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1

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....

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

3

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

4

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...

5

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

6

Understanding Contamination; Twenty Years of Simulating Radiological Contamination  

SciTech Connect

A wide variety of simulated contamination methods have been developed by researchers to reproducibly test radiological decontamination methods. Some twenty years ago a method of non-radioactive contamination simulation was proposed at the Idaho National Laboratory (INL) that mimicked the character of radioactive cesium and zirconium contamination on stainless steel. It involved baking the contamination into the surface of the stainless steel in order to 'fix' it into a tenacious, tightly bound oxide layer. This type of contamination was particularly applicable to nuclear processing facilities (and nuclear reactors) where oxide growth and exchange of radioactive materials within the oxide layer became the predominant model for material/contaminant interaction. Additional simulation methods and their empirically derived basis (from a nuclear fuel reprocessing facility) are discussed. In the last ten years the INL, working with the Defense Advanced Research Projects Agency (DARPA) and the National Homeland Security Research Center (NHSRC), has continued to develop contamination simulation methodologies. The most notable of these newer methodologies was developed to compare the efficacy of different decontamination technologies against radiological dispersal device (RDD, 'dirty bomb') type of contamination. There are many different scenarios for how RDD contamination may be spread, but the most commonly used one at the INL involves the dispersal of an aqueous solution containing radioactive Cs-137. This method was chosen during the DARPA projects and has continued through the NHSRC series of decontamination trials and also gives a tenacious 'fixed' contamination. Much has been learned about the interaction of cesium contamination with building materials, particularly concrete, throughout these tests. The effects of porosity, cation-exchange capacity of the material and the amount of dirt and debris on the surface are very important factors. The interaction of the contaminant/substrate with the particular decontamination technology is also very important. Results of decontamination testing from hundreds of contaminated coupons have lead to certain conclusions about the contamination and the type of decontamination methods being deployed. A recent addition to the DARPA initiated methodology simulates the deposition of nuclear fallout. This contamination differs from previous tests in that it has been developed and validated purely to simulate a 'loose' type of contamination. This may represent the first time that a radiologically contaminated 'fallout' stimulant has been developed to reproducibly test decontamination methods. While no contaminant/methodology may serve as a complete example of all aspects that could be seen in the field, the study of this family of simulation methods provides insight into the nature of radiological contamination.

Emily Snyder; John Drake; Ryan James

2012-02-01T23:59:59.000Z

7

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

8

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

9

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

10

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

11

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

12

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

13

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

14

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

15

Radiological Contamination Control Training for Laboratory Research  

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

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

16

Radiological Contamination Control Training for Laboratory Research  

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

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

17

THE RADIOLOGICAL ASSESSMENT AND RECOVERY OF CONTAMINATED AREAS  

SciTech Connect

The Civil Effects Test Operation Exercise CEX-57.1 following Operation Plumbbob was carried out to obtain information on decontamination procedures that could be used as radiological countermeasures. The test was conducted on D + 1 and D + 2 days after shot Coulomb C. Data were obtained on reclamation of land areas by scraping with a motorgrader, on fire-hosing and scrubbing a concrete- slab roof, and on fire-hosing a composition roof. In addition, some shielding data were obtained for a small building with 6-in.-thick concrete walls and roof. The conceptual nature of a radiological defense system and the role of decontamination or reclamation in such a system are discussed. Most of the report deals with methods for reducing the observed data to interpretive form because the data were taken within a large contaminated area. The decontamination effectiveness in terms of the fraction of contamination remaining was computed. It is concluded that low levels of contamination at the Nevada Test Site could be utilized to advantage to obtain data on gamma -radiation properties, such as the effects of materials and source geometries on the attenuation of fission-product gamma rays. However, higher levels of fall-out in terms of the fall-out particle mass, are required to obtain useful information and training on decontamination techniques; therefore the use of low levels of contamination to conduct studies in this area is not recommended. (auth)

Miller, C.F.

1958-03-01T23:59:59.000Z

18

Assessment of SRS radiological liquid and airborne contaminants and pathways  

Science Conference Proceedings (OSTI)

This report compiles and documents the radiological critical-contaminant/critical-pathway analysis performed for SRS. The analysis covers radiological releases to the atmosphere and to surface water, which are the principal media that carry contaminants off site. During routine operations at SRS, limited amounts of radionuclides are released to the environment through atmospheric and/or liquid pathways. These releases potentially result in exposure to offsite people. Though the groundwater beneath an estimated 5 to 10 percent of SRS has been contaminated by radionuclides, there is no evidence that groundwater contaminated with these constituents has migrated offsite (Arnett, 1996). Therefore, with the notable exception of radiological source terms originating from shallow surface water migration into site streams, onsite groundwater was not considered as a potential exposure pathway to offsite people.

Jannik, G.T.

1997-04-01T23:59:59.000Z

19

Biological Treatment of Petroleum in Radiologically Contaminated Soil  

DOE Green Energy (OSTI)

This chapter describes ex situ bioremediation of the petroleum portion of radiologically co-contaminated soils using microorganisms isolated from a waste site and innovative bioreactor technology. Microorganisms first isolated and screened in the laboratory for bioremediation of petroleum were eventually used to treat soils in a bioreactor. The bioreactor treated soils contaminated with over 20,000 mg/kg total petroleum hydrocarbon and reduced the levels to less than 100 mg/kg in 22 months. After treatment, the soils were permanently disposed as low-level radiological waste. The petroleum and radiologically contaminated soil (PRCS) bioreactor operated using bioventing to control the supply of oxygen (air) to the soil being treated. The system treated 3.67 tons of PCRS amended with weathered compost, ammonium nitrate, fertilizer, and water. In addition, a consortium of microbes (patent pending) isolated at the Savannah River National Laboratory from a petroleum-contaminated site was added to the PRCS system. During operation, degradation of petroleum waste was accounted for through monitoring of carbon dioxide levels in the system effluent. The project demonstrated that co-contaminated soils could be successfully treated through bioventing and bioaugmentation to remove petroleum contamination to levels below 100 mg/kg while protecting workers and the environment from radiological contamination.

BERRY, CHRISTOPHER

2005-11-14T23:59:59.000Z

20

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...

Note: This page contains sample records for the topic "radiologically contaminated material" 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

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

22

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

23

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...

24

Radiological control criteria for materials considered for recycle and reuse  

Science Conference Proceedings (OSTI)

Pacific Northwest Laboratory (PNL) is conducting technical analyses to support the US Department of Energy (DOE), Office of Environmental Guidance, Air, Water, and Radiation Division (DOE/EH-232) in developing radiological control criteria for recycling or reuse of metals or equipment containing residual radioactive contamination from DOE operations. The criteria, framed as acceptable concentrations for release of materials for recycling or reuse, are risk-based and were developed through analysis of generic radiation exposure scenarios and pathways. The analysis includes evaluation of relevant radionuclides, potential mechanisms of exposure, and non-health-related impacts of residual radioactivity on electronics and film. The analysis considers 42 key radionuclides that DOE operations are known to generate and that may be contained in recycled or reused metals or equipment. Preliminary results are compared with similar results reported by the International Atomic Energy Agency, by radionuclide grouping.

Kennedy, W.E. Jr.; Hill, R.L.; Aaberg, R.L. [Pacific Northwest Lab., Richland, WA (United States); Wallo, A. III [USDOE Assistant Secretary for Environment, Safety, and Health, Washington, DC (United States). Office of Environmental Guidance

1994-11-01T23:59:59.000Z

25

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...

26

HTO Contamination on Polymeric Materials  

Science Conference Proceedings (OSTI)

Contamination and Waste / Proceedings of the Ninth International Conference on Tritium Science and Technology

Yasunori Iwai; Kazuhiro Kobayashi; Toshihiko Yamanishi

27

GTRI's Nuclear and Radiological Material Protection | National Nuclear  

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

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

28

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

National Nuclear Security Administration (NNSA)

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

29

Estimating the exposure to first receivers from a contaminated victim of a radiological dispersal device detonation  

E-Print Network (OSTI)

The threat of a Radiological Dispersal Device (RDD) detonation arouses the concern of contaminated victims of all ages. The purpose of this study was to investigate the dose to a uniformly contaminated five-year old male. It also explores the exposure rates surrounding the victim to be used by first receivers to estimate their exposure from the victim. The victim was modeled as an anthropomorphic phantom using the BodyBuilder program. A thin layer of source material was added to the surface of the phantom’s skin to simulate whole-body contamination. The computer code MCNP5 was used to tally the doses to the individual organs of the phantom and create a mesh to generate contour exposure rate lines. Using an activity of 37 GBq m-2, the five-year-old victim received an effective dose 158.23 mSv in one hour. Contour lines were produced that showed the exposure rates around the victims ranging from 0.5 to 10 R/h. The contour exposure-rate contour lines were also generated after the removal of contaminated clothing. Removing the victim’s clothing reduced the exposure rates by eighty percent.

Phillips, Holly Anne

2008-08-01T23:59:59.000Z

30

Treatment options for low-level radiologically contaminated ORNL filtercake  

Science Conference Proceedings (OSTI)

Water softening sludge (>4000 stored low level contaminated drums; 600 drums per year) generated by the ORNL Process Waste Treatment Plant must be treated, stabilized, and placed in safe storage/disposal. The sludge is primarily CaCO{sub 3} and is contaminated by low levels of {sup 90}Sr and {sup 137}Cs. In this study, microwave sintering and calcination were evaluated for treating the sludge. The microwave melting experiments showed promise: volume reductions were significant (3-5X), and the waste form was durable with glass additives (LiOH, fly ash). A commercial vendor using surrogate has demonstrated a melt mineralization process that yields a dense monolithic waste form with a volume reduction factor (VR) of 7.7. Calcination of the sludge at 850-900 C yielded a VR of 2.5. Compaction at 4500 psi increased the VR to 4.2, but the compressed form is not dimensionally stable. Addition of paraffin helped consolidate fines and yielded a VR of 3.5. In conclusion, microwave melting or another form of vitrification is likely to be the best method; however for immediate implementation, the calculation/compaction/waxing process is viable.

Lee, Hom-Ti [Oak Ridge Associated Universities, Inc., TN (United States); Bostick, W.D. [Oak Ridge K-25 Site, TN (United States)

1996-04-01T23:59:59.000Z

31

Potential Radiological Doses From Groundwater Contaminated By The Saltstone Disposal Facility  

SciTech Connect

Assessments of radiological dose from usage of groundwater potentially contaminated by the Saltstone Disposal Facility (Z-Area) were made for a hypothetical future resident farmer. These assessments were made using the routine aqueous release model LADTAP XL (C), which is the model used for demonstrating liquid pathway dose compliance at SRS. The dose factors used in LADTAP XL (C) are those specified by the Department of Energy.

GERALD, JANNIK

2005-02-14T23:59:59.000Z

32

Bioremediation of Petroleum and Radiological Contaminated Soils at the Savannah River Site: Laboratory to Field Scale Applications  

DOE Green Energy (OSTI)

In the process of Savannah River Site (SRS) operations limited amounts of waste are generated containing petroleum, and radiological contaminated soils. Currently, this combination of radiological and petroleum contaminated waste does not have an immediate disposal route and is being stored in low activity vaults. SRS developed and implemented a successful plan for clean up of the petroleum portion of the soils in situ using simple, inexpensive, bioreactor technology. Treatment in a bioreactor removes the petroleum contamination from the soil without spreading radiological contamination to the environment. This bioreactor uses the bioventing process and bioaugmentation or the addition of the select hydrocarbon degrading bacteria. Oxygen is usually the initial rate-limiting factor in the biodegradation of petroleum hydrocarbons. Using the bioventing process allowed control of the supply of nutrients and moisture based on petroleum contamination concentrations and soil type. The results of this work have proven to be a safe and cost-effective means of cleaning up low level radiological and petroleum-contaminated soil. Many of the other elements of the bioreactor design were developed or enhanced during the demonstration of a ''biopile'' to treat the soils beneath a Polish oil refinery's waste disposal lagoons. Aerobic microorganisms were isolated from the aged refinery's acidic sludge contaminated with polycyclic aromatic hydrocarbons (PAHs). Twelve hydrocarbon-degrading bacteria were isolated from the sludge. The predominant PAH degraders were tentatively identified as Achromobacter, Pseudomonas Burkholderia, and Sphingomonas spp. Several Ralstonia spp were also isolated that produce biosurfactants. Biosurfactants can enhance bioremediation by increasing the bioavailability of hydrophobic contaminants including hydrocarbons. The results indicated that the diversity of acid-tolerant PAH-degrading microorganisms in acidic oil wastes may be much greater than previously demonstrated and they have numerous applications to environmental restoration. Twelve of the isolates were subsequently added to the bioreactor to enhance bioremediation. In this study we showed that a bioreactor could be bioaugmented with select bacteria to enhance bioremediation of petroleum-contaminated soils under radiological conditions.

BRIGMON, ROBINL.

2004-06-07T23:59:59.000Z

33

Radiological engineering services for the design of special contamination containments. Final report  

SciTech Connect

The purpose of this study was to provide radiological engineering services for the design of special contamination containments. These containments were to be used during the replacement of leaking and damaged gaskets on the glove boxes in Technical Area-55 (TA-55). The damaged gaskets involved 18 windows and 5 interconnecting spool pieces in fuel processing glove boxes. The work scope included the design and manufacture of special contamination containment enclosures (containments), the preparation of procedures and tool lists to support gasket replacement while using the containments, and the training of appropriate TA-55 personnel in the proper installation, operation and removal of the containments. It was originally anticipated that two basic containment designs would be required, one for the windows and one for spool pieces. Upon examination of the glove boxes it was evident that the individual space envelopes and interferences associated with each glove box would require uniquely designed containments for effective gasket replacement. This resulted in 13 individual containment designs that accommodated the interferences and allowed gasket replacement within the containment. Successful use of the containments for glove box gasket replacement was a significant accomplishment. The operation has proven that a properly managed containment program can enhance routine maintenance of the glove boxes while preventing a contamination release. The ability to perform these operations in containments reduces costs by preventing a contaminant release and eliminating the associated cleanup expenses, reduced radioactive waste and fuel processing down time.

NONE

1996-12-31T23:59:59.000Z

34

Methods for removing contaminant matter from a porous material  

DOE Patents (OSTI)

Methods of removing contaminant matter from porous materials include applying a polymer material to a contaminated surface, irradiating the contaminated surface to cause redistribution of contaminant matter, and removing at least a portion of the polymer material from the surface. Systems for decontaminating a contaminated structure comprising porous material include a radiation device configured to emit electromagnetic radiation toward a surface of a structure, and at least one spray device configured to apply a capture material onto the surface of the structure. Polymer materials that can be used in such methods and systems include polyphosphazine-based polymer materials having polyphosphazine backbone segments and side chain groups that include selected functional groups. The selected functional groups may include iminos, oximes, carboxylates, sulfonates, .beta.-diketones, phosphine sulfides, phosphates, phosphites, phosphonates, phosphinates, phosphine oxides, monothio phosphinic acids, and dithio phosphinic acids.

Fox, Robert V. (Idaho Falls, ID); Avci, Recep (Bozeman, MT); Groenewold, Gary S. (Idaho Falls, ID)

2010-11-16T23:59:59.000Z

35

Radiological Monitoring Equipment For Real-Time Quantification Of Area Contamination In Soils And Facility Decommissioning  

SciTech Connect

The environmental restoration industry offers several sys¬tems that perform scan-type characterization of radiologically contaminated areas. The Idaho National Laboratory (INL) has developed and deployed a suite of field systems that rapidly scan, characterize, and analyse radiological contamination in surface soils. The base system consists of a detector, such as sodium iodide (NaI) spectrometers, a global positioning system (GPS), and an integrated user-friendly computer interface. This mobile concept was initially developed to provide precertifica¬tion analyses of soils contaminated with uranium, thorium, and radium at the Fernald Closure Project, near Cincinnati, Ohio. INL has expanded the functionality of this basic system to create a suite of integrated field-deployable analytical systems. Using its engineering and radiation measurement expertise, aided by computer hardware and software support, INL has streamlined the data acquisition and analysis process to provide real-time information presented on wireless screens and in the form of coverage maps immediately available to field technicians. In addition, custom software offers a user-friendly interface with user-selectable alarm levels and automated data quality monitoring functions that validate the data. This system is deployed from various platforms, depending on the nature of the survey. The deployment platforms include a small all-terrain vehicle used to survey large, relatively flat areas, a hand-pushed unit for areas where manoeuvrability is important, an excavator-mounted system used to scan pits and trenches where personnel access is restricted, and backpack- mounted systems to survey rocky shoreline features and other physical settings that preclude vehicle-based deployment. Variants of the base system include sealed proportional counters for measuring actinides (i.e., plutonium-238 and americium-241) in building demolitions, soil areas, roadbeds, and process line routes at the Miamisburg Closure Project near Dayton, Ohio. In addition, INL supports decontamination operations at the Oak Ridge National Laboratory.

M. V. Carpenter; Jay A. Roach; John R Giles; Lyle G. Roybal

2005-09-01T23:59:59.000Z

36

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...

37

Control levels for residual contamination in materials considered for recycle and reuse  

Science Conference Proceedings (OSTI)

Pacific Northwest Laboratory (PNL) is collecting data and conducting technical analyses to support joint efforts by the U.S. Department of Energy (DOE), Office of Environmental Guidance, Air, Water and Radiation Division (DOE/EH-232); by the U.S. Environmental Protection Agency (EPA); and by the U.S. Nuclear Regulatory Commission (NRC) to develop radiological control criteria for the recycle and reuse of scrap materials and equipment that contain residual radioactive contamination. The initial radiological control levels are the concentrations in or on materials considered for recycle or reuse that meet the individual (human) or industrial (electronics/film) dose criteria. The analysis identifies relevant radionuclides, potential mechanisms of exposure, and methods to determine possible non-health-related impacts from residual radioactive contamination in materials considered for recycle or reuse. The generic methodology and scenarios described here provide a basic framework for numerically deriving radiological control criteria for recycle or reuse. These will be adequately conservative for most situations.

Hill, R.L.; Aaberg, R.L.; Baker, D.A.; Kennedy, W.E. Jr.

1993-09-01T23:59:59.000Z

38

RESRAD-RECYCLE : a computer model for analyzing radiation exposures resulting from recycling radioactively contaminated scrap metals or reusing ratioactively surface-contaminated materials and equipment.  

Science Conference Proceedings (OSTI)

RESRAD-RECYCLE is a computer code designed by Argonne National Laboratory (ANL) to be used in making decisions about the disposition of radioactively contaminated materials and scrap metals. It implements a pathway analysis methodology to evaluate potential radiation exposures resulting from the recycling of contaminated scrap metals and the reuse of surface-contaminated materials and equipment. For modeling purposes, it divides the entire metal recycling process into six steps: (1) scrap delivery, (2) scrap melting, (3) ingot delivery, (4) product fabrication, (5) product distribution, and (6) use of finished product. RESRAD-RECYCLE considers the reuse of surface-contaminated materials in their original forms. It contains representative exposure scenarios for each recycling step and the reuse process; users can also specify scenarios if desired. The model calculates individual and collective population doses for workers involved in the recycling process and for the public using the finished products. The results are then used to derive clearance levels for the contaminated materials on the basis of input dose restrictions. The model accounts for radiological decay and ingrowth, dilution and partitioning during melting, and distribution of refined metal in the various finished products, as well as the varying densities and geometries of the radiation sources during the recycling process. A complete material balance in terms of mass and radioactivity during the recycling process can also be implemented. In an international validation study, the radiation doses calculated by RESRAD-RECYCLE were shown to agree fairly well with actual measurement data.

Cheng, J. J.; Kassas, B.; Yu, C.; Arnish, J. J.; LePoire, D.; Chen, S.-Y.; Williams, W. A.; Wallo, A.; Peterson, H.; Environmental Assessment; DOE; Univ. of Texas

2004-11-01T23:59:59.000Z

39

Radiation dose assessments to support evaluations of radiological control levels for recycling or reuse of materials and equipment  

Science Conference Proceedings (OSTI)

Pacific Northwest Laboratory is providing Environmental Protection Support and Assistance to the USDOE, Office of Environmental Guidance. Air, Water, and Radiation Division. As part of this effort, PNL is collecting data and conducting technical evaluations to support DOE analyses of the feasibility of developing radiological control levels for recycling or reuse of metals, concrete, or equipment containing residual radioactive contamination from DOE operations. The radiological control levels will be risk-based, as developed through a radiation exposure scenario and pathway analysis. The analysis will include evaluation of relevant radionuclides, potential mechanisms of exposure, and both health and non-health-related impacts. The main objective of this report is to develop a methodology for establishing radiological control levels for recycle or reuse. This report provides the results of the radiation exposure scenario and pathway analyses for 42 key radionuclides generated during DOE operations that may be contained in metals or equipment considered for either recycling or reuse. The scenarios and information developed by the IAEA. Application of Exemption Principles to the Recycle and Reuse of Materials from Nuclear Facilities, are used as the initial basis for this study. The analyses were performed for both selected worker populations at metal smelters and for the public downwind of a smelter facility. Doses to the public downwind were estimated using the US (EPA) CAP88-PC computer code with generic data on atmospheric dispersion and population density. Potential non-health-related effects of residual activity on electronics and on film were also analyzed.

Hill, R.L.; Aaberg, R.L.; Baker, D.A.; Kennedy, W.E. Jr.

1995-07-01T23:59:59.000Z

40

A radiological and chemical investigation of the 7500 Area Contamination Site at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

Science Conference Proceedings (OSTI)

A radiological and chemical investigation of the 7500 Area Contamination Site at Oak Ridge National Laboratory (ORNL) was conducted intermittently from February 1992 through May 1992. The investigation was performed by the Measurement Applications and Development Group of the Health and Safety Research Division of ORNL at the request of the US Department of Energy`s Oak Ridge Operations Office and the ORNL Environmental Restoration Program. Results of this investigation indicate that the source of radioactive contamination at the point of the contamination incident is from one of the underground abandoned lines. The contamination in soil is likely the result of residual contamination from years of waste transport and maintenance operations (e.g., replacement of degraded joints, upgrading or replacement of entire pipelines, and associated landscaping activities). However, because (1) there is currently an active LLW line positioned in the same subsurface trench with the abandoned lines and (2) the physical condition of the abandoned lines may be brittle, this inquiry could not determine which abandoned line was responsible for the subsurface contamination. Soil sampling at the location of the contamination incident and along the pipeline route was performed in a manner so as not to damage the active LLW line and abandoned lines. Recommendations for corrective actions are included.

Williams, J.K.; Foley, R.D.; Tiner, P.F.; Hatmaker, T.L.; Uziel, M.S.; Swaja, R.E.

1993-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiologically contaminated material" 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

Controlling Beryllium Contaminated Material And Equipment For The Building 9201-5 Legacy Material Disposition Project  

SciTech Connect

This position paper addresses the management of beryllium contamination on legacy waste. The goal of the beryllium management program is to protect human health and the environment by preventing the release of beryllium through controlling surface contamination. Studies have shown by controlling beryllium surface contamination, potential airborne contamination is reduced or eliminated. Although there are areas in Building 9201-5 that are contaminated with radioactive materials and mercury, only beryllium contamination is addressed in this management plan. The overall goal of this initiative is the compliant packaging and disposal of beryllium waste from the 9201-5 Legacy Material Removal (LMR) Project to ensure that beryllium surface contamination and any potential airborne release of beryllium is controlled to levels as low as practicable in accordance with 10 CFR 850.25.

Reynolds, T. D.; Easterling, S. D.

2010-10-01T23:59:59.000Z

42

Standard Guide for Post-Deactivation Surveillance and Maintenance of Radiologically Contaminated Facilities  

E-Print Network (OSTI)

1.1 This guide outlines a method for developing a Surveillance and Maintenance (S&M) plan for inactive nuclear facilities. It describes the steps and activities necessary to prevent loss or release of radioactive or hazardous materials, and to minimize physical risks between the deactivation phase and the start of facility decontamination and decommissioning (D&D). 1.2 The primary concerns for S&M are related to (1) animal intrusion, (2) structural integrity degradation, (3) water in-leakage, (4) contamination migration, (5) unauthorized personnel entry, and (6) theft/intrusion. This document is intended to serve as a guide only, and is not intended to modify existing regulations.

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

43

Active Neutron Interrogation of Non-Radiological Materials with NMIS  

Science Conference Proceedings (OSTI)

The Nuclear Materials Identification System (NMIS) at Oak Ridge National Laboratory (ORNL), although primarily designed for analyzing special nuclear material, is capable of identifying nonradiological materials with a wide range of measurement techniques. This report demonstrates four different measurement methods, complementary to fast-neutron imaging, which can be used for material identification: DT transmission, DT scattering, californium transmission, and active time-tagged gamma spectroscopy. Each of the four techniques was used to evaluate how these methods can be used to identify four materials: aluminum, polyethylene, graphite, and G-10 epoxy. While such measurements have been performed individually in the past, in this project, all four measurements were performed on the same set of materials. The results of these measurements agree well with predicted results. In particular, the results of the active gamma spectroscopy measurements demonstrate the technique's applicability in a future version of NMIS which will incorporate passive and active gamma-ray spectroscopy. This system, designated as a fieldable NMIS (FNMIS), is under development by the US Department of Energy Office of Nuclear Verification.

Walker, Mark E [ORNL; Mihalczo, John T [ORNL

2012-02-01T23:59:59.000Z

44

Radiological dose assessment related to management of naturally occurring radioactive materials generated by the petroleum industry  

Science Conference Proceedings (OSTI)

A preliminary radiological dose assessment related to equipment decontamination, subsurface disposal, landspreading, equipment smelting, and equipment burial was conducted to address concerns regarding the presence of naturally occurring radioactive materials in production waste streams. The assessment evaluated the relative dose of these activities and included a sensitivity analysis of certain input parameters. Future studies and potential policy actions are recommended.

Smith, K.P.; Blunt, D.L.; Williams, G.P.; Tebes, C.L. [Argonne National Lab., IL (United States). Environmental Assessment Div.

1995-05-01T23:59:59.000Z

45

Radiological, physical, and chemical characterization of low-level alpha contaminated wastes stored at the Idaho National Engineering Laboratory  

SciTech Connect

This document provides radiological, physical, and chemical characterization data for low-level alpha-contaminated radioactive and low-level alpha-contaminated radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program. Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 97 waste streams which represent an estimated total volume of 25,450 m 3 corresponding to a total mass of approximately 12,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats-generated waste forms stored at the INEL are provided to assist in facility design specification.

Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

1994-03-01T23:59:59.000Z

46

Standard practice for radiologic examination of flat panel composites and sandwich core materials used in aerospace applications  

E-Print Network (OSTI)

1.1 This practice is intended to be used as a supplement to Practices E 1742, E 1255, and E 2033. 1.2 This practice describes procedures for radiologic examination of flat panel composites and sandwich core materials made entirely or in part from fiber-reinforced polymer matrix composites. Radiologic examination is: a) radiographic (RT) with film, b) Computed Radiography (CR) with Imaging Plate, c) Digital Radiology (DR) with Digital Detector Array’s (DDA), and d) Radioscopic (RTR) Real Time Radiology with a detection system such as an Image Intensifier. The composite materials under consideration typically contain continuous high modulus fibers (> 20 GPa), such as those listed in 1.4. 1.3 This practice describes established radiological examination methods that are currently used by industry that have demonstrated utility in quality assurance of flat panel composites and sandwich core materials during product process design and optimization, process control, after manufacture inspection, in service exami...

American Society for Testing and Materials. Philadelphia

2009-01-01T23:59:59.000Z

47

Radiolytic gas generation in plutonium contaminated waste materials  

DOE Green Energy (OSTI)

Many plutonium contaminated waste materials decompose into gaseous products because of exposure to alpha radiation. The gases generated (usually hydrogen) over long-storage periods may create hazardous conditions. To determine the extent of such hazards, knowing the gas generation yields is necessary. These yields were measured by contacting some common Rocky Flats Plant waste materials with plutonium and monitoring the enclosed atmospheres for extensive periods of time. The materials were Plexiglas, polyvinyl chloride, glove-box gloves, machining oil, carbon tetrachloride, chlorothene VG solvent, Kimwipes (dry and wet), polyethylene, Dowex-1 resin, and surgeon's gloves. Both /sup 239/Pu oxide and /sup 238/Pu oxide were used as radiation sources. The gas analyses were made by mass spectrometry and the results obtained were the total gas generation, the hydrogen generation, the oxygen consumption rate, and the gas composition over the entire storage period. Hydrogen was the major gas produced in most of the materials. The total gas yields varied from 0.71 to 16 cm/sup 3/ (standard temperature pressure) per day per curie of plutonium. The oxygen consumption rates varied from 0.0088 to 0.070 millimoles per day per gram of plutonium oxide-239 and from 0.0014 to 0.0051 millimoles per day per milligram /sup 238/Pu.

Kazanjian, A.R.

1976-10-29T23:59:59.000Z

48

MERCURY CONTAMINATED MATERIAL DECONTAMINATION METHODS: INVESTIGATION AND ASSESSMENT  

Science Conference Proceedings (OSTI)

Over the years mercury has been recognized as having serious impacts on human health and the environment. This recognition has led to numerous studies that deal with the properties of various mercury forms, the development of methods to quantify and speciate the forms, fate and transport, toxicology studies, and the development of site remediation and decontamination technologies. This report reviews several critical areas that will be used in developing technologies for cleaning mercury from mercury-contaminated surfaces of metals and porous materials found in many DOE facilities. The technologies used for decontamination of water and mixed wastes (solid) are specifically discussed. Many technologies that have recently appeared in the literature are included in the report. Current surface decontamination processes have been reviewed, and the limitations of these technologies for mercury decontamination are discussed. Based on the currently available technologies and the processes published recently in the literature, several processes, including strippable coatings, chemical cleaning with iodine/iodide lixiviant, chemisorbing surface wipes with forager sponge and grafted cotton, and surface/pore fixation through amalgamation or stabilization, have been identified as potential techniques for decontamination of mercury-contaminated metal and porous surfaces. Their potential merits and applicability are discussed. Finally, two processes, strippable coatings and chemical cleaning with iodine/iodide lixiviant, were experimentally investigated in Phase II of this project.

M.A. Ebadian, Ph.D.

2001-01-01T23:59:59.000Z

49

Radiological Dose Assessment Related to Management of Naturally Occurring Radioactive Materials Generated by the Petroleum Industry  

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

Tebes is affiliated with the University of Illinois. Tebes is affiliated with the University of Illinois. ANL/EAD-2 Radiological Dose Assessment Related to Management of Naturally Occurring Radioactive Materials Generated by the Petroleum Industry by K.P. Smith, D.L. Blunt, G.P. Williams, and C.L. Tebes * Environmental Assessment Division Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439 September 1996 Work sponsored by the United States Department of Energy, Office of Policy iii CONTENTS ACKNOWLEDGMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vii NOTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . viii ABSTRACT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

50

Development and Testing of an Air Fluorescence Imaging System for the Detection of Radiological Contamination  

SciTech Connect

Detection of radionuclides emitting short-range radiation, such as {alpha} and low-energy {beta} particles, has always presented a challenge, particularly when such radionuclides are dispersed over a wide area. In this situation, conventional detection methods require the area of interest to be surveyed using a fragile probe at very close range--a slow, error-prone, and potentially dangerous process that may take many hours for a single room. The instrument under development uses a novel approach by imaging radiation-induced fluorescence in the air surrounding a contaminated area, rather than detecting the radiation directly. A robust and portable system has been designed and built that will allow contaminated areas to be rapidly detected and delineated. The detector incorporates position-sensitive photo-multiplier tubes, UV filters, a fast electronic shutter and an aspherical phase mask that significantly increases the depth-of-field. Preliminary tests have been conducted using sealed {sup 241}Am sources of varying activities and surface areas. The details of the instrument design will be described and the results of recent testing will be presented.

Inrig, Elizabeth [Defence R and D Canada - Ottawa, 3701 Carling Avenue, Ottawa, Ontario (Canada); Koslowsky, Vern; Andrews, Bob; Dick, Michael; Forget, Patrick; Ing, Harry [Bubble Technology Industries, Box 100, Chalk River, Ontario (Canada); Hugron, Roger [Director General Nuclear Safety, 101 Colonel By Drive, Ottawa, Ontario (Canada); Wong, Larry [Canadian Nuclear Safety Commission, 3484 Limebank Road, Ottawa, Ontario (Canada)

2011-12-13T23:59:59.000Z

51

Evaluation of internal contamination levels after a radiological dispersal device incident using portal monitors  

SciTech Connect

Following a radioactive dispersal device (RDD) incident, it may be necessary to evaluate the internal contamination levels of a large number of potentially affected individuals to determine if immediate medical follow-up is necessary. Since the current laboratory capacity to screen for internal contamination is limited, rapid field screening methods can be useful in prioritizing individuals. This study evaluated the suitability of a radiation portal monitor for such screening. A model of the portal monitor was created for use with models of six anthropomorphic phantoms in Monte Carlo N-Particle Transport Code Version 5 (MCNP) X-5 Monte Carlo Team (MCNP A General Monte Carlo N-Particle Transport Code Version 5. LA-CP-03-0245. Vol. 2. Los Alamos National Laboratory, 2004.). The count rates of the portal monitor were simulated for inhalation and ingestion of likely radionuclides from an RDD for each of the phantoms. The time-dependant organ concentrations of the radionuclides were determined using Dose and Risk Calculation Software Eckerman, Leggett, Cristy, Nelson, Ryman, Sjoreen and Ward (Dose and Risk Calculation Software Ver. 8.4. ORNL/TM-2001/190. Oak Ridge National Laboratory, 2006.). Portal monitor count rates corresponding to a committed effective dose E(50) of 10 mSv are reported.

Palmer, R.C. [Georgia Institute of Technology; Hertel, Nolan [Georgia Institute of Technology; Ansari, A. [Centers for Disease Control and Prevention; Manger, Ryan P [ORNL; Freibert, E.J. [Georgia Institute of Technology

2012-01-01T23:59:59.000Z

52

Corrective Action Decision Document for Corrective Action Unit 168: Area 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada, Rev. No.: 2 with Errata Sheet  

SciTech Connect

This Corrective Action Decision Document has been prepared for Corrective Action Unit (CAU) 168: Area 25 and 26, Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada. The purpose of this Corrective Action Decision Document is to identify and provide a rationale for the selection of a recommended corrective action alternative for each corrective action site (CAS) within CAU 168. The corrective action investigation (CAI) was conducted in accordance with the ''Corrective Action Investigation Plan for Corrective Action Unit 168: Area 25 and 26, Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada'', as developed under the ''Federal Facility Agreement and Consent Order'' (1996). Corrective Action Unit 168 is located in Areas 25 and 26 of the Nevada Test Site, Nevada and is comprised of the following 12 CASs: CAS 25-16-01, Construction Waste Pile; CAS 25-16-03, MX Construction Landfill; CAS 25-19-02, Waste Disposal Site; CAS 25-23-02, Radioactive Storage RR Cars; CAS 25-23-13, ETL - Lab Radioactive Contamination; CAS 25-23-18, Radioactive Material Storage; CAS 25-34-01, NRDS Contaminated Bunker; CAS 25-34-02, NRDS Contaminated Bunker; CAS 25-99-16, USW G3; CAS 26-08-01, Waste Dump/Burn Pit; CAS 26-17-01, Pluto Waste Holding Area; and CAS 26-19-02, Contaminated Waste Dump No.2. Analytes detected during the CAI were evaluated against preliminary action levels (PALs) to determine contaminants of concern (COCs) for CASs within CAU 168. Radiological measurements of railroad cars and test equipment were compared to unrestricted (free) release criteria. Assessment of the data generated from the CAI activities revealed the following: (1) Corrective Action Site 25-16-01 contains hydrocarbon-contaminated soil at concentrations exceeding the PAL. The contamination is at discrete locations associated with asphalt debris. (2) No COCs were identified at CAS 25-16-03. Buried construction waste is present in at least two disposal cells contained within the landfill boundaries. (3) No COCs were identified at CAS 25-19-02. (4) Radiological surveys at CAS 25-23-02 identified 13 railroad cars that exceeded the NV/YMP Radiological Control Manual limits for free release. Six railroad cars were below these limits and therefore met the free-release criteria. (5) An In-Situ Object Counting System survey taken at CAS 25-23-02 identified two railroad cars possibly containing fuel fragments; both exceeded the NV/YMP Radiological Control Manual free release criteria. (6) Corrective Action Site 25-23-18 contains total petroleum hydrocarbons-diesel-range organics, Aroclor-1260, uranium-234, uranium-235, strontium-90, and cesium-137 that exceed PALs. (7) Radiological surveys at CAS 25-34-01 indicate that there were no total contamination readings that exceeded the NV/YMP Radiological Control Manual limits for free release. (8) Radiological surveys at CAS 25-34-02 indicate that there were no total contamination readings that exceeded the NV/YMP Radiological Control Manual limits for free release. (9) Radiological surveys at CAS 25-23-13 identified six pieces of equipment that exceed the NV/YMP Radiological Control Manual limits for free release. (10) Corrective Action Site 25-99-16 was not investigated. A review of historical documentation and current site conditions showed that no further characterization was required to select the appropriate corrective action. (11) Corrective Action Site 26-08-01 contains hydrocarbon-contaminated soil at concentrations exceeding the PAL. The contamination is at discrete locations associated with asphalt debris. (12) Corrective Action Site 26-17-01 contains total petroleum hydrocarbons-diesel-range organics and Aroclor-1260 exceeding the PALs. (13) Radiological surveys at CAS 26-19-02 identified metallic debris that exceeded the NV/YMP Radiological Control Manual limits for free release. Concentrations of radiological or chemical constituents in soil did not exceed PALs.

Wickline, Alfred

2006-12-01T23:59:59.000Z

53

Radiological Assessment of Target Materials for Accelerator Transmutation of Waste (ATW) Applications  

Science Conference Proceedings (OSTI)

This paper issues the first published research of the radiation absorbed dose rate (rad-h-1) to tissue from radioactive spallation products in target materials of Ta, W, Pb, Bi, and LBE which are used in Accelerator Transmutation of Waste (ATW) applications. No previous works have provided an estimate of the absorbed dose rate (rad-h-1) from activated targets for ATW applications. The results of this paper are useful for planning the radiological safety assessment to personnel, and for the design, construction, maintenance, and disposition of target materials of high-energy particle accelerators for ATW applications. In addition, this paper provides the characterization of target materials of high-energy particle accelerators for the parameters of: 1) spallation neutron yield (neutrons/proton), 2) spallation products yield (nuclides/proton), 3) energy-dependent spallation neutron fluence distribution, 4) spallation neutron flux, 5) identification of radioactive spallation products for consideration in safety of personnel to high radiation dose rates, and 6) identification of the optimum geometrical dimensions for the target applicable to the maximum radial spallation neutron leakage from the target. Pb and Bi target materials yielded the lowest absorbed dose rates (rad-h-1) for a 10-year irradiation/50-year decay scheme, and would be the preferred target materials for consideration of the radiological safety of personnel during ATW operations. A beneficial characteristic of these target materials is that they do not produce radioactive transuranic isotopes, which have very long half-lives and require special handling and disposition requirements Furthermore, the targets are not considered High-Level Waste (HLW) such as reactor spent fuel for disposal purposes. It is a basic ATW system requirement that the spallation target after it has been expended should be disposable as Class C low-level radioactive waste. Therefore, the disposal of Pb and Bi targets would be optimally beneficial to the economy and environment. Future research should relate the target performance to other system parameters, specifically solid and liquid blanket systems that contain the radioactive waste to be transmuted. The methodology of this paper may be applied to any target material of a high-energy particle accelerator. (author)

Vickers, Linda D. [BWXT, U.S. Department of Energy, Pantex Plant, P.O. Box 30020, Hwy60/FM2373, Amarillo, TX 79120-0020 (United States)

2002-07-01T23:59:59.000Z

54

Guide for Characterization of Sites Contaminated with Energetic Materials  

E-Print Network (OSTI)

for the remediation of federal facility sites contaminated with explosives or radioactive wastes. EPA/625/R-93 be contaminated by EM: · Firing ranges - Small-arms ranges - Artillery ranges - Anti-tank ranges - Tank/013. EPA Method (1994) Nitroaromatics and nitramines by HPLC. In Test Methods for Evaluating Solid Waste

55

Radiological dose assessment for residual radioactive material in soil at the clean slate sites 1, 2, and 3, Tonopah Test Range  

SciTech Connect

A radiological dose assessment has been performed for Clean Slate Sites 1, 2, and 3 at the Tonopah Test Range, approximately 390 kilometers (240 miles) northwest of Las Vegas, Nevada. The assessment demonstrated that the calculated dose to hypothetical individuals who may reside or work on the Clean Slate sites, subsequent to remediation, does not exceed the limits established by the US Department of Energy for protection of members of the public and the environment. The sites became contaminated as a result of Project Roller Coaster experiments conducted in 1963 in support of the US Atomic Energy Commission (Shreve, 1964). Remediation of Clean Slate Sites 1, 2, and 3 is being performed to ensure that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works on a Clean Slate site should not exceed 100 millirems per year. The DOE residual radioactive material guideline (RESRAD) computer code was used to assess the dose. RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines (Yu et al., 1993a). In May and June of 1963, experiments were conducted at Clean Slate Sites 1, 2, and 3 to study the effectiveness of earth-covered structures for reducing the dispersion of nuclear weapons material as a result of nonnuclear explosions. The experiments required the detonation of various simulated weapons using conventional chemical explosives (Shreve, 1964). The residual radioactive contamination in the surface soil consists of weapons grade plutonium, depleted uranium, and their radioactive decay products.

NONE

1997-06-01T23:59:59.000Z

56

ASSET RECOVERY OF HAZARDOUS MATERIALS BENEFICIAL REUSE OF RADIOLOGICALLY ENCUMBERED LEAD STOCKS  

Science Conference Proceedings (OSTI)

Underutilized and surplus lead stocks and leaded components are a common legacy environmental problem across much of the Department of Energy (DOE) Complex. While seeking to dispose of these items through its Environmental Management Program, DOE operational programs continue to pursue contemporary mission requirements such as managing and/or storing radioactive isotopes that require lead materials for shielding. This paradox was identified in late 1999 when DOE's policies for managing scrap metal were assessed. In January 2000, the Secretary of Energy directed the National Center of Excellence for Materials Recycle (NMR) to develop and implement a comprehensive lead reuse program for all of DOE. Fluor Hanford, contractor for DOE Richland Operations, subsequently contacted NMR to pilot lead reclamation and reuse at the Hanford Site. This relationship resulted in the development of a beneficial reuse pathway for lead reclaimed from spent fuel transport railcars being stored at Hanford. The 1.3 million pounds of lead in the railcars is considered radiologically encumbered due to its prior use. Further, the material was considered a mixed Resource Conservation and Recovery Act (RCRA) low-level radioactive waste that would require expensive storage or macro encapsulation to meet land disposal restrictions prior to burial. Working closely with Flour Hanford and the Office of Air, Water, and Radiation (EH-412), NMR developed a directed reuse pathway for this and other radiologically encumbered lead. When derived supplemental release limits were used, the lead recovered from these railcars became eligible for reuse in shielding products to support DOE and commercial nuclear industry operations. Using this disposition pathway has saved Hanford one third of the cost of disposing of the lead and the cost of acquiring additional lead for nuclear shielding applications. Furthermore, the environmental costs associated with mining and producing new lead for shielding products a nd stewardship of the waste was eliminated. Methods and processes developed in cooperation with Fluor Hanford are applicable to, and have been successfully applied to, lead stocks at DOE sites such as Savannah River, Mound, Los Alamos, and Idaho.

Lloyd, E.R.; Meehan, R.W.

2003-02-27T23:59:59.000Z

57

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

58

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

59

Power-law distributions in events involving nuclear and radiological materials  

E-Print Network (OSTI)

Nuclear and radiological events are large-impact, hard-to-predict rare events, whose associated probability is exceedingly low. They can exert monumental impacts and lead to grave environmental and economic consequences. ...

Chow, Jijun

2009-01-01T23:59:59.000Z

60

Study of gas contaminants and interaction with materials in RPC closed loop system  

E-Print Network (OSTI)

Resistive Plate Counters (RPC) detectors at the Large Hadron Collider (LHC) experiments use gas recirculation systems to cope with large gas mixture volumes and costs. In this paper a long-term systematic study about gas purifiers, gas contaminants and detector performance is discussed. The study aims at measuring the lifetime of purifiers with new and used cartridge material along with contaminants release in the gas system. During the data-taking the response of several RPC double-gap detectors was monitored in order to characterize the correlation between dark currents, filter status and gas contaminants.

S. Colafranceschi; R. Aurilio; L. Benussi; S. Bianco; L. Passamonti; D. Piccolo; D. Pierluigi; A. Russo; M. Ferrini; T. Greci; G. Saviano; C. Vendittozzi; M. Abbrescia; C. Calabria; A. Colaleo; G. Iaselli; M. Maggi; S. Nuzzo; G. Pugliese; P. Verwilligen; A. Sharma

2013-02-21T23:59:59.000Z

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


61

Study of gas contaminants and interaction with materials in RPC closed loop system  

E-Print Network (OSTI)

Resistive Plate Counters (RPC) detectors at the Large Hadron Collider (LHC) experiments use gas recirculation systems to cope with large gas mixture volumes and costs. In this paper a long-term systematic study about gas purifiers, gas contaminants and detector performance is discussed. The study aims at measuring the lifetime of purifiers with new and used cartridge material along with contaminants release in the gas system. During the data-taking the response of several RPC double-gap detectors was monitored in order to characterize the correlation between dark currents, filter status and gas contaminants.

Colafranceschi, S; Benussi, L; Bianco, S; Passamonti, L; Piccolo, D; Pierluigi, D; Russo, A; Ferrini, M; Greci, T; Saviano, G; Vendittozzi, C; Abbrescia, M; Calabria, C; Colaleo, A; Iaselli, G; Maggi, M; Nuzzo, S; Pugliese, G; Verwilligen, P; Sharma, A

2013-01-01T23:59:59.000Z

62

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...

63

Forward model calculations for determining isotopic compositions of materials used in a radiological dispersal device  

E-Print Network (OSTI)

In the event that a radiological dispersal device (RDD) is detonated in the U.S. or near U.S. interests overseas, it will be crucial that the actors involved in the event can be identified quickly. If irradiated nuclear fuel is used as the dispersion material for the RDD, it will be beneficial for law enforcement officials to quickly identify where the irradiated nuclear fuel originated. One signature which may lead to the identification of the spent fuel origin is the isotopic composition of the RDD debris. The objective of this research was to benchmark a forward model methodology for predicting isotopic composition of spent nuclear fuel used in an RDD while at the same time optimizing the fidelity of the model to reduce computational time. The code used in this study was Monteburns-2.0. Monteburns is a Monte Carlo based neutronic code utilizing both MCNP and ORIGEN. The size of the burnup step used in Monteburns was tested and found to converge at a value of 3,000 MWd/MTU per step. To ensure a conservative answer, 2,500 MWd/MTU per step was used for the benchmarking process. The model fidelity ranged from the following: 2-dimensional pin cell, multiple radial-region pin cell, modified pin cell, 2D assembly, and 3D assembly. The results showed that while the multi-region pin cell gave the highest level of accuracy, the difference in uncertainty between it and the 2D pin cell (0.07% for 235U) did not warrant the additional computational time required. The computational time for the multiple radial-region pin cell was 7 times that of the 2D pin cell. For this reason, the 2D pin cell was used to benchmark the isotopics with data from other reactors. The reactors from which the methodology was benchmarked were Calvert Cliffs Unit #1, Takahama Unit #3, and Trino Vercelles. Calvert Cliffs is a pressurized water reactor (PWR) using Combustion Engineering 14??14 assemblies. Takahama is a PWR using Mitsubishi Heavy Industries 17??17 assemblies. Trino Vercelles is a PWR using non-standard lattice assemblies. The measured isotopic concentrations from all three of the reactors showed good agreement with the calculated values.

Burk, David Edward

2005-05-01T23:59:59.000Z

64

Radiological, physical, and chemical characterization of additional alpha contaminated and mixed low-level waste for treatment at the advanced mixed waste treatment project  

SciTech Connect

This document provides physical, chemical, and radiological descriptive information for a portion of mixed waste that is potentially available for private sector treatment. The format and contents are designed to provide treatment vendors with preliminary information on the characteristics and properties for additional candidate portions of the Idaho National Engineering Laboratory (INEL) and offsite mixed wastes not covered in the two previous characterization reports for the INEL-stored low-level alpha-contaminated and transuranic wastes. This report defines the waste, provides background information, briefly reviews the requirements of the Federal Facility Compliance Act (P.L. 102-386), and relates the Site Treatment Plans developed under the Federal Facility Compliance Act to the waste streams described herein. Each waste is summarized in a Waste Profile Sheet with text, charts, and tables of waste descriptive information for a particular waste stream. A discussion of the availability and uncertainty of data for these waste streams precedes the characterization descriptions.

Hutchinson, D.P.

1995-07-01T23:59:59.000Z

65

REAL-TIME IDENTIFICATION AND CHARACTERIZATION OF ASBESTOS AND CONCRETE MATERIALS WITH RADIOACTIVE CONTAMINATION  

SciTech Connect

Concrete and asbestos-containing materials were widely used in DOE building construction in the 1940s and 1950s. Over the years, many of these porous materials have been contaminated with radioactive sources, on and below the surface. To improve current practice in identifying hazardous materials and in characterizing radioactive contamination, an interdisciplinary team from Rensselaer has conducted research in two aspects: (1) to develop terahertz time-domain spectroscopy and imaging system that can be used to analyze environmental samples such as asbestos in the field, and (2) to develop algorithms for characterizing the radioactive contamination depth profiles in real-time in the field using gamma spectroscopy. The basic research focused on the following: (1) mechanism of generating of broadband pulsed radiation in terahertz region, (2) optimal free-space electro-optic sampling for asbestos, (3) absorption and transmission mechanisms of asbestos in THz region, (4) the role of asbestos sample conditions on the temporal and spectral distributions, (5) real-time identification and mapping of asbestos using THz imaging, (7) Monte Carlo modeling of distributed contamination from diffusion of radioactive materials into porous concrete and asbestos materials, (8) development of unfolding algorithms for gamma spectroscopy, and (9) portable and integrated spectroscopy systems for field testing in DOE. Final results of the project show that the combination of these innovative approaches has the potential to bring significant improvement in future risk reduction and cost/time saving in DOE's D and D activities.

XU, X. George; Zhang, X.C.

2002-05-10T23:59:59.000Z

66

Remediation Strategies for Source Materials and Contaminated Media at Manufactured Gas Plant (MGP) Sites  

Science Conference Proceedings (OSTI)

This report contains information on remediation technologies that can be used to manage source material and contaminated media at manufactured gas plant (MGP) sites. It describes each technology, discusses its advantages and limitations, and defines the key factors that should be taken into account before selecting the technology for use at a given site.

1995-01-28T23:59:59.000Z

67

Determination of contamination in rare earth materials by promptgamma activation analysis (PGAA)  

SciTech Connect

Prompt gamma activation analysis (PGAA) has been used to detect and quantify impurities in the analyses of rare earth (RE) oxides. The analytical results are discussed with respect to the importance of having a thorough identification and understanding of contaminant elements in these compounds regarding the function of the materials in their various applications. Also, the importance of using PGAA to analyze materials in support of other physico-chemical studies of the materials is discussed, including the study of extremely low concentrations of ions such as the rare earth ions themselves in bulk material matrices.

Perry, D.L.; English, G.A.; Firestone, R.B.; Molnar, G.L.; Revay,Zs.

2004-11-09T23:59:59.000Z

68

IMPACT OF TARGET MATERIAL ACTIVATION ON PERSONNEL EXPOSURE AND RADIOACTIVE CONTAMINATION IN THE NATIONAL IGNITION FACILITY  

Science Conference Proceedings (OSTI)

Detailed activation analyses are performed for the different materials under consideration for use in the target capsules and hohlraums used during the ignition campaign on the National Ignition Facility. Results of the target material activation were additionally used to estimate the levels of contamination within the NIF target chamber and the workplace controls necessary for safe operation. The analysis examined the impact of using Be-Cu and Ge-doped CH capsules on the external dose received by workers during maintenance activities. Five days following a 20 MJ shot, dose rates inside the Target Chamber (TC) due to the two proposed capsule materials are small ({approx} 1 {micro}rem/h). Gold and depleted-uranium (DU) are considered as potential hohlraum materials. Following a shot, gold will most probably get deposited on the TC first wall. On the other hand, while noble-gas precursors from the DU are expected to stay in the TC, most of the noble gases are pumped out of the chamber and end up on the cryopumps. The dose rates inside the TC due to activated gold or DU, at 5 days following a 20 MJ shot, are about 1 mrem/h. Dose rates in the vicinity of the cryo-pumps (containing noble 'fission' gases) drop-off to about 1 mrem/h during the first 12 hours following the shot. Contamination from activation of NIF targets will result in the NIF target chamber exceeding DOE surface contamination limits. Objects removed from the TC will need to be managed as radioactive material. However, the results suggest that airborne contamination from resuspension of surface contamination will not be significant and is at levels that can be managed by negative ventilation when accessing the TC attachments.

Khater, H; Epperson, P; Thacker, R; Beale, R; Kohut, T; Brereton, S

2009-06-30T23:59:59.000Z

69

Initial laboratory studies into the chemical and radiological aging of organic materials in underground storage tanks at the Hanford Complex  

SciTech Connect

The underground storage tanks at the Hanford Complex contain wastes generated over many years from plutonium production and recovery processes, and mixed wastes from radiological degradation processes. The chemical changes of the organic materials used in the extraction processes have a direct bearing on several specific safety issues, including potential energy releases from these tanks. The major portion of organic materials that have been added to the tanks consists of tributyl phosphate, dibutyl phosphate, butyl alcohol, hexone (methyl isobutyl ketone), normal paraffin hydrocarbons (NPH), ethylenediaminetetraacetic acid (EDTA), hydroxyethylethylenediaminetriadetic acid (HEDTA), other complexants, and lesser quantities of ion exchange polymers and minor organic compounds. A study of how thermal and radiological processes that may have changed the composition of organic tanks constituents has been initiated after a review of the open literature revealed little information was available about the rates and products of these processes under basic pH conditions. This paper will detail the initial findings as they relate to gas generation, e.g. H{sub 2}, CO, NH{sub 3}, CH{sub 4}, and to changes in the composition of the organic and inorganic components brought about by ``Aging`` processes.

Samuels, W.D.; Camaioni, D.M. [Pacific Northwest Lab., Richland, WA (United States); Babad, H. [Westinghouse Hanford Co., Richland, WA (United States)

1994-03-01T23:59:59.000Z

70

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

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

13-1 13-1 DEPARTMENT OF ENERGY LESSON PLAN Course Material Topic: Radiological Aspects of Accelerators Objectives: Upon completion of this lesson, the participant will be able to: 1. Identify the general characteristics of accelerators. 2. Identify the types of particles accelerated. 3. Identify the two basic types of accelerators. 4. Identify uses for accelerators. 5. Define prompt radiation. 6. Identify prompt radiation sources. 7. Define radioactivation. 8. Explain how contaminated material differs from activated material with regard to radiological concerns. 9. Identify activation sources. 10. Identify engineered and administrative controls at accelerator facilities. 11. Identify the special radiological concern and recommended instrument for each

71

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

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

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

72

Laboratory Investigation into the Contribution of Contaminants to Ground Water from Equipment Materials Used in Sampling  

SciTech Connect

Benzene contamination was detected in well water samples from the Ogallala Aquifer beneath and adjacent to the Department of Energy's Pantex Plant near Amarillo, Texas. This study assessed whether or not the materials used in multilevel sampling equipment at this site could have contributed to the contaminants found in well water samples. As part of this investigation, laboratory testing of the sample equipment material was conducted. Results from the laboratory test indicated three different materials from two types of multilevel samplers did, in fact, contribute volatile and semivolatile organic compounds to the ground water samples from static leach tests that were conducted during an eight week period. The nylon-11 tubing contributed trace concentrations of benzene (1.37 ?g/L) and relatively high concentrations of the plasticizer N-butylbenzenesulfonamide (NBSA) (764 mg/L) to the water; a urethane-coated nylon well liner contributed relatively high concentrations of toluene (278 ?g/L) and trace amounts of NBSA; and a sampling port spacer material made of nylon/polypropylene/polyester-composite contributed trace amounts of toluene and NBSA. While the concentrations of benzene and toluene measured in the laboratory tests were below the concentrations measured in actual ground water samples, the concentrations of organics from these equipment materials were sufficient to render the results reported for the ground water samples suspect.

Gilmore, Tyler J.; Mitroshkov, Alexandre V.; Dresel, P Evan; Sklarew, Debbie S.

2004-08-30T23:59:59.000Z

73

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

74

Modeling for Airborne Contamination  

SciTech Connect

The objective of Modeling for Airborne Contamination (referred to from now on as ''this report'') is to provide a documented methodology, along with supporting information, for estimating the release, transport, and assessment of dose to workers from airborne radioactive contaminants within the Monitored Geologic Repository (MGR) subsurface during the pre-closure period. Specifically, this report provides engineers and scientists with methodologies for estimating how concentrations of contaminants might be distributed in the air and on the drift surfaces if released from waste packages inside the repository. This report also provides dose conversion factors for inhalation, air submersion, and ground exposure pathways used to derive doses to potentially exposed subsurface workers. The scope of this report is limited to radiological contaminants (particulate, volatile and gaseous) resulting from waste package leaks (if any) and surface contamination and their transport processes. Neutron activation of air, dust in the air and the rock walls of the drift during the preclosure time is not considered within the scope of this report. Any neutrons causing such activation are not themselves considered to be ''contaminants'' released from the waste package. This report: (1) Documents mathematical models and model parameters for evaluating airborne contaminant transport within the MGR subsurface; and (2) Provides tables of dose conversion factors for inhalation, air submersion, and ground exposure pathways for important radionuclides. The dose conversion factors for air submersion and ground exposure pathways are further limited to drift diameters of 7.62 m and 5.5 m, corresponding to the main and emplacement drifts, respectively. If the final repository design significantly deviates from these drift dimensions, the results in this report may require revision. The dose conversion factors are further derived by using concrete of sufficient thickness to simulate the drift walls. The gamma-ray scattering properties of concrete are sufficiently similar to those of the host rock and proposed insert material; use of concrete will have no significant impact on the conclusions. The information in this report is presented primarily for use in performing pre-closure radiological safety evaluations of radiological contaminants, but it may also be used to develop strategies for contaminant leak detection and monitoring in the MGR. Included in this report are the methods for determining the source terms and release fractions, and mathematical models and model parameters for contaminant transport and distribution within the repository. Various particle behavior mechanisms that affect the transport of contaminant are included. These particle behavior mechanisms include diffusion, settling, resuspension, agglomeration and other deposition mechanisms.

F.R. Faillace; Y. Yuan

2000-08-31T23:59:59.000Z

75

Estimation of Internal Radiation Dose from both Immediate Releases and Continued Exposures to Contaminated Materials  

Science Conference Proceedings (OSTI)

A brief description is provided of the basic concepts related to 'internal dose' and how it differs from doses that result from radioactive materials and direct radiation outside of the body. The principles of radiation dose reconstruction, as applied to both internal and external doses, is discussed based upon a recent publication prepared by the US National Council on Radiation Protection and Measurements. Finally, ideas are introduced related to residual radioactive contamination in the environment that has resulted from the releases from the damaged reactors and also to the management of wastes that may be generated in both regional cleanup and NPP decommissioning.

Napier, Bruce A.

2012-03-26T23:59:59.000Z

76

Radiological Assessment of Target Materials for Accelerator Transmutation of Waste Applications  

SciTech Connect

This paper provides the radiation absorbed dose rates (rad-h{sup -1}) to a tissue-equivalent torus ring at 1 meter from radioactive spallation products in Ta, W, Pb, Bi, and LBE target materials used in Accelerator Transmutation of Waste (ATW) applications. No previous works have provided an estimate of the absorbed dose rates (rad-h{sup -1}) to tissue from activated targets for ATW applications. In addition, this paper provides the characterization of target materials of high-energy particle accelerators for the parameters of (a) spallation neutron yield (neutrons/proton), (b) spallation products yield (nuclides/proton), (c) energy-dependent spallation neutron fluence distribution (n-cm{sup -2} MeV{sup -1}), and (d) identification of the optimal target dimensions to yield the maximum radial spallation neutron leakage from the target. A beneficial characteristic of these target materials (Ta, W, Pb, Bi, and LBE) is they do not produce radioactive transuranic isotopes, which have very long half-lives and require special handling and disposition controls. In addition, these activated, spent targets are not considered high-level radioactive waste for disposal purposes such as spent fuel from a nuclear power reactor.

Vickers, Linda D

2003-11-15T23:59:59.000Z

77

Hazardous Materials Incident Response Procedure | Department of Energy  

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

Hazardous Materials Incident Response Procedure Hazardous Materials Incident Response Procedure Hazardous Materials Incident Response Procedure The purpose of this procedure is to provide guidance for developing an emergency response plan, as outlined in OSHA's 29 CFR 1910.120(q), for facility response. This model has been adopted and applied to work for response to transportation accidents involving radioactive material or other hazardous materials incidents Hazardous Materials Incident Response Procedure.docx More Documents & Publications Handling and Packaging a Potentially Radiologically Contaminated Patient Decontamination Dressdown at a Transportation Accident Involving Radioactive Material Medical Examiner/Coroner on the Handling of a Body/Human Remains that are Potentially Radiologically Contaminated

78

Radiological Monitoring Results for Groundwater Samples Associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Pond: November 1, 2011-October 31, 2012  

SciTech Connect

This report summarizes radiological monitoring performed on samples from specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond WRU-I-0160-01, Modification 1 (formerly LA-000160-01). The radiological monitoring was performed to fulfill Department of Energy requirements under the Atomic Energy Act.

Mike lewis

2013-02-01T23:59:59.000Z

79

Radiological Monitoring Results For Groundwater Samples Associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Pond: May 1, 2010-October 31, 2010  

SciTech Connect

This report summarizes radiological monitoring performed on samples from specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond (#LA-000160-01). The radiological monitoring was performed to fulfill Department of Energy requirements under the Atomic Energy Act.

David B. Frederick

2011-02-01T23:59:59.000Z

80

Radiological Monitoring Results For Groundwater Samples Associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Pond: November 1, 2010-October 31, 2011  

SciTech Connect

This report summarizes radiological monitoring performed on samples from specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit for the Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond (No.LA-000160-01). The radiological monitoring was performed to fulfill Department of Energy requirements under the Atomic Energy Act.

David Frederick

2012-02-01T23:59:59.000Z

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


81

Corrective Action Investigation Plan for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada, Rev. No.: 0  

SciTech Connect

Corrective Action Unit 166 is located in Areas 2, 3, 5, and 18 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit (CAU) 166 is comprised of the seven Corrective Action Sites (CASs) listed below: (1) 02-42-01, Cond. Release Storage Yd - North; (2) 02-42-02, Cond. Release Storage Yd - South; (3) 02-99-10, D-38 Storage Area; (4) 03-42-01, Conditional Release Storage Yard; (5) 05-19-02, Contaminated Soil and Drum; (6) 18-01-01, Aboveground Storage Tank; and (7) 18-99-03, Wax Piles/Oil Stain. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation (CAI) before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on February 28, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 166. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the CAI for CAU 166 includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling. (2) Conduct radiological surveys. (3) Perform field screening. (4) Collect and submit environmental samples for laboratory analysis to determine if contaminants of concern are present. (5) If contaminants of concern are present, collect additional step-out samples to define the extent of the contamination. (6) Collect samples of investigation-derived waste, as needed, for waste management and minimization purposes. This Corrective Action Investigation Plan has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the ''Federal Facility Agreement and Consent Order'', this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection, and field work will commence following approval.

David Strand

2006-06-01T23:59:59.000Z

82

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

83

Closure Report for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada  

Science Conference Proceedings (OSTI)

Corrective Action Unit (CAU) 166 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Storage Yards and Contaminated Materials' and consists of the following seven Corrective Action Sites (CASs), located in Areas 2, 3, 5, and 18 of the Nevada Test Site: CAS 02-42-01, Condo Release Storage Yd - North; CAS 02-42-02, Condo Release Storage Yd - South; CAS 02-99-10, D-38 Storage Area; CAS 03-42-01, Conditional Release Storage Yard; CAS 05-19-02, Contaminated Soil and Drum; CAS 18-01-01, Aboveground Storage Tank; and CAS 18-99-03, Wax Piles/Oil Stain. Closure activities were conducted from March to July 2009 according to the FF ACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 166 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action and Clean Closure. Closure activities are summarized. CAU 166, Storage Yards and Contaminated Materials, consists of seven CASs in Areas 2, 3, 5, and 18 of the NTS. The closure alternatives included No Further Action and Clean Closure. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 166 as documented in this CR: (1) At CAS 02-99-10, D-38 Storage Area, approximately 40 gal of lead shot were removed and are currently pending treatment and disposal as MW, and approximately 50 small pieces of DU were removed and disposed as LLW. (2) At CAS 03-42-01, Conditional Release Storage Yard, approximately 7.5 yd{sup 3} of soil impacted with lead and Am-241 were removed and disposed as LLW. As a BMP, approximately 22 ft{sup 3} of asbestos tile were removed from a portable building and disposed as ALLW, approximately 55 gal of oil were drained from accumulators and are currently pending disposal as HW, the portable building was removed and disposed as LLW, and accumulators, gas cylinders, and associated debris were removed and are currently pending treatment and disposal as MW. (3) At CAS 05-19-02, Contaminated Soil and Drum, as a BMP, an empty drum was removed and disposed as sanitary waste. (4) At CAS 18-01-01, Aboveground Storage Tank, approximately 165 gal of lead-impacted liquid were removed and are currently pending disposal as HW, and approximately 10 gal of lead shot and 6 yd{sup 3} of wax embedded with lead shot were removed and are currently pending treatment and disposal as MW. As a BMP, approximately 0.5 yd{sup 3} of wax were removed and disposed as hydrocarbon waste, approximately 55 gal of liquid were removed and disposed as sanitary waste, and two metal containers were grouted in place. (5) At CAS 18-99-03, Wax Piles/Oil Stain, no further action was required; however, as a BMP, approximately l.5 yd{sup 3} of wax were removed and disposed as hydrocarbon waste, and one metal container was grouted in place.

NSTec Environmental Restoration

2009-08-01T23:59:59.000Z

84

Durability Prediction of Solid Oxide Fuel Cell Anode Material under Thermo-Mechanical and Fuel Gas Contaminants Effects  

Science Conference Proceedings (OSTI)

Solid Oxide Fuel Cells (SOFCs) operate under harsh environments, which cause deterioration of anode material properties and service life. In addition to electrochemical performance, structural integrity of the SOFC anode is essential for successful long-term operation. The SOFC anode is subjected to stresses at high temperature, thermal/redox cycles, and fuel gas contaminants effects during long-term operation. These mechanisms can alter the anode microstructure and affect its electrochemical and structural properties. In this research, anode material degradation mechanisms are briefly reviewed and an anode material durability model is developed and implemented in finite element analysis. The model takes into account thermo-mechanical and fuel gas contaminants degradation mechanisms for prediction of long-term structural integrity of the SOFC anode. The proposed model is validated experimentally using a NexTech ProbostatTM SOFC button cell test apparatus integrated with a Sagnac optical setup for simultaneously measuring electrochemical performance and in-situ anode surface deformation.

Iqbal, Gulfam; Guo, Hua; Kang , Bruce S.; Marina, Olga A.

2011-01-10T23:59:59.000Z

85

EA-1599: Disposition of Radioactively Contaminated Nickel Located at the  

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

99: Disposition of Radioactively Contaminated Nickel Located 99: Disposition of Radioactively Contaminated Nickel Located at the East Tennessee Technology Park, Oak Ridge, Tennessee, and the Paducah Gaseous Diffusion Plant, Paducah, Kentucky, for Controlled Radiological Applications EA-1599: Disposition of Radioactively Contaminated Nickel Located at the East Tennessee Technology Park, Oak Ridge, Tennessee, and the Paducah Gaseous Diffusion Plant, Paducah, Kentucky, for Controlled Radiological Applications Summary This EA was being prepared to evaluate potential environmental impacts of a proposal to dispose of nickel scrap that is volumetrically contaminated with radioactive materials and that DOE recovered from equipment it had used in uranium enrichment. This EA is on hold. Public Comment Opportunities No public comment opportunities at this time.

86

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

87

EA-1599: Disposition of Radioactively Contaminated Nickel Located at the East Tennessee Technology Park, Oak Ridge, Tennessee, and the Paducah Gaseous Diffusion Plant, Paducah, Kentucky, for Controlled Radiological Applications  

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

This EA was being prepared to evaluate potential environmental impacts of a proposal to dispose of nickel scrap that is volumetrically contaminated with radioactive materials and that DOE recovered from equipment it had used in uranium enrichment. This EA is on hold.

88

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

89

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

90

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

91

Radiological assessment of the decontamination and decommissioning of a small-scale fuel-reprocessing plant  

SciTech Connect

Decontamination and decommissioning (D and D) of surplus radiological facilities is becoming a major concern as buildings built during the 1940's and 1950's reach the end of their useful lives. Prior to the start of a D and D project, a detailed radiological characterization of the facility is required to determine the nature and extent of residual contamination. The Oak Ridge National Laboratory (ORNL) has recently begun such a characterization of Building 3505, originally called the Metal Recovery Facility, which served as a small-scale fuel reprocessing plant during the 1950's. Extensive contamination remains within areas of the facility, including transuranic (TRU) materials. Laboratory analyses were used in conjunction with in situ measurements of dose rate and contamination levels to determine the current status of the building and surrounding area. This information will be used to estimate the amount of decontamination required and the quantity of radioactive waste.

Simpson, D.R.; Emery, J.F.

1981-01-01T23:59:59.000Z

92

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

93

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

94

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...

95

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

96

Program on Technology Innovation: Controlled Recycling of Contaminated Materials for Nuclear Industry Uses  

Science Conference Proceedings (OSTI)

This report addresses opportunities to recycle materials in radioactive waste by decontamination and fabrication into new components for use in the nuclear industry. In particular, a novel approach called "controlled recycling" involves a procedure that controls the material during decontamination, metal processing and remanufacture into components for reuse in the nuclear industry.

2006-11-09T23:59:59.000Z

97

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

98

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

99

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

100

DECOMMISSIONING PLAN AND RADIOLOGICAL  

E-Print Network (OSTI)

Cabot Performance Materials (Cabot) holds NRC License SMC-1562, covering storage of radioactive materials at both their Revere and Reading sites in Pennsylvania. Former ore processing at the Revere facility generated waste slag contaminated with uranium and thorium. In 1988, Cabot began onsite decommissioning activities for the Revere facility, including site

unknown authors

2001-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiologically contaminated material" 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

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

102

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

103

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

104

Corrective Action Plan for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada  

SciTech Connect

Corrective Action Unit (CAU) 166, Storage Yards and Contaminated Materials, is listed in the Federal Facility Agreement and Consent Order (FFACO) of 1996 (FFACO, 1996). CAU 166 consists of seven Corrective Action Sites (CASs) located in Areas 2, 3, 5, and 18 of the Nevada Test Site (NTS), which is located approximately 65 miles northwest of Las Vegas, Nevada (Figure 1). CAU 166 consists of the following CASs: (1) CAS 02-42-01, Cond. Release Storage Yd - North; (2) CAS 02-42-02, Cond. Release Storage Yd - South; (3) CAS 02-99-10, D-38 Storage Area; (4) CAS 03-42-01, Conditional Release Storage Yard; (5) CAS 05-19-02, Contaminated Soil and Drum; (6) CAS 18-01-01, Aboveground Storage Tank; and (7) CAS 18-99-03, Wax Piles/Oil Stain. Details of the site history and site characterization results for CAU 166 are provided in the approved Corrective Action Investigation Plan (CAIP) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2006) and in the approved Corrective Action Decision Document (CADD) (NNSA/NSO, 2007).

NSTec Environmental Restoration

2007-10-01T23:59:59.000Z

105

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

106

Standard for Communicating Waste Characterization and DOT Hazard Classification Requirements for Low Specific Activity Materials and Surface Contaminated Objects  

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

STD-5507-2013 STD-5507-2013 February 2013 DOE STANDARD Standard for Communicating Waste Characterization and DOT Hazard Classification Requirements for Low Specific Activity Materials and Surface Contaminated Objects [This Standard describes acceptable, but not mandatory means for complying with requirements. Standards are not requirements documents and are not to be construed as requirements in any audit or appraisal for compliance with associated rule or directives.] U.S. Department of Energy SAFT 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,

107

Radiological assessment report for the University of Rochester Annex, 400 Elmwood Avenue, Rochester, New York, April-May 1984  

Science Conference Proceedings (OSTI)

In light of the results of the comprehensive radiological assessment of the annex and auxiliary facilities, the following conclusions can be made: There is no immediate hazard from the elevated levels of radioactivity detected; however, some of these levels are above criteria. The radon, thoron, actinon, long-lived particulates, and tritium in the air are all below criteria for unrestricted use. Some ductwork has been identified as being contaminated. All ductwork must, therefore, be considered potentially contaminated. Since several floor drains were found to exhibit elevated readings, and the samples had elevated concentrations of radionuclides, it must be concluded that the drain and sewer systems of the Annex are contaminated with radioactive material. Since the samples collected from the storm and sewer systems outside the building also had elevated concentrations of radionuclides, these systems are also considered contaminated with radioactive material. The grounds around the Annex have exhibited background concentrations of radionuclides. Two rooms, B-330 and B-332, were inaccessible for survey due to the presence of stored furniture and equipment. Therefore, no comment about their radiological status can be made. At the common baseboard for Room C-12 and C-16 and on the floor below the tile in Room C-40, contamination appeared to be masked by construction modifications. Other areas of the Annex must also be considered potentially contaminated where modifications may have masked the contamination.

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

1984-12-01T23:59:59.000Z

108

Estimation of Cosmic Induced Contamination in Ultra-low Background Detector Materials  

SciTech Connect

Executive Summary This document presents the result of investigating a way to reliably determine cosmic induced backgrounds for ultra-low background materials. In particular, it focuses on those radioisotopes produced by the interactions with cosmic ray particles in the detector materials that act as a background for experiments looking for neutrinoless double beta decay. This investigation is motivated by the desire to determine background contributions from cosmic ray activation of the electroformed copper that is being used in the construction of the MAJORANA DEMONSTRATOR. The most important radioisotope produced in copper that contributes to the background budget is 60Co, which has the potential to deposit energy in the region of interest of this experiment. Cobalt-60 is produced via cosmic ray neutron collisions in the copper. This investigation aims to provide a method for determining whether or not the copper has been exposed to cosmic radiation beyond the threshold which the Majorana Project has established as the maximum exposure. This threshold is set by the Project as the expected contribution of this source of background to the overall background budget. One way to estimate cosmic ray neutron exposure of materials on the surface of the Earth is to relate it to the cosmic ray muon exposure. Muons are minimum-ionizing particles and the available technologies to detect muons are easier to implement than those to detect neutrons. We present the results of using a portable, ruggedized muon detector, the µ-Witness made by our research group, for determination of muon exposure of materials for the MAJORANA DEMONSTRATOR. From the muon flux measurement, this report presents a method to estimate equivalent sea-level exposure, and then infer the neutron exposure of the tracked material and thus the cosmogenic activation of the copper. This report combines measurements of the muon flux taken by the µ-Witness detector with Geant4 simulations in order to assure our understanding of the µ-Witness prototype. As a proof of concept, we present the results of using this detector with electroformed copper during its transport from Pacific Northwest National Laboratory, where the copper is grown, to the underground lab in Lead, South Dakota, where the experiment is being deployed. The development of a code to be used with the Majorana parts tracking database, designed to aid in estimating the cosmogenic activation, is also presented.

Aguayo Navarrete, Estanislao; Kouzes, Richard T.; Orrell, John L.; Berguson, Timothy J.; Greene, Austen T.

2012-08-01T23:59:59.000Z

109

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 . . :

110

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

111

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

112

GUIDANCE FOR THE PROPER CHARACTERIZATION AND CLASSIFICATION OF LOW SPECIFIC ACTIVITY MATERIALS AND SURFACE CONTAMINATED OBJECTS FOR DISPOSAL  

SciTech Connect

Regulatory concerns over the proper characterization of certain waste streams led CH2M HILL Plateau Remediation Company (CHPRC) to develop written guidance for personnel involved in Decontamination & Decommissioning (D&D) activities, facility management and Waste Management Representatives (WMRs) involved in the designation of wastes for disposal on and off the Hanford Site. It is essential that these waste streams regularly encountered in D&D operations are properly designated, characterized and classified prior to shipment to a Treatment, Storage or Disposal Facility (TSDF). Shipments of waste determined by the classification process as Low Specific Activity (LSA) or Surface Contaminated Objects (SCO) must also be compliant with all applicable U.S. Department of Transportation (DOE) regulations as well as Department of Energy (DOE) orders. The compliant shipment of these waste commodities is critical to the Hanford Central Plateau cleanup mission. Due to previous problems and concerns from DOE assessments, CHPRC internal critiques as well as DOT, a management decision was made to develop written guidance and procedures to assist CHPRC shippers and facility personnel in the proper classification of D&D waste materials as either LSA or SCO. The guidance provides a uniform methodology for the collection and documentation required to effectively characterize, classify and identify candidate materials for shipping operations. A primary focus is to ensure that waste materials generated from D&D and facility operations are compliant with the DOT regulations when packaged for shipment. At times this can be difficult as the current DOT regulations relative to the shipment of LSA and SCO materials are often not clear to waste generators. Guidance is often sought from NUREG 1608/RAMREG-003 [3]: a guidance document that was jointly developed by the DOT and the Nuclear Regulatory Commission (NRC) and published in 1998. However, NUREG 1608 [3] is now thirteen years old and requires updating to comply with the newer DOT regulations. Similar challenges present themselves throughout the nuclear industry in both commercial and government operations and therefore, this is not only a Hanford Site problem. Shipping radioactive wastes as either LSA or SCO rather than repacking it is significantly cheaper than other DOT radioactive materials shipping classifications particularly when the cost of packages is included. Additionally, the need to 'repackage' materials for transport can often increase worker exposure, necessitated by 'repackaging' waste materials into DOT 7 A Type A containers.

PORTSMOUTH JH; BLACKFORD LT

2012-02-13T23:59:59.000Z

113

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...

114

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

115

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

116

Radiological Contamination Control Training for Laboratory Research  

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

instructors. The program should contain theory and practice of instructional skills and techniques; adult learning; and planning, conducting, and evaluating classroom, simulator,...

117

Radiological assessment and remedial action report for the ''Son of Lansdowne'' property, 186 North Lansdowne Avenue, Lansdowne, Pennsylvania  

SciTech Connect

This document reports the results of a radiological assessment and remedial action program conducted by Argonne National Laboratory personnel at a radioactively contaminated private residence in Lansdowne, Pennsylvania. The program was conducted on the residence at 186 Lansdowne Avenue. The survey conducted by the ANL personnel indicated that several dozen areas or spots of contamination were present on all floors and the basement of the three-story house. Contamination was found on furniture, carpeting, walls, floors, woodwork, and ceilings. Remedial action undertaken to remove the contamination ranged from scrubbing, to scraping, to shaving of wood, to removal and disposal of items and material that could not be adequately decontaminated. Outdoors, contaminated soil was removed from the backyard, and the driveway was dug up so the contaminated subsurface material could be removed. The remedial action generated quantities of radioactive waste, including four 55-gallon drums and one M-III bin (120 ft/sup 3/) containing floor tile, concrete, personal items, furniture, floor scrapings, vermiculite absorbed scrub water, and other items. In addition, there were 24 M-III bins containing approximately 112 tons of contaminated soil and rock from the two contaminated areas in the backyard and from the contaminated subsurface of the driveway. 2 refs., 39 figs., 12 tabs.

Smith, W.H.; Wynveen, R.A.

1987-08-01T23:59:59.000Z

118

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

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

Contamination Control Contamination Control Instructor's Guide 2.05-1 Course Title: Radiological Control Technician Module Title: Contamination Control Module Number: 2.05 Objectives: 2.05.01 Define the terms "removable and fixed surface contamination," state the difference between them and list common methods used to measure each. 2.05.02 State the components of a radiological monitoring program for contamination control and common methods used to accomplish them. 2.05.03 State the basic goal of a contamination control program and list actions that contribute to its success. 2.05.04 State the basic principles of contamination control and list examples of implementation methods. 2.05.05 List and describe the possible engineering control methods used for contamination control. 2.05.06

119

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

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

Contamination Control Contamination Control Study Guide 2.05-1 Course Title: Radiological Control Technician Module Title: Contamination Control Module Number: 2.05 Objectives: 2.05.01 Define the terms "removable and fixed surface contamination," state the difference between them and list common methods used to measure each. 2.05.02 State the components of a radiological monitoring program for contamination control and common methods used to accomplish them. 2.05.03 State the basic goal of a contamination control program and list actions that contribute to its success. 2.05.04 State the basic principles of contamination control and list examples of implementation methods. 2.05.05 List and describe the possible engineering control methods used for contamination control. 2.05.06

120

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

Note: This page contains sample records for the topic "radiologically contaminated material" 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

RADIOLOGICAL ASSESSMENT  

Office of Legacy Management (LM)

ASSESSMENT ASSESSMENT and STABILIZATION' SCENARIOS PARRERSBURG,'W. VA. SITE FEBRUARY 1980 M. CARSON J. COFFMAN N. MANDELTORT, ! Division of Nuclear Service Operations Chem-Nuclear\ Systems, Inc. 240 Stoneridge Dr., Suite 100 Columbia, South Carolina 29210 Prepared for AMAX Specialty Hetals Corporation One Greenwich Plaza Greenwich, Connecticut 06830 During July' 1978, Chem-Nuclear Systems, Inc. (CNSI) began an assessment program for AMAX Specialty Metals Corp."(AMAX) u to locate, quantify, and evaluate the'extent of environmental radioactive contamination at the AMAX Parkersburg., West Virginia former zirconium/hafnium processing facility. In addition, preliminary ive assessments were to be made to assist AMAX in evaluat ,ing alternat methods for site cleanup.

122

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...

123

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.

124

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.

125

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

126

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

127

Contaminant distributions at typical U.S. uranium milling facilities and their effect on remedial action decisions  

SciTech Connect

Past operations at uranium processing sites throughout the US have resulted in local contamination of soils and ground water by radionuclides, toxic metals, or both. Understanding the origin of contamination and how the constituents are distributed is a basic element for planning remedial action decisions. This report describes the radiological and nonradiological species found in ground water at a typical US uranium milling facility. The report will provide the audience with an understanding of the vast spectrum of contaminants that must be controlled in planning solutions to the long-term management of these waste materials.

Hamp, S. [USDOE Albuquerque Operations Office, NM (United States). Uranium Mill Tailings Remedial Action Project Office; Jackson, T.J. [Geraghty and Miller, Inc., Albuquerque, NM (United States); Dotson, P.W. [Roy F. Weston, Inc., Albuquerque, NM (United States)

1995-03-01T23:59:59.000Z

128

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

129

Site-specific analysis of radiological and physical parameters for cobbly soils at the Gunnison, Colorado, processing site  

Science Conference Proceedings (OSTI)

The remedial action at the Gunnison, Colorado, processing site is being performed under the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 [Public Law (PL) 95-6041]. Under UMTRCA, the US Environmental Protection Agency (EPA) is charged with the responsibility of developing appropriate and applicable standards for the cleanup of radiologically contaminated land and buildings at 24 designated sites, including the Gunnison, Colorado, inactive processing site. The remedial action at the processing site will be conducted to remove the tailings and contaminated materials to meet the EPA bulk soil cleanup standards for surface and subsurface soils. The site areas disturbed by remedial action excavation will be either contoured or backfilled with radiologically uncontaminated soil and contoured to restore the site. The final contours will produce a final surface grade that will create positive drainage from the site.

Not Available

1993-10-01T23:59:59.000Z

130

Application of the base catalyzed decomposition process to treatment of PCB-contaminated insulation and other materials associated with US Navy vessels. Final report  

SciTech Connect

The BCD process was applied to dechlorination of two types of PCB-contaminated materials generated from Navy vessel decommissioning activities at Puget Sound Naval Shipyard: insulation of wool felt impregnated with PCB, and PCB-containing paint chips/debris from removal of paint from metal surfaces. The BCD process is a two-stage, low-temperature chemical dehalogenation process. In Stage 1, the materials are mixed with sodium bicarbonate and heated to 350 C. The volatilized halogenated contaminants (eg, PCBs, dioxins, furans), which are collected in a small volume of particulates and granular activated carbon, are decomposed by the liquid-phase reaction (Stage 2) in a stirred-tank reactor, using a high-boiling-point hydrocarbon oil as the reaction medium, with addition of a hydrogen donor, a base (NaOH), and a catalyst. The tests showed that treating wool felt insulation and paint chip wastes with Stage 2 on a large scale is feasible, but compared with current disposal costs for PCB-contaminated materials, using Stage 2 would not be economical at this time. For paint chips generated from shot/sand blasting, the solid-phase BCD process (Stage 1) should be considered, if paint removal activities are accelerated in the future.

Schmidt, A.J.; Zacher, A.H.; Gano, S.R.

1996-09-01T23:59:59.000Z

131

Categorical Exclusion 4596: High Contamination Area (HCA) Cleanup Project  

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

Detennination Form Detennination Form PropQsed Action Tit!~: High Contamination Area (HCA) C!e;;Jnup Project (4596) Pro~ram or Field Offif.s: Y-12 Site OffiCe Locmion(s) (City/CountvLState): Oak Ridge, Anderson County, Tennessee Prot?Oscd Action Description: PAGE 02/04 l,:·:~:.s:~.t?)fuiW6v:: ~ 4fB~ir:::8~1 The proposed action is to disposition the materiels and equipment stored in a radiological high contamination area (HCA). This area is paved and fenced with no roof or shelter. Tile HCA was used as an accumulation area for rad contaminated materials and equipment from operations. Categorical Exclusion(s) Avoli!¢l: 81.3- ~outine maintenance For the complete DOE National Environmental Policy Act regulnti011s regaruing categorical exclusions, including the full text of each

132

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...

133

Radiological Risk Assessment for King County Wastewater Treatment Division  

SciTech Connect

Staff of the King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into the combined sanitary and storm sewer system in King County, Washington. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include "dirty bombs" that are not nuclear detonations but are explosives designed to spread radioactive material (National Council on Radiation Protection and Measurements (NCRP) 2001). Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. This document develops plausible and/or likely scenarios, including the identification of likely radioactive materials and quantities of those radioactive materials to be involved. These include 60Co, 90Sr, 137Cs, 192Ir, 226Ra, plutonium, and 241Am. Two broad categories of scenarios are considered. The first category includes events that may be suspected from the outset, such as an explosion of a "dirty bomb" in downtown Seattle. The explosion would most likely be heard, but the type of explosion (e.g., sewer methane gas or RDD) may not be immediately known. Emergency first responders must be able to quickly detect the radioisotopes previously listed, assess the situation, and deploy a response to contain and mitigate (if possible) detrimental effects resulting from the incident. In such scenarios, advance notice of about an hour or two might be available before any contaminated wastewater reaches a treatment plant. The second category includes events that could go initially undetected by emergency personnel. Examples of such a scenario would be the inadvertent or surreptitious introduction of radioactive material into the sewer system. Intact rogue radioactive sources from industrial radiography devices, well-logging apparatus, or moisture density gages may get into wastewater and be carried to a treatment plant. Other scenarios might include a terrorist deliberately putting a dispersible radioactive material into wastewater. Alternatively, a botched terrorism preparation of an RDD may result in radioactive material entering wastewater without anyone's knowledge. Drinking water supplies may also be contaminated, with the result that some or most of the radioactivity ends up in wastewater.

Strom, Daniel J.

2005-08-05T23:59:59.000Z

134

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

135

Corrective Action Decision Document/Closure Report for Corrective Action Unit 529: Area 25 Contaminated Materials, Nevada Test Site, Nevada, Rev. No.: 1  

SciTech Connect

This Corrective Action Decision Document (CADD)/Closure Report (CR) has been prepared for Corrective Action Unit (CAU) 529, Area 25 Contaminated Materials, Nevada Test Site (NTS), Nevada, in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) that was agreed to by the State of Nevada, U.S. Department of Energy (DOE), and the U.S. Department of Defense (FFACO, 1996). The NTS is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Site (CAS) 25-23-17, Contaminated Wash, is the only CAS in CAU 529 and is located in Area 25 of the NTS, in Nye County, Nevada (Figure 1-2). Corrective Action Site 25-23-17, Contaminated Wash, was divided into nine parcels because of the large area impacted by past operations and the complexity of the source areas. The CAS was subdivided into separate parcels based on separate and distinct releases as determined and approved in the Data Quality Objectives (DQO) process and Corrective Action Investigation Plan (CAIP). Table 1-1 summarizes the suspected sources for the nine parcels. Corrective Action Site 25-23-17 is comprised of the following nine parcels: (1) Parcel A, Kiwi Transient Nuclear Test (TNT) 16,000-foot (ft) Arc Area (Kiwi TNT); (2) Parcel B, Phoebus 1A Test 8,000-ft Arc Area (Phoebus); (3) Parcel C, Topopah Wash at Test Cell C (TCC); (4) Parcel D, Buried Contaminated Soil Area (BCSA) l; (5) Parcel E, BCSA 2; (6) Parcel F, Borrow Pit Burial Site (BPBS); (7) Parcel G, Drain/Outfall Discharges; (8) Parcel H, Contaminated Soil Storage Area (CSSA); and (9) Parcel J, Main Stream/Drainage Channels.

Robert F. Boehlecke

2004-11-01T23:59:59.000Z

136

Corrective Action Investigation Plan for Corrective Action Unit 529: Area 25 Contaminated Materials, Nevada Test Site, Nevada, Rev. 0, Including Record of Technical Change No. 1  

SciTech Connect

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 529, Area 25 Contaminated Materials, Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. CAU 529 consists of one Corrective Action Site (25-23-17). For the purpose of this investigation, the Corrective Action Site has been divided into nine parcels based on the separate and distinct releases. A conceptual site model was developed for each parcel to address the translocation of contaminants from each release. The results of this investigation will be used to support a defensible evaluation of corrective action alternatives in the corrective action decision document.

U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2003-02-26T23:59:59.000Z

137

Investigation of materials performances in high moisture environments including corrosive contaminants typical of those arising by using alternative fuels in gas turbines  

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

materials performances in high moisture materials performances in high moisture environments including corrosive contaminants typical of those arising by using alternative fuels in gas turbines Gerald Meier, Frederick Pettit and Keeyoung Department of Materials Science and Engineering, Jung University of Pittsburgh Pittsburgh, PA 15260 Peer review Workshop III UTSR Project 04 01 SR116 October 18-20, 2005 Project Approach Task I Selection and Preparation of Specimens Task II Selection of Test Conditions Specimens : GTD111+CoNiCrAlY and Pt Aluminides, N5+Pt Aluminides Deposit : No Deposit, CaO, CaSO 4 , Na 2 SO 4 1150℃ Dry 1150℃ Wet 950℃ Wet 750℃ SO 3 950℃ Dry Selection of Test Temperature, T 1 , Gas Environment and Deposit Composition, D

138

Three Dimensional, Integrated Characterization and Archival System for Remote Facility Contaminant Characterization  

DOE Green Energy (OSTI)

The largest problem facing the Department of Energy's Office of Environmental Management (EM) is the cleanup of the Cold War legacy nuclear production plants that were built and operated from the mid-forties through the late eighties. EM is now responsible for the remediation of no less than 353 projects at 53 sites across the country at, an estimated cost of $147 billion over the next 72 years. One of the keys to accomplishing a thorough cleanup of any site is a rigorous but quick contaminant characterization capability. If the contaminants present in a facility can be mapped accurately, the cleanup can proceed with surgical precision, using appropriate techniques for each contaminant type and location. The three dimensional, integrated characterization and archival system (3D-ICAS) was developed for the purpose of rapid, field level identification, mapping, and archiving of contaminant data. The system consists of three subsystems, an integrated work and operating station, a 3-D coherent laser radar, and a contaminant analysis unit. Target contaminants that can be identified include chemical (currently organic only), radiological, and base materials (asbestos). In operation, two steps are required. First, the remotely operable 3-D laser radar maps an area of interest in the spatial domain. Second, the remotely operable contaminant analysis unit maps the area of interest in the chemical, radiological, and base material domains. The resultant information is formatted for display and archived using an integrated workstation. A 3-D model of the merged spatial and contaminant domains cart be displayed along with a color-coded contaminant tag at each analysis point. In addition, all of the supporting detailed data are archived for subsequent QC checks. The 3D-ICAS system is capable of performing all contaminant characterization in a dwell time of 6 seconds. The radiological and chemical sensors operate at US Environmental Protection Agency regulatory levels. Base materials identification is accomplished using a molecular vibrational spectroscopy, which can identify materials such as asbestos, concrete, wood, or transite. The multipurpose sensor head is positioned robotically using a small CRS Robotics A465 arm, which is registered to the environment map by the 3-D laser radar.

Barry, R.E.; Gallman, P.; Jarvis, G.; Griffiths, P.

1999-04-25T23:59:59.000Z

139

Radiological Instrumentation Assessment for King County Wastewater Treatment Division  

SciTech Connect

The King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into its combined sanitary and storm sewer system. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include "dirty bombs" that are not nuclear detonations but are explosives designed to spread radioactive material. Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. Volume 2 of PNNL-15163 assesses the radiological instrumentation needs for detection of radiological or nuclear terrorism, in support of decisions to treat contaminated wastewater or to bypass the West Point Treatment Plant (WPTP), and in support of radiation protection of the workforce, the public, and the infrastructure of the WPTP. Fixed radiation detection instrumentation should be deployed in a defense-in-depth system that provides 1) early warning of significant radioactive material on the way to the WPTP, including identification of the radionuclide(s) and estimates of the soluble concentrations, with a floating detector located in the wet well at the Interbay Pump Station and telemetered via the internet to all authorized locations; 2) monitoring at strategic locations within the plant, including 2a) the pipe beyond the hydraulic ram in the bar screen room; 2b) above the collection funnels in the fine grit facility; 2c) in the sampling tank in the raw sewage pump room; and 2d) downstream of the concentration facilities that produce 6% blended and concentrated biosolids. Engineering challenges exist for these applications. It is necessary to deploy both ultra-sensitive detectors to provide early warning and identification and detectors capable of functioning in high-dose rate environments that are likely under some scenarios, capable of functioning from 10 microrems per hour (background) up to 1000 rems per hour. Software supporting fixed spectroscopic detectors is needed to provide prompt, reliable, and simple interpretations of spectroscopic outputs that are of use to operators and decision-makers. Software to provide scientists and homeland security personnel with sufficient technical detail for identification, quantification, waste management decisions, and for the inevitable forensic and attribution needs must be developed. Computational modeling using MCNP software has demonstrated that useful detection capabilities can be deployed. In particular, any of the isotopes examined can be detected at levels between 0.01 and 0.1 ?Ci per gallon. General purpose instruments that can be used to determine the nature and extent of radioactive contamination and measure radiation levels for purposes of protecting personnel and members of the public should be available. One or more portable radioisotope identifiers (RIIDs) should be available to WTD personnel. Small, portable battery-powered personal radiation monitors should be widely available WTD personnel. The personal monitors can be used for personal and group radiation protection decisions, and to alert management to the need to get expert backup. All considerations of radiological instrumentation require considerations of training and periodic retraining of personnel, as well as periodic calibration and maintenance of instruments. Routine “innocent” alarms will occur due to medical radionuclides that are legally discharged into sanitary sewers on a daily basis.

Strom, Daniel J.; McConn, Ronald J.; Brodzinski, Ronald L.

2005-05-19T23:59:59.000Z

140

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

Note: This page contains sample records for the topic "radiologically contaminated material" 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

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

142

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

143

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

144

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

145

Addendum to the Corrective Action Decision Document/Closure Report for Corrective Action Unit 529: Area 25 Contaminated Materials, Nevada Test Site, Nevada, Revision 1  

SciTech Connect

This document constitutes an addendum to the Corrective Action Decision Document/Closure Report for Corrective Action Unit 529: Area 25 Contaminated Materials, Nevada Test Site, Nevada as described in the document Recommendations and Justifications To Remove Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office Federal Facility Agreement and Consent Order dated September 2013. The Use Restriction (UR) Removal document was approved by the Nevada Division of Environmental Protection on October 16, 2013. The approval of the UR Removal document constituted approval of each of the recommended UR removals. In conformance with the UR Removal document, this addendum consists of: This page that refers the reader to the UR Removal document for additional information The cover, title, and signature pages of the UR Removal document The NDEP approval letter The corresponding section of the UR Removal document This addendum provides the documentation justifying the cancellation of the UR for CAS 25-23-17, Contaminated Wash (Parcel H). This UR was established as part of FFACO corrective actions and was based on the presence of total petroleum hydrocarbon diesel-range organics contamination at concentrations greater than the NDEP action level at the time of the initial investigation.

Krauss, Mark J.

2013-10-01T23:59:59.000Z

146

DOE-HDBK-1143-2001; Radiological Control Training for Supervisors - Course Introduction  

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

143-2001 143-2001 Instructor's Guide DEPARTMENT OF ENERGY LESSON PLAN Course Material Topic: Administrative Policies and Procedures Objectives: Upon completion of this training, the student will be able to: 1. Identify the radiological controlled areas a person should be allowed to enter after successfully completing General Employee Radiological Training, Radiological Worker I training, and Radiological Worker II training. 2. List five actions used to increase the awareness level of workers relating to proper radiological work practices. 3. Identify three conditions when a "Stop Radiological Work" should be initiated. 4. Identify the actions that should be performed, prior to recommencement of work, after a "Stop Radiological Work" order has been initiated.

147

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...

148

Method for contamination control and barrier apparatus with filter for containing waste materials that include dangerous particulate matter  

DOE Patents (OSTI)

A container for hazardous waste materials that includes air or other gas carrying dangerous particulate matter has incorporated barrier material, preferably in the form of a flexible sheet, and one or more filters for the dangerous particulate matter sealably attached to such barrier material. The filter is preferably a HEPA type filter and is preferably chemically bonded to the barrier materials. The filter or filters are preferably flexibly bonded to the barrier material marginally and peripherally of the filter or marginally and peripherally of air or other gas outlet openings in the barrier material, which may be a plastic bag. The filter may be provided with a backing panel of barrier material having an opening or openings for the passage of air or other gas into the filter or filters. Such backing panel is bonded marginally and peripherally thereof to the barrier material or to both it and the filter or filters. A coupling or couplings for deflating and inflating the container may be incorporated. Confining a hazardous waste material in such a container, rapidly deflating the container and disposing of the container, constitutes one aspect of the method of the invention. The chemical bonding procedure for producing the container constitutes another aspect of the method of the invention. 3 figs.

Pinson, P.A.

1998-02-24T23:59:59.000Z

149

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

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

Study Guide Study Guide 2.14-1 Course Title: Radiological Control Technician Module Title: Personnel Decontamination Module Number: 2.14 Objectives: 2.14.01 List the three factors which determine the actions taken in decontamination of personnel. i 2.14.02 List the preliminary actions and notifications required by the RCT for an individual suspected to be contaminated. i 2.14.03 List the actions to be taken by the RCT when contamination of clothing is confirmed. i 2.14.04 List the actions to be taken by the RCT when skin contamination is confirmed. i 2.14.05 List the steps for using decontamination reagents to decontaminate personnel. INTRODUCTION In our work environment, one of the major concerns of radiological control is the prevention of personnel contamination. When personnel contamination has been

150

Corrective Action Plan for Corrective Action Unit 168: Area 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada, REV 1  

SciTech Connect

Corrective Action Unit (CAU) 168 is identified in the Federal Facility Agreement and Consent Order of 1996 as Area 25 and 26 Contaminated Materials and Waste Dumps. CAU 168 consists of twelve Corrective Action Sites (CASs) in Areas 25 and 26 of the Nevada Test Site, which is approximately 105 kilometers (65 miles) northwest of Las Vegas, Nevada. The CASs contain surface and subsurface debris, impacted soil, and contaminated materials. Site characterization activities were conducted in 2002, and the results are presented in the Corrective Action Decision Document (CADD) for CAU 168 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2006). Site characterization results indicated that soil at several sites exceeded the clean-up criteria for total petroleum hydrocarbons (TPH), polychlorinated biphenyls (PCBs), and radionuclides. The Nevada Division of Environmental Protection approved the proposed corrective actions specified in the CADD (NNSA/NSO, 2006). The approved corrective actions include no further action, clean closure, and closure in place with administrative controls.

NSTec Environmental Restoration

2007-12-01T23:59:59.000Z

151

Radiological Contingency Planning for the Mars Science Laboratory Launch  

SciTech Connect

This paper describes the contingency planning for the launch of the Mars Science Laboratory scheduled for the 21-day window beginning on September 15, 2009. National Security Technologies, LLC (NSTec), based in Las Vegas, Nevada, will support the U.S. Department of Energy (DOE) in its role for managing the overall radiological contingency planning support effort. This paper will focus on new technologies that NSTec’s Remote Sensing Laboratory (RSL) is developing to enhance the overall response capability that would be required for a highly unlikely anomaly. This paper presents recent advances in collecting and collating data transmitted from deployed teams and sensors. RSL is responsible to prepare the contingency planning for a range of areas from monitoring and assessment, sample collection and control, contaminated material release criteria, data management, reporting, recording, and even communications. The tools RSL has available to support these efforts will be reported. The data platform RSL will provide shall also be compatible with integration of assets and field data acquired with other DOE, National Aeronautics and Space Administration, state, and local resources, personnel, and equipment. This paper also outlines the organizational structure for response elements in radiological contingency planning.

Paul Guss, Robert Augdahl, Bill Nickels, Cassandra Zellers

2008-04-16T23:59:59.000Z

152

Radiological Contingency Planning for the Mars Science Laboratory Launch  

SciTech Connect

This paper describes the contingency planning for the launch of the Mars Science Laboratory scheduled for the 21-day window beginning on September 15, 2009. National Security Technologies, LLC (NSTec), based in Las Vegas, Nevada, will support the U.S. Department of Energy (DOE) in its role for managing the overall radiological contingency planning support effort. This paper will focus on new technologies that NSTec’s Remote Sensing Laboratory (RSL) is developing to enhance the overall response capability that would be required for a highly unlikely anomaly. This paper presents recent advances in collecting and collating data transmitted from deployed teams and sensors. RSL is responsible to prepare the contingency planning for a range of areas from monitoring and assessment, sample collection and control, contaminated material release criteria, data management, reporting, recording, and even communications. The tools RSL has available to support these efforts will be reported. The data platform RSL will provide shall also be compatible with integration of assets and field data acquired with other DOE, National Space and Aeronautics and Space Administration (NASA), state, and local resources, personnel, and equipment. This paper also outlines the organizational structure for response elements in radiological contingency planning.

Paul P. Guss

2008-04-01T23:59:59.000Z

153

Dose assessment for management alternatives for NORM-contaminated equipment within the petroleum industry  

Science Conference Proceedings (OSTI)

The contamination of drilling and production equipment by naturally occurring radioactive material (NORM) is a growing concern for the petroleum industry and regulators. Large volumes of NORM-contaminated scrap metal are generated by the industry each year. The contamination generally occurs as surface contamination on the interior of water-handling equipment. The source of this contamination is accumulation of by-product wastes, in the form of scale and sludge contaminated with NORM that are generated by extraction processes. The primary radionuclides of concern in petroleum industry NORM-wastes are radium-226 (Ra-226), and radium-228 (Ra-228). These isotopes are members of the uranium-238 and thorium-232 decay series, respectively. The uranium and thorium isotopes, which are naturally present in the subsurface formations from which hydrocarbons are extracted, are largely immobile and remain in the subsurface. The more soluble radium can become mobilized in the formation water and be transported to the surface in the produced water waste stream. The radium either remains in solution or precipitates in scale or sludge deposits, depending on water salinity and on temperature and pressure phase changes. NORM-containing scale consists of radium that has coprecipitated with barium, calcium, or strontium sulfates, and sludge typically consists of radium-containing silicates and carbonates. This assessment is limited to the evaluation of potential radiological doses from management options that specifically involve recycle and reuse of contaminated metal. Doses from disposal of contaminated equipment are not addressed. Radiological doses were estimated for workers and the general public for equipment decontamination and smelting. Results of this assessment can be used to examine policy issues concerning the regulation and management of NORM-contaminated wastes generated by the petroleum industry.

Blunt, D.L.; Smith, K.P.

1995-08-01T23:59:59.000Z

154

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

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

EA-1919: Recycle of Scrap Metals Originating from Radiological EA-1919: Recycle of Scrap Metals Originating from Radiological Areas EA-1919: Recycle of Scrap Metals Originating from Radiological Areas Summary This Programmatic EA evaluates alternatives for the management of scrap metal originating from DOE radiological control areas, including the proposed action to allow for the recycle of uncontaminated scrap metal that meets the requirements of DOE Order 458.1. (Metals with volumetric radioactive contamination are not included in the scope of this Programmatic EA.) PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD December 28, 2012 EA-1919: Notice of Public Comment Period Extension Recycling of Scrap Metals Originating from Radiological Areas December 12, 2012 EA-1919: Notice of Availability of a Draft Programmatic Environmental

155

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

SciTech Connect

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

Farmer, Joseph C. (Tracy, CA)

2012-03-13T23:59:59.000Z

156

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

157

Doffing Procedures for Firefighters' Contaminated Turnout Gear: Documentation for Videotape  

Science Conference Proceedings (OSTI)

Firefighting in an area contaminated by radioactive materials can result in contaminated clothing that requires careful handling. This report documents a videotape that provides simple how-to procedures for doffing contaminated or potentially contaminated firefighter turnout gear.

1992-07-01T23:59:59.000Z

158

Corrective Action Decision Document for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada with Errata Sheet  

Science Conference Proceedings (OSTI)

This Corrective Action Decision Document (CADD) has been prepared for Corrective Action Unit (CAU) 166, Storage Yards and Contaminated Materials, in accordance with the Federal Facility Agreement and Consent Order (1996). The corrective action sites (CASs) are located in Areas 2, 3, 5, and 18 of the Nevada Test Site, Nevada. Corrective Action Unit 166 is comprised of the following CASs: • 02-42-01, Cond. Release Storage Yd - North • 02-42-02, Cond. Release Storage Yd - South • 02-99-10, D-38 Storage Area • 03-42-01, Conditional Release Storage Yard • 05-19-02, Contaminated Soil and Drum • 18-01-01, Aboveground Storage Tank • 18-99-03, Wax Piles/Oil Stain The purpose of this CADD is to identify and provide the rationale for the recommendation of a corrective action alternative (CAA) for the seven CASs within CAU 166. Corrective action investigation (CAI) activities were performed from July 31, 2006, through February 28, 2007, as set forth in the CAU 166 Corrective Action Investigation Plan (NNSA/NSO, 2006).

Grant Evenson

2007-03-01T23:59:59.000Z

159

Sensors & Materials | Argonne National Laboratory  

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

and engineering expertise to develop, test, and deploy sensors and materials to detect nuclear and radiological materials, chemical and biological agents and explosives. Argonne...

160

A HUMAN RELIABILITY-CENTERED APPROACH TO THE DEVELOPMENT OF JOB AIDS FOR REVIEWERS OF MEDICAL DEVICES THAT USE RADIOLOGICAL BYPRODUCT MATERIALS.  

SciTech Connect

The U.S. Nuclear Regulatory Commission (NRC) is engaged in an initiative to risk-inform the regulation of byproduct materials. Operating experience indicates that human actions play a dominant role in most of the activities involving byproduct materials, which are radioactive materials other than those used in nuclear power plants or in weapons production, primarily for medical or industrial purposes. The overall risk of these activities is strongly influenced by human performance. Hence, an improved understanding of human error, its causes and contexts, and human reliability analysis (HRA) is important in risk-informing the regulation of these activities. The development of the human performance job aids was undertaken by stages, with frequent interaction with the prospective users. First, potentially risk significant human actions were identified based on reviews of available risk studies for byproduct material applications and of descriptions of events for byproduct materials applications that involved potentially significant human actions. Applications from the medical and the industrial domains were sampled. Next, the specific needs of the expected users of the human performance-related capabilities were determined. To do this, NRC headquarters and region staff were interviewed to identify the types of activities (e.g., license reviews, inspections, event assessments) that need HRA support and the form in which such support might best be offered. Because the range of byproduct uses regulated by NRC is so broad, it was decided that initial development of knowledge and tools would be undertaken in the context of a specific use of byproduct material, which was selected in consultation with NRC staff. Based on needs of NRC staff and the human performance related characteristics of the context chosen, knowledge resources were then compiled to support consideration of human performance issues related to the regulation of byproduct materials. Finally, with information sources and an application context identified, a set of strawman job aids was developed, which was then presented to prospective users for critique and comment. Work is currently under way to develop training materials and refine the job aids in preparation for a pilot evaluation.

COOPER, S.E.; BROWN, W.S.; WREATHALL, J.

2005-02-02T23:59:59.000Z

Note: This page contains sample records for the topic "radiologically contaminated material" 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 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...

162

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

163

Measurements and Standards for Contaminants in ...  

Science Conference Proceedings (OSTI)

Measurements and Standards for Contaminants in Environmental Samples. ... Kelly, WR, Long, SE, and Seiber, JR, Standard Reference Materials ...

2013-07-23T23:59:59.000Z

164

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

165

ASSESSMENT OF RADIOACTIVE AND NON-RADIOACTIVE CONTAMINANTS FOUND IN LOW LEVEL RADIOACTIVE WASTE STREAMS  

Science Conference Proceedings (OSTI)

This paper describes and presents the findings from two studies undertaken for the European Commission to assess the long-term impact upon the environment and human health of non-radioactive contaminants found in various low level radioactive waste streams. The initial study investigated the application of safety assessment approaches developed for radioactive contaminants to the assessment of nonradioactive contaminants in low level radioactive waste. It demonstrated how disposal limits could be derived for a range of non-radioactive contaminants and generic disposal facilities. The follow-up study used the same approach but undertook more detailed, disposal system specific calculations, assessing the impacts of both the non-radioactive and radioactive contaminants. The calculations undertaken indicated that it is prudent to consider non-radioactive, as well as radioactive contaminants, when assessing the impacts of low level radioactive waste disposal. For some waste streams with relatively low concentrations of radionuclides, the potential post-closure disposal impacts from non-radioactive contaminants can be comparable with the potential radiological impacts. For such waste streams there is therefore an added incentive to explore options for recycling the materials involved wherever possible.

R.H. Little, P.R. Maul, J.S.S. Penfoldag

2003-02-27T23:59:59.000Z

166

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

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

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

167

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

168

DOE-HDBK-1122-99; Radiological Technician Training  

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

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

169

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

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

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

170

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

171

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

172

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

173

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

174

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

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

4-1 4-1 DEPARTMENT OF ENERGY LESSON PLAN Course Material Topic: Elements of a Radiological Control Program Objectives: Upon completion of this lesson, the participant will be able to: 1. Identify factors that influence the scope and magnitude of a Radiological Control Program at any nuclear facility. 2. Identify typical elements of a Radiological Control Program. Training Aids: Overhead Transparencies (OTs): OT 4.1 - OT 4.5 (may be supplemented or substituted with updated or site-specific information) Handouts - "List of Radiological Control Program Elements" "Elements of a Radiological Control Program" Equipment Needs: Overhead projector Screen Flip chart Markers Masking tape Student Materials: Student's Guide

175

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

176

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

177

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

178

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

179

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

180

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

Note: This page contains sample records for the topic "radiologically contaminated material" 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

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

National Nuclear Security Administration (NNSA)

efforts result in permanent threat reduction. NNSA is returning Russian-origin highly enriched uranium (HEU) fresh and spent fuel from Russian-designed research reactors worldwide...

182

Nuclear and Radiological Material Security | National Nuclear...  

National Nuclear Security Administration (NNSA)

17, 2013 NNSA, Republic of Korea Ministry Agree to Minimize Use of HEU in Nuclear Reactors Sep 3, 2013 NNSA Conducts Two Emergency Response Training Courses in Armenia Aug 29, 2013...

183

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

National Nuclear Security Administration (NNSA)

17, 2013 NNSA, Republic of Korea Ministry Agree to Minimize Use of HEU in Nuclear Reactors Sep 3, 2013 NNSA Conducts Two Emergency Response Training Courses in Armenia Aug 29, 2013...

184

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

National Nuclear Security Administration (NNSA)

of national regulatory infrastructures; Provide remote monitoring and orphan source search and recovery capabilities to support national efforts to strengthen the control and...

185

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

186

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

187

Subsurface Contamination Control  

Science Conference Proceedings (OSTI)

There are two objectives of this report, ''Subsurface Contamination Control''. The first is to provide a technical basis for recommending limiting radioactive contamination levels (LRCL) on the external surfaces of waste packages (WP) for acceptance into the subsurface repository. The second is to provide an evaluation of the magnitude of potential releases from a defective WP and the detectability of the released contents. The technical basis for deriving LRCL has been established in ''Retrieval Equipment and Strategy for Wp on Pallet'' (CRWMS M and O 2000g, 6.3.1). This report updates the derivation by incorporating the latest design information of the subsurface repository for site recommendation. The derived LRCL on the external surface of WPs, therefore, supercede that described in CRWMS M and O 2000g. The derived LRCL represent the average concentrations of contamination on the external surfaces of each WP that must not be exceeded before the WP is to be transported to the subsurface facility for emplacement. The evaluation of potential releases is necessary to control the potential contamination of the subsurface repository and to detect prematurely failed WPs. The detection of failed WPs is required in order to provide reasonable assurance that the integrity of each WP is intact prior to MGR closure. An emplaced WP may become breached due to manufacturing defects or improper weld combined with failure to detect the defect, by corrosion, or by mechanical penetration due to accidents or rockfall conditions. The breached WP may release its gaseous and volatile radionuclide content to the subsurface environment and result in contaminating the subsurface facility. The scope of this analysis is limited to radioactive contaminants resulting from breached WPs during the preclosure period of the subsurface repository. This report: (1) documents a method for deriving LRCL on the external surfaces of WP for acceptance into the subsurface repository; (2) provides a table of derived LRCL for nuclides of radiological importance; (3) Provides an as low as is reasonably achievable (ALARA) evaluation of the derived LRCL by comparing potential onsite and offsite doses to documented ALARA requirements; (4) Provides a method for estimating potential releases from a defective WP; (5) Provides an evaluation of potential radioactive releases from a defective WP that may become airborne and result in contamination of the subsurface facility; and (6) Provides a preliminary analysis of the detectability of a potential WP leak to support the design of an airborne release monitoring system.

Y. Yuan

2001-12-12T23:59:59.000Z

188

Subsurface Contamination Control  

Science Conference Proceedings (OSTI)

There are two objectives of this report, ''Subsurface Contamination Control''. The first is to provide a technical basis for recommending limiting radioactive contamination levels (LRCL) on the external surfaces of waste packages (WP) for acceptance into the subsurface repository. The second is to provide an evaluation of the magnitude of potential releases from a defective WP and the detectability of the released contents. The technical basis for deriving LRCL has been established in ''Retrieval Equipment and Strategy for Wp on Pallet'' (CRWMS M and O 2000g, 6.3.1). This report updates the derivation by incorporating the latest design information of the subsurface repository for site recommendation. The derived LRCL on the external surface of WPs, therefore, supercede that described in CRWMS M and O 2000g. The derived LRCL represent the average concentrations of contamination on the external surfaces of each WP that must not be exceeded before the WP is to be transported to the subsurface facility for emplacement. The evaluation of potential releases is necessary to control the potential contamination of the subsurface repository and to detect prematurely failed WPs. The detection of failed WPs is required in order to provide reasonable assurance that the integrity of each WP is intact prior to MGR closure. An emplaced WP may become breached due to manufacturing defects or improper weld combined with failure to detect the defect, by corrosion, or by mechanical penetration due to accidents or rockfall conditions. The breached WP may release its gaseous and volatile radionuclide content to the subsurface environment and result in contaminating the subsurface facility. The scope of this analysis is limited to radioactive contaminants resulting from breached WPs during the preclosure period of the subsurface repository. This report: (1) documents a method for deriving LRCL on the external surfaces of WP for acceptance into the subsurface repository; (2) provides a table of derived LRCL for nuclides of radiological importance; (3) Provides an as low as is reasonably achievable (ALARA) evaluation of the derived LRCL by comparing potential onsite and offsite doses to documented ALARA requirements; (4) Provides a method for estimating potential releases from a defective WP; (5) Provides an evaluation of potential radioactive releases from a defective WP that may become airborne and result in contamination of the subsurface facility; and (6) Provides a preliminary analysis of the detectability of a potential WP leak to support the design of an airborne release monitoring system.

Y. Yuan

2001-11-16T23:59:59.000Z

189

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

190

Radiological Contingency Planning for the Mars Science Laboratory Launch  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) provides technical support to the requesting federal agency such as the Federal Bureau of Investigation, Department of Defense, the National Space and Aeronautics and Space Administration (NASA), or a state agency to address the radiological consequences of an event. These activities include measures to alleviate damage, loss, hardship, or suffering caused by the incident; protect public health and safety; restore essential government services; and provide emergency assistance to those affected. Scheduled to launch in the fall of 2009, Mars Science Laboratory is part of NASA's Mars Exploration Program, a long-term effort of robotic exploration of the red planet. Mars Science Laboratory is a rover that will assess whether Mars ever was, or is still today, an environment able to support microbial life. In other words, its mission is to determine the planet's "habitability." The Mars Science Laboratory rover will carry a radioisotope power system that generates electricity from the heat of plutonium's radioactive decay. This power source gives the mission an operating lifespan on Mars' surface of a full Martian year (687 Earth days) or more, while also providing significantly greater mobility and operational flexibility, enhanced science payload capability, and exploration of a much larger range of latitudes and altitudes than was possible on previous missions to Mars. National Security Technologies, LLC (NSTec), based in Las Vegas, Nevada, will support the DOE in its role for managing the overall radiological contingency planning support effort. This paper will focus on new technologies that NSTec is developing to enhance the overall response capability that would be required for a highly unlikely anomaly. This paper presents recent advances in collecting and collating data transmitted from deployed teams and sensors. NSTec is responsible to prepare the contingency planning for a range of areas from monitoring and assessment, sample collection and control, contaminated material release criteria, data management, reporting, recording, and even communications. The tools NSTec has available to support these efforts will be reported. The data platform NSTec will provide shall also be compatible with integration of assets and field data acquired with other DOE, NASA, state, and local resources, personnel, and equipment. This paper also outlines the organizational structure for response elements in radiological contingency planning.

Paul Guss

2008-03-01T23:59:59.000Z

191

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

192

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

193

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

194

NREL: Hydrogen and Fuel Cells Research - Fuel Cell System Contaminants...  

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

Fuel Cell System Contaminants Material Screening Data NREL designed this interactive material selector tool to help fuel cell developers and material suppliers explore the results...

195

Materials  

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

Materials Materials and methods are available as supplementary materials on Science Online. 16. W. Benz, A. G. W. Cameron, H. J. Melosh, Icarus 81, 113 (1989). 17. S. L. Thompson, H. S. Lauson, Technical Rep. SC-RR-710714, Sandia Nat. Labs (1972). 18. H. J. Melosh, Meteorit. Planet. Sci. 42, 2079 (2007). 19. S. Ida, R. M. Canup, G. R. Stewart, Nature 389, 353 (1997). 20. E. Kokubo, J. Makino, S. Ida, Icarus 148, 419 (2000). 21. M. M. M. Meier, A. Reufer, W. Benz, R. Wieler, Annual Meeting of the Meteoritical Society LXXIV, abstr. 5039 (2011). 22. C. B. Agnor, R. M. Canup, H. F. Levison, Icarus 142, 219 (1999). 23. D. P. O'Brien, A. Morbidelli, H. F. Levison, Icarus 184, 39 (2006). 24. R. M. Canup, Science 307, 546 (2005). 25. J. J. Salmon, R. M. Canup, Lunar Planet. Sci. XLIII, 2540 (2012). Acknowledgments: SPH simulation data are contained in tables S2 to S5 of the supplementary materials. Financial support

196

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.

197

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

198

Material  

DOE Green Energy (OSTI)

Li(Ni{sub 0.4}Co{sub 0.15}Al{sub 0.05}Mn{sub 0.4})O{sub 2} was investigated to understand the effect of replacement of the cobalt by aluminum on the structural and electrochemical properties. In situ X-ray absorption spectroscopy (XAS) was performed, utilizing a novel in situ electrochemical cell, specifically designed for long-term X-ray experiments. The cell was cycled at a moderate rate through a typical Li-ion battery operating voltage range. (1.0-4.7 V) XAS measurements were performed at different states of charge (SOC) during cycling, at the Ni, Co, and the Mn edges, revealing details about the response of the cathode to Li insertion and extraction processes. The extended X-ray absorption fine structure (EXAFS) region of the spectra revealed the changes of bond distance and coordination number of Ni, Co, and Mn absorbers as a function of the SOC of the material. The oxidation states of the transition metals in the system are Ni{sup 2+}, Co{sup 3+}, and Mn{sup 4+} in the as-made material (fully discharged), while during charging the Ni{sup 2+} is oxidized to Ni{sup 4+} through an intermediate stage of Ni{sup 3+}, Co{sup 3+} is oxidized toward Co{sup 4+}, and Mn was found to be electrochemically inactive and remained as Mn{sup 4+}. The EXAFS results during cycling show that the Ni-O changes the most, followed by Co-O, and Mn-O varies the least. These measurements on this cathode material confirmed that the material retains its symmetry and good structural short-range order leading to the superior cycling reported earlier.

Rumble, C.; Conry, T.E.; Doeff, Marca; Cairns, Elton J.; Penner-Hahn, James E.; Deb, Aniruddha

2010-06-14T23:59:59.000Z

199

Engineering evaluation/cost analysis for the proposed removal of contaminated materials from Pad 1 at the Elza Gate site, Oak Ridge, Tennessee  

Science Conference Proceedings (OSTI)

This engineering evaluation/cost analysis (EE/CA) has been prepared in support of the proposed removal action for cleanup of radioactively contaminated concrete and soil beneath a building on privately owned commercial property in Oak Ridge, Tennessee. The property, known as the Elza Gate site, became contaminated with uranium-238, radium-226, thorium-232, thorium-230, and decay products as a result of the Manhattan Engineer District storing uranium ore and ore processing residues at the site in the early 1940s. The US Department of Energy (DOE) has responsibility for cleanup of the property under its Formerly Utilized Sites Remedial Action Program (FUSRAP). The DOE plans to remove the cracked and worn concrete pad and contaminated subsoil beneath the pad, after which the property owner/tenant will provide clean backfill and new concrete. Portions of the pad and subsoil are contaminated and, if stored or disposed of improperly, may represent a potential threat to public health or welfare and the environment. The EE/CA report is the appropriate documentation for the proposed removal action, as identified in guidance from the US Environmental Protection Agency. the objective of the EE/CA report, in addition to identifying the planned removal action, is to document the selection of response activities that will mitigate the potential for release of contaminants from the property into the environment and minimize the related threats to public health or welfare and the environment. 7 refs., 2 figs., 3 tabs.

Not Available

1990-06-01T23:59:59.000Z

200

Engineering evaluation/cost analysis for the proposed removal of contaminated materials from pad 1 at the Elza Gate site, Oak Ridge, Tennessee  

SciTech Connect

This engineering evaluation/cost analysis (EE/CA) has been prepared in support of the proposed removal action for cleanup of radioactively contaminated concrete and soil beneath a building on privately owned commercial property in Oak Ridge, Tennessee. The property, known as the Elza Gate site, became contaminated with uranium-238, radium-226, thorium-232, thorium-230, and decay products as a result of the Manhattan Engineer District storing uranium ore and ore processing residues at the site in the early 1940s. The US Department of Energy (DOE) has responsibility for cleanup of the property under its Formerly Utilized Sites Remedial Action Program (FUSRAP). The DOE plans to remove the cracked and worn concrete pad and contaminated subsoil beneath the pad, after which the property owner/tenant will provide clean backfill and new concrete. Portions of the pad and subsoil are contaminated and, if stored or disposed of improperly, may represent a potential threat to public health or welfare and the environment. The EE/CA report is the appropriate documentation for the proposed removal action, as identified in guidance from the US Environmental Protection Agency. The objective of the EE/CA report, in addition to identifying the planned removal action, is to document the selection of response activities that will mitigate the potential for release of contaminants from the property into the environment and minimize the related threats to public health or welfare and the environment. 7 refs., 2 figs., 3 tabs.

Not Available

1990-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiologically contaminated material" 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

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 ...

202

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

203

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

204

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

205

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

206

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,

207

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

208

Method of removing contaminants from plastic resins  

DOE Patents (OSTI)

A method for removing contaminants from synthetic resin material containers using a first organic solvent system and a second carbon dioxide system. The organic solvent is utilized for removing the contaminants from the synthetic resin material and the carbon dioxide is used to separate any residual organic solvent from the synthetic resin material.

Bohnert, George W. (Harrisonville, MO); Hand, Thomas E. (Lee' s Summit, MO); DeLaurentiis, Gary M. (Jamestown, CA)

2008-11-18T23:59:59.000Z

209

Method for removing contaminants from plastic resin  

Science Conference Proceedings (OSTI)

A method for removing contaminants from synthetic resin material containers using a first organic solvent system and a second carbon dioxide system. The organic solvent is utilized for removing the contaminants from the synthetic resin material and the carbon dioxide is used to separate any residual organic solvent from the synthetic resin material.

Bohnert, George W. (Harrisonville, MO); Hand, Thomas E. (Lee's Summit, MO); DeLaurentiis, Gary M. (Jamestown, CA)

2008-12-30T23:59:59.000Z

210

Method of removing contaminants from plastic resins  

Science Conference Proceedings (OSTI)

A method for removing contaminants from synthetic resin material containers using a first organic solvent system and a second carbon dioxide system. The organic solvent is utilized for removing the contaminants from the synthetic resin material and the carbon dioxide is used to separate any residual organic solvent from the synthetic resin material.

Bohnert,George W. (Harrisonville, MO); Hand,Thomas E. (Lee's Summit, MO); Delaurentiis,Gary M. (Jamestown, CA)

2007-08-07T23:59:59.000Z

211

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

212

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

213

ORISE: REAC/TS Radiological Incident Medical Consultation  

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

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

214

CLEANING OF RADIOACTIVE CONTAMINATED OCCUPATIONAL CLOTHING  

SciTech Connect

The soiling and contamination of work clothing and ways of removing this contamination are discussed. Means of disinfection, washing tests with radioactive-contaminated cotton clothing, construction of the laundry, and cleaning protective clothing of plastic and other materials with the help of washing methods and polyphosphates are described. (M.C.G.)

Siewert, G.; Schikora, Th.

1963-11-01T23:59:59.000Z

215

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...

216

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...

217

The radiological impact of the 2000 Hanford Fire (24-Command Fire)  

E-Print Network (OSTI)

The range fire at the Hanford facility in late June 2000 coupled with the fire at Los Alamos during the same year have raised a number of questions about the potential migration and/or transport of radioactive materials off U.S. nuclear sites into more populated areas. This paper examines the radiological impact of the 24-Command Fire, which occurred on the Hanford Site in late June 2000. Several different approaches are compared against each other to determine the validity of the results. The approaches include physical calculations from collected data as well as estimates from current transport and diffusion software. The analysis begins with the estimation of release. There are sufficient data on the concentrations of radionuclides in the most contaminated areas of the Hanford Site, but very little on the land in between. Once soil concentrations were determined, resuspension factors were applied to estimate releases of material from these areas. A Hanford-specific diffusion and dispersion program, a dose assessment program, and a calculation by hand were used to determine the estimated transport of material to areas populated by the general public. These results are compared against each other as well as the air monitoring results obtained and reported by the United States Environmental Protection Agency and the Washington State Department of Health. Air concentrations from all three methods were used to calculate the associated doses and risks to individuals in these areas. From the analyses, the radiological impact of the fire was determined to be minimal. The ensuing wind events, resuspending particulate matter from the contaminated areas burned during the fire, resulted in a committed effective dose of approximately 10 []Sv (0.01 mrem) from the inhalation of contaminated air. This dose is insignificant when compared to the 360 mrem per year average dose of a member of the general public from indoor and outdoor sources of background radiation. The ingestion pathway was analyzed but found to contribute less than 2 Bq yr?¹ for the most important foodstuffs: vegetables and fruits.

Henderson, Ashley David

2001-01-01T23:59:59.000Z

218

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.

219

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

220

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

Note: This page contains sample records for the topic "radiologically contaminated material" 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

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

222

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

223

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

224

Radiological Control Technician Training  

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

Documentation Documentation ............................................................................2.01-1 Module 2.02 Communication Systems ..................................................................................2.02-1 Module 2.03 Counting Errors and Statistics ..........................................................................2.03-1 Module 2.04 Dosimetry .........................................................................................................2.04-1 Module 2.05 Contamination Control .....................................................................................2.05-1 Module 2.06 Airborne Sampling Program/Methods .............................................................2.06-1 Module 2.07 Respiratory Protection ......................................................................................2.07-1

225

Radiological Control Technician Training  

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

Documentation ............................................................................2.01-1 Documentation ............................................................................2.01-1 Module 2.02 Communication Systems ..................................................................................2.02-1 Module 2.03 Counting Errors and Statistics ..........................................................................2.03-1 Module 2.04 Dosimetry .........................................................................................................2.04-1 Module 2.05 Contamination Control .....................................................................................2.05-1 Module 2.06 Airborne Sampling Program/Methods .............................................................2.06-1 Module 2.07 Respiratory Protection ......................................................................................2.07-1

226

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

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

Instructor's Guide Instructor's Guide 2.14-1 Course Title: Radiological Control Technician Module Title: Personnel Decontamination Module Number: 2.14 Objectives: 2.14.01 List the three factors which determine the actions taken in decontamination of personnel. L 2.14.02 List the preliminary actions and notifications required by the RCT for an individual suspected to be contaminated. L 2.14.03 List the actions to be taken by the RCT when contamination of clothing is confirmed. L 2.14.04 List the actions to be taken by the RCT when skin contamination is confirmed. L 2.14.05 List the steps for using decontamination reagents to decontaminate personnel. References: (Site Specific) Instructional Aids: 1. Overheads 2. Overhead projector/screen 3. Chalkboard/whiteboard 4. Lessons learned DOE-HDBK-1122-99 Module 2.14 Personnel Decontamination

227

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.

228

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

229

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

230

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.

231

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...

232

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

233

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

234

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

235

Special Training Materials | Y-12 National Security Complex  

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

Nuclear and Radiological Field Training Center Special Training Materials Special Training Materials Members of the 54th WMD Civil Support Team (Wisconsin National Guard) operate...

236

Radiological assessment. A textbook on environmental dose analysis  

SciTech Connect

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

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

1983-09-01T23:59:59.000Z

237

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

238

Model for Electron-Beam-Induced Current Analysis of mc-Si Addressing Defect Contrast Behavior in Heavily Contaminated PV Material: Preprint  

DOE Green Energy (OSTI)

Much work has been done to correlate electron-beam-induced current (EBIC) contrast behavior of extended defects with the character and degree of impurity decoration. However, existing models fail to account for recently observed contrast behavior of defects in heavily contaminated mc-Si PV cells. We have observed large increases in defect contrast with decreasing temperature for all electrically active defects, regardless of their initial contrast signatures at ambient temperature. This negates the usefulness of the existing models in identifying defect character and levels of impurity decoration based on the temperature dependence of the contrast behavior. By considering the interactions of transition metal impurities with the silicon lattice and extended defects, we attempt to provide an explanation for these observations. Our findings will enhance the ability of the PV community to understand and mitigate the effects of these types of defects as the adoption of increasingly lower purity feedstocks for mc-Si PV production continues.

Guthrey, H.; Gorman, B.; Al-Jassim, M.

2012-06-01T23:59:59.000Z

239

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

240

Neutron Energy Measurements in Radiological Emergency Response Applications  

Science Conference Proceedings (OSTI)

We present significant results in recent advances in the determination of neutron energy. Neutron energy measurements are a small but very significant part of radiological emergency response applications. Mission critical information can be obtained by analyzing the neutron energy given off from radioactive materials. In the case of searching for special nuclear materials, neutron energy information from an unknown source can be of paramount importance.

Sanjoy Mukhopadhyay, Paul Guss, Michael Hornish, Scott Wilde, Tom Stampahar, Michael Reed

2009-04-30T23:59:59.000Z

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


241

Radiological 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

242

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

243

RADIOLOGICAL CRITERIA FOR LICENSE TERMINATION OF URANIUM RECOVERY FACILITIES  

E-Print Network (OSTI)

radiological criteria for building surfaces and radionuclides other than radium in soil, for termination of uranium recovery licenses. SUMMARY: In a Staff Requirements Memorandum (SRM) on SECY-98-084, dated August 11, 1998 (Attachment 1), the Commission indicated that it did not object to the staff's recommendation to use the radium benchmark dose in developing a final rule applicable to uranium recovery licensees. The final rule addresses radiological criteria for decommissioning land and buildings required for license termination for uranium recovery facilities, e.g., uranium mills and in situ leach facilities (ISLs). The final rule will provide a clear and consistent regulatory basis for determining the extent to which lands and structures can be considered to be decommissioned. BACKGROUND: On August 22, 1994 (59 FR 43200), the U.S. Nuclear Regulatory Commission (NRC) published a proposed rule for comment in the Federal Register, to amend 10 CFR Part 20, "Standards for Protection Against Radiation, " to include radiological criteria for decommissioning as subpart E. The proposed rule applied to uranium mill facilities and other NRC licensees, but did not apply to mill tailings disposal or to soil radium cleanup at mills because the radiological criteria for these activities are regulated under 10 CFR Part 40, Appendix A. Some commenters recommended that the rule exempt conventional thorium and uranium mill facilities and ISLs. In SECY-97-046A, dated March 28, 1997, entitled "Final Rule on Radiological Criteria for License Termination, " the staff recommended that the final rule indicate that for uranium and thorium mill facilities the cleanup of radionuclides other than radium from soil and buildings must result in a dose no greater than the dose resulting from the cleanup of radium-contaminated soil (benchmark

William D. Travers /s

1999-01-01T23:59:59.000Z

244

Clearance Levels For Redundant Material From Decommissioning Of Nuclear Facilities  

E-Print Network (OSTI)

Currently, a great deal is happening in the regulatory field regarding the release of radiologically contaminated material: . The IAEA is working on the revision of Safety Series 89 (governing the principles of exemption and clearance) and of the TECDOC 855 on clearance levels. . The European Commission Directive on basic safety standards for protection against ionizing radiation in both nuclear and non-nuclear industries will become effective in May 2000. . The U.S. NRC has issued its draft on clearance of material from nuclear facilities (NUREG 1640), as well as an "issues" paper on the release of solid materials. The U.S. State Department has launched an International Radioactive Source Management Initiative, one of the objectives being to "develop international standards and guidelines and `harmonize' U.S. and IAEA radioactive clearance levels." Of great significance to the implementor of clearance regulations in the nuclear industry is the emergence of the NORM issue durin...

Shankar Menon Program; Shankar Menon

2000-01-01T23:59:59.000Z

245

Influence of Wetting and Mass Transfer Properties of Organic Chemical Mixtures in Vadose Zone Materials on Groundwater Contamination by Nonaqueous Phase Liquids  

Science Conference Proceedings (OSTI)

Previous studies have found that organic acids, organic bases, and detergent-like chemicals change surface wettability. The wastewater and NAPL mixtures discharged at the Hanford site contain such chemicals, and their proportions likely change over time due to reaction-facilitated aging. The specific objectives of this work were to (1) determine the effect of organic chemical mixtures on surface wettability, (2) determine the effect of organic chemical mixtures on CCl4 volatilization rates from NAPL, and (3) accurately determine the migration, entrapment, and volatilization of organic chemical mixtures. Five tasks were proposed to achieve the project objectives. These are to (1) prepare representative batches of fresh and aged NAPL-wastewater mixtures, (2) to measure interfacial tension, contact angle, and capillary pressure-saturation profiles for the same mixtures, (3) to measure interphase mass transfer rates for the same mixtures using micromodels, (4) to measure multiphase flow and interphase mass transfer in large flow cell experiments, all using the same mixtures, and (5) to modify the multiphase flow simulator STOMP in order to account for updated P-S and interphase mass transfer relationships, and to simulate the impact of CCl4 in the vadose zone on groundwater contamination. Results and findings from these tasks and summarized in the attached final report.

Charles J Werth; Albert J Valocchi, Hongkyu Yoon

2011-05-21T23:59:59.000Z

246

Tonopah Test Range Air Monitoring: CY2012 Meteorological, Radiological, and Airborne Particulate Observations  

SciTech Connect

In 1963, the Atomic Energy Commission (AEC), predecessor to the US Department of Energy (DOE), implemented Operation Roller Coaster on the Tonopah Test Range (TTR) and an adjacent area of the Nevada Test and Training Range (NTTR) (formerly the Nellis Air Force Range (NAFR)). Operation Roller Coaster consisted of four tests in which chemical explosions were detonated in the presence of nuclear devices to assess the dispersal of radionuclides and evaluate the effectiveness of storage structures to contain the ejected radionuclides. These tests resulted in dispersal of plutonium over the ground surface downwind of the test ground zero. Three tests, Clean Slate 1, 2, and 3, were conducted on the TTR in Cactus Flat; the fourth, Double Tracks, was conducted in Stonewall Flat on the NTTR. DOE is working to clean up and close all four sites. Substantial cleaned up has been accomplished at Double Tracks and Clean Slate 1. Cleanup of Clean Slate 2 and 3 is on the DOE planning horizon for some time in the next several years. The Desert Research Institute installed two monitoring stations, number 400 at the Sandia National Laboratories Range Operations Center and number 401 at Clean Slate 3, in 2008 and a third monitoring station, number 402 at Clean Slate 1, in 2011 to measure radiological, meteorological, and dust conditions. The primary objectives of the data collection and analysis effort are to (1) monitor the concentration of radiological parameters in dust particles suspended in air, (2) determine whether winds are re-distributing radionuclides or contaminated soil material, (3) evaluate the controlling meteorological conditions if wind transport is occurring, and (4) measure ancillary radiological, meteorological, and environmental parameters that might provide insight to the above assessments. The following observations are based on data collected during CY2012. The mean annual concentration of gross alpha and gross beta is highest at Station 400 and lowest at Station 401. This difference may be the result of using filter media at Station 400 with a smaller pore size than the media used at the other two stations. Average annual gamma exposure at Station 401 is slightly greater than at Station 400 and 402. Average annual gamma exposure at all three TTR stations are in the upper range to slightly higher than values reported for the CEMP stations surrounding the TTR. At higher wind speeds, the saltation counts are greater at Station 401 than at Station 402 while the suspended particulate concentrations are greater at Station 402 than at Statin 401. Although these observations seem counterintuitive, they are likely the result of differences in the soil material present at the two sites. Station 401 is located on an interfluve elevated above two adjacent drainage channels where the soil surface is likely to be composed of coarser material. Station 402 is located in finer sediments at the playa edge and is also subject to dust from a dirt road only 500 m to the north. During prolonged high wind events, suspended dust concentrations at Station 401 peaked with the initial winds then decreased whereas dust concentrations at Station 402 peaked with each peak in the wind speed. This likely reflects a limited PM10 source that is quickly expended at Station 401 relative to an abundant PM10 source at Station 402. In CY2013, to facilitate comparisons between radiological analyses of collected dust, the filter media at all three stations will be standardized. In addition, a sequence of samples will be collected at Station 400 using both types of filter media to enable development of a mathematical relationship between the results derived from the two filter types. Additionally, having acquired approximately four years of observations at Stations 400 and 401 and a year of observations at Station 402, a period-of-record analysis of the radiological and airborne dust conditions will be undertaken.

Mizell, Steve A; Nikolich, George; Shadel, Craig; McCurdy, Greg; Miller, Julianne J

2013-07-01T23:59:59.000Z

247

Corrective Action Decision Document for Corrective Action Unit 168: Areas 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada: Revision 0, Including Record of Technical Change No. 1  

SciTech Connect

This Corrective Action Decision Document identifies and rationalizes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's selection of recommended corrective action alternatives (CAAs) to facilitate the closure of Corrective Action Unit (CAU)168: Areas 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. Located in Areas 25 and 26 at the NTS in Nevada, CAU 168 is comprised of twelve Corrective Action Sites (CASs). Review of data collected during the corrective action investigation, as well as consideration of current and future operations in Areas 25 and 26 of the NTS, led the way to the development of three CAAs for consideration: Alternative 1 - No Further Action; Alternative 2 - Clean Closure; and Alternative 3 - Close in Place with Administrative Controls. As a result of this evaluation, a combination of all three CAAs is recommended for this CAU. Alternative 1 was the preferred CAA for three CASs, Alternative 2 was the preferred CAA for six CASs (and nearly all of one other CAS), and Alternative 3 was the preferred CAA for two CASs (and a portion of one other CAS) to complete the closure at the CAU 168 sites. These alternatives were judged to meet all requirements for the technical components evaluated as well as all applicable state and federal regulations for closure of the sites and elimination of potential future exposure pathways to the contaminated soils at CAU 168.

U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2003-08-08T23:59:59.000Z

248

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

249

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

250

Standard practice for radiologic examination of semiconductors and electronic components  

E-Print Network (OSTI)

1.1 This practice provides the minimum requirements for nondestructive radiologic examination of semiconductor devices, microelectronic devices, electromagnetic devices, electronic and electrical devices, and the materials used for construction of these items. 1.2 This practice covers the radiologic examination of these items to detect possible defective conditions within the sealed case, especially those resulting from sealing the lid to the case, and internal defects such as extraneous material (foreign objects), improper interconnecting wires, voids in the die attach material or in the glass (when sealing glass is used) or physical damage. 1.3 The values stated in inch-pound units are to be regarded as standard. No other units of measurement are included in this practice. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the app...

American Society for Testing and Materials. Philadelphia

2009-01-01T23:59:59.000Z

251

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...

252

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...

253

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...

254

Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Gunnison, Colorado. Attachment 5, Supplemental radiological data: Final report  

Science Conference Proceedings (OSTI)

Diffusion coefficients for radon gas in earthen materials are required to design suitable radon-barrier covers for uranium tailings impoundments and other materials that emit radon gas. Many early measurements of radon diffusion coefficients relied on the differences in steady-state radon fluxes measured from radon source before and after installation of a cover layer of the material being tested. More recent measurements have utilized the small-sample transient (SST) technique for greater control on moistures and densities of the test soils, greater measurement precision, and reduced testing time and costs. Several of the project sites for the US Department of Energy`s Uranium Mill Tailings Remedial Action (UMTRA) Program contain radiologically contaminated subsurface material composed predominantly of cobbles, gravels andsands. Since remedial action designs require radon diffusion coefficients for the source materials as well as the cover materials, these cobbly and gravelly materials also must be tested. This report contains the following information: a description of the test materials used and the methods developed to conduct the SST radon diffusion measurements on cobbly soils; the protocol for conducting radon diffusion tests oncobbly soils; the results of measurements on the test samples; and modifications to the FITS computer code for analyzing the time-dependent radon diffusion data.

Not Available

1992-10-01T23:59:59.000Z

255

Current Trends in Gamma Radiation 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. In recent years, since the establishment of the Domestic Nuclear Detection Office by the Department of Homeland Security, a tremendous amount of progress has been made in detection materials (scintillators, semiconductors), imaging techniques (Compton imaging, use of active masking and hybrid imaging), data acquisition systems with digital signal processing, field programmable gate arrays and embedded isotopic analysis software (viz. gamma detector response and analysis software [GADRAS]1), fast template matching, and data fusion (merging radiological data with geo-referenced maps, digital imagery to provide better situational awareness). In this stride to progress, a significant amount of interdisciplinary research and development has taken place–techniques and spin-offs from medical science (such as x-ray radiography and tomography), materials engineering (systematic planned studies on scintillators to optimize several qualities of a good scintillator, nanoparticle applications, quantum dots, and photonic crystals, just to name a few). No trend analysis of radiation detection systems would be complete without mentioning the unprecedented strategic position taken by the National Nuclear Security Administration (NNSA) to deter, detect, and interdict illicit trafficking in nuclear and other radioactive materials across international borders and through the global maritime transportation–the so-called second line of defense.

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

2011-09-01T23:59:59.000Z

256

Resources Process Contaminants  

Science Conference Proceedings (OSTI)

General Information on process contaminants(3-MCPD). Reference list included. Resources Process Contaminants 3-MCPD 2-diol 3-MCPD 3-MCPD Esters 3-monochloropropane-1 acid analysis aocs april articles certified chemists chloropropanediol contaminants dete

257

Process Contaminants (3-MCPD)  

Science Conference Proceedings (OSTI)

General information on process contaminants(3-MCPD). Reference list included. Process Contaminants (3-MCPD) 3-MCPD 2-diol 3-MCPD 3-MCPD Esters 3-monochloropropane-1 acid analysis aocs april articles certified chemists chloropropanediol contaminants deter

258

Decontamination and decommissioning of the Argonne National Laboratory East Area radioactively contaminated surplus facilities: Final report  

Science Conference Proceedings (OSTI)

ANL has decontaminated and decommissioned (D and D) seven radiologically contaminated surplus facilities at its Illinois site: a ''Hot'' Machine Shop (Building 17) and support facilities; Fan House No. 1 (Building 37), Fan House No. 2 (Building 38), the Pangborn Dust Collector (Building 41), and the Industrial Waste Treatment Plant (Building 34) for exhaust air from machining of radioactive materials. Also included were a Nuclear Materials Storage Vault (Building 16F) and a Nuclear Research Laboratory (Building 22). The D and D work involved dismantling of all process equipment and associated plumbing, ductwork, drain lines, etc. After radiation surveys, floor and wall coverings, suspended ceilings, room partitions, pipe, conduit and electrical gear were taken down as necessary. In addition, underground sewers were excavated. The grounds around each facility were also thoroughly surveyed. Contaminated materials and soil were packaged and shipped to a low-level waste burial site, while nonactive debris was buried in the ANL landfill. Clean, reusable items were saved, and clean metal scrap was sold for salvage. After the decommissioning work, each building was torn down and the site relandscaped. The project was completed in 1985, ahead of schedule, with substantial savings.

Kline, W.H.; Fassnacht, G.F.; Moe, H.J.

1987-07-01T23:59:59.000Z

259

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

260

WIPP radiological assistance team dispatched to Los Alamos as precautionary measure  

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

Radiological Assistance Team Dispatched Radiological Assistance Team Dispatched To Los Alamos as Precautionary Measure CARLSBAD, N.M., May 11, 2000 - A team of radiological experts has been dispatched from the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) in response to a week-long forest fire that is threatening Los Alamos National Laboratory (LANL), one of the nation's premiere research laboratories. "We are responding completely as a precautionary measure," said Jere Galle, team leader for the WIPP Radiological Assistance Program (RAP) team. "It is our understanding that nuclear materials at LANL are not in harm's way. Our primary concern, however, is always to protect human health and the environment." The RAP team's mission is to provide radiological assistance to federal agencies, state,

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261

U.S. Department of Energy Region 6 Radiological Assistance Program response plan. Revision 2  

Science Conference Proceedings (OSTI)

Upon request, the DOE, through the Radiological Assistance Program (RAP), makes available and will provide radiological advice, monitoring, and assessment activities during radiological incidents where the release of radioactive materials is suspected or has occurred. Assistance will end when the need for such assistance is over, or if there are other resources available to adequately address the incident. The implementation of the RAP is usually accomplished through the recommendation of the DOE Regional Coordinating Office`s (RCO) on duty Regional Response Coordinator (RRC) with the approval of the Regional Coordinating Office Director (RCOD). The DOE Idaho Operations Office (DOE-ID) is the designated RCO for DOE Region 6 RAP. The purpose of this document is: to describe the mechanism for responding to any organization or private citizen requesting assistance to radiological incidents; to coordinate radiological assistance among participating federal agencies, states, and tribes in DOE Region 6; and to describe the RAP Scaled Response concept of operations.

Jakubowski, F.M.

1998-02-01T23:59:59.000Z

262

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...

263

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

264

ORISE: Dose Coefficients for Intakes of Radionuclides via Contaminated  

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

Dose Coefficients for Intakes of Radionuclides via Contaminated Wounds Dose Coefficients for Intakes of Radionuclides via Contaminated Wounds Dose coefficients for 38 radionuclides based on NCRP Wound Model and ICRP biokinetic models This report is intended to assist health physics and medical staff in more rapidly assessing the potential dosimetric consequences of a contaminated wound. The National Council on Radiation Protection and Measurements Wound Model describing the retention of selected radionuclides at the site of a contaminated wound and their uptake into the transfer compartment has been combined with the International Commission on Radiological Protection element-specific systemic models for those radionuclides to derive dose coefficients for intakes via contaminated wounds. Examples are also provided on using the dose coefficients to generate derived reference

265

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

266

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

267

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

268

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

269

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

270

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

271

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

272

The enclosed file contains aerial radiological data that was collected with a fi  

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

enclosed file contains aerial radiological data that was collected with a fixed-wing aircraft (C-12) off enclosed file contains aerial radiological data that was collected with a fixed-wing aircraft (C-12) off of the east coast of Japan on three separate flights dated April 5, 2011, April 18, 2011, and May 9, 2011. Please note that the normal analysis of aerial radiological data assumes that the material is deposited on the ground and is not constantly moving. Therefore, this data set differs from previously posted aerial data in that the data must be viewed as three separate "snapshots" of the radiological signature from the ocean on these three dates, and NOT as one contiguous data set or flow pattern of the same deposition taken on different dates. Further, the vertical profile of the material is more ambiguous for over-sea data than for terrestrial data.

273

2011 Vittorio de Nora Award Winner: Recycling of Contaminated ...  

Science Conference Proceedings (OSTI)

Removal of contaminants such as the coat and organic materials- applied for protection and appearance- are the tail that wags the recycling dog. Successful ...

274

Effect of System Contaminants on PEMFC Performance and Durability...  

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

liquid-based contaminants derived from structural plastics and assembly aid materials (lubricant, grease, adhesive, seal). A minor part of our efforts is focused on an in situ...

275

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

276

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

277

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

278

UNDERWATER COATINGS FOR CONTAMINATION CONTROL  

SciTech Connect

The Idaho National Laboratory (INL) deactivated several aging nuclear fuel storage basins. Planners for this effort were greatly concerned that radioactive contamination present on the basin walls could become airborne as the sides of the basins became exposed during deactivation and allowed to dry after water removal. One way to control this airborne contamination was to fix the contamination in place while the pool walls were still submerged. There are many underwater coatings available on the market for marine, naval and other applications. A series of tests were run to determine whether the candidate underwater fixatives were easily applied and adhered well to the substrates (pool wall materials) found in INL fuel pools. Lab-scale experiments were conducted by applying fourteen different commercial underwater coatings to four substrate materials representative of the storage basin construction materials, and evaluating their performance. The coupons included bare concrete, epoxy painted concrete, epoxy painted carbon steel, and stainless steel. The evaluation criteria included ease of application, adherence to the four surfaces of interest, no change on water clarity or chemistry, non-hazardous in final applied form and be proven in underwater applications. A proprietary two-part, underwater epoxy owned by S. G. Pinney and Associates was selected from the underwater coatings tested for application to all four pools. Divers scrubbed loose contamination off the basin walls and floors using a ship hull scrubber and vacuumed up the sludge. The divers then applied the coating using a special powered roller with two separate heated hoses that allowed the epoxy to mix at the roller surface was used to eliminate pot time concerns. The walls were successfully coated and water was removed from the pools with no detectable airborne contamination releases.

Julia L. Tripp; Kip Archibald; Ann Marie Phillips; Joseph Campbell

2004-02-01T23:59:59.000Z

279

RadSTraM: Radiological Source Tracking and Monitoring, Phase II Final Report  

SciTech Connect

This report focuses on the technical information gained from the Radiological Source Tracking and Monitoring (RadSTraM) Phase II investigation and its implications. The intent of the RadSTraM project was to determine the feasibility of tracking radioactive materials in commerce, particularly International Atomic Energy Agency (IAEA) Category 3 and 4 materials. Specifically, Phase II of the project addressed tracking radiological medical isotopes in commerce. These categories of materials are susceptible to loss or theft but the problem is not being addressed by other agencies.

Warren, Tracy A [ORNL; Walker, Randy M [ORNL; Hill, David E [ORNL; Gross, Ian G [ORNL; Smith, Cyrus M [ORNL; Abercrombie, Robert K [ORNL

2008-12-01T23:59:59.000Z

280

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...

Note: This page contains sample records for the topic "radiologically contaminated material" 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 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

282

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...

283

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...

284

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

285

The long-term problems of contaminated land: Sources, impacts and countermeasures  

SciTech Connect

This report examines the various sources of radiological land contamination; its extent; its impacts on man, agriculture, and the environment; countermeasures for mitigating exposures; radiological standards; alternatives for achieving land decontamination and cleanup; and possible alternatives for utilizing the land. The major potential sources of extensive long-term land contamination with radionuclides, in order of decreasing extent, are nuclear war, detonation of a single nuclear weapon (e.g., a terrorist act), serious reactor accidents, and nonfission nuclear weapons accidents that disperse the nuclear fuels (termed ''broken arrows'').

Baes, C.F. III

1986-11-01T23:59:59.000Z

286

Materials Susceptibility in Contaminated Alternative Fuel  

Science Conference Proceedings (OSTI)

... Jet Fuel certification ... 50% of fuel should be alterative fuel blends by 2025 • Many alternative fuels have already been certified ...

2013-08-28T23:59:59.000Z

287

Disposal of NORM-Contaminated Oil Field Wastes in Salt Caverns  

Science Conference Proceedings (OSTI)

In 1995, the U.S. Department of Energy (DOE), Office of Fossil Energy, asked Argonne National Laboratory (Argonne) to conduct a preliminary technical and legal evaluation of disposing of nonhazardous oil field waste (NOW) into salt caverns. That study concluded that disposal of NOW into salt caverns is feasible and legal. If caverns are sited and designed well, operated carefully, closed properly, and monitored routinely, they can be a suitable means of disposing of NOW (Veil et al. 1996). Considering these findings and the increased U.S. interest in using salt caverns for NOW disposal, the Office of Fossil Energy asked Argonne to conduct further research on the cost of cavern disposal compared with the cost of more traditional NOW disposal methods and on preliminary identification and investigation of the risks associated with such disposal. The cost study (Veil 1997) found that disposal costs at the four permitted disposal caverns in the United States were comparable to or lower than the costs of other disposal facilities in the same geographic area. The risk study (Tomasko et al. 1997) estimated that both cancer and noncancer human health risks from drinking water that had been contaminated by releases of cavern contents were significantly lower than the accepted risk thresholds. Since 1992, DOE has funded Argonne to conduct a series of studies evaluating issues related to management and disposal of oil field wastes contaminated with naturally occurring radioactive material (NORM). Included among these studies were radiological dose assessments of several different NORM disposal options (Smith et al. 1996). In 1997, DOE asked Argonne to conduct additional analyses on waste disposal in salt caverns, except that this time the wastes to be evaluated would be those types of oil field wastes that are contaminated by NORM. This report describes these analyses. Throughout the remainder of this report, the term ''NORM waste'' is used to mean ''oil field waste contaminated by NORM''.

Blunt, D.L.; Elcock, D.; Smith, K.P.; Tomasko, D.; Viel, J.A.; and Williams, G.P.

1999-01-21T23:59:59.000Z

288

Resources for Process Contaminants  

Science Conference Proceedings (OSTI)

Detailed information regarding 3-MCPD esters and a reference list by topic. Resources for Process Contaminants 3-MCPD 2-diol 3-MCPD 3-MCPD Esters 3-monochloropropane-1 acid analysis aocs april articles certified chemists chloropropanediol contaminants de

289

Estimation of Radionuclide Content in Contaminated Laundry  

SciTech Connect

Radioactively contaminated laundry is normally sent off site for processing. Laundry is defined as radiologically contaminated anti-cs and respirators. This laundry is shipped as "limited quantity," in accordance with 49CFR173.421. This requires that 95% of the radionuclides shipped are characterized and quantified. In addition, the total quantity must be 10(-3) below the A2 limits specified in 49CFR173. In any facility evaluated, the most conservative (highest activity) waste stream was used as the source term. If a new waste stream is established for a facility, its normalized activity should be compared to the evaluated waste stream to ensure the limits are not exceeded. This article documents a method used for estimating the radionuclide content in contaminated laundry. The maximum values were compared to 49CFR173. Itwas determined that if the contaminated laundry/respirators are shipped in an Interstate Nuclear Services (INS), L-59, limited quantity shipping container and the highest contact radiation level on any side, as measured with an ion chamber, does not exceed 0.5 mR h(-1), the container complies with the requirements of 49CFR173 and could be shipped "limited quantity" from any of the facilities evaluated.

Schrader, Bradley J

2001-08-01T23:59:59.000Z

290

Feed gas contaminant removal in ion transport membrane systems  

DOE Patents (OSTI)

An oxygen ion transport membrane process wherein a heated oxygen-containing gas having one or more contaminants is contacted with a reactive solid material to remove the one or more contaminants. The reactive solid material is provided as a deposit on a support. The one or more contaminant compounds in the heated oxygen-containing gas react with the reactive solid material. The contaminant-depleted oxygen-containing gas is contacted with a membrane, and oxygen is transported through the membrane to provide transported oxygen.

Underwood, Richard Paul (Allentown, PA); Makitka, III, Alexander (Hatfield, PA); Carolan, Michael Francis (Allentown, PA)

2012-04-03T23:59:59.000Z

291

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

292

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

293

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

294

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

295

Technical Basis for Radiological Emergency Plan Annex for WTD Emergency Response Plan: West Point Treatment Plant  

Science Conference Proceedings (OSTI)

Staff of the King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into the combined sanitary and storm sewer system in King County, Washington. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include "dirty bombs" that are not nuclear detonations but are explosives designed to spread radioactive material (National Council on Radiation Protection and Measurements (NCRP) 2001). Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. This document, Volume 3 of PNNL-15163 is the technical basis for the Annex to the West Point Treatment Plant (WPTP) Emergency Response Plan related to responding to a radiological emergency at the WPTP. The plan primarily considers response to radioactive material that has been introduced in the other combined sanitary and storm sewer system from a radiological dispersion device, but is applicable to any accidental or deliberate introduction of materials into the system.

Hickey, Eva E.; Strom, Daniel J.

2005-08-01T23:59:59.000Z

296

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

297

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...

298

Method for removing contaminants from plastic resin  

Science Conference Proceedings (OSTI)

A resin recycling method that produces essentially contaminant-free synthetic resin material in an environmentally safe and economical manner. The method includes receiving the resin in container form. The containers are then ground into resin particles. The particles are exposed to a solvent, the solvent contacting the resin particles and substantially removing contaminants on the resin particles. After separating the particles and the resin, a solvent removing agent is used to remove any residual solvent remaining on the resin particles after separation.

Bohnert, George W. (Harrisonville, MO); Hand, Thomas E. (Lee's Summit, MO); DeLaurentiis, Gary M. (Jamestown, CA)

2008-12-09T23:59:59.000Z

299

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

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

Air Sampling Program/Methods Air Sampling Program/Methods Study Guide 2.06-1 Course Title: Radiological Control Technician Module Title: Air Sampling Program/Methods Module Number: 2.06 Objectives: 2.06.01 State the primary objectives of an air monitoring program. 2.06.02 Describe the three physical states of airborne radioactive contaminants. 2.06.03 List and describe the primary considerations to ensure a representative air sample is obtained. 2.06.04 Define the term "isokinetic sampling" as associated with airborne radioactivity sampling. 2.06.05 Identify the six general methods for obtaining samples or measurements of airborne radioactivity concentrations and describe the principle of operation for each method. a. Filtration b. Volumetric c. Impaction/impingement d. Adsorption e.

300

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

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

Air Sampling Program/Methods Air Sampling Program/Methods Instructor's Guide 2.06-1 Course Title: Radiological Control Technician Module Title: Air Sampling Program/Methods Module Number: 2.06 Objectives: 2.06.01 State the primary objectives of an air monitoring program. 2.06.02 Describe the three physical states of airborne radioactive contaminants. 2.06.03 List and describe the primary considerations to ensure a representative air sample is obtained. 2.06.04 Define the term "isokinetic sampling" as associated with airborne radioactivity sampling. 2.06.05 Identify the six general methods for obtaining samples or measurements of airborne radioactivity concentrations and describe the principle of operation for each method. a. Filtration b. Volumetric c. Impaction/impingement d. Adsorption e. Condensation/dehumidification

Note: This page contains sample records for the topic "radiologically contaminated material" 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

Passive neutron techniques for the nondestructive assay of nuclear material  

E-Print Network (OSTI)

Three drums containing potentially contaminated lead bricks were assayed with the Segmented Gamma Scan Neutron Assay System (SGSNAS) at Pacific Northwest National Laboratory's (PNNL) Nondestructive Assay Center. The assay system reported that the drums contained transuranic material. These results were based solely on the number of time-correlated neutron events. The gamma spectra for all three drums were inspected and no gamma ray lines corresponding to transuranic nuclides were found. Further investigations found that the lead in one of the drums had not been part of a contaminated area cleanup and should not be radiologically contaminated. This thesis examines the nuclear reactions that produce neutrons, the principles of neutron detectors including the circuitry required for coincidence counting, and how neutrons interact with matter. The premise is that time-correlated neutrons are produced from high-energy muon interactions with the lead nucleus, a spallation reaction. Muons are a component of the "air shower cascade" as cosmic rays traverse through the earth's atmosphere; therefore, an extensive study of cosmic rays has been undertaken. Verification that time-correlated neutrons are emitted from lead was performed using three completely separate systems.

Mapili, Gabriel

2000-01-01T23:59:59.000Z

302

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

303

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

304

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

305

Stack Characterization System for Inspection of Contaminated Off-Gas Stacks  

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

Stack Characterization System for Inspection of Contaminated Stack Characterization System for Inspection of Contaminated Off-Gas Stacks Stack Characterization System for Inspection of Contaminated Off-Gas Stacks The stack characterization system (SCS) is a tele-operated remote system that collects samples and data to characterize the quantitative and qualitative levels of contamination inside off-gas stacks protecting workers from the physical, radiological and chemical hazards of deteriorating contaminated stacks. Stack Characterization System for Inspection of Contaminated Off-Gas Stacks More Documents & Publications Uranium Downblending and Disposition Project Technology Readiness Assessment Independent Oversight Activity Report, Hanford Waste Treatment and Immobilization Plant - November 2013 EA-1488: Environmental Assessment for the U-233 Disposition, Medical

306

Stack Characterization System for Inspection of Contaminated Off-Gas Stacks  

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

Stack Characterization System for Inspection of Contaminated Stack Characterization System for Inspection of Contaminated Off-Gas Stacks Stack Characterization System for Inspection of Contaminated Off-Gas Stacks The stack characterization system (SCS) is a tele-operated remote system that collects samples and data to characterize the quantitative and qualitative levels of contamination inside off-gas stacks protecting workers from the physical, radiological and chemical hazards of deteriorating contaminated stacks. Stack Characterization System for Inspection of Contaminated Off-Gas Stacks More Documents & Publications Uranium Downblending and Disposition Project Technology Readiness Assessment EA-1488: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge

307

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

308

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

National Nuclear Security Administration (NNSA)

Removal | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our...

309

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

National Nuclear Security Administration (NNSA)

members - Canada, the Czech Republic, Finland, New Zealand, Norway, the Republic of Korea and the United Kingdom - to pursue nonproliferation efforts around the world,...

310

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

311

Underwater Coatings for Contamination Control  

Science Conference Proceedings (OSTI)

The Idaho National Engineering and Environmental Laboratory (INEEL) is deactivating several fuel storage basins. Airborne contamination is a concern when the sides of the basins are exposed and allowed to dry during water removal. One way of controlling this airborne contamination is to fix the contamination in place while the pool walls are still submerged. There are many underwater coatings available on the market that are used in marine, naval and other applications. A series of tests were run to determine whether the candidate underwater fixatives are easily applied and adhere well to the substrates (pool wall materials) found in INEEL fuel pools. The four pools considered included 1) Test Area North (TAN-607) with epoxy painted concrete walls; 2) Idaho Nuclear Technology and Engineering Center (INTEC) (CPP-603) with bare concrete walls; 3) Materials Test Reactor (MTR) Canal with stainless steel lined concrete walls; and 4) Power Burst Facility (PBF-620) with stainless steel lined concrete walls on the bottom and epoxy painted carbon steel lined walls on the upper portions. Therefore, the four materials chosen for testing included bare concrete, epoxy painted concrete, epoxy painted carbon steel, and stainless steel. The typical water temperature of the pools varies from 55oF to 80oF dependent on the pool and the season. These tests were done at room temperature. The following criteria were used during this evaluation. The underwater coating must: · Be easy to apply · Adhere well to the four surfaces of interest · Not change or have a negative impact on water chemistry or clarity · Not be hazardous in final applied form · Be proven in other underwater applications. In addition, it is desirable for the coating to have a high pigment or high cross-link density to prevent radiation from penetrating. This paper will detail the testing completed and the test results. A proprietary two-part, underwater epoxy owned by S. G. Pinney and Associates was selected to be applied by divers after scrubbing loose contamination off the basin walls and floors using a ship hull scrubber and vacuuming up the sludge. A special powered roller with two separate heated hoses that allowed the epoxy to mix at the roller surface was used to eliminate pot time concerns. The walls were successfully coated and water was removed from the pool with no airborne contamination problems.

Julia L. Tripp; Kip Archibald; Ann-Marie Phillips; Joseph Campbell

2004-02-01T23:59:59.000Z

312

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...

313

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...

314

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

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

Internal Exposure Control Internal Exposure Control Instructor's Guide 1.12-1 Course Title: Radiological Control Technician Module Title: Internal Exposure Control Module Number: 1.12 Objectives: 1.12.01 Identify four ways in which radioactive materials can enter the body. 1.12.02 Given a pathway for radioactive materials into the body, identify one method to prevent or minimize entry by that pathway. 1.12.03 Identify the definition and distinguish between the terms "Annual Limit on Intake" (ALI) and "Derived Air Concentration" (DAC). 1.12.04 Identify the basis for determining Annual Limit on Intake (ALI). 1.12.05 Identify the definition of "reference man". 1.12.06 Identify a method of using DACs to minimize internal exposure potential. 1.12.07 Identify three factors that govern the behavior of radioactive materials in the

315

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

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

Internal Exposure Control Internal Exposure Control Study Guide 1.12-1 Course Title: Radiological Control Technician Module Title: Internal Exposure Control Module Number: 1.12 Objectives: 1.12.01 Identify four ways in which radioactive materials can enter the body. 1.12.02 Given a pathway for radioactive materials into the body, identify one method to prevent or minimize entry by that pathway. 1.12.03 Identify the definition and distinguish between the terms "Annual Limit on Intake" (ALI) and "Derived Air Concentration" (DAC). 1.12.04 Identify the basis for determining Annual Limit on Intake (ALI). 1.12.05 Identify the definition of "reference man". 1.12.06 Identify a method of using DACs to minimize internal exposure potential. 1.12.07 Identify three factors that govern the behavior of radioactive materials in the

316

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

317

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

318

Tritium Surface Contamination  

SciTech Connect

Glovebox wipe surveys were conducted to correlate surface tritium contamination with atmospheric tritium levels. Surface contamination was examined as a function of tritium concentration and of tritium form, HT/T2 and HTO. The relationship between atmospheric HTO concentration and cleanup time was also investigated.

Sienkiewicz, Charles J.

1985-04-01T23:59:59.000Z

319

Contamination Control Techniques  

SciTech Connect

Welcome to a workshop on contamination Control techniques. This work shop is designed for about two hours. Attendee participation is encouraged during the workshop. We will address different topics within contamination control techniques; present processes, products and equipment used here at Hanford and then open the floor to you, the attendees for your input on the topics.

EBY, J.L.

2000-05-16T23:59:59.000Z

320

Technical basis for radiological release of Grand Junction Office Building 2. Volume 1, dose assessment  

SciTech Connect

Building 2 on the US Department of Energy (DOE) Grand Junction Office (GJO) site is part of the GJO Remedial Action Program (GJORAP). During evaluation of Building 2 for determination of radiological release disposition, some inaccessible surface contamination measurements were detected to be greater than the generic surface contamination guidelines of DOE Order 5400.5 (which are functionally equivalent to US Nuclear Regulatory Commission [NRC] Regulatory Guide 1.86). Although the building is nominal in size, it houses the site telecommunications system, that is critical to continued GJO operations, and demolition is estimated at $1.9 million. Because unrestricted release under generic surface contamination guidelines is cost-prohibitive, supplemental standards consistent with DOE Order 5400.5 are being pursued. This report describes measurements and dose analysis modeling efforts to evaluate the radiation dose to members of the public who might occupy or demolish Building 2, a 2,480 square-foot (ft) building constructed in 1944. The north portion of the building was used as a shower facility for Manhattan Project uranium-processing mill workers and the south portion was a warehouse. Many originally exposed surfaces are no longer accessible for contamination surveys because expensive telecommunications equipment have been installed on the floors and mounted on panels covering the walls. These inaccessible surfaces are contaminated above generic contamination limits.

Morris, R.; Warga, J.; Thorne, D.

1997-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "radiologically contaminated material" 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

Bioremediation of contaminated groundwater  

DOE Patents (OSTI)

Disclosed is an apparatus and method for in situ remediation of contaminated subsurface soil or groundwater contaminated by chlorinated hydrocarbons. A nutrient fluid (NF) is selected to simulated the growth and reproduction of indigenous subsurface microorganisms capable of degrading the contaminants; an oxygenated fluid (OF) is selected to create an aerobic environment with anaerobic pockets. NF is injected periodically while OF is injected continuously and both are extracted so that both are drawn across the plume. NF stimulates microbial colony growth; withholding it periodically forces the larger, healthy colony of microbes to degrade the contaminants. Treatment is continued until the subsurface concentration of contaminants is acceptable. NF can be methane and OF be air, for stimulating production of methanotrophs to break down chlorohydrocarbons, especially TCE and tetrachloroethylene.

Hazen, T.C.; Fliermans, C.B.

1994-01-01T23:59:59.000Z

322

Radiological health implications of lead-210 and polonium-210 accumulations in LPG refineries  

SciTech Connect

Radon-222, a naturally occurring radioactive noble gas, is often a contaminant in natural gas. During fractionation at processing plants, Radon tends to be concentrated in the Liquified Petroleum Gas (LPG) product stream. Radon-222 decays into a number of radioactive metallic daughters which can plate out on the interior surfaces of plant machinery. The hazards associated with gamma-emitting short-lived radon daughters have been investigated previously. The present work reports an analysis of the hazards associated with the long-lived daughters; Pb-210, Bi-210, and Po-210. These nuclides do not emit appreciable penetrating radiation, and hence do not represent a hazard as long as they remain on the inside surfaces of equipment. However, when equipment that has had prolonged exposure to an LPG stream is disassembled for repair or routine maintenance, opportunities for exposure to radioactive materials can occur. A series of measurements made on an impeller taken from a pump in an LPG facility is reported. Alpha spectroscopy revealed the presence of Po-210, and further measurements showed that the amount on the impeller surface was well above the exempt quantity. Breathing zone measurements made in the course of cleaning the impeller showed that an inhalation exposure equivalent to breathing Po-210 at the Maximum Permissible Concentration (MPC) for 60 hours could be delivered in less than half an hour. It was concluded that maintenance and repair work on LPG and derivitive product stream equipment must be carried out with the realization that a potential radiological health problem exists.

Summerlin, J. Jr.; Prichard, H.M.

1985-04-01T23:59:59.000Z

323

Desiccant contamination research: Report on the desiccant contamination test facility  

DOE Green Energy (OSTI)

The activity in the cooling systems research involves research on high performance dehumidifiers and chillers that can operate efficiently with the variable thermal outputs and delivery temperatures associated with solar collectors. It also includes work on advanced passive cooling techniques. This report describes the work conducted to improve the durability of solid desiccant dehumidifiers by investigating the causes of degradation of desiccant materials from airborne contaminants and thermal cycling. The performance of a dehumidifier strongly depends on the physical properties and durability of the desiccant material. To make durable and reliable dehumidifiers, an understanding is needed of how and to what degree the performance of a dehumidifier is affected by desiccant degradation. This report, an account of work under Cooling Systems Research, documents the efforts to design and fabricate a test facility to investigate desiccant contamination based on industry and academia recommendations. It also discusses the experimental techniques needed for obtaining high-quality data and presents plans for next year. Researchers of the Mechanical and Industrial Technology Division performed this work at the Solar Energy Research Institute in FY 1988 for DOE's Office of Solar Heat Technologies. 7 refs., 19 figs., 1 tab.

Pesaran, A.A.; Bingham, C.E.

1991-07-01T23:59:59.000Z

324

Desiccant contamination research: Report on the desiccant contamination test facility  

SciTech Connect

The activity in the cooling systems research involves research on high performance dehumidifiers and chillers that can operate efficiently with the variable thermal outputs and delivery temperatures associated with solar collectors. It also includes work on advanced passive cooling techniques. This report describes the work conducted to improve the durability of solid desiccant dehumidifiers by investigating the causes of degradation of desiccant materials from airborne contaminants and thermal cycling. The performance of a dehumidifier strongly depends on the physical properties and durability of the desiccant material. To make durable and reliable dehumidifiers, an understanding is needed of how and to what degree the performance of a dehumidifier is affected by desiccant degradation. This report, an account of work under Cooling Systems Research, documents the efforts to design and fabricate a test facility to investigate desiccant contamination based on industry and academia recommendations. It also discusses the experimental techniques needed for obtaining high-quality data and presents plans for next year. Researchers of the Mechanical and Industrial Technology Division performed this work at the Solar Energy Research Institute in FY 1988 for DOE's Office of Solar Heat Technologies. 7 refs., 19 figs., 1 tab.

Pesaran, A.A.; Bingham, C.E.

1991-07-01T23:59:59.000Z

325

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

326

A transportable fluorescence imagining system for detecting fecal contaminants  

Science Conference Proceedings (OSTI)

Feces are the primary source of many pathogenic organisms that can potentially contaminate agricultural commodities. Feces generally contain chlorophyll a and related compounds due to ingestion of plant materials. Fluorescent responses of these compounds ... Keywords: Fecal contamination, Fluorescence, Food safety, Multispectral imaging

Alan M. Lefcourt; Moon S. Kim; Yud-Ren Chen

2005-07-01T23:59:59.000Z

327

Complexity of Groundwater Contaminants at DOE Sites  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) is responsible for the remediation and long-term stewardship of one of the world's largest groundwater contamination portfolios, with a significant number of plumes containing various contaminants, and considerable total mass and activity. As of 1999, the DOE's Office of Environmental Management was responsible for remediation, waste management, or nuclear materials and facility stabilization at 144 sites in 31 states and one U.S. territory, out of which 109 sites were expected to require long-term stewardship. Currently, 19 DOE sites are on the National Priority List. The total number of contaminated plumes on DOE lands is estimated to be 10,000. However, a significant number of DOE sites have not yet been fully characterized. The most prevalent contaminated media are groundwater and soil, although contaminated sediment, sludge, and surface water also are present. Groundwater, soil, and sediment contamination are present at 72% of all DOE sites. A proper characterization of the contaminant inventory at DOE sites is critical for accomplishing one of the primary DOE missions -- planning basic research to understand the complex physical, chemical, and biological properties of contaminated sites. Note that the definitions of the terms 'site' and 'facility' may differ from one publication to another. In this report, the terms 'site,' 'facility' or 'installation' are used to identify a contiguous land area within the borders of a property, which may contain more than one plume. The term 'plume' is used here to indicate an individual area of contamination, which can be small or large. Even though several publications and databases contain information on groundwater contamination and remediation technologies, no statistical analyses of the contaminant inventory at DOE sites has been prepared since the 1992 report by Riley and Zachara. The DOE Groundwater Data Base (GWD) presents data as of 2003 for 221 groundwater plumes at 60 DOE sites and facilities. Note that Riley and Zachara analyzed the data from only 18 sites/facilities including 91 plumes. In this paper, we present the results of statistical analyses of the data in the GWD as guidance for planning future basic and applied research of groundwater contaminants within the DOE complex. Our analyses include the evaluation of a frequency and ranking of specific contaminants and contaminant groups, contaminant concentrations/activities and total contaminant masses and activities. We also compared the results from analyses of the GWD with those from the 1992 report by Riley and Zachara. The difference between our results and those summarized in the 1992 report by Riley and Zachara could be caused by not only additional releases, but also by the use of modern site characterization methods, which more accurately reveal the extent of groundwater contamination. Contaminated sites within the DOE complex are located in all major geographic regions of the United States, with highly variable geologic, hydrogeologic, soil, and climatic conditions. We assume that the information from the 60 DOE sites included in the GWD are representative for the whole DOE complex. These 60 sites include the major DOE sites and facilities, such as Rocky Flats Environmental Technology Site, Colorado; Idaho National Laboratory, Idaho; Savannah River Site, South Carolina; Oak Ridge Reservation, Tennessee; and Hanford Reservation, Washington. These five sites alone ccount for 71% of the value of the remediation work.

Hazen, T.C.; Faybishenko, B.; Jordan, P.

2010-12-03T23:59:59.000Z

328

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

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

Radioactive Source Control Radioactive Source Control Study Guide 2.08-1 Course Title: Radiological Control Technician Module Title: Radioactive Source Control Module Number: 2.08 Objectives: 2.08.01 Describe the requirements for radioactive sources per 10 CFR 835. i 2.08.02 Identify the characteristics of radioactive sources that must be controlled at your site. i 2.08.03 Identify the packaging, marking, and labeling requirements for radioactive sources. i 2.08.04 Describe the approval and posting requirements for radioactive materials areas. i 2.08.05 Describe the process and procedures used at your site for storage and accountability of radioactive sources. INTRODUCTION A radioactive source is material used for its emitted radiation. Sources are constructed as sealed or unsealed and are classified as accountable or exempt.

329

Bioremediation of contaminated groundwater  

DOE Patents (OSTI)

The present invention relates to a method for in situ bioremediation of contaminated soil and groundwater. In particular, the invention relates to remediation of contaminated soil and groundwater by the injection of nutrients to stimulate growth of pollutant-degrading microorganisms. The United States Government has rights in this invention pursuant to Contract No. DE-AC09-89SR18035 between the US Department of Energy and Westinghouse Savannah River Company.

Hazen, T.C.; Fliermans, C.B.

1992-12-31T23:59:59.000Z

330

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

331

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

332

Recovery Act-Funded Study Assesses Contamination at Former Test Site in  

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

Act-Funded Study Assesses Contamination at Former Test Act-Funded Study Assesses Contamination at Former Test Site in California Recovery Act-Funded Study Assesses Contamination at Former Test Site in California Workers in a study funded by $38 million from the American Recovery and Reinvestment Act to assess radiological contamination have collected more than 600 soil samples and surveyed 120 acres of land for gamma radiation. Under an interagency agreement with DOE, the Environmental Protection Agency (EPA) is conducting the study at Santa Susana Field Laboratory (SSFL) Area IV and the Northern Undeveloped Land. Recovery Act-Funded Study Assesses Contamination at Former Test Site in California More Documents & Publications EA-1345: Final Environmental Assessment EIS-0402: Notice of Intent to Prepare an Environmental Impact Statement

333

Analysis of surface contaminants on beryllium and aluminum windows  

Science Conference Proceedings (OSTI)

An effort has been made to document the types of contamination which form on beryllium window surfaces due to interaction with a synchrotron radiation beam. Beryllium windows contaminated in a variety of ways (exposure to water and air) exhibited surface powders, gels, crystals and liquid droplets. These contaminants were analyzed by electron diffraction, electron energy loss spectroscopy, energy dispersive x-ray spectroscopy and wet chemical methods. Materials found on window surfaces include beryllium oxide, amorphous carbon, cuprous oxide, metallic copper and nitric acid. Aluminum window surface contaminants were also examined.

Gmur, N.F.

1987-06-01T23:59:59.000Z

334

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

335

System for removing contaminants from plastic resin  

DOE Patents (OSTI)

A resin recycling system that produces essentially contaminant-free synthetic resin material in an environmentally safe and economical manner. The system includes receiving the resin in container form. A grinder grinds the containers into resin particles. The particles are exposed to a solvent in one or more solvent wash vessels, the solvent contacting the resin particles and substantially removing contaminants on the resin particles. A separator is used to separate the resin particles and the solvent. The resin particles are then placed in solvent removing element where they are exposed to a solvent removing agent which removes any residual solvent remaining on the resin particles after separation.

Bohnert, George W. (Harrisonville, MO); Hand, Thomas E. (Lee' s Summit, MO); DeLaurentiis, Gary M. (Jamestown, CA)

2010-11-23T23:59:59.000Z

336

Material Disposal Areas  

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

Material Disposal Areas Material Disposal Areas Material Disposal Areas Material Disposal Areas, also known as MDAs, are sites where material was disposed of below the ground surface in excavated pits, trenches, or shafts. Contact Environmental Communication & Public Involvement P.O. Box 1663 MS M996 Los Alamos, NM 87545 (505) 667-0216 Email Material Disposal Areas at LANL The following are descriptions and status updates of each MDA at LANL. To view a current fact sheet on the MDAs, click on LA-UR-13-25837 (pdf). MDA A MDA A is a Hazard Category 2 nuclear facility comprised of a 1.25-acre, fenced, and radiologically controlled area situated on the eastern end of Delta Prime Mesa. Delta Prime Mesa is bounded by Delta Prime Canyon to the north and Los Alamos Canyon to the south.

337

Ecotoxicity literature review of selected Hanford Site contaminants  

SciTech Connect

Available information on the toxicity, food chain transport, and bioconcentration of several Hanford Site contaminants were reviewed. The contaminants included cesium-137, cobalt-60, europium, nitrate, plutonium, strontium-90, technetium, tritium, uranium, and chromium (III and VI). Toxicity and mobility in both aquatic and terrestrial systems were considered. For aquatic systems, considerable information was available on the chemical and/or radiological toxicity of most of the contaminants in invertebrate animals and fish. Little information was available on aquatic macrophyte response to the contaminants. Terrestrial animals such as waterfowl and amphibians that have high exposure potential in aquatic systems were also largely unrepresented in the toxicity literature. The preponderance of toxicity data for terrestrial biota was for laboratory mammals. Bioconcentration factors and transfer coefficients were obtained for primary producers and consumers in representative aquatic and terrestrial systems; however, little data were available for upper trophic level transfer, particularly for terrestrial predators. Food chain transport and toxicity information for the contaminants were generally lacking for desert or sage brush-steppe organisms, particularly plants and reptiles

Driver, C.J.

1994-03-01T23:59:59.000Z

338

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

339

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

340

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

Note: This page contains sample records for the topic "radiologically contaminated material" 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

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...

342

Applications of RESRAD family of computer codes to sites contaminated with radioactive residues.  

Science Conference Proceedings (OSTI)

The RESIL4D family of computer codes was developed to provide a scientifically defensible answer to the question ''How clean is clean?'' and to provide useful tools for evaluating human health risk at sites contaminated with radioactive residues. The RESRAD codes include (1) RESRAD for soil contaminated with radionuclides; (2) RESRAD-BUILD for buildings contaminated with radionuclides; (3) RESRAD-CHEM for soil contaminated with hazardous chemicals; (4) RESRAD-BASELINE for baseline risk assessment with measured media concentrations of both radionuclides and chemicals; (5) RESRAD-ECORISK for ecological risk assessment; (6) RESRAD-RECYCLE for recycle and reuse of radiologically contaminated metals and equipment; and (7) RESRAD-OFFSITE for off-site receptor radiological dose assessment. Four of these seven codes (RESRAD, RESRAD-BUILD, RESRAD-RECYCLE, and RESRAD-OFFSITE) also have uncertainty analysis capabilities that allow the user to input distributions of parameters. RESRAD has been widely used in the United States and abroad and approved by many federal and state agencies. Experience has shown that the RESRAD codes are useful tools for evaluating sites contaminated with radioactive residues. The use of RESRAD codes has resulted in significant savings in cleanup cost. Analysis of 19 site-specific uranium guidelines is discussed in the paper.

Yu, C.; Kamboj, S.; Cheng, J.-J.; LePoire, D.; Gnanapragasam, E.; Zielen, A.; Williams, W. A.; Wallo, A.; Peterson, H.

1999-10-21T23:59:59.000Z

343

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

344

Portable spotter for fluorescent contaminants on surfaces  

DOE Patents (OSTI)

A portable fluorescence-based spotter for polynuclear aromatic hydrocarbon contamination on personnel and work area surfaces under ambient lighting conditions is provided. This instrument employs beam modulation and phase sensitive detection for discriminating between fluorescence from organic materials from reflected background light and inorganic fluorescent material. The device uses excitation and emission filters to provide differentiation between classes of aromatic organic compounds. Certain inorganic fluorescent materials, including heavy metal compounds, may also be distinguished from the organic compounds, despite both having similar optical properties.

Schuresko, Daniel D. (Oak Ridge, TN)

1980-01-01T23:59:59.000Z

345

Inspection Report - Radiological Waste Operations in Area G at Los Alamos National Laboratory, INS-O-13-03  

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

Inspection Report Inspection Report Radiological Waste Operations in Area G at Los Alamos National Laboratory INS-O-13-03 March 2013 Department of Energy Washington, DC 20585 March 20, 2013 MEMORANDUM FOR THE MANAGER, LOS ALAMOS FIELD OFFICE, NATIONAL NUCLEAR SECURITY ADMINISTRATION FROM: Sandra D. Bruce Assistant Inspector General for Inspections Office of Inspector General SUBJECT: INFORMATION: Inspection Report on "Radiological Waste Operations in Area G at Los Alamos National Laboratory" INTRODUCTION Los Alamos National Laboratory (Los Alamos) has a national security mission that includes science, engineering and technology related to radioactive and hazardous materials such as plutonium, americium, asbestos and lead. Material Disposal Area G, located in Technical Area

346

Areawide chemical contamination  

SciTech Connect

Nine case histories illustrate the mounting problems owing to chemical contamination that often extends beyond the workplace into the community. The effects include not only carcinogenesis and teratogenesis, so much in the public's mind, but also severe neurological and gonadal disabilities immediately after exposure. Recognition of causal relationships is often made by astute clinicians. The experience of the Atomic Bomb Casualty Commission in studying Japanese survivors in Hiroshima and Nagasaki serves as a model for future studies of communities exposed to unusual environmental contamination.

Miller, R.W.

1981-04-17T23:59:59.000Z

347

Situ treatment of contaminated groundwater  

DOE Green Energy (OSTI)

A system for treating dissolved halogenated organic compounds in groundwater that relies upon electrolytically-generated hydrogen to chemically reduce the halogenated compounds in the presence of a suitable catalyst. A direct current is placed across at least a pair, or an array, of electrodes which are housed within groundwater wells so that hydrogen is generated at the cathode and oxygen at the anode. A pump is located within the well housing in which the cathode(s) is(are) located and draws in groundwater where it is hydrogenated via electrolysis, passes through a well-bore treatment unit, and then transported to the anode well(s) for reinjection into the ground. The well-bore treatment involves a permeable cylinder located in the well bore and containing a packed bed of catalyst material that facilitates the reductive dehalogenation of the halogenated organic compounds by hydrogen into environmentally benign species such as ethane and methane. Also, electro-osmatic transport of contaminants toward the cathode also contributes to contaminant mass removal. The only above ground equipment required are the transfer pipes and a direct circuit power supply for the electrodes. The electrode wells in an array may be used in pairs or one anode well may be used with a plurality of cathode wells. The DC current flow between electrode wells may be periodically reversed which controls the formation of mineral deposits in the alkaline cathode well-bore water, as well as to help rejuvenate the catalysis.

McNab, Jr., Walt W. (Concord, CA); Ruiz, Roberto (Tracy, CA); Pico, Tristan M. (Livermore, CA)

2001-01-01T23:59:59.000Z

348

Solvent cleaning system and method for removing contaminants from solvent used in resin recycling  

DOE Patents (OSTI)

A two step solvent and carbon dioxide based system that produces essentially contaminant-free synthetic resin material and which further includes a solvent cleaning system for periodically removing the contaminants from the solvent so that the solvent can be reused and the contaminants can be collected and safely discarded in an environmentally safe manner.

Bohnert, George W. (Harrisonville, MO); Hand, Thomas E. (Lee' s Summit, MO); DeLaurentiis, Gary M. (Jamestown, CA)

2009-01-06T23:59:59.000Z

349

SIMON: A mobile robot for floor contamination surveys  

SciTech Connect

The Robotics Development group at the Savannah River Site is developing an autonomous robot to perform radiological surveys of potentially contaminated floors. The robot scans floors at a speed of one-inch/second and stops, sounds an alarm, and flashes lights when contamination in a certain area is detected. The contamination of interest here is primarily alpha and beta-gamma. The contamination levels are low to moderate. The robot, a Cybermotion K2A, is radio controlled, uses dead reckoning to determine vehicle position, and docks with a charging station to replenish its batteries and calibrate its position. It has an ultrasonic collision avoidance system as well as two safety bumpers that will stop the robot's motion when they are depressed. Paths for the robot are preprogrammed and the robot's motion can be monitored on a remote screen which shows a graphical map of the environment. The radiation instrument being used is an Eberline RM22A monitor. This monitor is microcomputer based with a serial I/O interface for remote operation. Up to 30 detectors may be configured with the RM22A. For our purposes, two downward-facing gas proportional detectors are used to scan floors, and one upward-facing detector is used for radiation background compensation. SIMON is interfaced with the RM22A in such a way that it scans the floor surface at one-inch/second, and if contamination is detected, the vehicle stops, alarms, and activates a voice synthesizer. Future development includes using the contamination data collected to provide a graphical contour map of a contaminated area. 3 refs.

Dudar, E.; Teese, G.; Wagner, D.

1991-01-01T23:59:59.000Z

350

SIMON: A mobile robot for floor contamination surveys  

SciTech Connect

The Robotics Development group at the Savannah River Site is developing an autonomous robot to perform radiological surveys of potentially contaminated floors. The robot scans floors at a speed of one-inch/second and stops, sounds an alarm, and flashes lights when contamination in a certain area is detected. The contamination of interest here is primarily alpha and beta-gamma. The contamination levels are low to moderate. The robot, a Cybermotion K2A, is radio controlled, uses dead reckoning to determine vehicle position, and docks with a charging station to replenish its batteries and calibrate its position. It has an ultrasonic collision avoidance system as well as two safety bumpers that will stop the robot`s motion when they are depressed. Paths for the robot are preprogrammed and the robot`s motion can be monitored on a remote screen which shows a graphical map of the environment. The radiation instrument being used is an Eberline RM22A monitor. This monitor is microcomputer based with a serial I/O interface for remote operation. Up to 30 detectors may be configured with the RM22A. For our purposes, two downward-facing gas proportional detectors are used to scan floors, and one upward-facing detector is used for radiation background compensation. SIMON is interfaced with the RM22A in such a way that it scans the floor surface at one-inch/second, and if contamination is detected, the vehicle stops, alarms, and activates a voice synthesizer. Future development includes using the contamination data collected to provide a graphical contour map of a contaminated area. 3 refs.

Dudar, E.; Teese, G.; Wagner, D.

1991-12-31T23:59:59.000Z

351

Advanced Assay Systems for Radionuclide Contamination in Soils  

SciTech Connect

Through the support of the Department of Energy (DOE) Office of Environmental Management (EM) Technical Assistance Program, the Idaho National Laboratory (INL) has developed and deployed a suite of systems that rapidly scan, characterize, and analyze surface soil contamination. The INL systems integrate detector systems with data acquisition and synthesis software and with global positioning technology to provide a real-time, user-friendly field deployable turn-key system. INL real-time systems are designed to characterize surface soil contamination using methodologies set forth in the Multi-Agency Radiation Surveys and Site Investigation Manual (MARSSIM). MARSSIM provides guidance for planning, implementing, and evaluating environmental and facility radiological surveys conducted to demonstrate compliance with a dose or risk-based regulation and provides real-time information that is immediately available to field technicians and project management personnel. This paper discusses the history of the development of these systems and describes some of the more recent examples and their applications.

J. R. Giles; L. G. Roybal; M. V. Carpenter; C. P. Oertel; J. A. Roach

2008-02-01T23:59:59.000Z

352

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

353

Hydrogen Contamination of Niobium Surfaces  

DOE Green Energy (OSTI)

The presence of hydrogen is blamed for dramatic reductions in cavity Q's. Hydrogen concentration is difficult to measure, so there is a great deal of Fear, Uncertainty, and Doubt (FUD) associated with the problem. This paper presents measurements of hydrogen concentration depth profiles, commenting on the pitfalls of the methods used and exploring how material handling can change the amount of hydrogen in pieces of niobium. Hydrogen analysis was performed by a forward scattering experiment with Helium used as the primary beam. This technique is variously known as FRES (Forward Recoil Elastic Scattering), FRS, HFS (Hydrogen Forward Scattering), and HRA (Hydrogen Recoil Analysis). Some measurements were also made using SIMS (Secondary Ion Mass Spectrometry). Both HFS and SIMS are capable of measuring a depth profile of Hydrogen. The primary difficulty in interpreting the results from these techniques is the presence of a surface peak which is due (at least in part) to contamination with either water or hydrocarbons. With HFS, the depth resolution is about 30 nm, and the maximum depth profiled is about 300 nm. (This 10-1 ratio is unusually low for ion beam techniques, and is a consequence of the compromises that must be made in the geometry of the experiment, surface roughness, and energy straggling in the absorber foil that must be used to filter out the forward scattered helium.) All the observed HFS spectra include a surface peak which includes both surface contamination and any real hydrogen uptake by the niobium surface. Some contamination occurs during the analysis. The vacuum in the analysis chamber is typically a few times 10{sup -6} torr, and some of the contamination is in the form of hydrocarbons from the pumping system. Hydrocarbons normally form a very thin (less than a monolayer) film which is in equilibrium between arrival rate and the evaporation rate. In the presence of the incoming ion beam, however, these hydrocarbons crack on the surface into non-volatile components. Equilibrium is lost, and the surface builds up a layer of carbon-based gunk.

Viet Nguyen-Tuong; Lawrence Doolittle

1993-10-01T23:59:59.000Z

354

Mercury contamination extraction  

DOE Patents (OSTI)

Mercury is removed from contaminated waste by firstly applying a sulfur reagent to the waste. Mercury in the waste is then permitted to migrate to the reagent and is stabilized in a mercury sulfide compound. The stable compound may then be removed from the waste which itself remains in situ following mercury removal therefrom.

Fuhrmann, Mark (Silver Spring, MD); Heiser, John (Bayport, NY); Kalb, Paul (Wading River, NY)

2009-09-15T23:59:59.000Z

355

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

356

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

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

8 Radioactive Source Control 8 Radioactive Source Control Instructor's Guide 2.08-1 Course Title: Radiological Control Technician Module Title: Radioactive Source Control Module Number: 2.08 Objectives: 2.08.01 Describe the requirements for radioactive sources per 10 CFR 835. L 2.08.02 Identify the characteristics of radioactive sources that must be controlled at your site. L 2.08.03 Identify the packaging, marking, and labeling requirements for radioactive sources. L 2.08.04 Describe the approval and posting requirements for radioactive materials areas. L 2.08.05 Describe the process and procedures used at your site for storage and accountability of radioactive sources. References: 1. 10 CFR 835, "Occupational Radiation Protection," (1998) Instructional Aids: 1. Overheads 2. Overhead projector and screen

357

HAZARDS OF THERMAL EXPANSION FOR RADIOLOGICAL CONTAINER ENGULFED IN FIRE  

SciTech Connect

Fire accidents pose a serious threat to nuclear facilities. It is imperative that transport casks or shielded containers designed to transport/contain radiological materials have the ability to withstand a hypothetical fire. A numerical simulation was performed for a shielded container constructed of stainless steel and lead engulfed in a hypothetical fire as outlined by 10 CFR §71.73. The purpose of this analysis was to determine the thermal response of the container during and after the fire. The thermal model shows that after 30 minutes of fire, the stainless steel will maintain its integrity and not melt. However, the lead shielding will melt since its temperature exceeds the melting point. Due to the method of construction of the container under consideration, ample void space must be provided to allow for thermal expansion of the lead upon heating and melting, so as to not overstress the weldment.

Donna Post Guillen

2013-05-01T23:59:59.000Z

358

An external dose reconstruction involving a radiological dispersal device  

E-Print Network (OSTI)

Recent events have underscored the need for the United States government to provide streamlined emergency response procedures and subsequent dose estimations for personnel responding to incidents involving radioactive material. Indeed, the National Council on Radiation Protection and Measurements Report No. 138 (NCRP 2001) indicates that exposures received by first responders will be important for a number of reasons, including planning for the appropriate use of key personnel in an extended emergency situation. In response, the Department of Homeland Security has published Protective Action Guides (DHS 2006) to help minimize these exposures and associated risks. This research attempts to provide some additional radiological exposure knowledge so that an Incident Commander, with limited or no information, can make more informed decisions about evacuation, sheltering-in-place, relocation of the public, turn-back levels, defining radiation hazard boundaries, and in-field radiological dose assessments of the radiation workers, responders, and members of the public. A method to provide such insight begins with providing a model that describes the physics of radiation interactions, radiation source and geometry, collection of field measurements, and interpretation of the collected data. A Monte Carlo simulation of the model is performed so that calculated results can be compared to measured values. The results of this investigation indicate that measured organ absorbed doses inside a tissue equivalent phantom compared favorably to the derived organ absorbed doses measured by the Panasonic thermoluminescence dosimeters and with Monte Carlo �N� Particle modeled results. Additionally, a Victoreen 450P pressurized ion chamber measured the integrated dose and these results compared well with the Panasonic right lateral TLD. This comparison indicates that the Victoreen 450P ionization chamber could potentially serve as an estimator of real-time effective dose and organ absorbed dose, if energy and angular dependence corrections could be taken into account. Finally, the data obtained in this investigation indicate that the MCNP model provided a reasonable method to determine organ absorbed dose and effective dose of a simulated Radiological Dispersal Device in an Inferior-Superior geometry with Na99mTcO4 as the source of radioactive material.

Hearnsberger, David Wayne

2006-12-01T23:59:59.000Z

359

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:

360

NEW MATERIALS DEVELOPED TO MEET REGULATORY AND TECHNICAL REQUIREMENTS ASSOCIATED WITH IN-SITU DECOMMISSIONING OF NUCLEAR REACTORS AND ASSOCIATED FACILITIES  

Science Conference Proceedings (OSTI)

For the 2010 ANS Embedded Topical Meeting on Decommissioning, Decontamination and Reutilization and Technology, Savannah River National Laboratory's Mike Serrato reported initial information on the newly developed specialty grout materials necessary to satisfy all requirements associated with in-situ decommissioning of P-Reactor and R-Reactor at the U.S. Department of Energy's Savannah River Site. Since that report, both projects have been successfully completed and extensive test data on both fresh properties and cured properties has been gathered and analyzed for a total of almost 191,150 m{sup 3} (250,000 yd{sup 3}) of new materials placed. The focus of this paper is to describe the (1) special grout mix for filling the P-Reactor vessel (RV) and (2) the new flowable structural fill materials used to fill the below grade portions of the facilities. With a wealth of data now in hand, this paper also captures the test results and reports on the performance of these new materials. Both reactors were constructed and entered service in the early 1950s, producing weapons grade materials for the nation's defense nuclear program. R-Reactor was shut down in 1964 and the P-Reactor in 1991. In-situ decommissioning (ISD) was selected for both facilities and performed as Comprehensive Environmental Response, Compensations and Liability Act actions (an early action for P-Reactor and a removal action for R-Reactor), beginning in October 2009. The U.S. Department of Energy concept for ISD is to physically stabilize and isolate intact, structurally robust facilities that are no longer needed for their original purpose of producing (reactor facilities), processing (isotope separation facilities), or storing radioactive materials. Funding for accelerated decommissioning was provided under the American Recovery and Reinvestment Act. Decommissioning of both facilities was completed in September 2011. ISD objectives for these CERCLA actions included: (1) Prevent industrial worker exposure to radioactive or hazardous contamination exceeding Principal Threat Source Material levels; (2) Minimize human and ecological exposure to unacceptable risk associated with radiological and hazardous constituents that are or may be present; (3) Prevent to the extent practicable the migration of radioactive or hazardous contaminants from the closed facility to the groundwater so that concentrations in groundwater do not exceed regulatory standards; (4) Eliminate or control all routes of human exposure to radiological and chemical contamination; and (5) Prevent animal intruder exposure to radioactive and hazardous contamination.

Blankenship, J.; Langton, C.; Musall, J.; Griffin, W.

2012-01-18T23:59:59.000Z

Note: This page contains sample records for the topic "radiologically contaminated material" 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

Safety philosophy in the transportation of radioactive material  

SciTech Connect

From Winter meeting of American Society of Mechanical Engineers; Detroit, Michigan, USA (11 Nov 1973). The radiological'' and common cause risks'' involved in transporting radioactive materials are briefly discussed. (TFD)

Langhaar, J.W.

1974-04-30T23:59:59.000Z

362

Radiological assessment report for the Lansdowne property, 105-107 East Stratford Avenue, Lansdowne, Pennsylvania, October-December 1984  

Science Conference Proceedings (OSTI)

Areas with elevated levels of radioactivity were found throughout both residences, as well as on the surrounding property. Contamination was also found in the garage behind the 105 East structure. The 105 East residence had substantially more contamination than the 107 East residence, as was expected. The chimneys, particularly the rear chimney, from the 105 East residence had extensive contamination, indicating that contaminated materials may have been burned at the site. The high background radiation emanating from this residence made it difficult to establish the relatively lower levels of contamination in the 107 East residence. The property surrounding the 105 East residence was found to have substantial contamination scattered throughout, with the highest level occurring in the backyard. The soil surface contamination seemed to drop markedly (but not entirely) at the property lines. The property surrounding 107 East was found to be less contaminated, although the background radiation emanating from the adjoining area made it difficult to establish the degree of surface or near-surface contamination from surface surveys. Subsurface investigation of the soil surrounding the structure indicated that radium contamination was widespread and extended to a depth of eight feet at some locations. There was evidence that some of this contamination extended onto adjoining properties and may have been transported off the site via subsurface migration. Additionally, analysis of samples from access points in the residence sewer system effluent established that the system was contaminated. 3 refs., 26 figs., 13 tabs.

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

1985-09-01T23:59:59.000Z

363

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

364

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

365

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

366

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

367

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

368

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

369

DEPLOYMENT OF INNOVATIVE CHARACTERIZATION TECHNOLOGIES AND IMPLEMENTATION OF THE MARSSIM PROCESS AT RADIOLOGICALLY CONTAMINATED SITES.  

Science Conference Proceedings (OSTI)

The success of this Accelerated Site Technology Deployment (ASTD) project is measured on several levels. First, the deployment of this innovative approach using in situ characterization, portable field laboratory measurements, and implementation of MARSSIM was successfully established for all three phases of D and D characterization, i.e., pre-job scoping, on-going disposition of waste, and final status surveys upon completion of the activity. Unlike traditional D and D projects, since the Brookhaven Graphite Research Reactor Decommissioning Project (BGRR-DP) is operating on an accelerated schedule, much of the work is being carried out simultaneously. Rather than complete a full characterization of the facility before D and D work begins, specific removal actions require characterization as the activity progresses. Thus, the need for rapid and cost-effective techniques for characterization is heightened. Secondly, since the approach used for this ASTD project was not thoroughly proven prior to deployment, a large effort was devoted to demonstrating technical comparability to project managers, regulators and stakeholders. During the initial phases, large numbers of replicate samples were taken and analyzed by conventional baseline techniques to ensure that BGRR-DP quality assurance standards were met. ASTD project staff prepared comparisons of data gathered using ISOCS and BetaScint with traditional laboratory methods and presented this information to BGRR-DP staff and regulators from EPA Region II, NYS Department of Environmental Conservation, and the Suffolk County Board of Health. As the results of comparability evaluations became available, approval for these methods was received and the techniques associated with in situ characterization, portable field laboratory measurements, and implementation of MARSSIM were gradually integrated into BGRR-DP procedures.

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

2001-05-01T23:59:59.000Z

370

Corrective Action Investigation Plan for Corrective Action Unit 168: Areas 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada (Rev. 0) includes Record of Technical Change No. 1 (dated 8/28/2002), Record of Technical Change No. 2 (dated 9/23/2002), and Record of Technical Change No. 3 (dated 6/2/2004)  

SciTech Connect

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit 168 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 168 consists of a group of twelve relatively diverse Corrective Action Sites (CASs 25-16-01, Construction Waste Pile; 25-16-03, MX Construction Landfill; 25-19-02, Waste Disposal Site; 25-23-02, Radioactive Storage RR Cars; 25-23-18, Radioactive Material Storage; 25-34-01, NRDS Contaminated Bunker; 25-34-02, NRDS Contaminated Bunker; CAS 25-23-13, ETL - Lab Radioactive Contamination; 25-99-16, USW G3; 26-08-01, Waste Dump/Burn Pit; 26-17-01, Pluto Waste Holding Area; 26-19-02, Contaminated Waste Dump No.2). These CASs vary in terms of the sources and nature of potential contamination. The CASs are located and/or associated wit h the following Nevada Test Site (NTS) facilities within three areas. The first eight CASs were in operation between 1958 to 1984 in Area 25 include the Engine Maintenance, Assembly, and Disassembly Facility; the Missile Experiment Salvage Yard; the Reactor Maintenance, Assembly, and Disassembly Facility; the Radioactive Materials Storage Facility; and the Treatment Test Facility Building at Test Cell A. Secondly, the three CASs located in Area 26 include the Project Pluto testing area that operated from 1961 to 1964. Lastly, the Underground Southern Nevada Well (USW) G3 (CAS 25-99-16), a groundwater monitoring well located west of the NTS on the ridgeline of Yucca Mountain, was in operation during the 1980s. Based on site history and existing characterization data obtained to support the data quality objectives process, contaminants of potential concern (COPCs) for CAU 168 are primarily radionuclide; however, the COPCs for several CASs were not defined. To address COPC uncertainty, the analytical program for most CASs will include volatile organic compounds, semivolatile organic compounds, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons, polychlorinated biphenyls, and radionuclides. Upon reviewing historical data and current site conditions, it has been determined that no further characterization is required at USW G3 (CAS 25-99-16) to select the appropriate corrective action. A cesium-137 source was encased in cement within the vadous zone during the drilling of the well (CAS 25-99-16). A corrective action of closure in place with a land-use restriction for drilling near USW G3 is appropriate. This corrective action will be documented in the Corrective Action Decision Document (CADD) for CAU 168. The results of the remaining field investigation will support a defensible evaluation of corrective action alternatives for the other CASs within CAU 168 in this CADD.

U.S. Department of Energy, National Nuclear Security Administration Nevada

2001-11-21T23:59:59.000Z

371

Protracted Hypofractionated Radiotherapy for Graves' Ophthalmopathy: A Pilot Study of Clinical and Radiologic Response  

Science Conference Proceedings (OSTI)

Purpose: To evaluate the clinical and radiologic response of patients with Graves' ophthalmopathy given low-dose orbital radiotherapy (RT) with a protracted fractionation. Methods and Materials: Eighteen patients (36 orbits) received orbital RT with a total dose of 10 Gy, fractionated in 1 Gy once a week over 10 weeks. Of these, 9 patients received steroid therapy as well. Patients were evaluated clinically and radiologically at 6 months after treatment. Clinical response assessment was carried out using three criteria: by physical examination, by a modified clinical activity score, and by a verbal questionnaire considering the 10 most common signs and symptoms of the disease. Radiologic response was assessed by magnetic resonance imaging. Results: Improvement in ocular pain, palpebral edema, visual acuity, and ocular motility was observed in all patients. Significant decrease in symptoms such as tearing (p < 0.001) diplopia (p = 0.008), conjunctival hyperemia (p = 0.002), and ocular grittiness (p = 0.031) also occurred. Magnetic resonance imaging showed decrease in ocular muscle thickness and in the intensity of the T2 sequence signal in the majority of patients. Treatments were well tolerated, and to date no complications from treatment have been observed. There was no statistical difference in clinical and radiologic response between patients receiving RT alone and those receiving RT plus steroid therapy. Conclusion: RT delivered in at a low dose and in a protracted scheme should be considered as a useful therapeutic option for patients with Graves' ophthalmopathy.

Casimiro de Deus Cardoso, Cejana; Giordani, Adelmo Jose [Department of Clinical and Experimental Oncology, Division of Radiotherapy, Federal University of Sao Paulo, Sao Paulo, SP (Brazil); Borri Wolosker, Angela Maria [Department of Radiology, Federal University of Sao Paulo, Sao Paulo, SP (Brazil); Souhami, Luis [Department of Radiotherapy, McGill University Heath Centre, Montreal, Quebec (Canada); Gois Manso, Paulo [Department of Ophthalmology, Federal University of Sao Paulo, Sao Paulo, SP (Brazil); Souza Dias, Rodrigo; Comodo Segreto, Helena Regina [Department of Clinical and Experimental Oncology, Division of Radiotherapy, Federal University of Sao Paulo, Sao Paulo, SP (Brazil); Araujo Segreto, Roberto, E-mail: segreto.dmed@epm.br [Department of Clinical and Experimental Oncology, Division of Radiotherapy, Federal University of Sao Paulo, Sao Paulo, SP (Brazil)

2012-03-01T23:59:59.000Z

372

Purifying contaminated water  

DOE Patents (OSTI)

Process for removing biorefractory compounds from contaminated water (e.g., oil shale retort waste-water) by contacting same with fragmented raw oil shale. Biorefractory removal is enhanced by preactivating the oil shale with at least one member of the group of carboxylic, acids, alcohols, aldehydes, ketones, ethers, amines, amides, sulfoxides, mixed ether-esters and nitriles. Further purification is obtained by stripping, followed by biodegradation and removal of the cells.

Daughton, Christian G. (San Pablo, CA)

1983-01-01T23:59:59.000Z

373

Contamination control device  

DOE Patents (OSTI)

A contamination control device for use in a gas-insulated transmission bus consisting of a cylindrical center conductor coaxially mounted within a grounded cylindrical enclosure. The contamination control device is electrically connected to the interior surface of the grounded outer shell and positioned along an axial line at the lowest vertical position thereon. The contamination control device comprises an elongated metallic member having a generally curved cross-section in a first plane perpendicular to the axis of the bus and having an arcuate cross-section in a second plane lying along the axis of the bus. Each opposed end of the metallic member and its opposing sides are tapered to form a pair of generally converging and downward sloping surfaces to trap randomly moving conductive particles in the relatively field-free region between the metallic member and the interior surface of the grounded outer shell. The device may have projecting legs to enable the device to be spot welded to the interior of the grounded housing. The control device provides a high capture probability and prevents subsequent release of the charged particles after the capture thereof.

Clark, Robert M. (Ligonier, PA); Cronin, John C. (Greensburg, PA)

1977-01-01T23:59:59.000Z

374

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.

375

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.

376

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.

377

Methods to quantify contamination effects on silica gel samples  

DOE Green Energy (OSTI)

This report describes a study to establish methods for measuring sorption degradation of contaminated solid desiccants and determining the identity and nature of the contaminants. A literature search was conducted to determine how contaminants affect the sorption properties of silica gel and advanced solid desiccant materials; the search yielded 73 papers. Silica gel was chosen for the contamination study; nine samples from various batches and suppliers were tested. Methods were established (1) to measure the degradation of desiccant adsorption capacity caused by regeneration processes and/or exposure to contaminants and (2) to determine the nature of these contaminants. Sorption measurements on a limited number of fresh silica gel samples showed that the water adsorption capacity varied about +-10%. The silica gel sample regenerated with electric heaters exhibited a maximum capacity degradation of 7%. Silica gel samples processed in other ways lost between 20% and 47% capacity, depending on the age and cycle of regeneration. The contaminants found were silicon, oxygen, carbon, and nitrogen using x-ray photoelectron spectroscopy. Contamination can degrade the water sorption capacity of desiccants.

Pesaran, A.A.; Thomas, T.M.; Penney, T.R.; Czanderna, A.W.

1986-09-01T23:59:59.000Z

378

Site-specific analysis of radiological and physical parameters for cobbly soils at the Gunnison, Colorado, processing site. Revision 1  

Science Conference Proceedings (OSTI)

The remedial action at the Gunnison, Colorado, processing site is being performed under the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978. Under UMTRCA, the US Environmental Protection Agency (EPA) is charged with the responsibility of developing appropriate and applicable standards for the cleanup of radiologically contaminated land and buildings at 24 designated sites, including the Gunnison, Colorado, inactive processing site. Section 108 of Public Law 95-604 states that the US Department of Energy (DOE) shall ``select and perform remedial actions at the designated processing sites and disposal sites in accordance with the general standards`` prescribed by the EPA. Regulations governing the required remedial action at inactive uranium processing sites were promulgated by the EPA in 1983 and are contained in 40 CFR Part 192 (1993), Health and Environmental Protection Standards for Uranium and Thorium Mill Tailings. This document describes the radiological and physical parameters for the remedial action of the soil.

Not Available

1994-01-01T23:59:59.000Z

379

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

380

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

Note: This page contains sample records for the topic "radiologically contaminated material" 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

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

382

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...

383

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...

384

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...

385

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...

386

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) *...

387

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...

388

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...

389

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

390

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...

391

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...

392

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

393

Radiological Assessment for the Removal of Legacy BPA Power Lines that Cross the Hanford Site  

SciTech Connect

This paper discusses some radiological field monitoring and assessment methods used to assess the components of an old electrical power transmission line that ran across the Hanford Site between the production reactors area (100 Area) and the chemical processing area (200 Area). This task was complicated by the presence of radon daughters?both beta and alpha emitters?residing on the surfaces, particularly on the surfaces of weathered metals and metals that had been electrically-charged. In many cases, these activities were high compared to the DOE Surface Contamination Guidelines, which were used as guides for the assessment. These methods included the use of the Toulmin model of argument?represented using Toulmin diagrams-- to represent the combined force of several strands of evidences, rather than a single measurement of activity, to demonstrate beyond a reasonable doubt that no or very little Hanford activity was present and mixed with the natural activity. A number of forms of evidence were used: the overall chance of Hanford contamination; measurements of removable activity, beta and alpha; 1-minute scaler counts of total surface activity, beta and alpha, using ?background makers?; the beta activity to alpha activity ratios; measured contamination on nearby components; NaI gamma spectral measurements to compare uncontaminated and potentially-contaminated spectra, as well as measurements for the sentinel radionuclides, Am- 241 and Cs-137 on conducting wire; comparative statistical analyses; and in-situ measurements of alpha spectra on conducting wire showing that the alpha activity was natural Po-210, as well as to compare uncontaminated and potentially-contaminated spectra.

Millsap, William J.; Brush, Daniel J.

2013-11-13T23:59:59.000Z

394

Contaminated nickel scrap processing  

Science Conference Proceedings (OSTI)

The DOE will soon choose between treating contaminated nickel scrap as a legacy waste and developing high-volume nickel decontamination processes. In addition to reducing the volume of legacy wastes, a decontamination process could make 200,000 tons of this strategic metal available for domestic use. Contaminants in DOE nickel scrap include {sup 234}Th, {sup 234}Pa, {sup 137}Cs, {sup 239}Pu (trace), {sup 60}Co, U, {sup 99}Tc, and {sup 237}Np (trace). This report reviews several industrial-scale processes -- electrorefining, electrowinning, vapormetallurgy, and leaching -- used for the purification of nickel. Conventional nickel electrolysis processes are particularly attractive because they use side-stream purification of process solutions to improve the purity of nickel metal. Additionally, nickel purification by electrolysis is effective in a variety of electrolyte systems, including sulfate, chloride, and nitrate. Conventional electrorefining processes typically use a mixed electrolyte which includes sulfate, chloride, and borate. The use of an electrorefining or electrowinning system for scrap nickel recovery could be combined effectively with a variety of processes, including cementation, solvent extraction, ion exchange, complex-formation, and surface sorption, developed for uranium and transuranic purification. Selected processes were reviewed and evaluated for use in nickel side-stream purification. 80 refs.

Compere, A.L.; Griffith, W.L.; Hayden, H.W.; Johnson, J.S. Jr.; Wilson, D.F.

1994-12-01T23:59:59.000Z

395

Problems Encountered During the Radiological Remediation of Old Buildings  

SciTech Connect

With several military base closures resulting in property transfer to public use and the decommissioning of many legacy waste facilities, the opportunity for remediation of older buildings is increasing. Along with these projects, come several problems that could give the potential remediator some surprises. During the preconstruction and planning phases of the original construction activities, several generations of drawings were most likely produced for approval and permit submittal. Over the years, buildings may undergo several renovations with or without the full characterization or remediation that should be done when radioactive materials are used on a site. New walls or floors may be built over the original construction materials. Contamination in and around the building may have resulted from processes that were accepted at the time or from inadvertent activities that may have been covered up, including accidental spills. Many buildings contain hidden rooms or accesses that over time became useless and have been closed up or over, these areas may not be very obvious. When characterizing a building the effluents of the building are usually forgotten, sewer lines are important areas to investigate. All these items could cause a remediator to overlook a potentially highly contaminated area. With more of these facilities being turned over for public use, correctly characterizing these buildings will become a more common problem.

Krieger, K. V.; Schillings, D. C.

2003-02-25T23:59:59.000Z

396

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

397

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

398

Armored Enzyme Nanoparticles for Remediation of Subsurface Contaminants  

Science Conference Proceedings (OSTI)

The remediation of subsurface contaminants is a critical problem for the Department of Energy, other government agencies, and our nation. Severe contamination of soil and groundwater exists at several DOE sites due to various methods of intentional and unintentional release. Given the difficulties involved in conventional removal or separation processes, it is vital to develop methods to transform contaminants and contaminated earth/water to reduce risks to human health and the environment. Transformation of the contaminants themselves may involve conversion to other immobile species that do not migrate into well water or surface waters, as is proposed for metals and radionuclides; or degradation to harmless molecules, as is desired for organic contaminants. Transformation of contaminated earth (as opposed to the contaminants themselves) may entail reductions in volume or release of bound contaminants for remediation. Research at Rensselaer focused on the development of haloalkane dehalogenase as a critical enzyme in the dehalogenation of contaminated materials (ultimately trichloroethylene and related pollutants). A combination of bioinformatic investigation and experimental work was performed. The bioinformatics was focused on identifying a range of dehalogenase enzymes that could be obtained from the known proteomes of major microorganisms. This work identified several candidate enzymes that could be obtained through relatively straightforward gene cloning and expression approaches. The experimental work focused on the isolation of haloalkane dehalogenase from a Xanthobacter species followed by incorporating the enzyme into silicates to form biocatalytic silicates. These are the precursors of SENs. At the conclusion of the study, dehalogenase was incorporated into SENs, although the loading was low. This work supported a single Ph.D. student (Ms. Philippa Reeder) for two years. The project ended prior to her being able to perform substantive bioinformatics efforts that would identify more promising dehalogenase enzymes. The SEN synthesis, however, was demonstrated to be partially successful with dehalogenases. Further work would provide optimized dehalogenases in SENs for use in pollution remission.

Jonathan S. Dordick; Jay Grate; Jungbae Kim

2007-02-19T23:59:59.000Z

399

Emission Standards for Contaminants (Iowa)  

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

These regulations list emissions standards for various contaminants, and contain special requirements for anaerobic lagoons. These regulations also describe alternative emissions limits, which may...

400

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

Note: This page contains sample records for the topic "radiologically contaminated material" 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

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

402

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

403

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

404

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

405

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

406

Nuclear Radiological Threat Task Force Established | National Nuclear  

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

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

407

How ORISE is Making a Difference: Radiological Assessment and Monitoring  

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

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

408

Helium leak testing of a radioactive contaminated vessel under high pressure in a contaminated environment  

Science Conference Proceedings (OSTI)

At ANL-W, with the shutdown of EBR-II, R&D has evolved from advanced reactor design to the safe handling, processing, packaging, and transporting spent nuclear fuel and nuclear waste. New methods of processing spent fuel rods and transforming contaminated material into acceptable waste forms are now in development. Storage of nuclear waste is a high interest item. ANL-W is participating in research of safe storage of nuclear waste, with the WIPP (Waste Isolation Pilot Plant) site in New Mexico the repository. The vessel under test simulates gas generated by contaminated materials stored underground at the WIPP site. The test vessel is 90% filled with a mixture of contaminated material and salt brine (from WIPP site) and pressurized with N2-1% He at 2500 psia. Test acceptance criteria is leakage jar method is used to determine leakage rate using a mass spectrometer leak detector (MSLD). The efficient MSLD and an Al bell jar replaced a costly, time consuming pressure decay test setup. Misinterpretation of test criterion data caused lengthy delays, resulting in the development of a unique procedure. Reevaluation of the initial intent of the test criteria resulted in leak tolerances being corrected and test efficiency improved.

Winter, M.E.

1996-10-01T23:59:59.000Z

409

Helium leak testing of a radioactive contaminated vessel under high pressure in a contaminated environment  

SciTech Connect

At ANL-W, with the shutdown of EBR-II, R&D has evolved from advanced reactor design to the safe handling, processing, packaging, and transporting spent nuclear fuel and nuclear waste. New methods of processing spent fuel rods and transforming contaminated material into acceptable waste forms are now in development. Storage of nuclear waste is a high interest item. ANL-W is participating in research of safe storage of nuclear waste, with the WIPP (Waste Isolation Pilot Plant) site in New Mexico the repository. The vessel under test simulates gas generated by contaminated materials stored underground at the WIPP site. The test vessel is 90% filled with a mixture of contaminated material and salt brine (from WIPP site) and pressurized with N2-1% He at 2500 psia. Test acceptance criteria is leakage < 10{sup -7} cc/seconds at 2500 psia. The bell jar method is used to determine leakage rate using a mass spectrometer leak detector (MSLD). The efficient MSLD and an Al bell jar replaced a costly, time consuming pressure decay test setup. Misinterpretation of test criterion data caused lengthy delays, resulting in the development of a unique procedure. Reevaluation of the initial intent of the test criteria resulted in leak tolerances being corrected and test efficiency improved.

Winter, M.E.

1996-10-01T23:59:59.000Z

410

Decontaminating and Melt Recycling Tritium Contaminated Stainless Steel  

SciTech Connect

The Westinghouse Savannah River Company, Idaho National Engineering Laboratory, and several university and industrial partners are evaluating recycling radioactively contaminated stainless steel. The goal of this program is to recycle contaminated stainless steel scrap from US Department of Energy national defense facilities. There is a large quantity of stainless steel at the DOE Savannah River Site from retired heavy water moderated Nuclear material production reactors (for example heat exchangers and process water piping), that will be used in pilot studies of potential recycle processes. These parts are contaminated by fission products, activated species, and tritium generated by neutron irradiation of the primary reactor coolant, which is heavy (deuterated) water. This report reviews current understanding of tritium contamination of stainless steel and previous studies of decontaminating tritium exposed stainless steel. It also outlines stainless steel refining methods, and proposes recommendations based on this review.

Clark, E.A.

1995-04-03T23:59:59.000Z

411

Radiologic characterization of the Mexican Hat, Utah, uranium mill tailings remedial action site: Addendum D1  

Science Conference Proceedings (OSTI)

This radiologic characterization of the inactive uranium millsite at Mexican Hat, Utah, was conducted by Bendix Field Engineering Corporation for the US Department of Energy (DOE), Grand Junctions Project Office in response to and in accord with a Statement of Work prepared by the DOE Uranium Mill Tailings Remedial Action Project (UMTRAP) Technical Assistance Contractor, Jacobs Engineering Group, Inc. The objective of this project was to determine the horizontal and vertical extent of contamination that exceeds the US Environmental Protection Agency (EPA) standards at the Mexican Hat site. The data presented in this report are required for characterization of the areas adjacent to the Mexican Hat tailings piles and for the subsequent design of cleanup activities. Some on- pile sampling was required to determine the depth of the 15-pCi/g Ra- 226 interface in an area where wind and water erosion has taken place.

Ludlam, J.R.

1985-01-01T23:59:59.000Z

412

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

413

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

414

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

415

Radiological Control Programs for Special Tritium Compounds  

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

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

416

Radiological Control Programs for Special Tritium Compounds  

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

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

417

Radiological Control Change Notice 1 Memorandum  

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

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

418

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

419

Corrective Action Investigation Plan for Corrective Action Unit 190: Contaminated Waste Sites Nevada Test Site, Nevada, Rev. No.: 0  

Science Conference Proceedings (OSTI)

Corrective Action Unit (CAU) 190 is located in Areas 11 and 14 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 190 is comprised of the four Corrective Action Sites (CASs) listed below: (1) 11-02-01, Underground Centrifuge; (2) 11-02-02, Drain Lines and Outfall; (3) 11-59-01, Tweezer Facility Septic System; and (4) 14-23-01, LTU-6 Test Area. These sites are being investigated because existing information is insufficient on the nature and extent of potential contamination to evaluate and recommend corrective action alternatives. Additional information will be obtained before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS by conducting a corrective action investigation (CAI). The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on August 24, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture, and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 190. The scope of the CAU 190 CAI includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling; (2) Conduct radiological and geophysical surveys; (3) Perform field screening; (4) Collect and submit environmental samples for laboratory analysis to determine whether contaminants of concern (COCs) are present; (5) If COCs are present, collect additional step-out samples to define the lateral and vertical extent of the contamination; (6) Collect samples of source material, if present, to determine the potential for a release; (7) Collect samples of investigation-derived waste, as needed, for waste management and minimization purposes; and (8) Collect quality control samples. This Corrective Action Investigation Document (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) agreed to by the State of Nevada, U.S. Department of Energy, and U.S. Department of Defense. Under the FFACO, this CAIP will be submitted to the Nevada Division of Environmental Protection for approval. Field work will be conducted following approval.

Wickline, Alfred

2006-12-01T23:59:59.000Z

420

US Army Radiological Bioassay and Dosimetry: The RBD software package  

Science Conference Proceedings (OSTI)

The RBD (Radiological Bioassay and Dosimetry) software package was developed for the U. S. Army Material Command, Arlington, Virginia, to demonstrate compliance with the radiation protection guidance 10 CFR Part 20 (ref. 1). Designed to be run interactively on an IBM-compatible personal computer, RBD consists of a data base module to manage bioassay data and a computational module that incorporates algorithms for estimating radionuclide intake from either acute or chronic exposures based on measurement of the worker`s rate of excretion of the radionuclide or the retained activity in the body. In estimating the intake,RBD uses a separate file for each radionuclide containing parametric representations of the retention and excretion functions. These files also contain dose-per-unit-intake coefficients used to compute the committed dose equivalent. For a given nuclide, if measurements exist for more than one type of assay, an auxiliary module, REPORT, estimates the intake by applying weights assigned in the nuclide file for each assay. Bioassay data and computed results (estimates of intake and committed dose equivalent) are stored in separate data bases, and the bioassay measurements used to compute a given result can be identified. The REPORT module creates a file containing committed effective dose equivalent for each individual that can be combined with the individual`s external exposure.

Eckerman, K.F.; Ward, R.C.; Maddox, L.B.

1993-01-01T23:59:59.000Z

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