decision-making skills in a series of six simulated patient case studies depicting hypothetical radiological...

296

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

297

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

National Nuclear Security Administration (NNSA)

advice for both domestic and international nuclear or radiological incidents. It is led by a Senior Energy Official who runs the NNSA field operation and who coordinates NNSA...

298

RADIOLOGICAL ASSESSMENT OF BALLOD AND ASSOCIATES PROPERTY  

Office of Legacy Management (LM)

Cotton, Robert Gosslee, Jonathan Sowell, Clayton Weaver FINAL REPORT July 30, 1981 Work performed by Radiological Site Assessment Program Manpower Education, Research, and...

299

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

300

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

Note: This page contains sample records for the topic "handled radiological surveys" 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

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

302

Human error contribution to nuclear materials-handling events  

E-Print Network (OSTI)

This thesis analyzes a sample of 15 fuel-handling events from the past ten years at commercial nuclear reactors with significant human error contributions in order to detail the contribution of human error to fuel-handling ...

Sutton, Bradley (Bradley Jordan)

2007-01-01T23:59:59.000Z

303

Innovative Methods for Corn Stover Collecting, Handling, Storing and Transporting  

DOE Green Energy (OSTI)

Investigation of innovative methods for collecting, handling, storing, and transporting corn stover for potential use for production of cellulosic ethanol.

Atchison, J. E.; Hettenhaus, J. R.

2003-03-01T23:59:59.000Z

304

Chris Densham T2K Target Remote Handling  

E-Print Network (OSTI)

Chris Densham T2K Target Remote Handling CJ Densham, MD Fitton, M Baldwin, M Woodward Rutherford are handled by remote controlled crane. Concrete shield Horns are shielded by iron and concrete shields A numerical controlled crane is used in the TS. A remote handling machine is attached to this crane. Crane

McDonald, Kirk

305

The Remote-Handled TRU Waste Program  

SciTech Connect

RH TRU Waste is radioactive waste that requires shielding in addition to that provided by the container to protect people nearby from radiation exposure. By definition, the radiation dose rate at the outer surface of the container is greater than 200 millirem per hour and less than 1,000 rem per hour. The DOE is proposing a process for the characterization of RH TRU waste planned for disposal in the WIPP. This characterization process represents a performance-driven approach that satisfies the requirements of the New Mexico Hazardous Waste Act, the Environmental Protection Agency (EPA) regulations for WIPP long-term performance, the transportation requirements of the Nuclear Regulatory Commission (NRC) and the Department of Transportation, as well as the technical safety requirements of RH TRU waste handling. The transportation, management and disposal of RH TRU waste is regulated by external government agencies as well as by the DOE itself. Externally, the characterization of RH-TRU waste for disposal at the WIPP is regulated by 20.4.1.500 New Mexico Administrative Code (incorporating 40 CFR 261.13) for the hazardous constituents and 40 CFR 194.24 for the radioactive constituents. The Nuclear Regulatory Commission certifies the shipping casks and the transportation system must meet DOT regulations. Internally, the DOE evaluates the environmental impacts of RH TRU waste transportation, handling and disposal through its National Environmental Policy Act program. The operational safety is assessed in the RH TRU Waste Safety Analysis Report, to be approved by the DOE. The WIPP has prepared a modification request to the Hazardous Waste Facility Permit that includes modifications to the WIPP facility for the safe receipt and handling of RH TRU waste and the addition of an RH TRU waste analysis plan. Modifications to the facility include systems and equipment for safe handling of RHTRU containers. Two shipping casks are to be used to optimize RH TRU was te throughput: the RH-72B and the CNS 10-160B transportation casks. Additionally, a draft Notification of Proposed Change to the EPA 40 CFR 194 Certification of the WIPP has been prepared, which contains a proposal for the RH TRU characterization program for compliance with the EPA requirements.

Gist, C. S.; Plum, H. L.; Wu, C. F.; Most, W. A.; Burrington, T. P.; Spangler, L. R.

2002-02-26T23:59:59.000Z

306

System for handling and storing radioactive waste  

DOE Patents (OSTI)

A system and method are claimed for handling and storing spent reactor fuel and other solid radioactive waste, including canisters to contain the elements of solid waste, storage racks to hold a plurality of such canisters, storage bays to store these racks in isolation by means of shielded doors in the bays. This system also includes means for remotely positioning the racks in the bays and an access tunnel within which the remotely operated means is located to position a rack in a selected bay. The modular type of these bays will facilitate the construction of additional bays and access tunnel extension.

Anderson, J.K.; Lindemann, P.E.

1982-07-19T23:59:59.000Z

307

Safety Advice for Storage and Handling of  

E-Print Network (OSTI)

"This document is intended for information only and sets out advice for the safe storage and handling of anhydrous titanium tetrachloride. The information contained in these guidelines is provided in good faith and, while it is accurate as far as the authors are aware, no representations or warranties are made with regards to its completeness. For guidance on individual circumstances specific advice should be sought and in all cases the applicable national, European and international regulations should always be complied with. No responsibility will be assumed by Cefic in relation to the information

unknown authors

2007-01-01T23:59:59.000Z

308

System for handling and storing radioactive waste  

DOE Patents (OSTI)

A system and method for handling and storing spent reactor fuel and other solid radioactive waste, including canisters to contain the elements of solid waste, storage racks to hold a plurality of such canisters, storage bays to store these racks in isolation by means of shielded doors in the bays. This system also includes means for remotely positioning the racks in the bays and an access tunnel within which the remotely operated means is located to position a rack in a selected bay. The modular type of these bays will facilitate the construction of additional bays and access tunnel extension.

Anderson, John K. (San Diego, CA); Lindemann, Paul E. (Escondido, CA)

1984-01-01T23:59:59.000Z

309

NUCLEAR ENGINEERING & RADIOLOG SC BSE Plan Requirements  

E-Print Network (OSTI)

NUCLEAR ENGINEERING & RADIOLOG SC BSE Plan Requirements 1 Campus: UMICH RG = Requirement Group Career: UENG RQ = Requirement Program: LN = Line Plan: 6000BSE RG 6412 NUCLEAR ENGINEERING no exceptions here) RG 6521 NUCLEAR ENGINEERING AND RADIOLOGICAL SCIENCES RESIDENCY, GPA REQUIREMENTS Effective

Shyy, Wei

310

Nevada Test Site Radiological Control Manual  

Science Conference Proceedings (OSTI)

This document supersedes DOE/NV/25946--801, “Nevada Test Site Radiological Control Manual,” Revision 0 issued in October 2009. Brief Description of Revision: A minor revision to correct oversights made during revision to incorporate the 10 CFR 835 Update; and for use as a reference document for Tenant Organization Radiological Protection Programs.

Radiological Control Managers' Council Nevada Test Site

2010-02-09T23:59:59.000Z

311

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

312

NNSA Conducts Radiological Training in Slovenia | National Nuclear...  

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

Blog > NNSA Conducts Radiological Training in Slovenia NNSA Conducts Radiological Training in Slovenia Posted By Office of Public Affairs NNSA Blog NNSA today concluded...

313

Process Knowledge Summary Report for Materials and Fuels Complex Contact-Handled Transuranic Debris Waste  

SciTech Connect

This Process Knowledge Summary Report summarizes the information collected to satisfy the transportation and waste acceptance requirements for the transfer of transuranic (TRU) waste between the Materials and Fuels Complex (MFC) and the Advanced Mixed Waste Treatment Project (AMWTP). The information collected includes documentation that addresses the requirements for AMWTP and the applicable portion of their Resource Conservation and Recovery Act permits for receipt and treatment of TRU debris waste in AMWTP. This report has been prepared for contact-handled TRU debris waste generated by the Idaho National Laboratory at MFC. The TRU debris waste will be shipped to AMWTP for purposes of supercompaction. This Process Knowledge Summary Report includes information regarding, but not limited to, the generation process, the physical form, radiological characteristics, and chemical contaminants of the TRU debris waste, prohibited items, and packaging configuration. This report, along with the referenced supporting documents, will create a defensible and auditable record for waste originating from MFC.

R. P. Grant; P. J. Crane; S. Butler; M. A. Henry

2010-02-01T23:59:59.000Z

314

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

Science Conference Proceedings (OSTI)

The objectives of the confirmatory surveys were to confirm that remedial actions had been effective in meeting established release criteria and that documentation accurately and adequately describes the final radiological conditions of the PSR Impacted Areas.

W.C. Adams

2008-06-27T23:59:59.000Z

315

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

316

Performance Assessment for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Facility  

Science Conference Proceedings (OSTI)

This performance assessment for the Remote-Handled Low-Level Radioactive Waste Disposal Facility at the Idaho National Laboratory documents the projected radiological dose impacts associated with the disposal of low-level radioactive waste at the facility. This assessment evaluates compliance with the applicable radiological criteria of the U.S. Department of Energy and the U.S. Environmental Protection Agency for protection of the public and the environment. The calculations involve modeling transport of radionuclides from buried waste to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses are calculated for both offsite receptors and individuals who inadvertently intrude into the waste after site closure. The results of the calculations are used to evaluate the future performance of the low-level radioactive waste disposal facility and to provide input for establishment of waste acceptance criteria. In addition, one-factor-at-a-time, Monte Carlo, and rank correlation analyses are included for sensitivity and uncertainty analysis. The comparison of the performance assessment results to the applicable performance objectives provides reasonable expectation that the performance objectives will be met

Annette L. Schafer; A. Jeffrey Sondrup; Arthur S. Rood

2012-05-01T23:59:59.000Z

317

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

318

Survey Expectations  

E-Print Network (OSTI)

of Michigan and is known as the Michigan survey, with many other similar surveys conducted across OECD countries so as to provide up to date information on consumer expectations. Questions on expectations are also sometimes included in panel surveys... be formed, do of course make it possible to assess whether, or how far, such expectations are well-founded by comparing the experiences of individual households with their prior expectations. A key aspect of the Michigan survey, and of many other more recent...

Pesaran, M Hashem; Weale, Martin

2006-03-14T23:59:59.000Z

319

Fuel handling system for a nuclear reactor  

DOE Patents (OSTI)

A pool type nuclear fission reactor has a core, with a plurality of core elements and a redan which confines coolant as a hot pool at a first end of the core separated from a cold pool at a second end of the core by the redan. A fuel handling system for use with such reactors comprises a core element storage basket located outside of the redan in the cold pool. An access passage is formed in the redan with a gate for opening and closing the passage to maintain the temperature differential between the hot pool and the cold pool. A mechanism is provided for opening and closing the gate. A lifting arm is also provided for manipulating the fuel core elements through the access passage between the storage basket and the core when the redan gate is open.

Saiveau, James G. (Hickory Hills, IL); Kann, William J. (Park Ridge, IL); Burelbach, James P. (Glen Ellyn, IL)

1986-01-01T23:59:59.000Z

320

Primer on tritium safe handling practices  

Science Conference Proceedings (OSTI)

This Primer is designed for use by operations and maintenance personnel to improve their knowledge of tritium safe handling practices. It is applicable to many job classifications and can be used as a reference for classroom work or for self-study. It is presented in general terms for use throughout the DOE Complex. After reading it, one should be able to: describe methods of measuring airborne tritium concentration; list types of protective clothing effective against tritium uptake from surface and airborne contamination; name two methods of reducing the body dose after a tritium uptake; describe the most common method for determining amount of tritium uptake in the body; describe steps to take following an accidental release of airborne tritium; describe the damage to metals that results from absorption of tritium; explain how washing hands or showering in cold water helps reduce tritium uptake; and describe how tritium exchanges with normal hydrogen in water and hydrocarbons.

Not Available

1994-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "handled radiological surveys" 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

METHOD AND APPARATUS FOR HANDLING RADIOACTIVE PRODUCTS  

DOE Patents (OSTI)

A device is described for handling fuel elements being discharged from a nuclear reactor. The device is adapted to be disposed beneath a reactor within the storage canal for spent fuel elements. The device is comprised essentially of a cylinder pivotally mounted to a base for rotational motion between a vertical position. where the mouth of the cylinder is in the top portion of the container for receiving a fuel element discharged from a reactor into the cylinder, and a horizontal position where the mouth of the cylinder is remote from the top portion of the container and the fuel element is discharged from the cylinder into the storage canal. The device is operated by hydraulic pressure means and is provided with a means to prevent contaminated primary liquid coolant in the reactor system from entering the storage canal with the spent fuel element.

Nicoll, D.

1959-02-24T23:59:59.000Z

322

Method and system rapid piece handling  

DOE Patents (OSTI)

The advent of high-speed fabric cutters has made necessary the development of automated techniques for the collection and sorting of garment pieces into collated piles of pieces ready for assembly. The present invention enables a new method for such handling and sorting of garment parts, and to apparatus capable of carrying out this new method. The common thread is the application of computer-controlled shuttling bins, capable of picking up a desired piece of fabric and dropping it in collated order for assembly. Such apparatus with appropriate computer control relieves the bottleneck now presented by the sorting and collation procedure, thus greatly increasing the overall rate at which garments can be assembled.

Spletzer, Barry L. (9504 Arvilla, NE, Albuquerque, NM 87111)

1996-01-01T23:59:59.000Z

323

Overview on Hydrate Coring, Handling and Analysis  

SciTech Connect

Gas hydrates are crystalline, ice-like compounds of gas and water molecules that are formed under certain thermodynamic conditions. Hydrate deposits occur naturally within ocean sediments just below the sea floor at temperatures and pressures existing below about 500 meters water depth. Gas hydrate is also stable in conjunction with the permafrost in the Arctic. Most marine gas hydrate is formed of microbially generated gas. It binds huge amounts of methane into the sediments. Worldwide, gas hydrate is estimated to hold about 1016 kg of organic carbon in the form of methane (Kvenvolden et al., 1993). Gas hydrate is one of the fossil fuel resources that is yet untapped, but may play a major role in meeting the energy challenge of this century. In June 2002, Westport Technology Center was requested by the Department of Energy (DOE) to prepare a ''Best Practices Manual on Gas Hydrate Coring, Handling and Analysis'' under Award No. DE-FC26-02NT41327. The scope of the task was specifically targeted for coring sediments with hydrates in Alaska, the Gulf of Mexico (GOM) and from the present Ocean Drilling Program (ODP) drillship. The specific subjects under this scope were defined in 3 stages as follows: Stage 1: Collect information on coring sediments with hydrates, core handling, core preservation, sample transportation, analysis of the core, and long term preservation. Stage 2: Provide copies of the first draft to a list of experts and stakeholders designated by DOE. Stage 3: Produce a second draft of the manual with benefit of input from external review for delivery. The manual provides an overview of existing information available in the published literature and reports on coring, analysis, preservation and transport of gas hydrates for laboratory analysis as of June 2003. The manual was delivered as draft version 3 to the DOE Project Manager for distribution in July 2003. This Final Report is provided for records purposes.

Jon Burger; Deepak Gupta; Patrick Jacobs; John Shillinglaw

2003-06-30T23:59:59.000Z

324

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

325

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

326

Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project  

Science Conference Proceedings (OSTI)

In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

Boyd D. Chirstensen

2012-08-01T23:59:59.000Z

327

Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project  

SciTech Connect

In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

Boyd D. Chirstensen

2012-04-01T23:59:59.000Z

328

Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project  

SciTech Connect

In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

Gary Mecham

2010-10-01T23:59:59.000Z

329

Fukushima Radiological Assessment Tool: Benchmarking Radiological Assessment and Dose Models using Fukushima Dataset  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) is developing the Fukushima Radiological Assessment Tool (FRAT), a comprehensive database and software application for accessing, analyzing, and interpreting data related to radiological releases from the Fukushima Daiichi Nuclear Power Plant (NPP). This report documents the development of the FRAT to support the benchmarking of emergency response and dose modeling codes used by nuclear power plants, using radiological data from the Fukushima ...

2013-07-31T23:59:59.000Z

330

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.

331

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

332

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

333

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

334

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

SciTech Connect

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

E.M. Harpenau

2010-02-19T23:59:59.000Z

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

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

337

Radiological Safety Training for Plutonium Facilities  

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

Change Notice No. 1. and Reaffirmation January 2007 DOE HANDBOOK Radiological Safety Training for Plutonium Facilities U.S. Department of Energy AREA TRNG Washington, D.C. 20585...

338

Radiological Safety Training for Plutonium Facilities  

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

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...

339

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

340

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

Note: This page contains sample records for the topic "handled radiological surveys" 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

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

342

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

343

Glove Perforations During Interventional Radiological Procedures  

SciTech Connect

Intact surgical gloves are essential to avoid contact with blood and other body fluids. The objective of this study was to estimate the incidence of glove perforations during interventional radiological procedures. In this study, a total of 758 gloves used in 94 interventional radiological procedures were examined for perforations. Eleven perforations were encountered, only one of which was of occult type. No significant difference in the frequency of glove perforation was found between the categories with varying time duration.

Leena, R. V., E-mail: leenarv_76@yahoo.co.uk; Shyamkumar, N. K. [Christian Medial College, Department of Radiodiagnosis (India)

2010-04-15T23:59:59.000Z

344

Nuclear Maintenance Applications Center: Material Handling Application Guide  

Science Conference Proceedings (OSTI)

Although the majority of the material handling activities at nuclear power plant sites are similar to the material handling activities in many other industries, there are several differences unique to the nuclear power industry. This guide to material handling equipment and its safe and effective operation at nuclear plants covers basic common practices while taking into account those unique differences. Recent industry experiences provide context for the guidance in the report.

2007-11-30T23:59:59.000Z

345

Nuclear Maintenance Applications Center: Material Handling Application Guide  

Science Conference Proceedings (OSTI)

BackgroundDuring 2005 and 2006, there were nine Institute of Nuclear Power Operations (INPO) operating events (OEs) from material handling incidents. A fatality occurred at Browns Ferry on Oct. 1, 2005, when a small article radiation monitor overturned while being moved on a material handling cart (INPO OE21844).More than 50 serious OEs concerning material handling activities have occurred in the past 10 years. The majority of these incidents involved the ...

2012-09-28T23:59:59.000Z

346

Remote-Handled Transuranic Content Codes  

SciTech Connect

The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document describes the inventory of RH-TRU waste within the transportation parameters specified by the Remote-Handled Transuranic Waste Authorized Methods for Payload Control (RH-TRAMPAC).1 The RH-TRAMPAC defines the allowable payload for the RH-TRU 72-B. This document is a catalog of RH-TRU 72-B authorized contents by site. A content code is defined by the following components: • A two-letter site abbreviation that designates the physical location of the generated/stored waste (e.g., ID for Idaho National Laboratory [INL]). The site-specific letter designations for each of the sites are provided in Table 1. • A three-digit code that designates the physical and chemical form of the waste (e.g., content code 317 denotes TRU Metal Waste). For RH-TRU waste to be transported in the RH-TRU 72-B, the first number of this three-digit code is “3.” The second and third numbers of the three-digit code describe the physical and chemical form of the waste. Table 2 provides a brief description of each generic code. Content codes are further defined as subcodes by an alpha trailer after the three-digit code to allow segregation of wastes that differ in one or more parameter(s). For example, the alpha trailers of the subcodes ID 322A and ID 322B may be used to differentiate between waste packaging configurations. As detailed in the RH-TRAMPAC, compliance with flammable gas limits may be demonstrated through the evaluation of compliance with either a decay heat limit or flammable gas generation rate (FGGR) limit per container specified in approved content codes. As applicable, if a container meets the watt*year criteria specified by the RH-TRAMPAC, the decay heat limits based on the dose-dependent G value may be used as specified in an approved content code. If a site implements the administrative controls outlined in the RH-TRAMPAC and Appendix 2.4 of the RH-TRU Payload Appendices, the decay heat or FGGR limits based on a 10-day shipping period (rather than the standard 60-day shipping period) may be used as specified in an approved content code.

Washington TRU Solutions

2006-12-01T23:59:59.000Z

347

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"

348

Argonne Chemical Sciences & Engineering - Facilities - Remote Handling  

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

Facilities Facilities * Actinide * Analytical Chemistry * Premium Coal Samples * Electrochemical Analysis * Glovebox * Glassblowing Fundamental Interactions Catalysis & Energy Conversion Electrochemical Energy Storage Nuclear & Environmental Processes National Security Institute for Atom-Efficient Chemical Transformations Center for Electrical Energy Storage: Tailored Interfaces Contact Us CSE Intranet Remote Handling Mockup Facility Remote Handling Mockup Facility Radiochemist Art Guelis observes technician Kevin Quigley preparing to cut open a surrogate uranium target. Argonne designed and built a Remote Handling Mockup Facility to let engineers simulate the handling of radioactive materials in a non-radioactive environment. The ability to carry out the details of an

349

LM Records Handling System-Fernald Historical Records System...  

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

Management, LM Records Handling System (LMRHS01) - Rocky Flats Environmental Records Database, Office of Legacy Management Energy.gov Careers & Internships For Staff & Contractors...

350

Biodiesel Handling and Use Guide: Fourth Edition (Revised)  

DOE Green Energy (OSTI)

Intended for those who blend, distribute, and use biodiesel and its blends, this guide contains procedures for handling and using these fuels.

Not Available

2009-01-01T23:59:59.000Z

351

Handbook for Handling, Storing, and Dispensing E85  

DOE Green Energy (OSTI)

A guidebook that contains information about EPAct alternative fuels regulations for fleets, flexible fuel vehicles, E85 properties and specifications, and E85 handling and storage guidelines.

Not Available

2002-04-01T23:59:59.000Z

352

Production and Handling Slide 1: The Uranium Fuel Cycle  

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

and Handling The Uranium Fuel Cycle Skip Presentation Navigation Next Slide Last Presentation Table of Contents The Uranium Fuel Cycle Refer to caption below for image...

353

Unit load and material handling considerations in facility layout design  

E-Print Network (OSTI)

Dec 1, 2002 ... In this paper, the integration of unit load and material handling considerations in facility layout design is presented. This integration is based on ...

354

Handbook for Handling, Storing, and Dispensing E85  

DOE Green Energy (OSTI)

Guidebook contains information about EPAct alternative fuels regulations for fleets, flexible fuel vehicles, E85 properties and specifications, and E85 handling and storage guidelines.

Not Available

2008-04-01T23:59:59.000Z

355

Chromoblastomycosis associated with in a carpenter handling exotic woods  

E-Print Network (OSTI)

in a carpenter handling exotic woods Nuno Menezes 1 , Pauloas saprophytes in the soil, wood and vegetation [ 3 ]. Theyare normally made of tropical wood [ 9 ]. The inoculation

2008-01-01T23:59:59.000Z

356

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

357

FINAL REPORT FOR INDEPENDENT CONFIRMATORY SURVEY SUMMARY AND RESULTS FOR THE HEMATITE DECOMMISSIONING PROJECT, FESTUS, MISSOURI  

SciTech Connect

ORAU conducted confirmatory surveys of the Hematite site during the period of June 12 through June 13, 2012. The survey activities included in-process inspections, document review, walkover surveys, sampling activities, and laboratory analysis of split samples. WEC was forthcoming with information relating to practices, procedures, and surface scan results. Scans performed by the WEC technician were extremely thorough and methodical. The WEC and ORAU technicians identified the same areas of elevated activity with comparable detector responses. WEC sampling of re-use soils, waste soils, sediments, and groundwater were conducted under ORAU observation. The sampling efforts observed by ORAU were performed in accordance with site-specific procedures and in a manner sufficient to provide quality supporting data. Three observations were made during groundwater sampling activities. First, the water level indicator was re-used without submitting rinse blank. Second, bubbles created during tubing extraction could indicate the presence of volatilized organic compounds. Third, samplers did not use a photo ionization detector prior to sample collection to indicate the presence of volatile organic vapors. Results of split samples indicated a high level of comparability between the WEC and ORAU/ORISE radiological laboratories. Analytical practices and procedures appear to be sufficient in providing quality radiochemical data. All concentrations from the Soil Re-Use Area and sediment samples are below Uniform radionuclide-specific derived concentration guideline level (DCGL{sub W}) limits; thus, comparisons to the less conservative stratified geometry were not required. Results were compared to individual DCGLs and using the sum of fractions approach. Both composite soil samples collected from the Waste Handling Area (Bins 1 and 4) were well below the prescribed USEI waste acceptance criteria.

Bailey, Erika N.; Lee, Jason D.

2012-09-21T23:59:59.000Z

358

ITER Engineering Design Activities -R & DITER-In-Vessel Remote Handling  

E-Print Network (OSTI)

ITER Engineering Design Activities - R & DITER- In-Vessel Remote Handling Blanket Module Remote Handling Project (L-6) Divertor Remote Handling Project (L-7) Objective To develop and demonstrate handling equipment, port handling equipment, auxiliary remote handling tools and a blanket mockup structure

359

SCO Survey  

Science Conference Proceedings (OSTI)

Survey on Future of NIST's Standards Information Services. June 5, 2013. *. Bookmark and Share. Contact: Clare Allocca 301-975-4359. ...

2013-06-05T23:59:59.000Z

360

An apparatus for remotely handling components  

DOE Patents (OSTI)

The inventive apparatus for remotely handling barlike components which define a longitudinal direction includes a gripper mechanism for gripping the component including first and second gripper members longitudinally fixedly spaced from each other and oriented parallel to each other in planes transverse to the longitudinal direction. Each gripper member includes a jaw having at least one V-groove with opposing surfaces intersecting at a base and extending radially relative to the longitudinal direction for receiving the component in an open end between the opposing surfaces. The V-grooves on the jaw plate of t he first and second gripper members are aligned in the longitudinal direction to support the component in the first and second gripper members. A jaw is rotatably mounted on and a part of each of the first and second gripper members for selectively assuming a retracted mode in which the open end of the V-groove is unobstructed and active mode in which the jaw spans the open end of the V-groove in the first and second gripper members. The jaw has a locking surface for contacting the component in the active mode to secure the component between the locking surface of the jaw and the opposing surfaces of the V-groove. The locking surface has a plurality of stepped portions, each defining a progressively decreasing radial distance between the base of the V-groove and the stepped portion opposing the base to accommodate varying sizes of components. In a preferred embodiment, the apparatus also includes a control mechanism for remotely controlling movement of the jaw in the locking mode to assume one of a plurality of locking positions corresponding to positioning one of the stepped portions opposite the base.

Szkrybalo, G.A.; Griffin, D.L.

1992-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "handled radiological surveys" 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

Reagent Storage and Handling for SCR and SNCR Systems  

Science Conference Proceedings (OSTI)

As utilities move to post-combustion nitrogen oxides (NOx) control technologies, the need to understand reagent storage and handling requirements for these systems increases. This report reviews various approaches to the storage and handling of anhydrous ammonia, aqueous ammonia, and urea. Systems that convert urea to ammonia also are included.

2002-05-30T23:59:59.000Z

362

MERCURY HANDLING FOR THE TARGET SYSTEM FOR A MUON COLLIDER  

E-Print Network (OSTI)

Cryostat 1. Remote handling The high radiation levels and presence of hazardous, ac- tivated mercury vaporsMERCURY HANDLING FOR THE TARGET SYSTEM FOR A MUON COLLIDER Van Graves , ORNL, Oak Ridge, TN 37830 placement within the Shielding Module in a remote environment. · Providing double containment of the mercury

McDonald, Kirk

363

Integrative path planning and motion control for handling large components  

Science Conference Proceedings (OSTI)

For handling large components a large workspace and high precision are required. In order to simplify the path planning for automated handling systems, this task can be divided into global, regional and local motions. Accordingly, different types of ... Keywords: integrative production, motion control, path planning, robotic assembly application

Rainer Müller; Martin Esser; Markus Janssen

2011-12-01T23:59:59.000Z

364

HANDLING FRESH FISH REFRIGERATION OF FISH -PART 2  

E-Print Network (OSTI)

(Fishery Leaflet 427) Cold-Storage Design and Refrigeration Equipment Part 3 (Fisher y Leaflet 429) FactorsHANDLING FRESH FISH REFRIGERATION OF FISH - PART 2 UNITED STATES DEPARTMENT OF THE INTERIOR FISH 428 Washington 25, D, C. December 1956 REFRIGERATION OF FISH - PART TWO HANDLING FRESH FISH By Charles

365

Dynamic manipulation inspired by the handling of a pizza peel  

Science Conference Proceedings (OSTI)

This paper discusses dynamic manipulation inspired by the handling mechanism of a pizza chef. The chef handles a tool called "pizza peel," where a plate is attached at the tip of a bar, and he remotely manipulates a pizza on the plate. We found that ... Keywords: dynamic manipulation, high-speed robot, robot skill

Mitsuru Higashimori; Keisuke Utsumi; Yasutaka Omoto; Makoto Kaneko

2009-08-01T23:59:59.000Z

366

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

367

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

368

T-625: Opera Frameset Handling Memory Corruption Vulnerability | Department  

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

5: Opera Frameset Handling Memory Corruption Vulnerability 5: Opera Frameset Handling Memory Corruption Vulnerability T-625: Opera Frameset Handling Memory Corruption Vulnerability May 18, 2011 - 3:05pm Addthis PROBLEM: A vulnerability has been reported in Opera, which can be exploited by malicious people to compromise a user's system. PLATFORM: Opera versions prior to 11.11 ABSTRACT: The vulnerability is caused due to an error when handling certain frameset constructs during page unloading and can be exploited to corrupt memory via a specially crafted web page. reference LINKS: Secunia Advisory: SA44611 Opera Knowledge Base Opera 11.11 for Windows Opera Download Opera Mobile IMPACT ASSESSMENT: High Discussion: Framesets allow web pages to hold other pages inside them. Certain frameset constructs are not handled correctly when the page is unloaded, causing a

369

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

370

Remote-Handled Transuranic Content Codes  

SciTech Connect

The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document representsthe development of a uniform content code system for RH-TRU waste to be transported in the 72-Bcask. It will be used to convert existing waste form numbers, content codes, and site-specificidentification codes into a system that is uniform across the U.S. Department of Energy (DOE) sites.The existing waste codes at the sites can be grouped under uniform content codes without any lossof waste characterization information. The RH-TRUCON document provides an all-encompassing|description for each content code and compiles this information for all DOE sites. Compliance withwaste generation, processing, and certification procedures at the sites (outlined in this document foreach content code) ensures that prohibited waste forms are not present in the waste. The contentcode gives an overall description of the RH-TRU waste material in terms of processes and|packaging, as well as the generation location. This helps to provide cradle-to-grave traceability ofthe waste material so that the various actions required to assess its qualification as payload for the72-B cask can be performed. The content codes also impose restrictions and requirements on themanner in which a payload can be assembled.The RH-TRU Waste Authorized Methods for Payload Control (RH-TRAMPAC), Appendix 1.3.7of the 72-B Cask Safety Analysis Report (SAR), describes the current governing procedures|applicable for the qualification of waste as payload for the 72-B cask. The logic for this|classification is presented in the 72-B Cask SAR. Together, these documents (RH-TRUCON,|RH-TRAMPAC, and relevant sections of the 72-B Cask SAR) present the foundation and|justification for classifying RH-TRU waste into content codes. Only content codes described in thisdocument can be considered for transport in the 72-B cask. Revisions to this document will be madeas additional waste qualifies for transport. |Each content code uniquely identifies the generated waste and provides a system for tracking theprocess and packaging history. Each content code begins with a two-letter site abbreviation thatindicates the shipper of the RH-TRU waste. The site-specific letter designations for each of the|DOE sites are provided in Table 1. Not all of the sites listed in Table 1 have generated/stored RH-|TRU waste.

Washington TRU Solutions

2001-08-01T23:59:59.000Z

371

FUEL HANDLING FACILITY CRITICALITY SAFETY CALCULATIONS  

SciTech Connect

The purpose of this design calculation is to perform a criticality evaluation of the Fuel Handling Facility (FHF) and the operations and processes performed therein. The current intent of the FHF is to receive transportation casks whose contents will be unloaded and transferred to waste packages (WP) or MGR Specific Casks (MSC) in the fuel transfer bays. Further, the WPs will also be prepared in the FHF for transfer to the sub-surface facility (for disposal). The MSCs will be transferred to the Aging Facility for storage. The criticality evaluation of the FHF features the following: (I) Consider the types of waste to be received in the FHF as specified below: (1) Uncanistered commercial spent nuclear fuel (CSNF); (2) Canistered CSNF (with the exception of horizontal dual-purpose canister (DPC) and/or multi-purpose canisters (MPCs)); (3) Navy canistered SNF (long and short); (4) Department of Energy (DOE) canistered high-level waste (HLW); and (5) DOE canistered SNF (with the exception of MCOs). (II) Evaluate the criticality analyses previously performed for the existing Nuclear Regulatory Commission (NRC)-certified transportation casks (under 10 CFR 71) to be received in the FHF to ensure that these analyses address all FHF conditions including normal operations, and Category 1 and 2 event sequences. (III) Evaluate FHF criticality conditions resulting from various Category 1 and 2 event sequences. Note that there are currently no Category 1 and 2 event sequences identified for FHF. Consequently, potential hazards from a criticality point of view will be considered as identified in the ''Internal Hazards Analysis for License Application'' document (BSC 2004c, Section 6.6.4). (IV) Assess effects of potential moderator intrusion into the fuel transfer bay for defense in depth. The SNF/HLW waste transfer activity (i.e., assembly and canister transfer) that is being carried out in the FHF has been classified as safety category in the ''Q-list'' (BSC 2003, p. A-6). Therefore, this design calculation is subject to the requirements of the ''Quality Assurance Requirements and Description'' (DOE 2004), even though the FHF itself has not yet been classified in the Q-list. Performance of the work scope as described and development of the associated technical product conform to the procedure AP-3.124, ''Design Calculations and Analyses''.

C.E. Sanders

2005-06-30T23:59:59.000Z

372

Routine Radiological Environmental Monitoring Plan. Volume 1  

SciTech Connect

The U.S. Department of Energy manages the Nevada Test Site in a manner that meets evolving DOE Missions and responds to the concerns of affected and interested individuals and agencies. This Routine Radiological Monitoring Plan addressess complicance with DOE Orders 5400.1 and 5400.5 and other drivers requiring routine effluent monitoring and environmental surveillance on the Nevada Test Site. This monitoring plan, prepared in 1998, addresses the activities conducted onsite NTS under the Final Environmental Impact Statement and Record of Decision. This radiological monitoring plan, prepared on behalf of the Nevada Test Site Landlord, brings together sitewide environmental surveillance; site-specific effluent monitoring; and operational monitoring conducted by various missions, programs, and projects on the NTS. The plan provides an approach to identifying and conducting routine radiological monitoring at the NTS, based on integrated technical, scientific, and regulatory complicance data needs.

Bechtel Nevada

1999-12-31T23:59:59.000Z

373

RADIOLOGICAL PROTECTIVE APPAREL PROGRAM AT HANFORD  

SciTech Connect

A program is described for providing adequate radiological protective clothing for all employees. The program consolidates all protective clothing requirements and the development and evaluation of clothing to be utilized, and establishes sound criteria for future procurement of accepted clothing. A council composed of representatives from all interested groups provides an effective means of consultation for the development, evaluation, and establishment of acceptable radiological apparel. Specifications and standards were established for use in the procurement of radiological protective apparel. Items of a non-launderable nature are warehoused and dispersed as requested. Routine reuse items which are laundry-maintained are dispersed through a central laundry facility. A chart illustrates the organization of the program. (C.H.)

Mehas, T.C.

1961-10-31T23:59:59.000Z

374

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

375

VLBI surveys  

E-Print Network (OSTI)

Systematic surveys of astronomical objects often lead to discoveries, but always provide invaluable information for statistical studies of well-defined samples. They also promote follow-up investigations of individual objects or classes. Surveys using a yet unexplored observing wavelength, a novel technique or a new instrument are of special importance. Significantly improved observing parameters (e.g. sensitivity, angular resolution, monitoring capability) provide new insight into the morphological and physical properties of the objects studied. I give a brief overview of the important Very Long Baseline Interferometry (VLBI) imaging surveys conducted in the past. A list of surveys guides us through the developments up until the present days. I also attempt to show directions for the near future.

S. Frey

2006-11-08T23:59:59.000Z

376

Handling effluent from nuclear thermal propulsion system ground tests  

SciTech Connect

A variety of approaches for handling effluent from nuclear thermal propulsion system ground tests in an environmentally acceptable manner are discussed. The functional requirements of effluent treatment are defined and concept options are presented within the framework of these requirements. System concepts differ primarily in the choice of fission-product retention and waste handling concepts. The concept options considered range from closed cycle (venting the exhaust to a closed volume or recirculating the hydrogen in a closed loop) to open cycle (real time processing and venting of the effluent). This paper reviews the different methods to handle effluent from nuclear thermal propulsion system ground tests.

Shipers, L.R.; Allen, G.C.

1992-09-09T23:59:59.000Z

377

Economizer Applications in Dual-Duct Air-Handling Units  

E-Print Network (OSTI)

This paper provides analytical tools and engineering methods to evaluate the feasibility of the economizer for dual-duct air-handling units. The results show that the economizer decreases cooling energy consumption without heating energy penalties for dual-fan, dual-duct air-handling units. The economizer has significant heating energy penalties for single-fan, dual-duct air-handling units. The penalties are higher than the cooling energy savings when the cold airflow is less than the hot airflow. Detailed engineering analyses are required to evaluate the feasibility of the economizer for single-fan, dual-duct systems.

Joo, I.; Liu, M.

2002-01-01T23:59:59.000Z

378

Site-specific waste management instruction - radiological screening facility  

DOE Green Energy (OSTI)

This Site-Specific Waste Management Instruction provides guidance for managing waste generated from radiological sample screening operations conducted to support the Environmental Restoration Contractor`s activities. This document applies only to waste generated within the radiological screening facilities.

G. G. Hopkins

1997-12-31T23:59:59.000Z

379

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

380

Trojan Nuclear Plant Decommissioning: Final Survey for the Independent Spent Fuel Storage Installation Site  

Science Conference Proceedings (OSTI)

This report describes the final radiological survey for the area where Portland General Electric (PGE) will construct the Independent Spent Fuel Storage Installation (ISFSI) at Trojan nuclear power plant. The survey fulfills the requirements for release of this area from Trojan's 10 CFR 50 license before radiation levels increase with spent fuel storage in the ISFSI.

1998-05-13T23:59:59.000Z

Note: This page contains sample records for the topic "handled radiological surveys" 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

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

SciTech Connect

During the period of February 14 to 15, 2012, ORISE performed radiological confirmatory survey activities for the former Fuel Oil Tank Area (FOTA) and additional radiological surveys of portions of the Humboldt Bay Power Plant site in Eureka, California. The radiological survey results demonstrate that residual surface soil contamination was not present significantly above background levels within the FOTA. Therefore, it is ORISE’s opinion that the radiological conditions for the FOTA surveyed by ORISE are commensurate with the site release criteria for final status surveys as specified in PG&E’s Characterization Survey Planning Worksheet. In addition, the confirmatory results indicated that the ORISE FOTA survey unit Cs-137 mean concentrations results compared favorably with the PG&E FOTA Cs-137 mean concentration results, as determined by ORISE from the PG&E characterization data. The interlaboratory comparison analyses of the three soil samples analyzed by PG&E’s onsite laboratory and the ORISE laboratory indicated good agreement for the sample results and provided confidence in the PG&E analytical procedures and final status survey soil sample data reporting.

WADE C. ADAMS

2012-04-09T23:59:59.000Z

382

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

SciTech Connect

The objectives of the confirmatory survey activities were to provide independent contractor field data reviews and to generate independent radiological data for use by the Nuclear Regulatory Commission (NRC) in evaluating the adequacy and accuracy of the licensee’s procedures and final status survey (FSS) results.

E.N. Bailey

2008-05-06T23:59:59.000Z

383

Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant  

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

NNSA presentation on Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant from May 13, 2011

384

NNSA, Philippine Nuclear Research Institute to Prevent Radiological...  

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

Philippine Nuclear Research Institute to Prevent Radiological Terrorism | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation...

385

US, Netherlands Expand Partnership to Secure Radiological Materials...  

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

Expand Partnership to Secure Radiological Materials Worldwide | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering...

386

Biodiesel Handling and Use Guide | Open Energy Information  

Open Energy Info (EERE)

Biodiesel Handling and Use Guide Biodiesel Handling and Use Guide Jump to: navigation, search Tool Summary Name: Biodiesel Handling and Use Guide Agency/Company /Organization: National Renewable Energy Laboratory Focus Area: Fuels & Efficiency Topics: Best Practices Website: www.nrel.gov/vehiclesandfuels/npbf/pdfs/43672.pdf This document is a guide for those who blend, store, distribute, and use biodiesel. It is intended to help fleets, individual users, blenders, distributors, and those involved in related activities understand procedures for handling and using biodiesel fuels. How to Use This Tool This tool is most helpful when using these strategies: Avoid - Cut the need for travel Shift - Change to low-carbon modes Improve - Enhance infrastructure & policies Learn more about the avoid, shift, improve framework for limiting air

387

Production and Handling Slide 20: Advantages of UF6  

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

UF6 Skip Presentation Navigation First Slide Previous Slide Next Slide Last Presentation Table of Contents Advantages of UF6 Only one isotope of F2 Can be handled at reasonable...

388

V-217: Microsoft Windows NAT Driver ICMP Packet Handling Denial...  

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

SCUSSION: The vulnerability is caused due to an error within the Windows NAT Driver when handling ICMP packets and can be exploited to cause the system to stop responding IMPACT:...

389

V-079: ISC BIND AAAA Record Lookup Handling Assertion Failure...  

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

Lets Remote Users Deny Service T-633: BIND RRSIG RRsets Negative Caching Off-by-one Bug Lets Remote Users Deny Service U-183: ISC BIND DNS Resource Records Handling Vulnerability...

390

Material handling resource utilization simulation study for stamping plant  

Science Conference Proceedings (OSTI)

This paper describes the application of dynamic simulation to evaluate material handling resource utilization for a stamping plant in the automotive industry. The other objective of this study was evaluation of throughput relative to press schedules, ...

Edward J. Williams; Onur M. Ulgen; Sheldon Bailiff; Ravindra Lote

2006-12-01T23:59:59.000Z

391

Input handling in agent-based micro-level simulators.  

E-Print Network (OSTI)

??In this thesis we presented a new direction for handling missing values in multi agent-based simulation (MABS) at micro-level by using truth tables and logical… (more)

Fayyaz, Muhammad

2010-01-01T23:59:59.000Z

392

Strategies for handling missing data in randomised trials  

E-Print Network (OSTI)

sensitivity analysis and how to handle missing baseline variables. Published: 13 December 2011 References 1. National Research Council: The prevention and treatment of missing data in clinical trials. The National Academies Press; Washington, DC; 2010 [http...

2011-12-13T23:59:59.000Z

393

PRIME VALUE METHOD TO PRIORITIZE RISK HANDLING STRATEGIES  

Science Conference Proceedings (OSTI)

Funding for implementing risk handling strategies typically is allocated according to either the risk-averse approach (the worst risk first) or the cost-effective approach (the greatest risk reduction per implementation dollar first). This paper introduces a prime value approach in which risk handling strategies are prioritized according to how nearly they meet the goals of the organization that disburses funds for risk handling. The prime value approach factors in the importance of the project in which the risk has been identified, elements of both risk-averse and cost-effective approaches, and the time period in which the risk could happen. This paper also presents a prioritizer spreadsheet, which employs weighted criteria to calculate a relative rank for the handling strategy of each risk evaluated.

Noller, D

2007-10-31T23:59:59.000Z

394

In-Plant Ash-Handling Reference Manual  

Science Conference Proceedings (OSTI)

Despite problems with ash-handling systems that have led to failures in electrostatic precipitators, there has been no extensive reference manual for specifying, operating, and maintaining such systems. The comprehensive manual compiled in this study serves as a reference for every phase of boiler bottom ash- and fly ash-handling systems design and operation as well as a primer for those unfamiliar with these systems.

1986-12-01T23:59:59.000Z

395

WIPP Remote Handled Waste Facility: Performance Dry Run Operations  

SciTech Connect

The Remote Handled (RH) TRU Waste Handling Facility at the Waste Isolation Pilot Plant (WIPP) was recently upgraded and modified in preparation for handling and disposal of RH Transuranic (TRU) waste. This modification will allow processing of RH-TRU waste arriving at the WIPP site in two different types of shielded road casks, the RH-TRU 72B and the CNS 10-160B. Washington TRU Solutions (WTS), the WIPP Management and Operation Contractor (MOC), conducted a performance dry run (PDR), beginning August 19, 2002 and successfully completed it on August 24, 2002. The PDR demonstrated that the RHTRU waste handling system works as designed and demonstrated the handling process for each cask, including underground disposal. The purpose of the PDR was to develop and implement a plan that would define in general terms how the WIPP RH-TRU waste handling process would be conducted and evaluated. The PDR demonstrated WIPP operations and support activities required to dispose of RH-TRU waste in the WIPP underground.

Burrington, T. P.; Britain, R. M.; Cassingham, S. T.

2003-02-24T23:59:59.000Z

396

Uranium hexafluoride: A manual of good handling practices. Revision 7  

SciTech Connect

The United States Enrichment Corporation (USEC) is continuing the policy of the US Department of Energy (DOE) and its predecessor agencies in sharing with the nuclear industry their experience in the area of uranium hexafluoride (UF{sub 6}) shipping containers and handling procedures. The USEC has reviewed Revision 6 or ORO-651 and is issuing this new edition to assure that the document includes the most recent information on UF{sub 6} handling procedures and reflects the policies of the USEC. This manual updates the material contained in earlier issues. It covers the essential aspects of UF{sub 6} handling, cylinder filling and emptying, general principles of weighing and sampling, shipping, and the use of protective overpacks. The physical and chemical properties of UF{sub 6} are also described. The procedures and systems described for safe handling of UF{sub 6} presented in this document have been developed and evaluated during more than 40 years of handling vast quantities of UF{sub 6}. With proper consideration for its nuclear properties, UF{sub 6} may be safely handled in essentially the same manner as any other corrosive and/or toxic chemical.

NONE

1995-01-01T23:59:59.000Z

397

Real Time Quantitative Radiological Monitoring Equipment for Environmental Assessment  

SciTech Connect

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

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

2006-03-01T23:59:59.000Z

398

Step-By-Step Guide for Waste Handling at WIPP - Fact Sheet  

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

the nation's nuclear waste disposal problem Step-By-Step Guide for Waste Handling at WIPP The handling and disposal of contact-handled transuranic waste at the Waste Isolation...

399

GIS Symbology for FRMAC/CMHT Radiological/Nuclear Products  

SciTech Connect

This document is intended to codify, to the extent currently possible, the representation of map products produced for and by the Federal Radiological Monitoring and Assessment Center (FRMAC) and the Consequence Management Home Team (CHMT), particularly those that include model products from the National Atmospheric Release Advisory Capability (NARAC). This is to facilitate consistency between GIS products produced by different members of these teams, which should ease the task of interpreting these products by both team members and those outside the team who may need to use these products during a response. The aspects of symbology being considered are primarily isopleths levels (breakpoints) and colors used to plot NARAC modeled dose or deposition fields on mpas, although some comments will be made about the handling of legend and supporting textual information. Other aspects of symbolizing such products (e.g., transparency) are being left to the individual team members to allow them to adapt to particular organizational needs or requirements that develop during a particular a response or exercise. This document has been written in coordination with the creation of training material in Baskett, et al., 2008. It is not intended as an aid to NARAC product interpretation but to facilitate the work of GIS specialists who deal with these products in map design and in the development of supporting scripts and software that partially or completely automate the integration of NARAC model products with other GIS data. This work was completed as part of the NA-42 Technical Integration Project on GIS Automated Data Processing and Map Production in FY 2008. Other efforts that are part of this work include (a) updating the NARAC shapefile product representation to facilitate the automation work proceed at RSL as part of the same TI effort and (b) to ensure that the NARAC shapefile construct includes all of the necessary legend and other textual data to interpret dispersion and deposition patterns and related products correctly. This document is focusing on the products produced by the GIS Division of the Remove Sensing Laboratory (RSL) and by the National Atmospheric Release Advisory Center (NARAC), both separately and in combination. The expectation is that standard products produced by either group independently or in combination should use the same key attributes in displaying the same kinds of data so that products of a given type generally look similar in key aspects of the presentation, thereby minimizing any confusion of users when a variety of products from these groups may be needed. This document is dealing with the set of common standard products used in responding to radiological/nuclear releases. There are a number of less standard products that are used occasionally or in certain specific situations that are not addressed here. This includes special products that are occasionally produced by both NARAC and RSL in responses and major exercises to meet immediate and unanticipated requirements. At some future time, it may be appropriate to review the handling of such special products by both organizations to determine if there are any areas that would benefit from being integrated with the conventions described here. A particular area that should be addressed in the near-term is that of Derived Response Levels (DRLs) calculated by the Consequence Management Home Team (CMHT) or FRMAC Assessment Scientists. A new calculation is done for every event assigning contour levels, or break-points, based upon field measurements. These contour levels can be applied to deposition or dose rate NARAC calculations. Because these calculations are different every time, they can not be stored in a database.

Walker, H; Aluzzi, F; Foster, K; Pobanz, B; Sher, B

2008-10-06T23:59:59.000Z

400

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 "handled radiological surveys" 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

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

402

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

403

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:

404

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

405

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

406

NV/YMP RADIOLOGICAL CONTROL MANUAL  

SciTech Connect

This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) and the Yucca Mountain Office of Repository Development (YMORD). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations Part 835 (10 CFR 835), Occupational Radiation Protection. Programs covered by this manual are located at the Nevada Test Site (NTS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Pleasanton, California; and at Andrews Air Force Base, Maryland. In addition, field work by NNSA/NSO at other locations is also covered by this manual.

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

2004-11-01T23:59:59.000Z

407

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

408

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

409

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

410

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

411

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

412

Fixation of Radiological Contamination; International Collaborative Development  

Science Conference Proceedings (OSTI)

A cooperative international project was conducted by the Idaho National Laboratory (INL) and the United Kingdom’s National Nuclear Laboratory (NNL) to integrate a capture coating with a high performance atomizing process. The initial results were promising, and lead to further trials. The somewhat longer testing and optimization process has resulted in a product that could be demonstrated in the field to reduce airborne radiological dust and contamination.

Rick Demmer

2013-03-01T23:59:59.000Z

413

Guide of Good Practices for Occupational Radiological Protection in Plutonium Facilities  

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

28-2008 28-2008 December 2008 DOE STANDARD GUIDE OF GOOD PRACTICES FOR OCCUPATIONAL RADIOLOGICAL PROTECTION IN PLUTONIUM FACILITIES U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive DOE-STD-1128-2008 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1128-2008 iii Foreword This Technical Standard does not contain any new requirements. Its purpose is to provide a guide to good practice, update existing reference material, and discuss practical lessons learned relevant to the safe handling of plutonium. U.S. Department of Energy (DOE) health physicists may adapt

414

Guide of Good Practices for Occupational Radiological Protection in Plutonium Facilities  

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

STD-1128-2008 STD-1128-2008 December 2008 DOE STANDARD GUIDE OF GOOD PRACTICES FOR OCCUPATIONAL RADIOLOGICAL PROTECTION IN PLUTONIUM FACILITIES U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive DOE-STD-1128-2008 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1128-2008 iii Foreword This Technical Standard does not contain any new requirements. Its purpose is to provide a guide to good practice, update existing reference material, and discuss practical lessons learned relevant to the safe handling of plutonium. U.S. Department of Energy (DOE) health physicists may adapt

415

An in situ survey of Clean Slate 1, 2, and 3, Tonopah Test Range, Central Nevada. Date of survey: September--November 1993  

SciTech Connect

A ground-based in situ radiological survey was conducted downwind of the Clean Slate 1, 2, and 3 nuclear safety test sites at the Tonopah Test Range in central Nevada from September through November 1993. The purpose of the study was to corroborate the americium-241 ({sup 241}Am) soil concentrations that were derived from the aerial radiological survey of the Clean Slate areas, which was conducted from August through October 1993. The presence of {sup 241}Am was detected at 140 of the 190 locations, with unrecoverable or lost data accounting for fifteen (15) of the sampling points. Good agreement was obtained between the aerial and in situ results.

NONE

1995-08-01T23:59:59.000Z

416

Finding and evaluating potential radiological problems in the vicinity of uranium milling sites  

Science Conference Proceedings (OSTI)

Tailings at inactive milling sites usually have a low frequency of human occupancy but continuously generate /sup 222/Rn into the atmosphere. Measurements of airborne /sup 222/Rn and /sup 222/Rn flux are made on the sites to define the tailings source term. Concurrently with these measurements, an ambient /sup 222/Rn monitoring network is established off-site and a meteolrololgical station is established at or near the mill site. Radioactivity can migrate to areas outside of site boundaries by wind and water erosion, groundwater transport, spillage of incoming purposes. In order to identify and assess off-site radioactivity on properties in the vicinity of milling sites, a combination of aerial and ground-level radiological monitoring techniques are used. The ground mobile gamma-ray scan is conducted using a vehicle equipped with sensitive gamma-ray detectors. The detectors are shielded so that gamma radiation input is viewed through only one side of the vehicle. This system is capable of precisely locating properties which have anomalously high gamma radiation levels caused by the presence of tailings. Subsequently, these properties are identified as candidate vicinity properties and are scheduled for radiological surveys subject to the property owner's consent. The comprehensive radiological surveys conducted at these vicinity properties determine the amount, type, and location of tailings materials. Structures on a vicinity property are carefully surveyed to determine the presence or absence of construction-related uses of tailings. If structural uses of tailings are found, air samples are analyzed for /sup 222/Rn progeny, short-term continuous /sup 222/Rn monitoring is instituted, and /sup 222/Rn flux rate from tailings are estimated. If warranted, long-term /sup 222/Rn and progeny measurements are made.

Goldsmith, W.A.; Yates, W.G.

1982-01-01T23:59:59.000Z

417

GN470094 - Handling Chemicals at SNL/CA  

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

094, Handling Chemicals at SNL/CA 094, Handling Chemicals at SNL/CA Sponsor: Michael W. Hazen, 4000 Revision Date: October 31, 2008 Replaces Document Dated: October 16, 2007 This document is no longer a CPR. This document implements the requirements of Corporate procedure ESH100.2.IH.25, Control Chemical Hazards at SNL/CA. IMPORTANT NOTICE: A printed copy of this document may not be the document currently in effect. The official version is the online version located on the Sandia Restricted Network (SRN). GN470094 - HANDLING CHEMICALS AT SNL/CA Subject Matter Expert: Al Buerer GN470094, Issue E Revision Date: October 31, 2008; Replaces Document Dated: October 16, 2007 Change History 1.0 Purpose, Scope, and Ownership 2.0 Responsibilities 3.0 Definitions 4.0 Training 5.0 Protective Equipment 6.0 Procurement of Chemicals

418

Remote-Handled Low Level Waste Disposal Project Alternatives Analysis  

Science Conference Proceedings (OSTI)

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

David Duncan

2010-10-01T23:59:59.000Z

419

Handbook for Handling, Storing, and Dispensing E85 | Open Energy  

Open Energy Info (EERE)

for Handling, Storing, and Dispensing E85 for Handling, Storing, and Dispensing E85 Jump to: navigation, search Tool Summary Name: Handbook for Handling, Storing, and Dispensing E85 Agency/Company /Organization: National Renewable Energy Laboratory Focus Area: Fuels & Efficiency Topics: Best Practices Website: www.afdc.energy.gov/afdc/pdfs/48162.pdf This document serves as a guide for blenders, distributors, sellers, and users of E85 as an alternative motor fuel. It provides basic information on the proper and safe use of E85 and offers supporting technical and policy references. How to Use This Tool This tool is most helpful when using these strategies: Avoid - Cut the need for travel Shift - Change to low-carbon modes Improve - Enhance infrastructure & policies Learn more about the avoid, shift, improve framework for limiting air

420

Certification plan transuranic waste: Hazardous Waste Handling Facility  

SciTech Connect

The purpose of this plan is to describe the organization and methodology for the certification of transuranic (TRU) waste handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). The plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Quality Assurance Implementing Management Plan (QAIMP) for the HWBF; and a list of the current and planned implementing procedures used in waste certification.

1992-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "handled radiological surveys" 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

Powered Remote Manipulators Perform Hazardous Retrieval, Handling, and Size Reduction Operations  

SciTech Connect

This paper describes a new lightweight, powered remote manipulator (PRM) that S.A.Robotics has developed for remote material handling and size reduction in hazardous environments such as reactor decommissioning projects. PRMs can be mounted to various deployment platforms such as remote controlled track-driven vehicles, commercial All Terrain Vehicles, or crane-mounted arms. They can also be installed as replacements for traditional Master-Slave Manipulators (MSMs) in hot cells. The PRM is a six degree of freedom manipulator with carbon fiber structural components that can provide up to a 3 meter (10 foot) reach. Either electric or hydraulic power options can be used and a variety of hydraulic fluids are available to meet combustible material limitations. The PRM is operated with easy-to-use joystick controls that allow operators to sit in a comfortable work station and handle 90 kg (200 pound) loads with a hydraulic power pack or 45 kg (100 pounds) with electric servo-motor driven equipment. With a quick disconnect tool changer, the manipulator can operate grippers, drills, shears, saws, sampling and survey instruments, and the arm can also deploy cameras and lights to support a wide range of remote applications. (authors)

Cole, M.D.; Owen, J.R.; Adams, S.R. [S.A.Robotics, Inc., 3985 S. Lincoln Avenue, Suite 100, Loveland, Colorado 80241 (United States)

2006-07-01T23:59:59.000Z

422

JOM Salary Survey - TMS  

Science Conference Proceedings (OSTI)

JOM Salary Survey. This survey is currently closed. Please contact the author of this survey for further assistance. Javascript is required for this site to function, ...

423

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

SciTech Connect

The Monitoring division is primarily responsible for the coordination and direction of: Aerial measurements to delineate the footprint of radioactive contaminants that have been released into the environment. Monitoring of radiation levels in the environment; Sampling to determine the extent of contaminant deposition in soil, water, air and on vegetation; Preliminary field analyses to quantify soil concentrations or depositions; and Environmental and personal dosimetry for FRMAC field personnel, during a Consequence Management Response Team (CMRT) and Federal Radiological Monitoring and Assessment Center (FRMAC) response. Monitoring and sampling techniques used during CM/FRMAC operations are specifically selected for use during radiological emergencies where large numbers of measurements and samples must be acquired, analyzed, and interpreted in the shortest amount of time possible. In addition, techniques and procedures are flexible so that they can be used during a variety of different scenarios; e.g., accidents involving releases from nuclear reactors, contamination by nuclear waste, nuclear weapon accidents, space vehicle reentries, or contamination from a radiological dispersal device. The Monitoring division also provides technicians to support specific Health and Safety Division activities including: The operation of the Hotline; FRMAC facility surveys; Assistance with Health and Safety at Check Points; and Assistance at population assembly areas which require support from the FRMAC. This volume covers deployment activities, initial FRMAC activities, development and implementation of the monitoring and assessment plan, the briefing of field teams, and the transfer of FRMAC to the EPA.

NSTec Aerial Measurement Systems

2012-07-31T23:59:59.000Z

424

Coal- and Ash-Handling Systems Reliability Conference and Workshop Proceedings  

Science Conference Proceedings (OSTI)

This report presents papers, discussion summaries, and conclusions from an EPRI workshop on reliability problems with coal- and ash-handling systems in power plants. Held in October 1980 in St. Louis, the workshop covered yard and in-plant coal handling, frozen coal, fugitive dust, fly ash handling, bottom ash handling, and ash disposal.

1981-08-01T23:59:59.000Z

425

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.

426

Radiological and Nuclear Security in A Global Context  

E-Print Network (OSTI)

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

Jones, Nick

2010-01-01T23:59:59.000Z

427

Method of preparing and handling chopped plant materials  

DOE Patents (OSTI)

The method improves efficiency of harvesting, storage, transport, and feeding of dry plant material to animals, and is a more efficient method for harvesting, handling and transporting dry plant material for industrial purposes, such as for production of bioenergy, and composite panels.

Bransby, David I. (2668 Wire Rd., Auburn, AL 36832)

2002-11-26T23:59:59.000Z

428

Some thoughts on using argumentation to handle trust  

Science Conference Proceedings (OSTI)

This paper describes some of our recent work on using argumentation to handle information about trust. We first discuss the importance of trust in computer science in general and in multi-agent systems in particular.We then describe the setting of our ...

Simon Parsons; Yuqing Tang; Kai Cai; Elizabeth Sklar; Peter McBurney

2011-07-01T23:59:59.000Z

429

Thermal decomposition study of hydroxylamine nitrate during storage and handling  

E-Print Network (OSTI)

Hydroxylamine nitrate (HAN), an important agent for the nuclear industry and the U.S. Army, has been involved in several costly incidents. To prevent similar incidents, the study of HAN safe storage and handling boundary has become extremely important for industries. However, HAN decomposition involves complicated reaction pathways due to its autocatalytic behavior and therefore presents a challenge for definition of safe boundaries of HAN storage and handling. This research focused on HAN decomposition behavior under various conditions and proposed isothermal aging testing and kinetic-based simulation to determine safety boundaries for HAN storage and handling. Specifically, HAN decomposition in the presence of glass, titanium, stainless steel with titanium, or stainless steel was examined in an Automatic Pressure Tracking Adiabatic Calorimeter (APTAC). n-th order kinetics was used for initial reaction rate estimation. Because stainless steel is a commonly used material for HAN containers, isothermal aging tests were conducted in a stainless steel cell to determine the maximum safe storage time of HAN. Moreover, by changing thermal inertia, data for HAN decomposition in the stainless steel cell were examined and the experimental results were simulated by the Thermal Safety Software package. This work offers useful guidance for industries that manufacture, handle, and store HAN. The experimental data acquired not only can help with aspects of process safety design, including emergency relief systems, process control, and process equipment selection, but also is a useful reference for the associated theoretical study of autocatalytic decomposition behavior.

Zhang, Chuanji

2003-05-01T23:59:59.000Z

430

Guidelines for Handling Confidential Information by Remote Access  

E-Print Network (OSTI)

Guidelines for Handling Confidential Information by Remote Access You have signed an OHSU of your access to OHSU electronic information and/or other sanctions. Remember, using remote access of the OHSU facilities. When you are utilizing remote access, you must provide the same level of security used

Chapman, Michael S.

431

A business process modeling notation extension for risk handling  

Science Conference Proceedings (OSTI)

During the years of prosperity, numerous organizations neglected numerous aspects of risk management. As systematic approach to handling identified risks is crucial to achieving success by the organization, modern business modeling standards and techniques ... Keywords: BPMN extension, business process modeling notation, risk management

Bartosz Marcinkowski; Michal Kuciapski

2012-09-01T23:59:59.000Z

432

Certification Plan, low-level waste Hazardous Waste Handling Facility  

SciTech Connect

The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan also incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF and a list of the current and planned implementing procedures used in waste certification. This plan provides guidance from the HWHF to waste generators, waste handlers, and the Waste Certification Specialist to enable them to conduct their activities and carry out their responsibilities in a manner that complies with the requirements of WHC-WAC. Waste generators have the primary responsibility for the proper characterization of LLW. The Waste Certification Specialist verifies and certifies that LBL LLW is characterized, handled, and shipped in accordance with the requirements of WHC-WAC. Certification is the governing process in which LBL personnel conduct their waste generating and waste handling activities in such a manner that the Waste Certification Specialist can verify that the requirements of WHC-WAC are met.

Albert, R.

1992-06-30T23:59:59.000Z

433

2012 NERSC User Survey  

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

Results 2012 User Survey Text 2012 NERSC User Survey Text The 2012 NERSC User Survey is closed. The following is the text of the survey. Section 1: Overall Satisfaction with...

434

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

435

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

436

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

437

CRAD, Radiological Controls - Y-12 Enriched Uranium Operations...  

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

Y-12 Enriched Uranium Operations Oxide Conversion Facility CRAD, Radiological Controls - Y-12 Enriched Uranium Operations Oxide Conversion Facility January 2005 A section of...

438

Health Physics journal features U.S. radiological response to...  

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

Physics journal features U.S. radiological response to Fukushima accident | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation...

439

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...

440

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

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

DOE-HDBK-1141-2001 Radiological Properties of Plutonium * 15 isotopes, all radioactive * Pu-238 (heat source) * Pu-239 (reactor fuel, weapons) * Pu-240 (reactor fuel, weapons) *...

Note: This page contains sample records for the topic "handled radiological surveys" 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

Insider Threat to Nuclear and Radiological Materials: Fact Sheet...  

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

Insider Threat to Nuclear and Radiological Materials: Fact Sheet | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the...

442

NNSA Nuclear/Radiological Incident Response | National Nuclear...  

National Nuclear Security Administration (NNSA)

field deployable teams of heath physics professionals equipped to conduct radiological search, monitoring, and assessment activities. Radiation Emergency Assistance CenterTraining...

443

DOE O 153.1, 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 ...

2007-06-27T23:59:59.000Z

444

Don Haward joins WIPP as manager of radiological control and...  

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

Don Harward Joins WIPP as Manager of Radiological Control and Emergency Preparedness CARLSBAD, N.M., May 12, 2000 - The Westinghouse Waste Isolation Division (WID) has named Don...

445

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

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

Field Training Center A site used for nuclear research in Oak Ridge, Tennessee during the Manhattan Project is now the Y-12 National Security Complex's Nuclear and Radiological...

446

Recycle of radiologically contaminated austenitic stainless steels  

Science Conference Proceedings (OSTI)

The United States Department of Energy owns large quantities of radiologically contaminated austenitic stainless steel which could by recycled for reuse if appropriate release standards were in place. Unfortunately, current policy places the formulation of a release standard for USA industry years, if not decades, away. The Westinghouse Savannah River Company, Idaho National Engineering Laboratory and various university and industrial partners are participating in initiative to recycle previously contaminated austenitic stainless steels into containers for the storage and disposal of radioactive wastes. This paper describes laboratory scale experiments which demonstrated the decontamination and remelt of stainless steel which had been contaminated with radionuclides.

Imrich, K.J.; Leader, D.R.; Iyer, N.C.; Louthan, M.R. Jr.

1995-02-01T23:59:59.000Z

447

Radiological Dose Calculations for Fusion Facilities  

Science Conference Proceedings (OSTI)

This report summarizes the results and rationale for radiological dose calculations for the maximally exposed individual during fusion accident conditions. Early doses per unit activity (Sieverts per TeraBecquerel) are given for 535 magnetic fusion isotopes of interest for several release scenarios. These data can be used for accident assessment calculations to determine if the accident consequences exceed Nuclear Regulatory Commission and Department of Energy evaluation guides. A generalized yearly dose estimate for routine releases, based on 1 Terabecquerel unit releases per radionuclide, has also been performed using averaged site parameters and assumed populations. These routine release data are useful for assessing designs against US Environmental Protection Agency yearly release limits.

Michael L. Abbott; Lee C. Cadwallader; David A. Petti

2003-04-01T23:59:59.000Z

448

Radiological Control Technician: Standardized technician Qualification Standard  

Science Conference Proceedings (OSTI)

The Qualification Standard states and defines the knowledge and skill requirements necessary for successful completion of the Radiological Control Technician Training Program. The standard is divided into three phases: Phase I concerns RCT Academic training. There are 13 lessons associated with the core academics program and 19 lessons associated with the site academics program. The staff member should sign the appropriate blocks upon successful completion of the examination for that lesson or group of lessons. In addition, facility specific lesson plans may be added to meet the knowledge requirements in the Job Performance Measures (JPM) of the practical program. Phase II concerns RCT core/site practical (JPMs) training. There are thirteen generic tasks associated with the core practical program. Both the trainer/evaluator and student should sign the appropriate block upon successful completion of the JPM. In addition, facility specific tasks may be added or generic tasks deleted based on the results of the facility job evaluation. Phase III concerns the oral examination board successful completion of the oral examination board is documented by the signature of the chairperson of the board. Upon completion of all of the standardized technician qualification requirements, final qualification is verified by the student and the manager of the Radiological Control Department and acknowledged by signatures on the qualification standard. The completed Qualification Standard shall be maintained as an official training record.

Not Available

1992-10-01T23:59:59.000Z

449

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

450

Luminescence analysis for radiological and nuclear forensic application  

Science Conference Proceedings (OSTI)

This paper briefly discusses recombination luminescence and its use in forensic radiation dosimetry. Recombination luminescence techniques offer a new capability for radiological forensic analysis of sites and vehicles previously cleared of isotopic ... Keywords: OSL, TL, environmental dosimetry, forensic, optically stimulated luminescence, radiological, retrospective population dosimetry, thermoluminescence

Nigel A. Spooner; Barnaby W. Smith

2008-01-01T23:59:59.000Z

451

Adapting collaborative radiological practice to low-resource environments  

Science Conference Proceedings (OSTI)

We describe how current radiological best practices are predicated on a sophisticated technological ecosystem usually comprised of multiple large-scale displays, and integrated record keeping and communication systems driven by high-speed networks. At ... Keywords: cscw, ictd, medicine, pacs, professional practice, radiology information systems, teleradiology

Beth E. Kolko; Alexis Hope; Waylon Brunette; Karen Saville; Wayne Gerard; Michael Kawooya; Robert Nathan

2012-02-01T23:59:59.000Z

452

Operation Castle. Radiological Safety. Volume 2. Final report  

SciTech Connect

This report is designed to cover the overall Operation Castle radiological safety matters from the viewpoint of those issues of direct concern to Headquarters, Joint Task Force Seven. It was written for the express purpose of assisting in the development of future radiological safety plans by presenting detailed discussion of the problems and solutions arising during Operation Castle.

Not Available

1985-09-01T23:59:59.000Z

453

Current Trends in Gamma Ray Detection for Radiological Emergency Response  

SciTech Connect

Passive and active detection of gamma rays from shielded radioactive materials, including special nuclear materials, is an important task for any radiological emergency response organization. This article reports on the current trends and status of gamma radiation detection objectives and measurement techniques as applied to nonproliferation and radiological emergencies.

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

2011-08-18T23:59:59.000Z

454

FRMAC Interactions During a Radiological or Nuclear Event  

SciTech Connect

During a radiological or nuclear event of national significance the Federal Radiological Emergency Monitoring and Assessment Center (FRMAC) assists federal, state, tribal, and local authorities by providing timely, high-quality predictions, measurements, analyses and assessments to promote efficient and effective emergency response for protection of the public and the environment from the consequences of such an event.

Wong, C T

2011-01-27T23:59:59.000Z

455

Conceptual flow sheets development for coal conversion plant coal handling-preparation and ash/slag removal operations  

SciTech Connect

This report presents 14 conceptual flow sheets and major equipment lists for coal handling and preparation operations that could be required for future, commercial coal conversion plants. These flow sheets are based on converting 50,000 tons per day of clean coal representative of the Pittsburgh and Kentucky No. 9 coal seams. Flow sheets were used by Union Carbide Corporation, Oak Ridge National Laboratory, in a survey of coal handling/preparation equipment requirements for future coal conversion plants. Operations covered in this report include run-of-mine coal breaking, coarse coal cleaning, fine coal cleaning, live storage and blending, fine crushing (crushing to top sizes ranging from 1/4-inch to 20 mesh), drying, and grinding (70 percent minus 200 mesh). Two conceptual flow sheets and major equipment lists are also presented for handling ash or granulated slag and other solid wastes produced by nine leading coal conversion processes. These flow sheets provide for solid wastes transport to an environmentally acceptable disposal site as either dry solids or as a water slurry.

1979-07-01T23:59:59.000Z

456

DOE Seeks Independent Evaluation of Remote-Handled Waste Program  

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

Seeks Independent Evaluation Seeks Independent Evaluation Of Remote-Handled Waste Program CARLSBAD, N.M., July 24, 2001 - An independent panel of scientific and engineering experts will convene July 30 in Carlsbad to evaluate U.S. Department of Energy (DOE) plans for managing remote-handled (RH) transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP). DOE's Carlsbad Field Office has asked the American Society of Mechanical Engineers and the Institute for Regulatory Science to review its proposed RH-TRU waste program. The program must be approved by the New Mexico Environment Department and the U.S. Environmental Protection Agency before DOE will be permitted to accept and dispose of RH-TRU waste at WIPP. "Safety and compliance are our primary considerations in developing the plans for

457

Development and implementation of automated radioactive materials handling systems  

SciTech Connect

Material handling of radioactive and hazardous materials has forced the need to pursue remotely operated and robotic systems in light of operational safety concerns. Manual maneuvering, repackaging, overpacking and inspecting of containers which store radioactive and hazardous materials is the present mode of operation at the Department of Energy (DOE) Fernald Environmental Management Project (FEMP) in Fernald Ohio. The manual methods are unacceptable in the eyes of concerned site workers and influential community oversight committees. As an example to respond to the FEMP material handling needs, design efforts have been initiated to provide a remotely operated system to repackage thousands of degradated drums containing radioactive Thorium: Later, the repackaged Thorium will be shipped offsite to a predesignated repository again requiring remote operation.

Jacoboski, D.L.

1992-12-01T23:59:59.000Z

458

Optimizing Ash Handling - SmartAshTM System Evaluation  

Science Conference Proceedings (OSTI)

High ash levels in electrostatic precipitator (ESP) hoppers are notorious for increasing particulate matter (PM) emissions and plume opacity. Conventional means of monitoring hopper ash levels and fly ash handling system performance have been time-consuming and problematic. Neundorfer, Inc., has developed a fly ash conveying system-monitoring package (SmartAshSystem) that provides improved monitoring of fly ash removal process parameters and provides graphical depictions of ash system performance. Additi...

2007-11-21T23:59:59.000Z

459

EURISOL-DS Multi-Megawatt Target: Remote Handling Equipment  

E-Print Network (OSTI)

The design proposed within Task #2 of the EURISOL Design Study for the remote handling of the mercury converter target and its associated loop is presented with particular emphasis on achieving rapid turn-around during routine maintenance.The converter target needs to be completely exchanged every four months due to the high irradiation damage sustained. Other components are less susceptible to damage but may need periodic maintenance; in particular the on-line isotopic separation unit in the mercury loop.

Cyril Kharoua, Olivier Choisnet, Yacine Kadi, Karel Samec (CERN)

460

Safety aspects of large-scale handling of hydrogen  

DOE Green Energy (OSTI)

Since the decade of the 1950s, there has been a large increase in the quantity of hydrogen, especially liquid hydrogen, that has been produced, transported, and used. The technology of hydrogen, as it relates to safety, has also developed at the same time. The possible sources of hazards that can arise in the large-scale handling of hydrogen are recognized, and for the most part, sufficiently understood. These hazard sources are briefly discussed. 26 refs., 4 figs.

Edeskuty, F.J.; Stewart, W.F.

1988-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "handled radiological surveys" 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

CLASSIFICATION OF THE MGR WASTE HANDLING BUILDING ELECTRICAL SYSTEM  

SciTech Connect

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) waste handling building electrical system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998).

S.E. Salzman

1999-08-31T23:59:59.000Z

462

Baseline descriptions for LWR spent fuel storage, handling, and transportation  

SciTech Connect

Baseline descriptions for the storage, handling, and transportation of reactor spent fuel are provided. The storage modes described include light water reactor (LWR) pools, away-from-reactor basins, dry surface storage, reprocessing-facility interim storage pools, and deep geologic storage. Land and water transportation are also discussed. This work was sponsored by the Department of Energy/Office of Safeguards and Security as part of the Sandia Laboratories Fixed Facility Physical Protection Program. 45 figs, 4 tables.

Moyer, J.W.; Sonnier, C.S.

1978-04-01T23:59:59.000Z

463

Best Practices for Biomass Handling in Wood Yard Operations  

Science Conference Proceedings (OSTI)

Utilities are beginning to add wood and other biomass fuels to fire their generating units to enable them to produce carbon-neutral electricity and participate in state or national renewable energy programs. However, because the material handling aspects of biomass differ from those of coal, firing at a significant scale requires new equipment to receive, store, and deliver the biomass to the flame front. This equipment is analogous in function to existing machinery but is quite different in detail, desi...

2011-08-29T23:59:59.000Z

464

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

465

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

466

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 > Nuclea