National Library of Energy BETA

Sample records for final radiological conditions

  1. Evaluation of Final Radiological Conditions at Areas of the Niagara...

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

    Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage ...

  2. Evaluation of Final Radiological Conditions at Areas of the Niagara Falls

    Office of Environmental Management (EM)

    Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program | Department of Energy Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program Evaluation of Final Radiological Conditions at Areas of the Niagara Falls

  3. Evaluation of Final Radiological Conditions at Areas of the Niagara Falls

    Energy Savers [EERE]

    Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program | Department of Energy Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program Paper presented at the Waste Management 2012 Conference. February 26 through

  4. Enewetak radiological support project. Final report

    SciTech Connect (OSTI)

    Friesen, B.

    1982-09-01

    From 1972 through 1980, the Department of Energy acted in an advisory role to the Defense Nuclear Agency during planning for and execution of the cleanup of Enewetak Atoll. The Nevada Operations Office of the Department of Energy was responsible for the radiological characterization of the atoll and for certification of radiological condition of each island upon completion of the project. In-situ measurements of gamma rays emitted by americium-241 were utilized along with wet chemistry separation of plutonium from soil samples to identify and delineate surface areas requiring removal of soil. Military forces removed over 100,000 cubic yards of soil from the surface of five islands and deposited this material in a crater remaining from the nuclear testing period. Subsurface soil was excavated and removed from several locations where measurements indicated the presence of radionuclides above predetermined criteria. The methodologies of data acquisition, analysis and interpretation are described and detailed results are provided in text, figures and microfiche. The final radiological condition of each of 43 islets is reported.

  5. Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program -12184

    SciTech Connect (OSTI)

    Clayton, Christopher; Kothari, Vijendra; Starr, Ken; Widdop, Michael; Gillespie, Joey

    2012-02-26

    The U. S. Department of Energy (DOE) methods and protocols allow evaluation of remediation and final site conditions to determine if remediated sites remain protective. Two case studies are presented that involve the Niagara Falls Storage Site (NFSS) and associated vicinity properties (VPs), which are being remediated under the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are a part of the former Lake Ontario Ordnance Works (LOOW). In response to stakeholders concerns about whether certain remediated NFSS VPs were putting them at risk, DOE met with stakeholders and agreed to evaluate protectiveness. Documentation in the DOE records collection adequately described assessed and final radiological conditions at the completed VPs. All FUSRAP wastes at the completed sites were cleaned up to meet DOE guidelines for unrestricted use. DOE compiled the results of the investigation in a report that was released for public comment. In conducting the review of site conditions, DOE found that stakeholders were also concerned about waste from the Separations Process Research Unit (SPRU) at the Knolls Atomic Power Laboratory (KAPL) that was handled at LOOW. DOE agreed to determine if SPRU waste remained at that needed to be remediated. DOE reviewed records of waste characterization, historical handling locations and methods, and assessment and remediation data. DOE concluded that the SPRU waste was remediated on the LOOW to levels that pose no unacceptable risk and allow unrestricted use and unlimited exposure. This work confirms the following points as tenets of an effective long-term surveillance and maintenance (LTS&M) program: ? Stakeholder interaction must be open and transparent, and DOE must respond promptly to stakeholder concerns. ? DOE, as the long-term custodian, must collect and preserve site records in order to demonstrate that remediated sites pose no unacceptable risk. ? DOE must continue to maintain constructive relationships with the U.S. Army Corps of Engineers and state and federal regulators.

  6. Microsoft Word - Berger Radiological Conditions.doc

    Office of Legacy Management (LM)

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

  7. Radiological Conditions at the Semipalatinsk Test Site, Kazakhstan: Preliminary Assessment and Recommendations for Further Study

    SciTech Connect (OSTI)

    Napier, Bruce A. )

    1999-01-01

    This is a review of the book ''Radiological Conditions at the Semipalatinsk Test Site, Kazakhstan: Preliminary Assessment and Recommendations for Further Study.''

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

    SciTech Connect (OSTI)

    T.J. Vitkus

    2008-04-07

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

  9. Hydroxylamine Nitrate Decomposition under Non-radiological Conditions

    SciTech Connect (OSTI)

    McFarlane, Joanna; Delmau, Laetitia Helene; DePaoli, David W.; Mattus, Catherine H.; Phelps, Clarice E.; Roach, Benjamin D.

    2015-07-01

    Hydroxylamine nitrate (HAN) is used to reduce Pu(IV) to Pu(III) in the separation of plutonium from uranium. HAN becomes unstable under certain conditions and has been known to explode, causing injury to humans including death. Hence, it is necessary to deactivate HAN once the reduction of plutonium is finished. This report reviews what is known about the chemistry of HAN and various methods to achieve a safe decomposition. However, there are areas where more information is needed to make a decision about the handling of HAN in reprocessing of nuclear fuel. Experiments have demonstrated a number of non-radiolytic ways to safely decompose HAN, including heating in HNO3, photolytic oxidation in the presence of H2O2, and the addition of a metal such as Fe(III) that will oxidize the HAN.

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

    SciTech Connect (OSTI)

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

    2008-12-01

    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.

  11. NIF final optics system: frequency conversion and beam conditioning

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

    NIF final optics system: frequency conversion and beam conditioning* P. Wegner, J. Auerbach, T. Biesiada, S. Dixit, J. Lawson, J. Menapace, T. Parham, D. Swift, P. Whitman, W. Williams Lawrence Livermore National Laboratory, PO Box 808, Livermore, CA, USA 94550 *Work performed under the auspices of the U.S. Department of Energy by the University of California, Lawrence Livermore National Laboratory under Contract No W-7405-Eng-48. ABSTRACT Installation and commissioning of the first of

  12. Final Radiological Assessment of External Exposure for CLEAR-Line Americium Recovery Operations

    SciTech Connect (OSTI)

    Davis, Adam C.; Belooussova, Olga N.; Hetrick, Lucas Duane

    2014-11-12

    Los Alamos National Laboratory is currently planning to implement an americium recovery program. The americium, ordinarily isotopically pure 241Am, would be extracted from existing Pu materials, converted to an oxide and shipped to support fabrication of americium oxide-beryllium neutron sources. These operations would occur in the currently proposed Chloride Extraction and Actinide Recovery (CLEAR) line of glove boxes. This glove box line would be collocated with the currently-operational Experimental Chloride Extraction Line (EXCEL). The focus of this document is to provide an in-depth assessment of the currently planned radiation protection measures and to determine whether or not further design work is required to satisfy design-goal and ALARA requirements. Further, this document presents a history of americium recovery operations in the Department of Energy and high-level descriptions of the CLEAR line operations to provide a basis of comparison. Under the working assumptions adopted by this study, it was found that the evaluated design appears to mitigate doses to a level that satisfies the ALARA-in-design requirements of 10 CFR 835 as implemented by the Los Alamos National Laboratory procedure P121. The analyses indicate that extremity doses would also meet design requirements. Dose-rate calculations were performed using the radiation transport code MCNP5 and doses were estimated using a time-motion study developed in consort with the subject matter expert. A copy of this report and all supporting documentation are located on the Radiological Engineering server at Y:\\Rad Engineering\\2013 PROJECTS\\TA-55 Clear Line.

  13. Radiological Control Technician Training

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

    ... using these values combined with a knowledge of the drinking water sources and the ... the technician (or line supervisor) informing workers of radiological conditions such as: ...

  14. Final Report - Membranes and MEA's for Dry, Hot Operating Conditions

    SciTech Connect (OSTI)

    Hamrock, Steven J.

    2011-06-30

    The focus of this program was to develop a new Proton Exchange Membrane (PEM) which can operate under hotter, dryer conditions than the state of the art membranes today and integrate it into a Membrane Electrode Assembly (MEA). These MEA's should meet the performance and durability requirements outlined in the solicitation, operating under low humidification conditions and at temperatures ranging from -20���ºC to 120���ºC, to meet 2010 DOE technical targets for membranes. This membrane should operate under low humidification conditions and at temperatures ranging from -20���ºC to 120���ºC in order to meet DOE HFCIT 2010 commercialization targets for automotive fuel cells. Membranes developed in this program may also have improved durability and performance characteristics making them useful in stationary fuel cell applications. The new membranes, and the MEA�¢����s comprising them, should be manufacturable at high volumes and at costs which can meet industry and DOE targets. This work included: A) Studies to better understand factors controlling proton transport within the electrolyte membrane, mechanisms of polymer degradation (in situ and ex situ) and membrane durability in an MEA; B) Development of new polymers with increased proton conductivity over the range of temperatures from -20���ºC to 120���ºC and at lower levels of humidification and with improved chemical and mechanical stability; C) Development of new membrane additives for increased durability and conductivity under these dry conditions; D) Integration of these new materials into membranes and membranes into MEA�¢����s, including catalyst and gas diffusion layer selection and integration; E) Verification that these materials can be made using processes which are scalable to commercial volumes using cost effective methods; F) MEA testing in single cells using realistic automotive testing protocols. This project addresses technical barriers A (Durability) and C (Performance) from the Fuel Cells section of the 2005 Hydrogen, Fuel Cells and Infrastructure Technologies Program Multi-Year R&D Plan. In the course of this four-year program we developed a new PEM with improved proton conductivity, chemical stability and mechanical stability. We incorporated this new membrane into MEAs and evaluated performance and durability.

  15. 324 Building Baseline Radiological Characterization

    SciTech Connect (OSTI)

    R.J. Reeder, J.C. Cooper

    2010-06-24

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

  16. DOE/EA-1499; Radiological/Nuclear Countermeasures Test and Evaluation Complex, Nevada Test Site Final Environmental Assessment

    National Nuclear Security Administration (NNSA)

    Suppleme 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 The DHS has identified a critical need to consolidate a broad spectrum of radiological and nuclear countermeasures test and evaluation activities as well as training and other operational needs throughout its organization. The NTS offers the isolation and security needed to successfully operate such a complex. In recognizing the ongoing need for DHS

  17. radiological. survey

    National Nuclear Security Administration (NNSA)

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

  18. Radiological Control

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

    2009-06-16

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

  19. Radiological Control

    Energy Savers [EERE]

    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

  20. Final Report - Advanced MEA's for Enhanced Operating Conditions, Amenable to High Volume Manufacture

    SciTech Connect (OSTI)

    Debe, Mark K.

    2007-09-30

    This report summarizes the work completed under a 3M/DOE contract directed at advancing the key fuel cell (FC) components most critical for overcoming the polymer electrolyte membrane fuel cell (PEMFC) performance, durability & cost barriers. This contract focused on the development of advanced ion exchange membranes & electrocatalysts for PEMFCs that will enable operation under ever more demanding automotive operating conditions & the use high volume compatible processes for their manufacture. Higher performing & more durable electrocatalysts must be developed for PEMFCs to meet the power density & lifetime hours required for FC vehicles. At the same time the amount of expensive Pt catalyst must be reduced to lower the MEA costs. While these two properties are met, the catalyst must be made resistant to multiple degradation mechanisms to reach necessary operating lifetimes. In this report, we present the work focused on the development of a completely new approach to PEMFC electrocatalyts, called nanostructured thin film (NSTF) catalysts. The carbon black supports are eliminated with this new approach which eliminates the carbon corrosion issue. The thin film nature of the catalyst significantly improves its robustness against dissolution & grain growth, preserving the surface area. Also, the activity of the NSTF for oxygen reduction is improved by over 500% compared to dispersed Pt catalyts. Finally, the process for fabricating the NSTF catalysts is consistent with high volume roll-good manufacturing & extremely flexible towards the introduction of new catalyst compositions & structures. This report documents the work done to develop new multi-element NSTF catalysts with properties that exceed pure Pt, that are optimized for use with the membranes discussed below, & advance the state-of-the-art towards meeting the DOE 2010 targets for PEMFC electrocatalysts. The work completed advances the understanding of the NSTF catalyst technology, identifies new NSTF-ternary catalyst materials for higher performance, documents enhanced durability under multiple types of accelerated tests by factors of 10x to 50x over conventional catalysts, & demonstrates their performance & durability in large area MEA FC stack tests. The PEMFC ion exchange membrane is the other key functioning FC component on which work was completed. While improvements have been made to standard PFSA type membranes, they still require humidification to achieve adequate proton conductivity & so their use at elevated temperatures & drier operating conditions is limited. Membranes with increased durability & conductivity under hotter, drier conditions allow the use of FC's in many applications, particularly automotive. Towards this goal, 2 approaches were pursued in the work reported here. The first part was designed for immediate application at drier conditions & operating temperatures between 85C and 120C, focused on the development of a membrane based on a low equivalent weight (EW), perfluorinated sulfonic acid (PFSA) ionomer for good ionic conductivity at low humidification, & the use of stabilizing additives for improved oxidative stability. The ionomer used was developed at 3M & has a shorter acid containing side-chain than the Nafion™ ionomer. This ionomer also has a higher T? & higher modulus than that of a Nafion™ membrane of the same EW, allowing lower EW ionomers to be prepared with very good mechanical properties. In addition, more than 50 stabilizing additives were evaluated in ex-situ, Fenton’s tests & more than 10 of these were incorporated into membranes & evaluated in accelerated FC tests. This work led to thin (25-30 micron) cast membranes with substantially improved conductivity & durability under simulated automotive conditions, compared to membranes currently available. The 2nd body of membrane work was focused on developing & characterizing 3 approaches for making new PEM's for operation under hot (>120C) & dry (dew point <80C) FC conditions: inorganic materials with enhanced proton conductivity, polymer matrices swollen with low molecular weight fluorinated acids & proton conducting ionic liquids. New materials developed show the promise of the development of new membranes with even better characteristics under demanding FC operating conditions, further improving the efficiency & viability of FC systems.

  1. RADIOLOGICAL SURWY

    Office of Legacy Management (LM)

    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".

  2. Radiological Control

    National Nuclear Security Administration (NNSA)

    NOT MEASUREMENT SENSITIVE 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,

  3. Radiological Protection

    National Nuclear Security Administration (NNSA)

    This document is an extract from ICRP Publication 103 The 2007 Recommendations of the International Commission on Radiological Protection The full report is available for purchase and may be ordered online at: http://www.elsevier.com/wps/find/bookdescription.cws_home/713998/description#description A shorter "users edition" is available at a lower cost and may be ordered here at: http://www.elsevier.com/wps/find/bookdescription.cws_home/714371/description#description Annals of the ICRP

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

    SciTech Connect (OSTI)

    Bailey, E. N.

    2008-02-25

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

  5. Final Expert Meeting Report: Simplified Space Conditioning Strategies for Energy Efficient Houses

    SciTech Connect (OSTI)

    Stecher, D.

    2011-07-01

    More research is needed to evaluate the level of energy efficiency and the conditions where simplified space conditioning systems will work in new and retrofitted houses. Guidance is needed on the design and installation of these systems to support a wider adoption throughout the new construction and retrofit market. The purpose of this expert meeting was to recap the current state of knowledge in this area and to provide a peer review of IBACOS's research plan for new and existing unoccupied test houses with minimized space conditioning systems.

  6. Radiological Control Manual

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

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

  7. Estimate of radionuclide release characteristics into containment under severe accident conditions. Final report

    SciTech Connect (OSTI)

    Nourbakhsh, H.P.

    1993-11-01

    A detailed review of the available light water reactor source term information is presented as a technical basis for development of updated source terms into the containment under severe accident conditions. Simplified estimates of radionuclide release and transport characteristics are specified for each unique combination of the reactor coolant and containment system combinations. A quantitative uncertainty analysis in the release to the containment using NUREG-1150 methodology is also presented.

  8. Final Expert Meeting Report: Simplified Space Conditioning Strategies for Energy Efficient Houses

    Energy Savers [EERE]

    Expert Meeting Report: Simplified Space Conditioning Strategies for Energy Efficient Houses Dave Stecher IBACOS, Inc. July 2011 NOTICE This report was prepared as an account of work sponsored by an agency of the United States government. Neither the United States government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus,

  9. Radiological Worker Training - Radiological Contamination Control...

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

    ... workers attending training programs unsuitable for their needs. Prerequisites A background and foundation of knowledge ... radiological work and informing the worker of the ...

  10. Conditional stochastic modeling of transport of contaminant in the vadose zone. Final project report

    SciTech Connect (OSTI)

    Yeh, T.C.J.; Harter, T.

    1995-06-01

    Spatial heterogeneity media leads to uncertainty in predicting both flow and transport in the vadose zone. In this work an efficient and flexible, combined analytical-numerical Monte Carlo approach is developed for the analysis of steady-state flow and transient transport processes in highly heterogeneous, variably saturated porous media. The approach is also used for the investigation of the validity of linear, first order analytical stochastic models. A combined analytical-numerical conditional simulation algorithm is developed to estimate the impact of in-situ soil hydraulic measurements on reducing the uncertainty of concentration and solute flux predictions.

  11. OTVE combustor wall condition monitoring. Final report, November 1986-September 1988

    SciTech Connect (OSTI)

    Szemenyei, B.; Nelson, R.S.; Barkhoudarian, S.

    1989-08-01

    Conventional ultrasonics, eddy current, and electromagnetic acoustic transduction (EMAT) technologies were evaluated to determine their capability of measuring wall thickness/wear of individual cooling channels in test specimens simulating conditions in the throat region of an OTVE combustion chamber liner. Quantitative results are presented for the eddy current technology, which was shown to measure up to the optimum 20-mil wall thickness with near single channel resolution. Additional results demonstrate the capability of the conventional ultrasonics and EMAT technologies to detect a thinning or cracked wall. Recommendations for additional eddy current and EMAT development tests are presented.

  12. Final Report - Durable Catalysts for Fuel Cell Protection during Transient Conditions

    SciTech Connect (OSTI)

    Atanasoski, Radoslav; van der Vliet, Dennis; Cullen, David; Atanasoska, Ljiljana

    2015-01-26

    The objective of this project was to develop catalysts that will enable proton exchange membranes (PEM) fuel cell systems to weather the damaging conditions in the fuel cell at voltages beyond the thermodynamic stability of water during the transient periods of start-up/shut-down and fuel starvation. Such catalysts are required to make it possible for the fuel cell to satisfy the 2015 DOE targets for performance and durability. The project addressed a key issue of importance for successful transition of PEM fuel cell technology from development to pre-commercial phase. This issue is the failure of the catalyst and the other thermodynamically unstable membrane electrode assembly (MEA) components during start-up/shut-down and local fuel starvation at the anode, commonly referred to as transient conditions. During these periods the electrodes can reach potentials higher than the usual 1.23V upper limit during normal operation. The most logical way to minimize the damage from such transient events is to minimize the potential seen by the electrodes. At lower positive potentials, increased stability of the catalysts themselves and reduced degradation of the other MEA components is expected.

  13. Condition monitoring through advanced sensor and computational technology : final report (January 2002 to May 2005).

    SciTech Connect (OSTI)

    Kim, Jung-Taek; Luk, Vincent K.

    2005-05-01

    The overall goal of this joint research project was to develop and demonstrate advanced sensors and computational technology for continuous monitoring of the condition of components, structures, and systems in advanced and next-generation nuclear power plants (NPPs). This project included investigating and adapting several advanced sensor technologies from Korean and US national laboratory research communities, some of which were developed and applied in non-nuclear industries. The project team investigated and developed sophisticated signal processing, noise reduction, and pattern recognition techniques and algorithms. The researchers installed sensors and conducted condition monitoring tests on two test loops, a check valve (an active component) and a piping elbow (a passive component), to demonstrate the feasibility of using advanced sensors and computational technology to achieve the project goal. Acoustic emission (AE) devices, optical fiber sensors, accelerometers, and ultrasonic transducers (UTs) were used to detect mechanical vibratory response of check valve and piping elbow in normal and degraded configurations. Chemical sensors were also installed to monitor the water chemistry in the piping elbow test loop. Analysis results of processed sensor data indicate that it is feasible to differentiate between the normal and degraded (with selected degradation mechanisms) configurations of these two components from the acquired sensor signals, but it is questionable that these methods can reliably identify the level and type of degradation. Additional research and development efforts are needed to refine the differentiation techniques and to reduce the level of uncertainties.

  14. Microbial Gas Generation Under Expected Waste Isolation Pilot Plant Repository Conditions: Final Report

    SciTech Connect (OSTI)

    Gillow, J.B.; Francis, A.

    2011-07-01

    Gas generation from the microbial degradation of the organic constituents of transuranic (TRU) waste under conditions expected in the Waste Isolation Pilot Plant (WIPP) was investigated. The biodegradation of mixed cellulosic materials and electron-beam irradiated plastic and rubber materials (polyethylene, polyvinylchloride, hypalon, leaded hypalon, and neoprene) was examined. We evaluated the effects of environmental variables such as initial atmosphere (air or nitrogen), water content (humid ({approx}70% relative humidity, RH) and brine inundated), and nutrient amendments (nitogen phosphate, yeast extract, and excess nitrate) on microbial gas generation. Total gas production was determined by pressure measurement and carbon dioxide (CO{sub 2}) and methane (CH{sub 4}) were analyzed by gas chromatography; cellulose degradation products in solution were analyzed by high-performance liquid chromatography. Microbial populations in the samples were determined by direct microscopy and molecular analysis. The results of this work are summarized.

  15. Final Technical Report Recovery Act: Online Nonintrusive Condition Monitoring and Fault Detection for Wind Turbines

    SciTech Connect (OSTI)

    Wei Qiao

    2012-05-29

    The penetration of wind power has increased greatly over the last decade in the United States and across the world. The U.S. wind power industry installed 1,118 MW of new capacity in the first quarter of 2011 alone and entered the second quarter with another 5,600 MW under construction. By 2030, wind energy is expected to provide 20% of the U.S. electricity needs. As the number of wind turbines continues to grow, the need for effective condition monitoring and fault detection (CMFD) systems becomes increasingly important [3]. Online CMFD is an effective means of not only improving the reliability, capacity factor, and lifetime, but it also reduces the downtime, energy loss, and operation and maintenance (O&M) of wind turbines. The goal of this project is to develop novel online nonintrusive CMFD technologies for wind turbines. The proposed technologies use only the current measurements that have been used by the control and protection system of a wind turbine generator (WTG); no additional sensors or data acquisition devices are needed. Current signals are reliable and easily accessible from the ground without intruding on the wind turbine generators (WTGs) that are situated on high towers and installed in remote areas. Therefore, current-based CMFD techniques have great economic benefits and the potential to be adopted by the wind energy industry. Specifically, the following objectives and results have been achieved in this project: (1) Analyzed the effects of faults in a WTG on the generator currents of the WTG operating at variable rotating speed conditions from the perspective of amplitude and frequency modulations of the current measurements; (2) Developed effective amplitude and frequency demodulation methods for appropriate signal conditioning of the current measurements to improve the accuracy and reliability of wind turbine CMFD; (3) Developed a 1P-invariant power spectrum density (PSD) method for effective signature extraction of wind turbine faults with characteristic frequencies in the current or current demodulated signals, where 1P stands for the shaft rotating frequency of a WTG; (4) Developed a wavelet filter for effective signature extraction of wind turbine faults without characteristic frequencies in the current or current demodulated signals; (5) Developed an effective adaptive noise cancellation method as an alternative to the wavelet filter method for signature extraction of wind turbine faults without characteristic frequencies in the current or current demodulated signals; (6) Developed a statistical analysis-based impulse detection method for effective fault signature extraction and evaluation of WTGs based on the 1P-invariant PSD of the current or current demodulated signals; (7) Validated the proposed current-based wind turbine CMFD technologies through extensive computer simulations and experiments for small direct-drive WTGs without gearboxes; and (8) Showed, through extensive experiments for small direct-drive WTGs, that the performance of the proposed current-based wind turbine CMFD technologies is comparable to traditional vibration-based methods. The proposed technologies have been successfully applied for detection of major failures in blades, shafts, bearings, and generators of small direct-drive WTGs. The proposed technologies can be easily integrated into existing wind turbine control, protection, and monitoring systems and can be implemented remotely from the wind turbines being monitored. The proposed technologies provide an alternative to vibration-sensor-based CMFD. This will reduce the cost and hardware complexity of wind turbine CMFD systems. The proposed technologies can also be combined with vibration-sensor-based methods to improve the accuracy and reliability of wind turbine CMFD systems. When there are problems with sensors, the proposed technologies will ensure proper CMFD for the wind turbines, including their sensing systems. In conclusion, the proposed technologies offer an effective means to achieve condition-based smart maintenance for wind turbines and have a gre

  16. OTVE turbopump condition monitoring, task E. 5. Final report, October 1988-September 1989

    SciTech Connect (OSTI)

    Coleman, P.T.; Collins, J.J.

    1989-08-01

    Recent work has been carried out on development of isotope wear analysis and optical and eddy current technologies to provide bearing wear measurements and real time monitoring of shaft speed, shaft axial displacement and shaft orbit of the Orbit Transfer Vehicle hydrostatic bearing tester. Results show shaft axial displacement can be optically measured (at the same time as shaft orbital motion and speed) to within 0.3 mils by two fiberoptic deflectometers. Evaluation of eddy current probes showed that, in addition to measuring shaft orbital motion, they can be used to measure shaft speed without having to machine grooves on the shaft surface as is the usual practice for turbomachinery. The interim results of this condition monitoring effort are presented.

  17. Catalyst dispersion and activity under conditions of temperature-staged liquefaction. Final report

    SciTech Connect (OSTI)

    Davis, A.; Schobert, H.H.; Mitchell, G.D.; Artok, L.

    1993-02-01

    This research program involves the investigation of the use of highly dispersed catalyst precursors for the pretreatment of coals by mild hydrogenation. During the course of this effort solvent preswelling of the coal was evaluated as a means of deeply impregnating catalysts into coal, active phases of catalysts under reaction conditions were studied and the impact of these techniques were evaluated during pretreatment and temperature-staged liquefaction. Two coals, a Texas subbituminous and a Utah high volatile A bituminous, were used to examine the effects of solvent swelling pretreatment and catalyst impregnation on conversion behavior at 275{degrees}C, representative of the first, low-temperature stage in a temperature-staged liquefaction reaction. Ferrous sulfate, iron pentacarbonyl, ammonium tetrathiomolybdate, and molybdenum hexacarbonyl were used as catalyst precursors. Without swelling pretreatment, impregnation of both coals increased conversion, mainly through increased yields of preasphaltenes.

  18. Standardized radiological dose evaluations

    SciTech Connect (OSTI)

    Peterson, V.L.; Stahlnecker, E.

    1996-05-01

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

  19. Data base on batteries, power-conditioning equipment, and photovoltaic arrays. Final report

    SciTech Connect (OSTI)

    Podder, A; Kapner, M; Morse, T

    1981-02-01

    The objective of this study was to compile an up-to-date comprehensive data base for research, design, and development of photovoltaic systems, primarily in the areas of applications and battery technology, and secondarily in the area of power conditioning and photovoltaic array technology. This volume contains the data base used to develop the end-use scenarios and identify the R and D needed for batteries to be used in photovoltaic power systems. In addition to its specific application to the present study, this data base is intended to provide state-of-the-art information to manufacturers of the various components of photovoltaic power systems, system designers, and researchers in this field. An extensive literature search was conducted to obtain technical data on batteries, power conditioners, and photovoltaic arrays. The data obtained from published technical literature and direct communication with manufacturers and developers are compiled. Principles of operation, types of systems, performance characteristics, test data, and cost data are included for each of the components. (WHK)

  20. RADIOLOGICAL ASSESSMENT OF BALLOD AND ASSOCIATES PROPERTY

    Office of Legacy Management (LM)

    ,..~ ,!-~ <-\ NJ' to RADIOLOGICAL ASSESSMENT OF BALLOD AND ASSOCIATES PROPERTY (STEPAN CHEMICAL COMPANY) MAYWOOD, NEW JERSEY Leslie W. Cole, Jim Berger, Phyllis Cotton, Robert Gosslee, Jonathan Sowell, Clayton Weaver FINAL REPORT July 30, 1981 Work performed by Radiological Site Assessment Program Manpower Education, Research, and Training Division Oak Ridge Associated Universities Oak Ridge, Tennessee 37830 Under Interagency Agreement DOE No. 40-770-80 NRC Fin. No. A-9093-0, Between the U.S.

  1. Radiological Assistance Program

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

    1992-04-10

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

  2. Office of Radiological Security

    National Nuclear Security Administration (NNSA)

    of physical security of radiological materials;

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

  5. Radiological Worker Training

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

    ... workers attending training programs unsuitable for their needs. Prerequisites A background and foundation of knowledge ... radiological work and informing the worker of the ...

  6. Radiological Worker Training

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

    ... be maintained by the organization 17 DOE-HDBK-1130-2008 ... Radiological Worker Training Program Management References ... facilitysite- specific Skin & other organs 50 NA facility...

  7. Radiological Assessor Training

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

    ... Uranium transported from the lungs is deposited in the bone (22%), kidney (12%), or other tissues (12%), or excreted (54%), according to International Commission on Radiological ...

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

    SciTech Connect (OSTI)

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

    2012-07-01

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

  9. Routine Radiological Environmental Monitoring Plan. Volume 1

    SciTech Connect (OSTI)

    Bechtel Nevada

    1999-12-31

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

  10. Radiological worker training

    SciTech Connect (OSTI)

    1998-10-01

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

  11. Radiological Worker Training - Radiological Control Training for Supervisors

    Energy Savers [EERE]

    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

  12. Interventional Radiology of Male Varicocele: Current Status

    SciTech Connect (OSTI)

    Iaccarino, Vittorio Venetucci, Pietro

    2012-12-15

    Varicocele is a fairly common condition in male individuals. Although a minor disease, it may cause infertility and testicular pain. Consequently, it has high health and social impact. Here we review the current status of interventional radiology of male varicocele. We describe the radiological anatomy of gonadal veins and the clinical aspects of male varicocele, particularly the physical examination, which includes a new clinical and ultrasound Doppler maneuver. The surgical and radiological treatment options are also described with the focus on retrograde and antegrade sclerotherapy, together with our long experience with these procedures. Last, we compare the outcomes, recurrence and persistence rates, complications, procedure time and cost-effectiveness of each method. It clearly emerges from this analysis that there is a need for randomized multicentre trials designed to compare the various surgical and percutaneous techniques, all of which are aimed at occlusion of the anterior pampiniform plexus.

  13. ISSUANCE 2015-06-30: Energy Conservation Program for Certain Industrial Equipment: Energy Conservation Standards and Test Procedures for Commercial Heating, Air-Conditioning, and Water-Heating Equipment, Final Rule

    Broader source: Energy.gov [DOE]

    Energy Conservation Program for Certain Industrial Equipment: Energy Conservation Standards and Test Procedures for Commercial Heating, Air-Conditioning, and Water-Heating Equipment, Final Rule

  14. Modeling of hydrologic conditions and solute movement in processed oil shale waste embankments under simulated climatic conditions. Final report, November 1995

    SciTech Connect (OSTI)

    1995-12-31

    A study is described on the hydrological and geotechnical behavior of an oil shale solid waste. The objective was to obtain information which can be used to assess the environmental impacts of oil shale solid waste disposal in the Green River Basin. The spent shale used in this study was combusted by the Lurgi-Ruhrgas process by Rio Blanco Oil Shale Company, Inc. Laboratory bench-scale testing included index properties, such as grain size distribution and Atterberg limits, and tests for engineering properties including hydraulic conductivity and shear strength. Large-scale tests were conducted on model spent shale waste embankments to evaluate hydrological response, including infiltration, runoff, and seepage. Large-scale tests were conducted at a field site in western Colorado and in the Environmental Simulation Laboratory (ESL)at the University of Wyoming. The ESL tests allowed the investigators to control rainfall and temperature, providing information on the hydrological response of spent shale under simulated severe climatic conditions. All experimental methods, materials, facilities, and instrumentation are described in detail, and results are given and discussed. 34 refs.

  15. Radiological Control Technician Training

    Energy Savers [EERE]

    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

  16. Radiological Control Technician Training

    Energy Savers [EERE]

    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

  17. Radiological Technician Training

    Energy Savers [EERE]

    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 . . . . . . . . . . . . . . . . . . . . . . . .

  18. EA-1499: Final Environmental Assessment | Department of Energy

    Office of Environmental Management (EM)

    Final Environmental Assessment EA-1499: Final Environmental Assessment Radiological/Nuclear Countermeasures Test and Evaluation Complex, Nevada Test Site The DOE, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), proposes to establish a radiological/nuclear countermeasures testing and evaluation complex at the Nevada Test Site (NTS) in Nye County, Nevada. PDF icon DOE/EA-1499; Radiological/Nuclear Countermeasures Test and Evaluation Complex, Nevada Test Site Final

  19. Radiological Control Technician Training

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

    DOE-HDBK-1122-2009 (Revised 2013) Module 2.03 Counting Errors and Statistics Instructor's Material Course Title: Radiological Control Technician Module Title: Counting Errors and Statistics Module Number: 2.03 Objectives: (This document, Instructor's Material, is referred to as Instructor's Guide in the Program Management Guide) 2.03.01. Identify five general types of errors that can occur when analyzing radioactive samples, and describe the effect of each source of error on sample

  20. Radiological Assessor Training

    Energy Savers [EERE]

    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

  21. General Employee Radiological Training

    Office of Environmental Management (EM)

    _______ 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

  22. General Employee Radiological Training

    Office of Environmental Management (EM)

    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

  1. General Employee Radiological Training

    Office of Environmental Management (EM)

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

  2. Final Optics

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

    Final Optics Schematic layout of NIF's final optics assembly (FOA). The suite of optics for one beamline is on the right. The final optics assemblies (FOAs) are the last element of the main laser system and the first of the target area systems. Each FOA contains four integrated optics modules (IOMs) that incorporate beam conditioning, frequency conversion, focusing, diagnostic sampling, and debris shielding capabilities into a single compact assembly. These optics are shown in the figure at

  3. DOE Final Report on Collaborative Research. Quantifying Climate Feedbacks of the Terrestrial Biosphere under Thawing Permafrost Conditions in the Arctic

    SciTech Connect (OSTI)

    Zhuang, Qianlai; Schlosser, C. Adam; Melillo, Jerry M.; Anthony, Katey Walter; Kicklighter, David; Gao, Xiang

    2015-11-03

    Our overall goal is to quantify the potential for threshold changes in natural emission rates of trace gases, particularly methane and carbon dioxide, from pan-arctic terrestrial systems under the spectrum of anthropogenically-forced climate warming, and the conditions under which these emissions provide a strong feedback mechanism to global climate warming. This goal is motivated under the premise that polar amplification of global climate warming will induce widespread thaw and degradation of the permafrost, and would thus cause substantial changes to the landscape of wetlands and lakes, especially thermokarst (thaw) lakes, across the Arctic. Through a suite of numerical experiments that encapsulate the fundamental processes governing methane emissions and carbon exchanges – as well as their coupling to the global climate system - we intend to test the following hypothesis in the proposed research: There exists a climate warming threshold beyond which permafrost degradation becomes widespread and stimulates large increases in methane emissions (via thermokarst lakes and poorly-drained wetland areas upon thawing permafrost along with microbial metabolic responses to higher temperatures) and increases in carbon dioxide emissions from well-drained areas. Besides changes in biogeochemistry, this threshold will also influence global energy dynamics through effects on surface albedo, evapotranspiration and water vapor. These changes would outweigh any increased uptake of carbon (e.g. from peatlands and higher plant photosynthesis) and would result in a strong, positive feedback to global climate warming.

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

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    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

  6. Nuclear Energy Plant Optimization (NEPO) final report on aging and condition monitoring of low-voltage cable materials.

    SciTech Connect (OSTI)

    Assink, Roger Alan; Gillen, Kenneth Todd; Bernstein, Robert

    2005-11-01

    This report summarizes results generated on a 5-year cable-aging program that constituted part of the Nuclear Energy Plant Optimization (NEPO) program, an effort cosponsored by the U. S. Department of Energy (DOE) and the Electric Power Research Institute (EPRI). The NEPO cable-aging effort concentrated on two important issues involving the development of better lifetime prediction methods as well as the development and testing of novel cable condition-monitoring (CM) techniques. To address improved life prediction methods, we first describe the use of time-temperature superposition principles, indicating how this approach improves the testing of the Arrhenius model by utilizing all of the experimentally generated data instead of a few selected and processed data points. Although reasonable superposition is often found, we show several cases where non-superposition is evident, a situation that violates the constant acceleration assumption normally used in accelerated aging studies. Long-term aging results over extended temperature ranges allow us to show that curvature in Arrhenius plots for elongation is a common occurrence. In all cases the curvature results in a lowering of the Arrhenius activation energy at lower temperatures implying that typical extrapolation of high temperature results over-estimates material lifetimes. The long-term results also allow us to test the significance of extrapolating through the crystalline melting point of semi-crystalline materials. By utilizing ultrasensitive oxygen consumption (UOC) measurements, we show that it is possible to probe the low temperature extrapolation region normally inaccessible to conventional accelerated aging studies. This allows the quantitative testing of the often-used Arrhenius extrapolation assumption. Such testing indicates that many materials again show evidence of ''downward'' curvature (E{sub a} values drop as the aging temperature is lowered) consistent with the limited elongation results and many literature results. It is also shown how the UOC approach allows the probing of temperatures that cross through the crystalline melting point region of semi-crystalline materials such as XLPO and EPR cable insulations. New results on combined environment aging of neoprene and hypalon cable jacketing materials are presented and offer additional evidence in support of our time-temperature-dose rate (t-T-DR) superposition approach that had been used successfully in the past for such situations.

  7. I COMPREHENSIVE RADIOLOGICAL SURVEY I

    Office of Legacy Management (LM)

    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

  8. ORISE: Radiological program assessment services

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

    Radiological program assessment services Minimizing the risk of human exposure to hazardous levels of radioactive materials requires designing a comprehensive safety program that...

  9. Overview of Radiological Dose

    Office of Environmental Management (EM)

    Upgrading RESRAD-RDD and Planning for Improvised Nuclear Device Incidents - The RESRAD-RDD&IND Charley Yu 1 , Carlos Corredor 2 , Jing-Jy Cheng 1 , Sunita Kamboj 1 , David LePoire 1 , and Paul Flood 1 1 Argonne National Laboratory, 2 U.S. Department of Energy July 16, 2014 HPS 59 th Annual Meeting, Baltimore, MD RESRAD-RDD Background  Computer model that runs on the .NET framework (4.0)  First released in 2004  Calculates operational guidelines for a radiological dispersal device

  10. Radiological Control Technician Training

    Energy Savers [EERE]

    _______ 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

  11. Radiological Control Technician Training

    Energy Savers [EERE]

    DOE-HDBK-1122-2009 (Revised 2013) Module 2.03 Counting Errors and Statistics Student's Material Course Title: Radiological Control Technician Module Title: Counting Errors and Statistics Module Number: 2.03 Objectives: (This document, Study Material, is referred to as Study Guide in the Program Management Guide) 2.03.01. Identify five general types of errors that can occur when analyzing radioactive samples, and describe the effect of each source of error on sample measurements. 2.03.02. State

  12. Radiological Control Technician Training

    Energy Savers [EERE]

    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

  13. For S Radiological

    Office of Legacy Management (LM)

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

  14. Smart Radiological Dosimeter

    DOE Patents [OSTI]

    Kosslow, William J.; Bandzuch, Gregory S.

    2004-07-20

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

  15. ORNL-5680 Radiological Surveys

    Office of Legacy Management (LM)

    DOVEV-0005/l (Supplement) ORNL-5680 Radiological Surveys of Properties in the Middlesex, New Jersey, Area R. W. Leggett D. L. Anderson F. F. Haywood D. J. Christian W. D. Cottrell R. W. Doane D. J. Crawford W. H. Shinpaugh E. B. Wagner T. E. Myrick W. A. Goldsmith 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: A07 Microfiche ,401 I I This

  16. Radiological Worker Computer Based Training

    Energy Science and Technology Software Center (OSTI)

    2003-02-06

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

  17. EA-1900: Final Environmental Assessment | Department of Energy

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

    900: Final Environmental Assessment EA-1900: Final Environmental Assessment Radiological Work and Storage Building at the Knolls Atomic Power Laboratory Kesselring Site, West Milton, New York This EA evaluates the potential environmental impacts of constructing and operating a new Radiological Work and Storage Building at the Knolls Atomic Power Laboratory Kesselring Site. A modernized radiological Work and Storage Building would streamline radioactive material handling and storage operations,

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

    Office of Scientific and Technical Information (OSTI)

    Sant'Andrea University Hospital, Interventional Radiology Unit (Italy) "Sacro Cuore" Catholic University, Radiology Department (Italy) Publication Date: 2013-11-06 OSTI Identifier: ...

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

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

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

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

    Office of Environmental Management (EM)

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

  1. Radiological Source Term Estimates for the February 14, 2014 WIPP Release

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

    Event | Department of Energy Radiological Source Term Estimates for the February 14, 2014 WIPP Release Event Radiological Source Term Estimates for the February 14, 2014 WIPP Release Event This document was used to determine facts and conditions during the Department of Energy Accident Investigation Board's investigation into the radiological release event at the Waste Isolation Pilot Plant. The Technical Assessment Team (TAT) has undertaken a deliberative investigation process to understand

  2. PIA - Radiological Work Permit | Department of Energy

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

    Radiological Work Permit PIA - Radiological Work Permit PIA - Radiological Work Permit PDF icon PIA - Radiological Work Permit More Documents & Publications PIA - Bonneville Power Adminstration Ethics Helpline Occupational Medical Surveillance System (OMSS) PIA, Idaho National Laboratory PIA - HSPD-12 Physical and Logical Access System

  3. Estimate Radiological Dose for Animals

    Energy Science and Technology Software Center (OSTI)

    1997-12-18

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

  4. Radiological cleanup of Enewetak Atoll

    SciTech Connect (OSTI)

    Not Available

    1981-01-01

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

  5. Radiological Control Manual. Revision 0, January 1993

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

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

  6. Radiological Protection for DOE Activities

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

    1995-09-29

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

  7. Radiological training for tritium facilities

    SciTech Connect (OSTI)

    1996-12-01

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

  8. ORISE: Radiological program assessment services

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

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

  9. LANL responds to radiological incident

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

    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

  10. Radiological Monitoring Continues at WIPP

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

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

  11. Radiological Dose Calculations for Fusion Facilities

    SciTech Connect (OSTI)

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

    2003-04-01

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

  12. Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado. Volume 2, Appendices D and E: Final report

    SciTech Connect (OSTI)

    Not Available

    1992-02-01

    This appendix assesses the present conditions and data gathered about the two inactive uranium mill tailings sites near Rifle, Colorado, and the designated disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions.

  13. Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Mexican Hat, Utah: Appendix D. Final report

    SciTech Connect (OSTI)

    1988-07-01

    This appendix is an assessment of the present conditions of the inactive uranium mill site near Mexican Hat, Utah. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan. Plan is to characterize the conditions at the mill and tailings site so that the Remedial Action Contractor may complete final designs of the remedial action.

  14. DOE standard: Radiological control

    SciTech Connect (OSTI)

    Not Available

    1999-07-01

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

  15. MINIMARS conceptual design: Final report

    SciTech Connect (OSTI)

    Lee, J.D.

    1986-09-01

    This volume contains the following sections: (1) fueling systems; (2) blanket; (3) alternative blanket concepts; (4) halo scraper/direct converter system study and final conceptual design; (5) heat-transport and power-conversion systems; (6) tritium systems; (7) minimars air detritiation system; (8) appropriate radiological safety design criteria; and (9) cost estimate. (MOW)

  16. Radiological control manual. Revision 1

    SciTech Connect (OSTI)

    Kloepping, R.

    1996-05-01

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

  17. DOE Issues Finding of No Significant Impact and Final Environmental

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

    Assessment on Radiological Response Training Range DOE Issues Finding of No Significant Impact and Final Environmental Assessment on Radiological Response Training Range October 14, 2010 Media contact: Tim Jackson (208) 526-8484 The U.S. Department of Energy has issued a Finding of No Significant Impact stemming from an environmental assessment it performed to examine the potential environmental impacts of operating a Radiological Response Training Range at Idaho National Laboratory. At the

  18. Memorandum, Reporting of Radiological Sealed Sources Transactions |

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

    Department of Energy Memorandum, Reporting of Radiological Sealed Sources Transactions Memorandum, Reporting of Radiological Sealed Sources Transactions December 16, 2010 The requirements for reporting transactions involving radiological sealed sources are identified in Department of Energy (DOE) Notice (N) 234.1, Reporting of Radioactive Sealed Sources. The data reported in accordance with DOE N 234.1 are maintained in the DOE Radiological Source Registry and Tracking (RSRT) database by the

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

    National Nuclear Security Administration (NNSA)

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

  20. International Data on Radiological Sources

    SciTech Connect (OSTI)

    Martha Finck; Margaret Goldberg

    2010-07-01

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

  1. Departmental Radiological Emergency Response Assets

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

    2007-06-27

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

  2. TEPP Training - Modular Emergency Response Radiological Transportation

    Energy Savers [EERE]

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

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

    Office of Environmental Management (EM)

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

  4. Radiological Control Training for Supervisors

    Energy Savers [EERE]

    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

  5. Understanding Mechanisms of Radiological Contamination

    SciTech Connect (OSTI)

    Rick Demmer; John Drake; Ryan James, PhD

    2014-03-01

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

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

    SciTech Connect (OSTI)

    Harpeneau, Evan M.

    2011-06-24

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

  7. Imperium/Lanzatech Syngas Fermentation Project - Biomass Gasification and Syngas Conditioning for Fermentation Evaluation: Cooperative Research and Development Final Report, CRADA Number CRD-12-474

    SciTech Connect (OSTI)

    Wilcox, E.

    2014-09-01

    LanzaTech and NREL will investigate the integration between biomass gasification and LanzaTech's proprietary gas fermentation process to produce ethanol and 2,3-butanediol. Using three feed materials (woody biomass, agricultural residue and herbaceous grass) NREL will produce syngas via steam indirect gasification and syngas conditioning over a range of process relevant operating conditions. The gasification temperature, steam-to-biomass ratio of the biomass feed into the gasifier, and several levels of syngas conditioning (based on temperature) will be varied to produce multiple syngas streams that will be fed directly to 10 liter seed fermenters operating with the Lanzatech organism. The NREL gasification system will then be integrated with LanzaTech's laboratory pilot unit to produce large-scale samples of ethanol and 2,3-butanediol for conversion to fuels and chemicals.

  8. ORISE: Radiological Assessment and Monitoring System (RAMS)

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

    Radiological Assessment and Monitoring System (RAMS) ORISE develops paperless tool to assist with data entry for radiological monitoring During the Empire 09 exercise, the Oak Ridge Institute for Science and Education tested for the first time a paperless system of data management to support the operations of the Federal Radiological Monitoring and Assessment Center. How ORISE is Making a Difference The paperless FRMAC provides tools that enables the FRMAC to collect and process field

  9. Radiological Contamination Control Training for Laboratory Research

    Energy Savers [EERE]

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

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

    Energy Savers [EERE]

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

  11. Progress Continues on Mitigation of Radiological Contamination

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

    August 13, 2015 Progress Continues on Mitigation of Radiological Contamination This week, WIPP personnel will complete the installation of the brattice cloth and salt barrier on a...

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

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

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

  13. Radiological Assistance Program Flight Planning Tool

    Energy Science and Technology Software Center (OSTI)

    2011-12-19

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

  14. Radiological Assistance Program Flight Planning Tool

    SciTech Connect (OSTI)

    2011-12-19

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

  15. Radiological Contamination Control Training for Laboratory Research

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

    ... workers attending training programs unsuitable for their needs. Prerequisites A background and foundation of knowledge ... radiological work and informing the worker of the ...

  16. Radiological Contamination Control Training for Laboratory Research

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

    ... the skills and knowledge needed to assist ... of tools, equipment, or workers. 2. Not wearing gloves, or ... radiological work and informing the worker of the ...

  17. Radiological Contamination Control Training for Laboratory Research

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

    ... of tools, equipment, or workers. 2. Not wearing gloves, or ... radiological work and informing the worker of the ... special survey techniques or by review of process knowledge. ...

  18. radiological. survey | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

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

  19. Environmental/Radiological Assistance Directory (ERAD) | Department...

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

    practices, emerging trends, compliance issues, etc. in support of radiological ... of Real and Personal Property RESRAD Family of Codes Knowledge Information Management ...

  20. NEVADA TEST SITE RADIOLOGICAL CONTROL MANUAL

    Office of Scientific and Technical Information (OSTI)

    ... are based on dose coefficients from International Commission on Radiological Protec- ... dose is: BS Bone surface, ET Extrathoracic, K Kidney, L Liver, and T Thyroid. ...

  1. Radiological Training for Accelerator Facilities

    Energy Savers [EERE]

    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

  2. Performance evaluation of Automatic Extraction System. Volume V. Geotechnical investigations of the roof conditions in the area mined by the AES machine. Final technical report

    SciTech Connect (OSTI)

    Bieniawski, Z.T.; Rafia, F.; Newman, D.A.

    1980-07-01

    This report presents the results of an in-depth geotechnical investigation aimed at assessing the roof, floor, and coal pillar conditions in the area mined by an experimental Automatic Extraction System (AES), built by National Mine Service Co. The study included diamond core drilling, borescope observations, and detailed engineering geological mapping in Consolidation Coal's McElroy coal mine in West Virginia. The field investigations were accompanied by regional geology studies involving aerial photography and lineament analysis as well as by laboratory testing of 103 rock and coal samples. The roof conditions were interpreted by means of an engineering rock mass classification system, known as the Geomechanics Classification. It was found that the roof quality in the areas mined by the AES machine was poor and that the action of the AES support beams could be detrimental to the overall roof stability. Improvements in the procedures for evaluating future AES-type mining are suggested.

  3. Surface coal mining in Alaska: an investigation of the Surface Mining Control and Reclamation Act of 1977 in relation to Alaskan conditions. Final report

    SciTech Connect (OSTI)

    Not Available

    1980-01-01

    This report was written in response to a mandate in section 708 of the Surface Mining Control and Reclamation Act of 1977 which required the study of surface coal mining conditions in the State of Alaska, in order to determine which, if any, of the provisions of the Act should be modified with respect to surface coal mining operations in Alaska. The report discusses both surface mining and the surface effects of underground mining. The report examines not only the impact of mining at the site of operations but also the effects that extend beyond the mine itself, including effects on social institutions, the economy, the physical well-being of people, and the use of land. The report considers Alaska conditions primarily from the perspective of a potential increase in coal development, not of mining limited to meeting local needs of energy.

  4. Evaluation of Water Quality Conditions Near Proposed Fish Production Sites Associated with the Yakima Fisheries Project, 1991-1993 Final Report.

    SciTech Connect (OSTI)

    Dauble, Dennis D.

    1994-05-01

    In 1991, the Pacific Northwest Laboratory (PNL) began studying water quality at several sites in the Yakima River Basin for the Bonneville Power Administration. These sites were being proposed as locations for fish culture facilities as part of the Yakima Fisheries Project (YFP). Surface water quality parameters near the proposed fish culture facilities are currently suitable for fish production. Water quality conditions in the mainstream Yakima River and its tributaries are generally excellent in the upper part of the watershed (i.e., near Cle Elum), but they are only fair to poor for the river downstream of Union Gap (river mile 107). Water quality of the Naches River near Oak Flats is also suitable for fish production. Groundwater supplies near the proposed fish production facilities typically have elevated concentrations of metals and dissolved gases. These conditions can be mitigated using best engineering practices such as precipitation and degasification. Additionally, mixing with surface water may improve these conditions. Depending on the location and depth of the well, groundwater temperatures may be warmer than optimum for acclimating and holding juvenile and adult fish. Water quality parameters measured in the Yakima River and tributaries sometimes exceed the range of values described as acceptable for culture of salmonids and for the protection of other aquatic life. However, constituent concentrations are within ranges that exist in many northwest fish hatcheries. Additionally, site-specific tests conducted by PNL (i.e., live box exposures and egg incubation studies) indicate that fish can be successfully reared in surface and well water near the proposed facility sites. Thus, there appear to be no constraints to artificial production for the YFP.

  5. Federal Radiological Monitoring and Assessment Center

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

    1992-12-02

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

  6. INL@Work Radiological Search & Response Training

    ScienceCinema (OSTI)

    Turnage, Jennifer

    2013-05-28

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

  7. Nevada Test Site Radiological Control Manual

    SciTech Connect (OSTI)

    Radiological Control Managers' Council - Nevada Test Site

    2009-10-01

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

  8. INL@Work Radiological Search & Response Training

    SciTech Connect (OSTI)

    Turnage, Jennifer

    2010-01-01

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

  9. Nevada Test Site Radiological Control Manual

    SciTech Connect (OSTI)

    Radiological Control Managers' Council Nevada Test Site

    2010-02-09

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

  10. Memorandum, Reporting of Radiological Sealed Sources Transactions

    Broader source: Energy.gov [DOE]

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

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

    Open Energy Info (EERE)

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

  12. Fifth Anniversary of Radiological Alarm Response Training for...

    National Nuclear Security Administration (NNSA)

    nuclear or radiological materials. Fifth Anniversary of Radiological Alarm Response Training The three-day course is held at NNSA's Y-12 National Security Complex in Oak...

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

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

    Los Alamos National Security Corrective Action Plan - Radiological Release Phase II Los Alamos National Security Corrective Action Plan - Radiological Release Phase II Los Alamos ...

  14. Radiological Source Term Estimates for the February 14, 2014...

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

    Radiological Source Term Estimates for the February 14, 2014 WIPP Release Event Radiological Source Term Estimates for the February 14, 2014 WIPP Release Event This document was...

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

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

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

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

    Office of Environmental Management (EM)

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

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

    Office of Environmental Management (EM)

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

  18. Final predictions of ambient conditions along the east-west crossdrift using the 3-D UZ site-scale model. Level 4 milestoneSP33ABM4.

    SciTech Connect (OSTI)

    Ritcey, A.C.; Sonnenthal, E.L.; Wu, Y.S.; Haukwa, C.; Bodvarsson,G.S.

    1998-03-01

    In 1998, the Yucca Mountain Site Characterization Project (YMP) is expected to continue construction of an East-West Cross Drift. The 5-meter diameter drift will extend from the North Ramp of the Exploratory Studies Facility (ESF), near Station 19+92, southwest through the repository block, and over to and through the Solitario Canyon Fault. This drift is part of a program designed to enhance characterization of Yucca Mountain and to complement existing surface-based and ESF testing studies. The objective of this milestone is to use the three-dimensional (3-D) unsaturated zone (UZ) site-scale model to predict ambient conditions along the East-West Cross Drift. These predictions provide scientists and engineers with a priori information that can support design and construction of the East-West Cross Drift and associated testing program. The predictions also provide, when compared with data collected after drift construction, an opportunity to test and verify the calibration of the 3-D UZ site-scale model.

  19. Technical Assessment Team Issues Final Report

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

    , 2015 Technical Assessment Team Issues Final Report This week the Department of Energy's Technical Assessment Team (TAT) visited Carlsbad and met with federal and contractor staff at WIPP and the Mayor's Nuclear Task Force to provide a briefing and answer questions on their final report that was released on March 26 th . The TAT, which was established shortly after the February 14, 2014 radiological release that occurred in the WIPP underground, was led by the Savannah River National Laboratory

  20. 2012 Environmental/Radiological Assistance Directory (ERAD) Presentations |

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

    Department of Energy 2 Environmental/Radiological Assistance Directory (ERAD) Presentations » 2012 Environmental/Radiological Assistance Directory (ERAD) Presentations 2012 Environmental/Radiological Assistance Directory (ERAD) Presentations 2012 Environmental/Radiological Assistance Directory (ERAD) Presentations PDF icon November 2012; Environmental Measurements in an Emergency: This is not a Drill!; Stephen V. Musolino; Brookhaven National Laboratory PDF icon November 2012; Brookhaven

  1. DOE Issues WIPP Radiological Release Investigation Report

    Broader source: Energy.gov [DOE]

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

  2. Radiological safety training for uranium facilities

    SciTech Connect (OSTI)

    1998-02-01

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

  3. Apparatus for safeguarding a radiological source

    DOE Patents [OSTI]

    Bzorgi, Fariborz M

    2014-10-07

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

  4. Contained radiological analytical chemistry module

    DOE Patents [OSTI]

    Barney, David M. (Scotia, NY)

    1990-01-01

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

  5. Contained radiological analytical chemistry module

    DOE Patents [OSTI]

    Barney, David M. (Scotia, NY)

    1989-01-01

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

  6. Radiological Primer Common Understanding of Terms

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

    Radiological Primer Understanding Radiological Terms Richard Bloom and Dr. Antone Brooks Health Safety Environmental Protection Committee Hanford Advisory Board Tom Rogers and Crystal Mathey Washington State Department of Health Radioactivity vs. Radiation  What is radioactivity?  Property exhibited by certain types of matter of emitting radiation spontaneously.  What is radiation?  Process by which energy is emitted from a source  Forms of ionizing radiation  Gamma (photons)

  7. Flashback: Rapid scanning for radiological threats

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

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

  8. Radiological Safety Training for Accelerator Facilities

    Energy Savers [EERE]

    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

  9. Remedial action plan and site conceptual design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado. Appendix D, Final report

    SciTech Connect (OSTI)

    1992-02-01

    This appendix assesses the present conditions and data gathered about the two designated inactive uranium mill tailings sites near Rifle, Colorado, and the proposed disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions.

  10. PRE-HOSPITAL PRACTICES FOR HANDLING A RADIOLOGICALLY CONTAMINATED PATIENT

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    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

  12. Final Report

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

    Final Report Document Number 11123-23.Final Field Demonstration of Eco-Friendly Creation of Propped Hydraulic Fractures Contract Number: 11123-23.Final February 16, 2015 Nadji Benrabah (Author) Engineer CSI Technologies 1930 W.W. Thorne Dr. Houston, TX 77073 Phil Van Trump (Principal Investigator) Chief Technology Officer DaniMer Scientific, LLC 1301 Colquitt Highway Bainbridge, GA 39817 2 LEGAL NOTICE This report was prepared by DaniMer Scientific, LLC as an account of work sponsored by the

  13. Final Report

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

    Simulation Software A simple fracture treatment design model was programed using Excel VBA. The goal was to estimate the pumping schedule and final conductivity of a fracture...

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

    SciTech Connect (OSTI)

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

    2008-07-01

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

  15. FINAL RELEASE

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

    RELEASE AWARDEE: ____________________________________________________ The work under Award No. DE-__________________________, dated ______________, between the United States of America (represented by the Department of Energy, National Energy Technology Laboratory, and the undersigned awardee, having been completed and finally accepted , and in consideration of Final Payment thereunder, the United States of America, its officers, agents and employees are hereby released from all liabilities,

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

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    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

  18. Emergency Response Planning for Radiological Releases

    SciTech Connect (OSTI)

    Biwer, B.M.; LePoire, D.J.; Lazaro, M.A.; Allison, T.; Kamboj, S.; Chen, S.Y.

    2006-07-01

    The emergency management planning tool RISK-RDD was developed to aid emergency response planners and decision makers at all levels of government to better understand and prepare for potential problems related to a radiological release, especially those in urban areas. Radioactive release scenarios were studied by using the RISK-RDD radiological emergency management program. The scenarios were selected to investigate the key aspects of radiological risk management not always considered in emergency planning as a whole. These aspects include the evaluation of both aerosolized and non-aerosolized components of an atmospheric release, methods of release, acute and chronic human health risks, and the concomitant economic impacts as a function of the risk-based cleanup level. (authors)

  19. NSTP 2002-2 Methodology for Final Hazard Categorization for Nuclear

    Office of Environmental Management (EM)

    Facilities from Category 3 to Radiological (11/13/02). | Department of Energy NSTP 2002-2 Methodology for Final Hazard Categorization for Nuclear Facilities from Category 3 to Radiological (11/13/02). NSTP 2002-2 Methodology for Final Hazard Categorization for Nuclear Facilities from Category 3 to Radiological (11/13/02). 0 CFR 830 Subpart B requires that all DOE nuclear facilities categorized as HC-3 or above have a DOE approved safety basis compliant with the requirements of Subpart B. The

  20. OAK RIDGE NATIONAL LABORATORY RESULTS OF RADIOLOGICAL

    Office of Legacy Management (LM)

    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

  1. Final Report

    SciTech Connect (OSTI)

    Biros, George

    2014-08-18

    This the final report for the project "Large-Scale Optimization for Bayesian Inference in Complex Systems," for the work in the group of the co-PI George Biros.

  2. Final Report

    SciTech Connect (OSTI)

    Gurney, Kevin R

    2015-01-12

    This document constitutes the final report under DOE grant DE-FG-08ER64649. The organization of this document is as follows: first, I will review the original scope of the proposed research. Second, I will present the current draft of a paper nearing submission to Nature Climate Change on the initial results of this funded effort. Finally, I will present the last phase of the research under this grant which has supported a Ph.D. student. To that end, I will present the graduate student’s proposed research, a portion of which is completed and reflected in the paper nearing submission. This final work phase will be completed in the next 12 months. This final workphase will likely result in 1-2 additional publications and we consider the results (as exemplified by the current paper) high quality. The continuing results will acknowledge the funding provided by DOE grant DE-FG-08ER64649.

  3. Final Report

    SciTech Connect (OSTI)

    DeTar, Carleton

    2012-12-10

    This document constitutes the Final Report for award DE-FC02-06ER41446 as required by the Office of Science. It summarizes accomplishments and provides copies of scientific publications with significant contribution from this award.

  4. Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant

    Office of Energy Efficiency and Renewable Energy (EERE)

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

  5. 2013 Environmental/Radiological Assistance Directory (ERAD) Presentations |

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

    Department of Energy 3 Environmental/Radiological Assistance Directory (ERAD) Presentations » 2013 Environmental/Radiological Assistance Directory (ERAD) Presentations 2013 Environmental/Radiological Assistance Directory (ERAD) Presentations Below are the presentations presented during the 2013 Environmental/Radiological Assistance Directory (ERAD) meetings PDF icon Nov 2013 Derived Intervention and Response Levels for Tritium Oxide at the Savannah River Site; Tim Janik, Savannah River Site

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

    Energy Savers [EERE]

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

  7. ORISE: Radiological Terrorism Toolkit | How ORISE is Making a Difference

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

    Radiological Terrorism Toolkit ORISE partners with CDC to develop Radiological Terrorism: A Toolkit for Public Health Officials Radiological Terrorism: A Toolkit for Public Health Officials How ORISE is Making a Difference Working closely with the Centers for Disease Control and Prevention (CDC), the Oak Ridge Institute for Science and Education (ORISE) distributed more than 400 radiological terrorism toolkits filled with key resources, such as training guidelines, clinical directives, details

  8. Accident Investigation Report - Radiological Release | Department of Energy

    Energy Savers [EERE]

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

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

    Office of Environmental Management (EM)

    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)

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

    Office of Environmental Management (EM)

    6.1 DOE-HDBK-1141-2001 Overhead 6.1 Radiological Aspects of Uranium Objectives: * Identify the radiological properties of uranium. * Describe the toxicological properties and behavior of uranium. * Identify appropriate instrumentation, measurement techniques, and special radiological survey methods for uranium. OT 6.2 DOE-HDBK-1141-2001 Overhead 6.2 Radiological Aspects of Uranium (cont.) Objectives: * Describe personnel protection requirements, external dose control techniques, and internal

  11. Radiological/biological/aerosol removal system

    DOE Patents [OSTI]

    Haslam, Jeffery J

    2015-03-17

    An air filter replacement system for existing buildings, vehicles, arenas, and other enclosed airspaces includes a replacement air filter for replacing a standard air filter. The replacement air filter has dimensions and air flow specifications that allow it to replace the standard air filter. The replacement air filter includes a filter material that removes radiological or biological or aerosol particles.

  12. Nuclear / Radiological Advisory Team | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration / Radiological Advisory Team | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our

  13. Environmental Radiological Effluent Monitoring and Environmental Surveillance

    Office of Environmental Management (EM)

    Environmental Radiological Effluent Monitoring and Environmental Surveillance U.S. Department of Energy AREA ENVR Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1216-2015 NOT MEASUREMENT SENSITIVE INTENTIONALLY BLANK DOE-HDBK-1216-2015 iii TABLE OF CONTENTS PARAGRAPH PAGE 1 INTRODUCTION ............................................................................................................... 1 1.1 Objectives

  14. Paint for detection of radiological or chemical agents

    DOE Patents [OSTI]

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

    2010-08-24

    A paint that warns of radiological or chemical substances comprising a paint operatively connected to the surface, an indicator material carried by the paint that provides an indication of the radiological or chemical substances, and a thermo-activation material carried by the paint. In one embodiment, a method of warning of radiological or chemical substances comprising the steps of painting a surface with an indicator material, and monitoring the surface for indications of the radiological or chemical substances. In another embodiment, a paint is operatively connected to a vehicle and an indicator material is carried by the paint that provides an indication of the radiological or chemical substances.

  15. Project RU LlSON COPY ON-SITE RADIOLOGICAL PROGRAMS DURING REENTRY DISILLING THROUGH PRODUCTION TESTING

    Office of Legacy Management (LM)

    RU LlSON COPY ON-SITE RADIOLOGICAL PROGRAMS DURING REENTRY DISILLING THROUGH PRODUCTION TESTING FINAL REPOAT EBERLlNE INSTRUMENT CORPORATION Santa Fe, New Mexico Date Published - December 1973 PREPARED FOR THE U. S. ATOMIC ENERGY COMMISSION N E V A D A OPERATIONS OFFICE UNDER CONTRACT NO. AT(26-11-294 DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. Project RULISON ON-S1l'E RADIOLOGICAL PROGRAMS D U

  16. NV/YMP RADIOLOGICAL CONTROL MANUAL

    SciTech Connect (OSTI)

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

    2004-11-01

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

  17. Nevada National Security Site Radiological Control Manual

    SciTech Connect (OSTI)

    Radiological Control Managers’ Council

    2012-03-26

    This document supersedes DOE/NV/25946--801, 'Nevada Test Site Radiological Control Manual,' Revision 1 issued in February 2010. Brief Description of Revision: A complete revision to reflect a recent change in name for the NTS; changes in name for some tenant organizations; and to update references to current DOE policies, orders, and guidance documents. Article 237.2 was deleted. Appendix 3B was updated. Article 411.2 was modified. Article 422 was re-written to reflect the wording of DOE O 458.1. Article 431.6.d was modified. The glossary was updated. This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE) and the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection.' Programs covered by this manual are located at the Nevada National Security Site (NNSS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Livermore, California; and Andrews Air Force Base, Maryland. In addition, fieldwork by NNSA/NSO at other locations is covered by this manual. Current activities at NNSS include operating low-level radioactive and mixed waste disposal facilities for United States defense-generated waste, assembly and execution of subcritical experiments, assembly/disassembly of special experiments, the storage and use of special nuclear materials, performing criticality experiments, emergency responder training, surface cleanup and site characterization of contaminated land areas, environmental activity by the University system, and nonnuclear test operations, such as controlled spills of hazardous materials at the Hazardous Materials Spill Center. Currently, the major potential for occupational radiation exposure is associated with the burial of low-level radioactive waste and the handling of radioactive sources. Remediation of contaminated land areas may also result in radiological exposures.

  18. Radiological Contamination Control Training for Laboratory Research

    Energy Savers [EERE]

    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,

  19. Radiological Contamination Control Training for Laboratory Research

    Energy Savers [EERE]

    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)

  20. Radiological Safety Training for Plutonium Facilities

    Energy Savers [EERE]

    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

  1. Fixation of Radiological Contamination; International Collaborative Development

    SciTech Connect (OSTI)

    Rick Demmer

    2013-03-01

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

  2. FINAL REPORT

    Office of Scientific and Technical Information (OSTI)

    FINAL REPORT Analytical and Elemental Analysis of Air and Soil Samples Facility and Public Awareness Partnership (Training/Public Awareness) Congressionally Awarded Grant No. DE-FG02-05ER64045 Submitted to: U.S. Department of Energy Attn: William Henson Submitted by: Alabama A&M University Research Institute (AAMURI) [pic] October 1, 2007 This report reflects a joint training program at the Integrated Environmental Research and Services (IERS) of the Alabama A&M University Research

  3. Final Report

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

    Cyber Security for Utility Operations NETL Project M63SNL34 Sponsored by the U.S. DOE Office of Energy Assurance Managed by NETL Final Report Period of Performance October, 2003 - April, 2005 Dennis Holstein and John Tengdin, OPUS Publishing Jay Wack and Roger Butler, TecSec, Inc. Timothy Draelos, Sandia National Laboratories 1 Paul Blomgren, SafeNet/Mykotronx April 18, 2005 1 Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States

  4. EA-1345: Final Environmental Assessment | Department of Energy

    Office of Environmental Management (EM)

    5: Final Environmental Assessment EA-1345: Final Environmental Assessment Cleanup and Closure of the Energy Technology Engineering Center, Oakland, California DOE will use this EA, and other relevant information, to determine (1) if the current cleanup standard for the radiological cleanup of ETEC facilities and all Area IV land for which DOE is responsible is appropriate for the remaining activity, and (2) whether to decontaminate and decommission the remaining sodium facility and other support

  5. Final Report

    SciTech Connect (OSTI)

    R Paul Drake

    2004-01-12

    OAK-B135 This is the final report from the project Hydrodynamics by High-Energy-Density Plasma Flow and Hydrodynamics and Radiation Hydrodynamics with Astrophysical Applications. This project supported a group at the University of Michigan in the invention, design, performance, and analysis of experiments using high-energy-density research facilities. The experiments explored compressible nonlinear hydrodynamics, in particular at decelerating interfaces, and the radiation hydrodynamics of strong shock waves. It has application to supernovae, astrophysical jets, shock-cloud interactions, and radiative shock waves.

  6. Liquid Effluent Retention Facility (LERF) Final Hazard Category Determination

    SciTech Connect (OSTI)

    HUTH, L.L.

    2001-06-06

    The Liquid Effluent Retention Facility was designed to store 242-A Evaporator process condensate and other liquid waste streams for treatment at the 200 East Area Effluent Treatment Facility. The Liquid Effluent Retention Facility has been previously classified as a Category 3 Nonreactor Nuclear Facility. As defined in Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports (DOE 1992, DOE 1997), Category 3 Nuclear Facilities have the potential for significant localized (radiological) consequences. However, based on current facility design, operations, and radioactive constituent concentrations, the Liquid Effluent Retention Facility does not have the potential for significant localized (radiological) consequences and is categorized as a Radiological Facility. This report documents the final hazard categorization process performed in accordance with DOE Order 5480.23, Nuclear Safety Analysis Reports. This report describes the current configuration and operations of the Liquid Effluent Retention Facility. Also included is a preliminary hazard categorization, which is based on current and proposed radioactive and hazardous material inventories, a preliminary hazards and accident analysis, and a final hazard category determination. The results of the hazards and accident analysis, based on the current configuration and operations of the Liquid Effluent Retention Facility and the current and proposed radioactive and hazardous material inventories, demonstrate that the Liquid Effluent Retention Facility does not have the potential for significant localized (radiological) consequences. Based on the final hazard category analysis, the Liquid Effluent Retention Facility is a Radiological Facility. The final hazard category determination is based on a comparative evaluation of the consequence basis for the Category 3 threshold quantities to the calculated consequences for credible releases The basis for the Category 3 threshold quantities is 10 rem-equivalent man at 30 meters (98 feet) (DOE 1992, DOE 1997). The calculated 12 hour consequences to an individual located at 30 meters (98 feet) for two credible scenarios, spray release and a pool release, are 3.50 rem and 1.32 rem, respectively, which based upon the original hazard categorization criteria (DOE 1992) classified the Liquid Effluent Retention Facility as a Radiological Facility. Comparison of the calculated 24 hour consequences to an individual located at 30 meters (98 feet) for two credible scenarios, spray release and a pool release, 7.00 rem and 2.64 rem respectively, confirmed the Liquid Effluent Retention Facility classification as a Radiological Facility under the current hazard categorization criteria (DOE 1997). Both result in dose consequence values less than the allowable, 10 rem, meeting the requirements for categorizing the Liquid Effluent Retention Facility as a Radiological Facility.

  7. Microsoft Word - Final Report

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

    7 Assessment of the Performance of COBRA-TF for the Prediction of Subcooled Boiling Conditions in Rod Bundles Dr. J. Michael Doster NCSU September 30, 2013 CASL-8-2013-0201-000 Final Report L3.THM.CFD.P7.07 Dr. J. Michael Doster Nuclear Engineering Department North Carolina State University Assessment of the Performance of COBRA-TF for the Prediction of Subcooled Boiling Conditions in Rod Bundles September 30, 2013 CASL-U-2013-0201-000 INTRODUCTION An assessment has been performed of the

  8. MODARIA: Modelling and Data for Radiological Impact Assessment Context and

    Office of Environmental Management (EM)

    Overview | Department of Energy MODARIA: Modelling and Data for Radiological Impact Assessment Context and Overview MODARIA: Modelling and Data for Radiological Impact Assessment Context and Overview Presentation from the 2015 Annual Performance and Risk Assessment (P&RA) Community of Practice (CoP) Technical Exchange Meeting held in Richland, Washington on December 15-16, 2015. PDF icon MODARIA: Modelling and Data for Radiological Impact Assessment Context and Overview More Documents

  9. Anniversary of Fire, Radiological Events Marks Major Progress at WIPP

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

    February 12, 2016 Anniversary of Fire, Radiological Events Marks Major Progress at WIPP February 2016 marks two years since the underground fire and radiological release events forced the temporary closure of the Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP), near Carlsbad, New Mexico. Since that time much progress has been made in the recovery of the underground including mine stability and habitability, initial panel closure, radiological risk remediation and the addition of

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

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

    Complex ... Nuclear and Radiological Field Training Center A site used for nuclear research in Oak Ridge, Tennessee during the Manhattan Project is now the Y-12 National Security Complex's Nuclear and Radiological Field Training Center - the only facility of its kind in the world. The Center provides world-class nuclear and radiological training in a safe, secure, realistic environment using expert instruction and personnel to serve as observers/evaluators for customer training. For military

  11. 2012 Environmental/Radiological Assistance Directory (ERAD) Presentations |

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

    Department of Energy Environmental/Radiological Assistance Directory (ERAD) Presentations 2012 Environmental/Radiological Assistance Directory (ERAD) Presentations 2012 Environmental/Radiological Assistance Directory (ERAD) Presentations PDF icon November 2012; Environmental Measurements in an Emergency: This is not a Drill!; Stephen V. Musolino; Brookhaven National Laboratory PDF icon November 2012; Brookhaven Graphite Research Reactor (BGRR) D&D Presentation for the DOE ERAD Working

  12. Environmental/Radiological Assistance Directory (ERAD) | Department of

    Energy Savers [EERE]

    Energy Environmental/Radiological Assistance Directory (ERAD) Environmental/Radiological Assistance Directory (ERAD) The Environmental Radiological Assistance Directory or ERAD, developed by AU-22, serves as an assistance tool to the DOE complex for protection of the public and environment from radiation. The ERAD is a combination webinar/conference call, designed to provide DOE and its contractors a forum to share information, lessons-learned, best practices, emerging trends, compliance

  13. Operational Guidelines/Radiological Emergency Response | Department of

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

    Energy Operational Guidelines/Radiological Emergency Response Operational Guidelines/Radiological Emergency Response This page provides information and resources concerning the development of operational guidelines as part of planning guidance for protection and recovery following Radiological Dispersal Device (RDD) and/or Improvised Nuclear Device (IND) incidents. Operational Guidelines Technical (OGT) Manual, 2009 RESRAD-RDD Complementing Software to OGT Manual EPA Protective Action

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

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

    Department of Energy 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

  15. Surface Contamination Guidelines/Radiological Clearance of Property |

    Energy Savers [EERE]

    Department of Energy Surface Contamination Guidelines/Radiological Clearance of Property Surface Contamination Guidelines/Radiological Clearance of Property Authorized limits govern the control and clearance of personal and real property. They are radionuclide concentrations or activity levels approved by DOE to permit the clearance of property from DOE radiological control for either restricted or unrestricted use, consistent with DOE's radiation protection framework and standards for the

  16. Recent Developments in Field Response for Mitigation of Radiological

    Energy Savers [EERE]

    Incidents | Department of Energy Developments in Field Response for Mitigation of Radiological Incidents Recent Developments in Field Response for Mitigation of Radiological Incidents Carlos Corredor*, Department of Energy; Charley Yu, Argonne National Labs Abstract: Since September 11, 2001, there has been a large effort by the government to develop new methods to reduce the consequence of potential radiological incidents. This is evident in the enhancement of technologies and methods to

  17. Accident Investigations of the February 14, 2014, Radiological Release at

    Energy Savers [EERE]

    the Waste Isolation Pilot Plant, Carlsbad, NM | Department of Energy Accident Investigations of the February 14, 2014, Radiological Release at the Waste Isolation Pilot Plant, Carlsbad, NM Accident Investigations of the February 14, 2014, Radiological Release at the Waste Isolation Pilot Plant, Carlsbad, NM February 14, 2014 Accident Investigations of the February 14, 2014, Radiological Release at the Waste Isolation Pilot Plant, Carlsbad, NM On February 14, 2014, at approximately 2314

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

    Office of Environmental Management (EM)

    9 Radiological Control Technician Training Fundamental Academic Training Instructor's Guide Phase I Coordinated and Conducted for Office of Environment, Safety & Health U.S. Department of Energy DOE-HDBK-1122-99 Radiological Control Technician Instructor's Guide ii This page intentionally left blank. DOE-HDBK-1122-99 Radiological Control Technician Instructor's Guide iii Course Developers William Egbert Lawrence Livermore National Laboratory Dave Lent Coleman Research Michael McNaughton Los

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

    Office of Environmental Management (EM)

    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)

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

    Office of Environmental Management (EM)

    9 Radiological Control Technician Training Fundamental Academic Training Study Guide Phase I Coordinated and Conducted for Office of Environment, Safety & Health U.S. Department of Energy DOE-HDBK-1122-99 Radiological Control Technician Study Guide ii This page intentionally left blank. DOE-HDBK-1122-99 Radiological Control Technician Study Guide iii Course Developers William Egbert Lawrence Livermore National Laboratory Dave Lent Coleman Research Michael McNaughton Los Alamos National

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

    Office of Environmental Management (EM)

    6 of 9 Radiological Control Technician Training Site Academic Training Study Guide Phase I Coordinated and Conducted for Office of Environment, Safety & Health U.S. Department of Energy DOE-HDBK-1122-99 Radiological Control Technician Study Guide ii This page intentionally left blank. DOE-HDBK-1122-99 Radiological Control Technician Study Guide iii Course Developers William Egbert Lawrence Livermore National Laboratory Dave Lent Coleman Research Michael McNaughton Los Alamos National

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

    Office of Environmental Management (EM)

    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.

  3. FINAL AGENDA

    Office of Environmental Management (EM)

    FINAL AGENDA 1 U.S. DEPARTMENT OF ENERGY TRANSPORTATION EXTERNAL COORDINATION WORKING GROUP (TEC) APRIL 4-5, 2005 PHOENIX, ARIZONA MONDAY, APRIL 4, 2005 7:30 a.m. - 5:00 p.m. General Registration 7:30 a.m. - 8:00 a.m. Continental Breakfast 8:00 a.m. - 10:00 am. Tribal Topic Group - Lead: Jay Jones, DOE/RW 10:00 a.m. - 10:30 a.m. Break 10:30 a.m. - 11:00 a.m. Welcome and Meeting Overview Introduction, Meeting Overview - Judith Holm, Director, DOE/RW, Operations Development Division, Office of

  4. DOE Issues WIPP Radiological Release Phase II Investigation Report...

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

    radiological event at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. ... second from left, receives the New Mexico Patriotic Employer Award from the N.M. ...

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

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

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

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

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

    Jan 1, 2009 The National Nuclear Security Administration (NNSA) has more than 60 years of nuclear weapons experience in responding to nuclear and radiological accidents and...

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

    National Nuclear Security Administration (NNSA)

    Dec 1, 2008 The National Nuclear Security Administration (NNSA) has over 60 years of nuclear weapons experience in responding to nuclear and radiological accidents and incidents....

  8. An Assessment Of The External Radiological Impact In Areas Of...

    Open Energy Info (EERE)

    Assessment Of The External Radiological Impact In Areas Of Greece With Elevated Natural Radioactivity Jump to: navigation, search OpenEI Reference LibraryAdd to library Journal...

  9. ORISE: Radiological Terrorism Toolkit | How ORISE is Making a...

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

    Education (ORISE) distributed more than 400 radiological terrorism toolkits filled with key resources, such as training guidelines, clinical directives, details about radioactive...

  10. Radiological Release Event at the Waste Isolation Pilot Plant...

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

    radiological release occurred at the Department of Energy Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. Because access to the underground was restricted following...

  11. The New Radiological and Environmental Sciences Laboratory (RESL...

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

    None File Format: Microsoft Windows WMV File Size: 19 Kb Video of Radiological and Environmental Sciences Laboratory (RESL) Editorial Date December 7, 2011 By Danielle Miller...

  12. Handling and Packaging a Potentially Radiologically Contaminated Patient

    Broader source: Energy.gov [DOE]

    The purpose of this procedure is to provide guidance to EMS care providers for properly handling and packaging potentially radiologically contaminated patients.

  13. Radiological Control Programs for Special Tritium Compounds

    Energy Savers [EERE]

    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

  14. Radiological Control Programs for Special Tritium Compounds

    Energy Savers [EERE]

    DOE.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

  15. Radiological Safety Training for Plutonium Facilities

    Energy Savers [EERE]

    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

  16. Lessons Learned from Raw Treatment in the Slovak Republic - Minimization for Final Disposal

    SciTech Connect (OSTI)

    Hanusik, V.; Hladky, E.; Krajc, T.; Pekar, A.; Stubna, M.; Urbanec, M. [Milan Zatkulak, VUJE, a.s., Trnava (Slovakia); Ehn, L.; Kover, M.; Remias, V.; Slezak, M. [JAVYS, a.s., Bohunice (Slovakia)

    2008-07-01

    This paper is referring about the utilization of technologies for the treatment and conditioning of low and intermediate level RAW from operation and decommissioning of nuclear facilities in Slovakia. This experience represents more than 116 reactor years of NPP operation, mainly of NPPs equipped with VVER 440 reactors, 30 years of decommissioning activities, 27 years of development and operation of technologies for the treatment and conditioning of RAW and 7 years of LLW and ILW final repository operation. These technologies are located in two localities: Jaslovske Bohunice and Mochovce. The complex treatment and conditioning center (cementation, bituminization, incineration, vitrification, fragmentation and compacting) for almost all types of radioactive waste is located in Jaslovske Bohunice NPP site. The treatment and conditioning center for liquid radioactive waste (cementation and bituminization) and the surface type repository for LLW and ILW final disposal are located in Mochovce area. The treated waste forms are disposed to repository in cubical Fiber Reinforced Concrete (FRC) containers. The experience from the phase of technology development and the phase of technology modifications for various types of RAW, the experience from long term operation of technologies and the experience from transportation of original and packed wastes are described in this paper. The method of optimally combined technology utilization in order to maximize the radionuclide inventory at the same time with respect of disposal safety limitations of repository is described, too. The significant RAW volume reduction for final disposal was achieved through mediation of the combination of treatment and conditioning technologies. The disposal of treated RAW in cubic FRC containers allowed the optimal utilization of volume and radiological capacity of LLW and ILW repository in Mochovce and the fulfillment of determined safety requirements at the same time. (authors)

  17. Nuclear and Radiological Forensics and Attribution Overview

    SciTech Connect (OSTI)

    Smith, D K; Niemeyer, S

    2005-11-04

    The goal of the U.S. Department of Homeland Security (DHS) Nuclear and Radiological Forensics and Attribution Program is to develop the technical capability for the nation to rapidly, accurately, and credibly attribute the origins and pathways of interdicted or collected materials, intact nuclear devices, and radiological dispersal devices. A robust attribution capability contributes to threat assessment, prevention, and deterrence of nuclear terrorism; it also supports the Federal Bureau of Investigation (FBI) in its investigative mission to prevent and respond to nuclear terrorism. Development of the capability involves two major elements: (1) the ability to collect evidence and make forensic measurements, and (2) the ability to interpret the forensic data. The Program leverages the existing capability throughout the U.S. Department of Energy (DOE) national laboratory complex in a way that meets the requirements of the FBI and other government users. At the same time the capability is being developed, the Program also conducts investigations for a variety of sponsors using the current capability. The combination of operations and R&D in one program helps to ensure a strong linkage between the needs of the user community and the scientific development.

  18. Final Report

    SciTech Connect (OSTI)

    Webb, Robert C.; Kamon, Teruki; Toback, David; Safonov, Alexei; Dutta, Bhaskar; Dimitri, Nanopoulos; Pope, Christopher; White, James

    2013-11-18

    Overview The High Energy Physics Group at Texas A&M University is submitting this final report for our grant number DE-FG02-95ER40917. This grant has supported our wide range of research activities for over a decade. The reports contained here summarize the latest work done by our research team. Task A (Collider Physics Program): CMS & CDF Profs. T. Kamon, A. Safonov, and D. Toback co-lead the Texas A&M (TAMU) collider program focusing on CDF and CMS experiments. Task D: Particle Physics Theory Our particle physics theory task is the combined effort of Profs. B. Dutta, D. Nanopoulos, and C. Pope. Task E (Underground Physics): LUX & NEXT Profs. R. Webb and J. White(deceased) lead the Xenon-based underground research program consisting of two main thrusts: the first, participation in the LUX two-phase xenon dark matter search experiment and the second, detector R&D primarily aimed at developing future detectors for underground physics (e.g. NEXT and LZ).

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

    Office of Legacy Management (LM)

    RADIOLOGICAL SURVEY AT 5823/5849 NORTH RAVENSWOOD AVEXJE CHICAGO, ILLINOIS Prepared by M.R. LANDIS Environmental Survey and Site Assessment Program Energy/Environment Systems Division Oak Ridge Associated Universities Oak Ridge, TN 37831-0117 Project Staff J.D. Berger R.C. Gosslee E.A. Powell G.R. Foltz M.J. Laudeman A. Wallo* C.F. Weaver Prepared for U.S. Department of Energy as part of the Formerly Utilized Sites - Remedial Action Program FINAL REPORT OCTOBER 1989 This report is based on work

  20. Cell Total Activity Final Estimate.xls

    Office of Legacy Management (LM)

    WSSRAP Cell Total Activity Final Estimate (calculated September 2002, Fleming) (Waste streams & occupied cell volumes from spreadsheet titled "cell waste volumes-8.23.02 with macros.xls") Waste Stream a Volume (cy) Mass (g) 2 Radiological Profile 3 Nuclide Activity (Ci) 4 Total % of Total U-238 U-234 U-235 Th-228 Th-230 Th-232 Ra-226 Ra-228 Rn-222 5 Activity if > 1% Raffinate Pits Work Zone (Ci) Raffinate processed through CSS Plant 1 159990 1.49E+11 Raffinate 6.12E+01 6.12E+01

  1. FRMAC Interactions During a Radiological or Nuclear Event

    SciTech Connect (OSTI)

    Wong, C T

    2011-01-27

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

  2. Current Trends in Gamma Ray Detection for Radiological Emergency Response

    SciTech Connect (OSTI)

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

    2011-08-18

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

  3. Radiological Security Partnership | Y-12 National Security Complex

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

    Radiological Security ... Radiological Security Partnership The mp4 video format is not supported by this browser. Download video Captions: On Time: 4:36 min. This voluntary program provides government-funded security enhancements at sites with radioactive materials of concern

  4. Final Report

    SciTech Connect (OSTI)

    Bauer, Susanne

    2015-02-09

    We participated in a FASTER SCM intercomparison for which we ran our SCM for 3 years at the SGP to analyze statistics of the precipitation field (Song et al., 2013). An important feature of these simulations was the use of relaxation forcing to observed T, q, which decouples the model convection from the forcing and allows precipitation errors to emerge. Because the GISS cumulus parameterization includes a trigger that prevents convection until sufficient lifting is present, and because convection at the SGP is usually triggered by mesoscale motions that are not represented in the forcing when relaxation is applied, the duration of SCM precipitation is shorter than observed (Del Genio and Wolf, 2012) and thus its mean precipitation less than observed. However, its diurnal cycle phase is correct, and it is the only operational cumulus parameterization in the intercomparison that does not produce excessive warm season precipitation under weak large-scale forcing conditions.

  5. Recovery from chemical, biological, and radiological incidents :

    SciTech Connect (OSTI)

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

    2012-06-01

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

  6. CONDITIONS OF PURCHASE

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

    of 2 GE Global Research CONDITIONS OF PURCHASE - SHORT FORM (May 2013) 1. ACCEPTANCE AND TERMS AND CONDITIONS: This purchase is subject to all of the terms and conditions set forth herein. This Order does not constitute an acceptance by GE of any offer to sell, quotation, or proposal. Any variation of the terms of this Order is not binding upon GE unless specifically accepted by GE in writing, and GE hereby rejects such proposed modifications. This Order is intended by the parties as a final,

  7. Final report

    SciTech Connect (OSTI)

    Joseph H. Simmons; Tracie J. Bukowski

    2002-08-07

    This grant was a continuation of research conducted at the University of Florida under Grant No. DE-FG05-91ER45462 in which we investigated the energy bandgap shifts produced in semiconductor quantum dots of sizes between 1.5 and 40 nm. The investigated semiconductors consisted of a series of Column 2-6 compounds (CdS, CdSe, CdTe) and pure Column IV elements (Si and Ge). It is well-known of course that the 2-6 semiconductors possess a direct-gap electronic structure, while the Column IV elements possess an indirect-gap structure. The investigation showed a major difference in quantum confinement behavior between the two sets of semiconductors. This difference is essentially associated with the change in bandgap energy resulting from size confinement. In the direct-gap semiconductors, the change in energy (blue shift) saturates when the crystals approach 2-3 nm in diameter. This limits the observed shift in energy to less than 1 eV above the bulk value. In the indirect-gap semiconductors, the energy shift does not show any sign of saturation and in fact, we produced Si and Ge nanocrystals with absorption edges in the UV. The reason for this difference has not been determined and will require additional experimental and theoretical studies. In our work, we suggest, but do not prove that mixing of conduction band side valleys with the central valley under conditions of size confinement may be responsible for the saturation in the blue-shift of direct-gap semiconductors. The discovery of large bandgap energy shifts with crystal size prompted us to suggest that these materials may be used to form photovoltaic cells with multi-gap layers for high efficiency in a U.S. Patent issued in 1998. However, this possibility depends strongly on the ability to collect photoexcited carriers from energy-confined crystals. The research conducted at the University of Arizona under the subject grant had a major goal of testing an indirect gap semiconductor in size-confined structures to determine if photocarriers could be collected. Thus, we tested a variety of semiconductor-glass nano-composite structures for photoconductivity. Tests were conducted in collaboration with the Laser Physics Division at Sandia National Laboratories. Nano-composite samples were formed consisting of Ge nanocrystals embedded in an indium-tin-oxide matrix. Photoconductivity measurements were conducted with exposure of the films to sub-bandgap and super-bandgap light. The results showed a clear photoconductivity effect arising from exposure to super-bandgap light only. These results suggest that the high-efficiency photovoltaic cell structure proposed in DOE sponsored U.S. Patent 5,720,827 is viable. The results of fabrication studies, structural characterization studies and photovoltaic measurements are presented in the report. This report is taken from a PhD dissertation of Tracie J. Bukowski submitted to the University of Florida in May 2002. ''The optical and photoconductive response in germanium quantum dots and indium tin oxide composite thin film structures,'' Dr. Bukowski conducted her PhD study under this grant at the University of Arizona and under Grant No DE-FG05-91ER45462 at the University of Florida, as well as during a two-year fellowship at Sandia National Laboratories.

  8. Radiological Safety Analysis Computer (RSAC) Program Version 7.2 Users’ Manual

    SciTech Connect (OSTI)

    Dr. Bradley J Schrader

    2010-10-01

    The Radiological Safety Analysis Computer (RSAC) Program Version 7.2 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

  9. Microsoft Word - S04932 History final.doc

    Office of Legacy Management (LM)

    FUSRAP History of the Chupadera Mesa, NM, Site December 2008 Doc. No. S0493200 (FUSRAP NM.04-5) Page 1 of 9 FUSRAP History of the Chupadera Mesa, NM, Site The following historical summary is provided to document the inclusion of the Chupadera Mesa, NM, Site into the Formerly Utilized Sites Remedial Action Program (FUSRAP). Although no remedial action was required, the site met eligibility criterion and was included under FUSRAP, under which the final radiological surveys were performed.

  10. Adaptively Reevaluated Bayesian Localization (ARBL): A Novel Technique for Radiological Source Localization

    SciTech Connect (OSTI)

    Miller, Erin A.; Robinson, Sean M.; Anderson, Kevin K.; McCall, Jonathon D.; Prinke, Amanda M.; Webster, Jennifer B.; Seifert, Carolyn E.

    2015-06-01

    Adaptively Reevaluated Bayesian Localization (ARBL): A Novel Technique for Radiological Source Localization

  11. INTERNATIONAL COOPERATION ON RADIOLOGICAL THREAT REDUCTION PROGRAMS IN RUSSIA

    SciTech Connect (OSTI)

    Landers, Christopher C.; Tatyrek, Aaron P.

    2009-10-07

    Since its inception in 2004, the United States Department of Energy’s Global Threat Reduction Initiative (GTRI) has provided the Russian Federation with significant financial and technical assistance to secure its highly vulnerable and dangerous radiological material. The three program areas of this assistance are the removal of radioisotope thermoelectric generators (RTG), the physical protection of vulnerable in-use radiological material of concern, and the recovery of disused or abandoned radiological material of concern. Despite the many successes of the GTRI program in Russia, however, there is still a need for increased international cooperation in these efforts. Furthermore, concerns exist over how the Russian government will ensure that the security of its radiological materials provided through GTRI will be sustained. This paper addresses these issues and highlights the successes of GTRI efforts and ongoing activities.

  12. Autonomous mobile robot for radiologic surveys

    DOE Patents [OSTI]

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

    1994-01-01

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

  13. Mobile autonomous robotic apparatus for radiologic characterization

    DOE Patents [OSTI]

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

    1999-01-01

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

  14. Autonomous mobile robot for radiologic surveys

    DOE Patents [OSTI]

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

    1994-06-28

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

  15. Mobile autonomous robotic apparatus for radiologic characterization

    DOE Patents [OSTI]

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

    1999-08-10

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

  16. Radiological Source Registry and Tracking (RSRT) | Department of Energy

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

    Radiological Source Registry and Tracking (RSRT) 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

  17. Portsmouth Training Exercise Helps Radiological Trainees Spot Mistakes

    Energy Savers [EERE]

    Safely | Department of Energy Portsmouth Training Exercise Helps Radiological Trainees Spot Mistakes Safely Portsmouth Training Exercise Helps Radiological Trainees Spot Mistakes Safely February 11, 2016 - 12:10pm Addthis Connie Martin performs work inside the Error Lab while trainees observe her actions for mistakes. Connie Martin performs work inside the Error Lab while trainees observe her actions for mistakes. Lorrie Graham (left) talks with trainees in a classroom setting before

  18. Cardiovascular and Interventional Radiological Society of Europe Guidelines

    Office of Scientific and Technical Information (OSTI)

    on Endovascular Treatment in Aortoiliac Arterial Disease (Journal Article) | SciTech Connect Cardiovascular and Interventional Radiological Society of Europe Guidelines on Endovascular Treatment in Aortoiliac Arterial Disease Citation Details In-Document Search Title: Cardiovascular and Interventional Radiological Society of Europe Guidelines on Endovascular Treatment in Aortoiliac Arterial Disease PurposeThese guidelines are intended for use in assessing the standard for technical success

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

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

    Hospital Triage in the First 24 Hours after a Nuclear or Radiological Disaster Medical professionals with the Radiation Emergency Assistance Center/Training Site (REAC/TS) at the Oak Ridge Institute for Science and Education (ORISE) authored an article that addresses the problems emergency physicians would likely face in the event of a nuclear or radiological catastrophe. The article specifically covers actions that would need to occur so that reasonable decisions are made during the critical

  20. DOE Subpart H Report. Annual NESHAPS Meeting on Radiological Emissions |

    Office of Environmental Management (EM)

    Department of Energy Subpart H Report. Annual NESHAPS Meeting on Radiological Emissions DOE Subpart H Report. Annual NESHAPS Meeting on Radiological Emissions Gustavo Vazquez*, DOE; Sandra Snyder, PNNL Abstract: The National Emissions Standards for Hazardous Air Pollutants, Subpart H, (NESHAPs - Radioactive Air) meeting provides an opportunity for federal and state regulators, Department of Energy employees and contractors, standards developers, and industry representatives to work together

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

    Office of Environmental Management (EM)

    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

  2. Radiological performance assessment for the E-Area Vaults Disposal Facility

    SciTech Connect (OSTI)

    Cook, J.R.

    2000-04-11

    This report is the first revision to ``Radiological Performance Assessment for the E-Area Vaults Disposal Facility, Revision 0'', which was issued in April 1994 and received conditional DOE approval in September 1994. The title of this report has been changed to conform to the current name of the facility. The revision incorporates improved groundwater modeling methodology, which includes a large data base of site specific geotechnical data, and special Analyses on disposal of cement-based wasteforms and naval wastes, issued after publication of Revision 0.

  3. Legacy Site Decontamination Experience as Applied to the Urban Radiological Dispersal Device

    SciTech Connect (OSTI)

    Drake, J.L.; MacKinney, J.A.

    2007-07-01

    Pursuant to the National Response Plan, Nuclear/Radiological Incident Annex [1], the Environmental Protection Agency (EPA) is assigned lead agency responsibility for decontamination and clean-up efforts following a domestic terrorist event involving a radiological dispersal device (RDD). An RDD incident in a modern city environment poses many of the same issues and problems traditionally faced at 'legacy' clean up projects being performed across our country. However there are also many aspects associated with an urban RDD clean-up that have never been faced in legacy site remediation. For example, the demolition and destructive technologies widely used in legacy remediation would be unacceptable in the case of historically or architecturally significant properties or those with prohibitively high replacement cost; contaminated properties will likely belong to numerous small private entities whose business interests are at stake; reducing the time required to decontaminate and return a city to normal use cannot be overemphasized due to its tremendous economic and political impact. The mission of the EPA's National Homeland Security Research Center (NHSRC) includes developing the best technology and tools needed for field personnel to achieve their goals should that event occur. To that end, NHSRC has been exploring how the vast experience within the legacy site remediation community could be tapped to help meet this need, and to identify gaps in decontamination technology. This paper articulates much of what has been learned over the past year as a result of efforts to identify these technology and procedural needs to address the urban RDD. This includes comparing and contrasting remediation techniques and methodologies currently used in nuclear facility and site cleanup with those that would be needed following an urban RDD event. Finally, this presentation includes an appeal to the radiological decontamination community to come forward with ideas and technologies for consideration to help meet this nationally significant need. (authors)

  4. In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis. Final report, volume 1. Development of experimental flow control loop, data analysis and plant monitoring

    SciTech Connect (OSTI)

    Upadhyaya, Belle; Hines, J. Wesley; Damiano, Brian; Mehta, Chaitanya; Collins, Price; Lish, Matthew; Cady, Brian; Lollar, Victor; de Wet, Dane; Bayram, Duygu

    2015-12-15

    The research and development under this project was focused on the following three major objectives: Objective 1: Identification of critical in-vessel SMR components for remote monitoring and development of their low-order dynamic models, along with a simulation model of an integral pressurized water reactor (iPWR). Objective 2: Development of an experimental flow control loop with motor-driven valves and pumps, incorporating data acquisition and on-line monitoring interface. Objective 3: Development of stationary and transient signal processing methods for electrical signatures, machinery vibration, and for characterizing process variables for equipment monitoring. This objective includes the development of a data analysis toolbox. The following is a summary of the technical accomplishments under this project: - A detailed literature review of various SMR types and electrical signature analysis of motor-driven systems was completed. A bibliography of literature is provided at the end of this report. Assistance was provided by ORNL in identifying some key references. - A review of literature on pump-motor modeling and digital signal processing methods was performed. - An existing flow control loop was upgraded with new instrumentation, data acquisition hardware and software. The upgrading of the experimental loop included the installation of a new submersible pump driven by a three-phase induction motor. All the sensors were calibrated before full-scale experimental runs were performed. - MATLAB-Simulink model of a three-phase induction motor and pump system was completed. The model was used to simulate normal operation and fault conditions in the motor-pump system, and to identify changes in the electrical signatures. - A simulation model of an integral PWR (iPWR) was updated and the MATLAB-Simulink model was validated for known transients. The pump-motor model was interfaced with the iPWR model for testing the impact of primary flow perturbations (upsets) on plant parameters and the pump electrical signatures. Additionally, the reactor simulation is being used to generate normal operation data and data with instrumentation faults and process anomalies. A frequency controller was interfaced with the motor power supply in order to vary the electrical supply frequency. The experimental flow control loop was used to generate operational data under varying motor performance characteristics. Coolant leakage events were simulated by varying the bypass loop flow rate. The accuracy of motor power calculation was improved by incorporating the power factor, computed from motor current and voltage in each phase of the induction motor.- A variety of experimental runs were made for steady-state and transient pump operating conditions. Process, vibration, and electrical signatures were measured using a submersible pump with variable supply frequency. High correlation was seen between motor current and pump discharge pressure signal; similar high correlation was exhibited between pump motor power and flow rate. Wide-band analysis indicated high coherence (in the frequency domain) between motor current and vibration signals. - Wide-band operational data from a PWR were acquired from AMS Corporation and used to develop time-series models, and to estimate signal spectrum and sensor time constant. All the data were from different pressure transmitters in the system, including primary and secondary loops. These signals were pre-processed using the wavelet transform for filtering both low-frequency and high-frequency bands. This technique of signal pre-processing provides minimum distortion of the data, and results in a more optimal estimation of time constants of plant sensors using time-series modeling techniques.

  5. Security Conditions

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

    2004-07-08

    This Notice ensures that DOE uniformly meets the requirements of the Homeland Security Advisory System outlined in Homeland Security Presidential Directive-3, Threat Conditions and Associated Protective Measures, dated 3-11-02, and provides responses specified in Presidential Decision Directive 39, U.S. Policy on Counterterrorism (U), dated 6-21-95. It cancels DOE N 473.8, Security Conditions, dated 8-7-02. Extended until 7-7-06 by DOE N 251.64, dated 7-7-05 Cancels DOE N 473.8

  6. WIPP Radiological Release Report Phase 1

    Office of Environmental Management (EM)

    of February 14, 2014. Analysis The DSA Chapter 2 descriptions of the underground and operations are consistent with conditions known and understood in Panel 7 Room 7 where TRU...

  7. ASPECT Emergency Response Chemical and Radiological Mapping

    ScienceCinema (OSTI)

    LANL

    2009-09-01

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

  8. ASPECT Emergency Response Chemical and Radiological Mapping

    SciTech Connect (OSTI)

    LANL

    2008-05-12

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

  9. Radiological assessment. A textbook on environmental dose analysis

    SciTech Connect (OSTI)

    Till, J.E.; Meyer, H.R.

    1983-09-01

    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.

  10. Weather Conditions at LBNL

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

    Weather Conditions at LBNL

  11. Meteorological Conditions at LBNL

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

    Meteorological Conditions at LBNL

  12. Radiological conditions at Bikini Atoll: Radionuclide concentrations in vegetation, soil, animals, cistern water, and ground water

    SciTech Connect (OSTI)

    Robison, W.L.; Conrado, C.L.; Stuart, M.L.

    1988-05-31

    This report is intended as a resource document for the eventual cleanup of Bikini Atoll and contains a summary of the data for the concentrations of /sup 137/Cs, /sup 90/Sr, /sup 239 +240/Pu, and /sup 241/Am in vegetation through 1987 and in soil through 1985 for 14 islands at Bikini Atoll. The data for the main residence island, Bikini, and the most important island, Eneu, are extensive; these islands have been the subject of a continuing research and monitoring program since 1974. Data for radionuclide concentrations in ground water, cistern water, fish and other marine species, and pigs from Bikini and Eneu Islands are presented. Also included are general summaries of our resuspension and rainfall data from Bikini and Eneu Islands. The data for the other 12 islands are much more limited because samples were collected as part of a screening survey and the islands have not been part of a continuing research and monitoring program. Cesium-137 is the radionuclide that produces most of the estimated dose for returning residents, mostly through uptake by terrestrial foods and secondly by direct external gamma exposure. Remedial measures for reducing the /sup 137/Cs uptake in vegetation are discussed. 40 refs., 32 figs., 131 tabs.

  13. Analytical methods for removing radiological constituents prior to organic analysis

    SciTech Connect (OSTI)

    Hakonson, K.; Monagle, M.; Cournoyer, M.

    1997-12-31

    Within the Department of Energy (DOE), there is a need to analyze mixed waste materials (i.e. materials that are contaminated with both radiological and hazardous components). As part of the technical support the Organic Analysis Group provides for programs within Los Alamos National Laboratory, methods are under development for radiologically contaminated oil samples being tested for polychlorinated biphenyls and other semivolatile constituents. Radionuclides are removed from oil samples by filtering the samples through a commercials available solid phase extraction cartridge. An aliquot of the eluent is then analyzed to quantitate the residual radioactivity.

  14. RADIOLOGICAL EFFLUENT AND ONSITE AREA MONITORING REPORT FOR THE

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

    327-33 a a RADIOLOGICAL EFFLUENT AND ONSITE AREA MONITORING REPORT FOR THE 0 NEVADA TEST SITE (JANUARY 1986 THROUGH DECEMBER 1986) BANEL A. GONZALEZ HEALTH PHY%ICIST SePTEMl3ER 1987 WORK PERFORMED UNDER CONTRACT NO. DE-ACXM-84-84NV10327 REYNOLDS ELECTRICAL & ENGINEERING CO., INC. POST OFFICE BOX 14400 LAS VEGAS, NV 89114 DOE/NV/10327-33 RADIOLOGICAL EFFLUENT AND ONSITE AREA MONITORING REPORT FOR THE NEVADA TEST SITE (JANUARY 1986 THROUGH DECEMBER 1986) Daniel A. Gonzalez Health Physicist

  15. Radiological Worker Training Power Point Slides for App. A

    Energy Savers [EERE]

    30-2008 DOE HANDBOOK Radiological Worker Training DOE-HDBK-1130-2008 Overheads December 2008 Reaffirmed 2013 OT 1.1 DOE-HDBK-1130-2008 Overhead 1.1 Regulatory Documents Objectives: * Identify the hierarchy of regulatory documents. * Define the purposes of 10 CFR Parts 820, 830 and 835. * Define the purpose of the DOE Radiological Control Standard. OT 1.2 DOE-HDBK-1130-2008 Overhead 1.2 Regulatory Documents (cont.) Objectives: * Define the terms "shall" and "should" as used in

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

    Office of Legacy Management (LM)

    Laboratory - CA 0-06 Naval Radiological Defense Laboratory - CA 0-06 FUSRAP Considered Sites Site: U. S. NAVAL RADIOLOGICAL DEFENSE LABORATORY (CA.0-06) Eliminated from consideration under FUSRAP - Referred to the DoD Designated Name: Not Designated Alternate Name: None Location: San Francisco , California CA.0-06-1 Evaluation Year: 1987 CA.0-06-1 Site Operations: NRC licensed DoD facility which used small quantities of nuclear materials for R&D purposes and decontaminated ships.

  17. RADIOLOGICAL EVALUATION OF DECONTAMINATION DEBRIS LOCATED AT THE

    Office of Legacy Management (LM)

    h ' . * ' 1. MI). q-8 RADIOLOGICAL EVALUATION OF DECONTAMINATION DEBRIS LOCATED AT THE FUTURA CHEMICAL COMPANY FACILITY 9200 LATTY AVENUE HAZELWOOD, MISSOURI L.W. Cole J.D. Berger W.O. Helton B.M. Putnam T.J. Sowell C.F. Weaver R.D. Condra September 9, 1981 Work performed by Radiological Site Assessment Program Manpower Education, Research, and Training Division Oak Ridge Associated Universities Oak Ridge, Tennessee 37830 Under Interagency Agreement DOE No. 40-770-80 NRC Fin. No. A-9093-0

  18. DOE-HDBK-1122-99; Radiological Control Technical Training

    Office of Environmental Management (EM)

    10 Access Control and Work Area Setup Study Guide 2.10-1 Course Title: Radiological Control Technician Module Title: Access Control and Work Area Setup Module Number: 2.10 Objectives: i 2.10.01 State the purpose of and information found on a Radiological Work Permit (RWP) including the different classifications at your site. i 2.10.02 State responsibilities in using or initiating a RWP. i 2.10.03 State the document that governs the ALARA program at your site. i 2.10.04 Describe how

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

    Office of Environmental Management (EM)

    ALARA Instructor's Guide 1.10-1 Course Title: Radiological Control Technician Module Title: ALARA Module Number: 1.10 Objectives: 1.10.01 Describe the assumptions on which the current ALARA philosophy is based. 1.10.02 Identify the ALARA philosophy for collective personnel exposure and individual exposure. 1.10.03 Identify the scope of an effective radiological ALARA program. 1.10.04 Identify the purposes for conducting pre-job and/or post-job ALARA reviews. 1.10.05 Identify RCT responsibilities

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

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    Access Control and Work Area Setup Instructor's Guide 2.10-1 Course Title: Radiological Control Technician Module Title: Access Control and Work Area Setup Module Number: 2.10 Objectives: L 2.10.01 State the purpose of and information found on a Radiological Work Permit (RWP) including the different classifications at your site. L 2.10.02 State responsibilities in using or initiating a RWP. L 2.10.03 State the document that governs the ALARA program at your site. L 2.10.04 Describe how

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

    Office of Environmental Management (EM)

    ALARA Study Guide 1.10-1 Course Title: Radiological Control Technician Module Title: ALARA Module Number: 1.10 Objectives: 1.10.01 Describe the assumptions on which the current ALARA philosophy is based. 1.10.02 Identify the ALARA philosophy for collective personnel exposure and individual exposure. 1.10.03 Identify the scope of an effective radiological ALARA program. 1.10.04 Identify the purposes for conducting pre-job and/or post-job ALARA reviews. 1.10.05 Identify RCT responsibilities for

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

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    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

  5. Radiological risk assessment of environmental radon

    SciTech Connect (OSTI)

    Khalid, Norafatin; Majid, Amran Ab; Yahaya, Redzuwan; Yasir, Muhammad Samudi

    2013-11-27

    Measurements of radon gas ({sup 222}Rn) in the environmental are important to assess indoor air quality and to study the potential risk to human health. Generally known that exposure to radon is considered the second leading cause of lung cancer after smoking. The environmental radon concentration depends on the {sup 226}Ra concentration, indoor atmosphere, cracking on rocks and building materials. This study was carried out to determine the indoor radon concentration from selected samples of tin tailings (amang) and building materials in an airtight sealed homemade radon chamber. The radiological risk assessment for radon gas was also calculated based on the annual exposure dose, effective dose equivalent, radon exhalation rates and fatal cancer risk. The continuous radon monitor Sun Nuclear model 1029 was used to measure the radon concentration emanates from selected samples for 96 hours. Five types of tin tailings collected from Kampar, Perak and four samples of building materials commonly used in Malaysia dwellings or building constructions were analysed for radon concentration. The indoor radon concentration determined in ilmenite, monazite, struverite, xenotime and zircon samples varies from 219.6 ± 76.8 Bq m{sup ?3} to 571.1 ± 251.4 Bq m{sup ?3}, 101.0 ± 41.0 Bq m{sup ?3} to 245.3 ± 100.2 Bq m{sup ?3}, 53.1 ± 7.5 Bq m{sup ?3} to 181.8 ± 9.7 Bq m{sup ?3}, 256.1 ± 59.3 Bq m{sup ?3} to 652.2 ± 222.2 Bq m{sup ?3} and 164.5 ± 75.9 Bq m{sup ?3} to 653.3 ± 240.0 Bq m{sup ?3}, respectively. Whereas, in the building materials, the radon concentration from cement brick, red-clay brick, gravel aggregate and cement showed 396.3 ± 194.3 Bq m{sup ?3}, 192.1 ± 75.4 Bq m{sup ?3}, 176.1 ± 85.9 Bq m{sup ?3} and 28.4 ± 5.7 Bq m{sup ?3}, respectively. The radon concentration in tin tailings and building materials were found to be much higher in xenotime and cement brick samples than others. All samples in tin tailings were exceeded the action level for radon gas of 148 Bq m{sup ?3} proposed by EPA except monazite 0.15 kg, struverite 0.15 kg and 0.25 kg. Whereas, all building material samples have exceeded the radon concentration in concrete and building materials of 3 to 7 Bq m{sup ?3} estimated by ICRP. The annual effective dose, effective dose equivalent, and radon exhalation rates in tin tailings were calculated to be in the range of 2.47 to 11.46 mSv, 5.94 to 1090.56 mSv y{sup ?1}, and 0.23 to 1.18 mBq kg{sup ?1} h{sup ?1}. For building materials, the calculated risk assessment of the annual effective dose, effective dose equivalent, radon exhalation rates and fatal cancer risk were 0.72 to 10.00 mSv, 1.73 to 24.00 mSv y{sup ?1}, 0.010 to 0.06 mBq kg{sup ?1} h{sup ?1} and 40 to 550 chances of persons will suffer the cancer per million (1 × 10{sup 6}), respectively.

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

    DOE Patents [OSTI]

    Farmer, Joseph C. (Tracy, CA)

    2010-08-24

    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.

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

    DOE Patents [OSTI]

    Farmer, Joseph C. (Tracy, CA)

    2012-03-13

    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.

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

    DOE Patents [OSTI]

    Farmer, Joseph C.

    2013-04-02

    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.

  9. Final EIS Volume 3

    Office of Environmental Management (EM)

    Volume 3 Final Environmental Impact Statement for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center DOE/EIS-0226 January 2010 The West Valley Site Comment Response Document Final Environmental Impact Statement for AVAILABILITY OF THE FINAL EIS FOR DECOMMISSIONING AND/OR LONG- TERM STEWARDSHIP AT THE WEST VALLEY DEMONSTRATION PROJECT AND WESTERN NEW YORK NUCLEAR SERVICE CENTER For further information on this Final

  10. WY Final EA DRAFT

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

    Final Environmental Assessment Wallooskee-Youngs Confluence Restoration Project Bonneville Power Administration DOE/EA-1974 July 2015 This document is the Final Environmental Assessment (EA) for the proposed Wallooskee-Youngs Confluence Restoration Project. This document has been prepared as an abbreviated Final EA because there have been no substantial changes to the proposed action, alternatives, or environmental analysis presented in the Draft EA. This abbreviated Final EA provides changes

  11. Order Module--DOE STD-1098-2008, DOE STANDARD: RADIOLOGICAL CONTROL |

    Energy Savers [EERE]

    Department of Energy STD-1098-2008, DOE STANDARD: RADIOLOGICAL CONTROL Order Module--DOE STD-1098-2008, DOE STANDARD: RADIOLOGICAL CONTROL "The radiological control program discussed in DOE-STD-1098-2008 goes beyond the scope of, and includes more details than, the documented radiation protection program (RPP) required by 10 CFR 835, -Occupational Radiation Protection.‖ To ensure implementation of a comprehensive and coherent radiological control program that exceeds basic

  12. DOE-HDBK-1141-2001; Radiological Assessor Training, Student's Guide

    Office of Environmental Management (EM)

    Student's Guide Notes Module 4-1 I. Introduction II. Radiological Control Program A. Overall program The Radiological Control Program consists of the commitments, policies, and procedures that are administered by a site or facility to meet the EH Health and Safety Policy. The Radiation Protection Program required by 10 CFR Part 835 is an element of the overall Radiological Control Program. The Radiological Control Program should address the following: * Requirements * Responsibilities *

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

    Office of Environmental Management (EM)

    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

  14. Radiology utilizing a gas multiwire detector with resolution enhancement

    DOE Patents [OSTI]

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

    1999-09-28

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

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

    Broader source: Energy.gov [DOE]

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

  16. Radiological safety training for accelerator facilities: DOE handbook

    SciTech Connect (OSTI)

    1997-03-01

    This program management guide describes the proper implementation standard for core training as outline in the DOE Radiological Control (RadCon) Manual. Its purpose is to assist DOE employees and Managing and Operating (M&O) contractors having responsibility for implementing the core training recommended by the RadCon Manual.

  17. EM-Led Radiological Incident Response Program Receives Honors

    Broader source: Energy.gov [DOE]

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

  18. Federal Radiological Monitoring and Assessment Center | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration Radiological Monitoring and Assessment Center | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo

  19. GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material |

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration Removing Vulnerable Civilian Nuclear and Radiological Material | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets

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

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration Insider Threat to Nuclear and Radiological Materials: Fact Sheet | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets

  1. NNSA Provides Tajikistan Specialized Vehicles to Transport Radiological

    National Nuclear Security Administration (NNSA)

    Materials | National Nuclear Security Administration Provides Tajikistan Specialized Vehicles to Transport Radiological Materials | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios

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

    National Nuclear Security Administration (NNSA)

    Berkeley, And Oakland, CA Areas | National Nuclear Security Administration Radiological Surveys Over San Francisco, Pacifica, Berkeley, And Oakland, CA Areas | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our

  3. Nuclear Radiological Threat Task Force Established | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration Radiological Threat Task Force Established | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo

  4. Radiological Laboratory, Utility, Office Building LEED Strategy & Achievement

    SciTech Connect (OSTI)

    Seguin, Nicole R.

    2012-07-18

    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.

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

    National Nuclear Security Administration (NNSA)

    Administration Nuclear/Radiological Incident Response | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs

  6. NNSA Recovers Radiological Material from Mexico | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Recovers Radiological Material from Mexico | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs

  7. Final Report to DOE

    SciTech Connect (OSTI)

    Ismail Gultepe

    2012-05-15

    This final report summarizes the accomplished goals and provide a list of the publications and presentations made during the project. The goals of the project were accomplished through the various publications submitted to Journals and presentations done at the DOE and international meetings and conferences. The 8 journal articles related to the goals of this project were accepted or submitted. The 23 presentations related to goals of the project were presented at the meetings. There were some minor changes regarding to project goals because of issues encountered during the analysis of the data. For example, a total water probe sensor mounted on the Convair-580 that can be used for defining mixed phase conditions and parameterization, had some problems to estimate magnitude of total water mass, and this resulted in issues providing an accurate parameterization for cloud fraction. Variability related aerosol number concentrations and their composition for direct and indirect effects were studied and published. Results were given to explain aerosol and ice microphysical effects on climate change studies. It is suggested that developed parameterizations should consider the variability in aerosol and ice parameters over the Arctic regions.

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

    SciTech Connect (OSTI)

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

    2013-07-01

    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.

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

    DOE Patents [OSTI]

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

    2012-03-27

    A paint that warns of radiological or chemical substances comprising a paint operatively connected to the surface, an indicator material carried by the paint that provides an indication of the radiological or chemical substances, and a thermo-activation material carried by the paint. In one embodiment, a method of warning of radiological or chemical substances comprising the steps of painting a surface with an indicator material, and monitoring the surface for indications of the radiological or chemical substances. In another embodiment, a paint is operatively connected to a vehicle and an indicator material is carried by the paint that provides an indication of the radiological or chemical substances.

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

    DOE Patents [OSTI]

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

    2013-04-02

    A paint that warns of radiological or chemical substances comprising a paint operatively connected to the surface, an indicator material carried by the paint that provides an indication of the radiological or chemical substances, and a thermo-activation material carried by the paint. In one embodiment, a method of warning of radiological or chemical substances comprising the steps of painting a surface with an indicator material, and monitoring the surface for indications of the radiological or chemical substances. In another embodiment, a paint is operatively connected to a vehicle and an indicator material is carried by the paint that provides an indication of the radiological or chemical substances.

  11. National Science Bowl Finals

    ScienceCinema (OSTI)

    None

    2010-09-01

    National Science Bowl finals and awards at the National Building Museum in Washington D.C. Monday 5/3/2010

  12. DOE Final Report

    SciTech Connect (OSTI)

    Hinzman, Larry D.; Long, James; Newby, Greg B.

    2014-01-08

    This final report contains a summary of work accomplished in the establishment of a Climate Data Center at the International Arctic Research Center, University of Alaska Fairbanks.

  13. Final Project Report

    SciTech Connect (OSTI)

    Wang, Qiang; Dandy, David S.

    2015-05-15

    This is the final technical report of the DOE project DE-FG02-07ER46448 awarded to Colorado State University.

  14. Microsoft PowerPoint - Final translated version of Tsinghua Speech |

    Office of Environmental Management (EM)

    Department of Energy Final translated version of Tsinghua Speech Microsoft PowerPoint - Final translated version of Tsinghua Speech PDF icon Microsoft PowerPoint - Final translated version of Tsinghua Speech More Documents & Publications Heating Ventilation and Air Conditioning Efficiency GNEP Element:Expand Domestic Use of Nuclear Power Greenpower Trap Mufflerl System

  15. Neutron Energy Measurements in Radiological Emergency Response Applications

    SciTech Connect (OSTI)

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

    2009-04-30

    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.

  16. E. Cardis, International V.K. Ivanov, Medical Radiological Rese

    Office of Scientific and Technical Information (OSTI)

    25026 E. Cardis, International V.K. Ivanov, Medical Radiological Rese K. Mabuchi, Radia A.E. Okeanov, Belarussian Centre for Medic EDITORLAL NOTE This unedited Background Paper is not to be referenced or quoted. The views expressed remain the responsibility of the named authors. The views are not necessarily those of the governments of the member states of the Sponsoring Organizations. Although great care has been taken to maintain the accuracy of information contained in t h i s Background

  17. ORISE Resources: Radiological and Nuclear Terrorism: Medical Response to

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

    Mass Casualties Training Clinicians for Response to a Radiological or Nuclear Terrorism Attack The Centers for Disease Control and Prevention and its Radiation Studies Branch in the National Center for Environmental Health asked the Oak Ridge Institute for Science and Education (ORISE) to develop a Web-based and CD-ROM training program to prepare clinicians-medical doctors and registered nurses in hospital emergency service settings-on how to locally respond to mass casualties that may

  18. Introduction The Radiological/Nuclear Countermeasures Test and Evaluation

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

    Radiological/Nuclear Countermeasures Test and Evaluation Complex (RNCTEC) is a multi-use test and evaluation platform that will serve the U.S. homeland security mission. Background The Department of Homeland Security's Domestic Nuclear Detection Office (DNDO), with assistance from the U.S. Department of Energy National Nuclear Security Administration, has established the RNCTEC at the Nevada National Security Site, formerly known as the Nevada Test Site, to support all federal agencies to

  19. Office of Radiological Security | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Radiological Security | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at

  20. Good Practices for Ocupational Radiological Protection in Plutonium Facilities

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    9 Radiological Control Technician Training Technician Qualification Standard Coordinated and Conducted for Office of Environment, Safety & Health U.S. Department of Energy DOE-HDBK-1122-99 ii This page intentionally left blank. DOE-HDBK-1122-99 iii Course Developers Dave Lent Coleman Research Joe DeMers EG&G Mound Applied Technologies (formerly) Andy Hobbs FERMCO Dennis Maloney RUST - GJPO Richard Cooke Argonne National Laboratory Bobby Oliver Lockheed Martin Energy Systems Michael

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

    Office of Environmental Management (EM)

    Sources of Radiation Instructor's Guide 1.05-1 Course Title: Radiological Control Technician Module Title: Sources of Radiation Module Number: 1.05 Objectives: 1.05.01 Identify the following four sources of natural background radiation including the origin, radionuclides, variables, and contribution to exposure. a. Terrestrial b. Cosmic c. Internal Emitters d. Radon 1.05.02 Identify the following four sources of artificially produced radiation and the magnitude of dose received from each. a.

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

    Office of Environmental Management (EM)

    Radioactivity & Radioactive Decay Instructor's Guide 1.06-1 Course Title: Radiological Control Technician Module Title: Radioactivity & Radioactive Decay Module Number: 1.06 Objectives: 1.06.01 Identify how the neutron to proton ratio is related to nuclear stability. 1.06.02 Identify the definition for the following terms: a. radioactivity b. radioactive decay 1.06.03 Identify the characteristics of alpha, beta, and gamma radiations. 1.06.04 Given simple equations identify the following

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

    Office of Environmental Management (EM)

    External Exposure Control Instructor's Guide 1.11-1 Course Title: Radiological Control Technician Module Title: External Exposure Control Module Number: 1.11 Objectives: 1.11.01 Identify the four basic methods for minimizing personnel external exposure. 1.11.02 Using the Exposure Rate = 6CEN equation, calculate the gamma exposure rate for specific radionuclides. 1.11.03 Identify "source reduction" techniques for minimizing personnel external exposures. 1.11.04 Identify

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

    Office of Environmental Management (EM)

    3 Radiation Detector Theory Instructor's Guide 1.13-1 Course Title: Radiological Control Technician Module Title: Radiation Detector Theory Module Number: 1.13 Objectives: 1.13.01 Identify the three fundamental laws associated with electrical charges. 1.13.02 Identify the definition of current, voltage and resistance and their respective units. 1.13.03 Select the function of the detector and readout circuitry components in a radiation measurement system. 1.13.04 Identify the parameters that

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

    Office of Environmental Management (EM)

    Respiratory Protection Instructor's Guide 2.07-1 Course Title: Radiological Control Technician Module Title: Respiratory Protection Module Number: 2.07 Objectives: 2.07.01 Explain the purpose of respiratory protection standards and regulations. 2.07.02 Identify the OSHA, ANSI, and DOE respiratory protection program requirements. 2.07.03 Identify the standards which regulate respiratory protection. 2.07.04 Describe the advantages and disadvantages (limitations) of each of the following

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

    Office of Environmental Management (EM)

    6 Radiation Survey Instrumentation Instructor's Guide 2.16-1 Course Title: Radiological Control Technician Module Title: Radiation Survey Instrumentation Module Number: 2.16 Objectives: 2.16.01 List the factors which affect an RCT's selection of a portable radiation survey instrument, and identify appropriate instruments for external radiation surveys. L 2.16.02 Identify the following features and specifications for ion chamber instruments used at your facility: a. Detector type b. Instrument

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

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    Instructor's Guide 2.19-1 Course Title: Radiological Control Technician Module Title: Counting Room Equipment Module Number: 2.19 Objectives: L 2.19.01 Describe the following features and specifications for commonly used laboratory counter or scalers: a. Detector type b. Detector shielding c. Detector window d. Types of radiation detected and measured e. Operator-adjustable controls f. Source check g. Procedure for sample counting L 2.19.02 Describe the following features and specifications for

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

    Office of Environmental Management (EM)

    - Sources of Radiation Study Guide 1.05-1 Course Title: Radiological Control Technician Module Title: Sources of Radiation Module Number: 1.05 Objectives: 1.05.01 Identify the following four sources of natural background radiation including the origin, radionuclides, variables, and contribution to exposure. a. Terrestrial b. Cosmic c. Internal Emitters d. Radon 1.05.02 Identify the following four sources of artificially produced radiation and the magnitude of dose received from each. a. Nuclear

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

    Office of Environmental Management (EM)

    - Radioactivity and Radioactive Decay Study Guide 1.06-1 Course Title: Radiological Control Technician Module Title: Radioactivity & Radioactive Decay Module Number: 1.06 Objectives: 1.06.01 Identify how the neutron to proton ratio is related to nuclear stability. 1.06.02 Identify the definition for the following terms: a. radioactivity b. radioactive decay 1.06.03 Identify the characteristics of alpha, beta, and gamma radiations. 1.06.04 Given simple equations identify the following

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

    Office of Environmental Management (EM)

    External Exposure Control Study Guide 1.11-1 Course Title: Radiological Control Technician Module Title: External Exposure Control Module Number: 1.11 Objectives: 1.11.01 Identify the four basic methods for minimizing personnel external exposure. 1.11.02 Using the Exposure Rate = 6CEN equation, calculate the gamma exposure rate for specific radionuclides. 1.11.03 Identify "source reduction" techniques for minimizing personnel external exposures. 1.11.04 Identify

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

    Office of Environmental Management (EM)

    Respiratory Protection Study Guide 2.07-1 Course Title: Radiological Control Technician Module Title: Respiratory Protection Module Number: 2.07 Objectives: 2.07.01 Explain the purpose of respiratory protection standards and regulations. 2.07.02 Identify the OSHA, ANSI, and DOE respiratory protection program requirements. 2.07.03 Identify the standards which regulate respiratory protection. 2.07.04 Describe the advantages and disadvantages (limitations) of each of the following respirators: a.

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

    Office of Environmental Management (EM)

    Instrumentation Study Guide 2.16-1 Course Title: Radiological Control Technician Module Title: Radiation Survey Instrumentation Module Number: 2.16 Objectives: 2.16.01 List the factors which affect an RCT's selection of a portable radiation survey instrument, and identify appropriate instruments for external radiation surveys. i 2.16.02 Identify the following features and specifications for ion chamber instruments used at your facility: a. Detector type b. Instrument operating range c. Detector

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

    Office of Environmental Management (EM)

    Study 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. i 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

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

    Office of Environmental Management (EM)

    Study Guide 2.19-1 Course Title: Radiological Control Technician Module Title: Counting Room Equipment Module Number: 2.19 Objectives: 2.19.01 Describe the features and specifications for commonly used laboratory counters or scalers: a. Detector type b. Detector shielding c. Detector window d. Types of radiation detected and measured e. Operator-adjustable controls f. Source check g. Procedure for sample counting 2.19.02 Describe the features and specifications for low-background automatic

  17. DOE-HDBK-1131-98; General Employee Radiological Training

    Office of Environmental Management (EM)

    DOE-HDBK-1131-98 December 1998 Change Notice No. 1 November 2003 Reaffirmation with Errata April 2004 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 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

  18. Radiological characterization of a vitrification facility for decommissioning

    SciTech Connect (OSTI)

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

    2007-07-01

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

  19. Current Trends in Gamma Radiation Detection for Radiological Emergency Response

    SciTech Connect (OSTI)

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

    2011-09-01

    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.

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

    SciTech Connect (OSTI)

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

    2007-09-15

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

  1. Final EIS Volume 2

    Office of Environmental Management (EM)

    Volume 2 Final Environmental Impact Statement for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center DOE/EIS-0226 January 2010 The West Valley Site (Appendices A through R) AVAILABILITY OF THE FINAL EIS FOR DECOMMISSIONING AND/OR LONG- TERM STEWARDSHIP AT THE WEST VALLEY DEMONSTRATION PROJECT AND WESTERN NEW YORK NUCLEAR SERVICE CENTER For further information on this Final EIS, or to request a copy of the EIS or

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

    SciTech Connect (OSTI)

    Cusick L.T.

    2002-09-25

    The U.S. Department of Energy (DOE) owns, operates, and manages the buildings and land areas on the Oak Ridge Reservation (ORR) in Oak Ridge, Tennessee. As land and buildings are declared excess or underutilized, it is the intent of DOE to either transfer the title of or lease suitable property to the Community Reuse Organization of East Tennessee (CROET) or other entities for public use. It is DOE's responsibility, in coordination with the U.S. Environmental Protection Agency (EPA), Region 4, and the Tennessee Department of Environment and Conservation (TDEC), to ensure that the land, facilities, and personal property that are to have the title transferred or are to be leased are suitable for public use. Release of personal property must also meet site requirements and be approved by the DOE contractor responsible for site radiological control. The terms title transfer and lease in this document have unique meanings. Title transfer will result in release of ownership without any restriction or further control by DOE. Under lease conditions, the government retains ownership of the property along with the responsibility to oversee property utilization. This includes involvement in the lessee's health, safety, and radiological control plans and conduct of site inspections. It may also entail lease restrictions, such as limiting access to certain areas or prohibiting digging, drilling, or disturbing material under surface coatings. Survey and sampling requirements are generally more rigorous for title transfer than for lease. Because of the accelerated clean up process, there is an increasing emphasis on title transfers of facilities and land. The purpose of this document is to describe the radiological survey and sampling protocols that are being used for assessing the radiological conditions and characteristics of building and land areas on the Oak Ridge Reservation that contain space potentially available for title transfer or lease. After necessary surveys and sampling and laboratory analyses are completed, the data are analyzed and included in an Environmental Baseline Summary (EBS) report for title transfer or in a Baseline Environmental Analysis Report (BEAR) for lease. The data from the BEAR is then used in a Screening-Level Human Health Risk Assessment (SHHRA) or a risk calculation (RC) to assess the potential risks to future owners/occupants. If title is to be transferred, release criteria in the form of specific activity concentrations called Derived Concentration Guideline Levels (DCGLs) will be developed for the each property. The DCGLs are based on the risk model and are used with the data in the EBS to determine, with statistical confidence, that the release criteria for the property have been met. The goal of the survey and sampling efforts is to (1) document the baseline conditions of the property (real or personal) prior to title transfer or lease, (2) obtain enough information that an evaluation of radiological risks can be made, and (3) collect sufftcient data so that areas that contain minimal residual levels of radioactivity can be identified and, following radiological control procedures, be released from radiological control. (It should be noted that release from radiological control does not necessarily mean free release because DOE may maintain institutional control of the site after it is released from radiological control). To meet the goals of this document, a Data Quality Objective (DQO) process will be used to enhance data collection efficiency and assist with decision-making. The steps of the DQO process involve stating the problem, identifying the decision, identifying inputs to the decision, developing study boundaries, developing the decision rule, and optimizing the design. This document describes the DQOs chosen for surveys and sampling efforts performed for the purposes listed above. The previous version to this document focused on the requirements for radiological survey and sampling protocols that are be used for leasing. Because the primary focus at this time is on title transfer, this revision applies to both situations.

  3. CFC Charity Fair Finale

    Broader source: Energy.gov [DOE]

    Finish out the 2012 CFC with the Charity Fair Finale! Buy cookies, participate in a putt-putt golf game, eat some popcorn, and meet and talk with CFC charity representatives.

  4. Aurora final report

    SciTech Connect (OSTI)

    Robert, Dross; Amedeo, Conti

    2013-12-06

    Final Technical report detailing the work done by Nuvera and its partners to fulfill the goals of the program "Transport Studies Enabling Efficiency Optimization of Cost-Competitive Fuel Cell Stacks" (a.k.a. AURORA)

  5. FINAL Submitted to NREL

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

    ... systems, usage feedback devices, optional demand-side FINAL Submitted to NREL 10-21-11 City of Naperville Case Study 4 programs, and intelligent charging options for electric cars. ...

  6. " Million Housing Units, Final...

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

    Water Heating in U.S. Homes, by Census Region, 2009" " Million Housing Units, Final" ,,"Census Region" ,"Total U.S.1 (millions)" ,,"Northeast","Midwest","South","West" "Water ...

  7. " Million Housing Units, Final...

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

    6 Water Heating in U.S. Homes, by Climate Region, 2009" " Million Housing Units, Final" ... Cold","Mixed- Humid","Mixed-Dry" "Water Heating",,"Cold",,"Hot-Dry","Hot-Humid","M...

  8. " Million Housing Units, Final...

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

    5 Water Heating in U.S. Homes, by Household Income, 2009" " Million Housing Units, Final" ... to 119,999","120,000 or More" "Water Heating" "Total Homes",113.6,23.7,27.5,21....

  9. " Million Housing Units, Final...

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

    Water Heating in U.S. Homes, by Housing Unit Type, 2009" " Million Housing Units, Final" ... Units","5 or More Units","Mobile Homes" "Water Heating" "Total Homes",113.6,71.8,6.7,9,19...

  10. H FINAL REPORT OF OFF-SITE SURVEILLANCE FOR THE FAULTLESS EVENT,

    Office of Legacy Management (LM)

    WRHL-Slr i, ' H FINAL REPORT OF OFF-SITE SURVEILLANCE FOR THE FAULTLESS EVENT, January 19. 1968 by the Southwe stern Radiological Health Laboratory Department of Health, Education. and Welfare Public Health Service Consume r Protection and Environmental Health Service April 1969 This surveillance perforrned under a Memorandum of Understanding (No. SF 54 373) for the U. S. ATOMIC ENERGY COMMISSION LEGAL NOTICE This report was prepared as an account of Government sponsored work. Neither the United

  11. Caspary Thesis Final

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

    DENSITY AND BETA LIMITS IN THE MADISON SYMMETRIC TORUS REVERSED-FIELD PINCH by KYLE JONATHAN CASPARY A dissertation submitted in partial fulfillment of the requirements for the degree of Doctor of Philosophy (PHYSICS) at the UNIVERSITY OF WISCONSIN-MADISON 2014 Date of final oral examination: March 24th, 2014 The dissertation is under review by the following members of the Final Oral Committee: Brett Chapman, Senior Scientist, Physics John Sarff, Professor, Physics Paul Terry, Professor, Physics

  12. Blackout Final Implementation Report

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

    Final Report on the Implementation of the Task Force Recommendations U.S.-Canada Power System Outage Task Force Natural Resources Canada U.S. Department of Energy September 2006 Final Report on the Implementation of the Task Force Recommendations U.S.-Canada Power System Outage Task Force September 2006 Natural Resources Canada U.S. Department of Energy Acknowledgments This document was prepared by staff of Natural Resources Canada and the U.S. Department of Energy. The principal contributors

  13. Final - Gasbuggy S

    Office of Legacy Management (LM)

    Gasbuggy S i t e Environmental Management End State Vision - January 2005 U.S. DEPARTMENT OF ENERGY Gasbuggy Site ENVIRONMENTAL MANAGEMENT END STATE VISION Final Final - Gasbuggy Site Environmental Management End State Vhion - fanuaty 2005 Executive Summary The Environmental Management End State Vision is to be used as the primary tool for communicating the individual site end state to the involved parties (e.g., U.S. Department of Energy [DOE], regulators, public stakeholders, Tribal Nations).

  14. OFF-SITE SURVEILLANCE ACTIVITIES 0" THE SOUTHWESTERN RADIOLOGICAL HEALTH LABORATORY

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

    977 7 OFF-SITE SURVEILLANCE ACTIVITIES 0" THE SOUTHWESTERN RADIOLOGICAL HEALTH LABORATORY from January through June 1969 Environmental Surveillance Southwestern Radiological Health Laboratory ENVIRONMENTAL PROTECTION AGENCY February 1971 This surveillance performed under a Memorandum of Understanding (No. SF 54 373) for the U. S. ATOMIC ENERGY COMMISSION -- SWRHL-97r pf' SWRHL-97r OFF-SITE SURVEILLANCE ACTIVITIES OF THE SOUTHWESTERN RADIOLOGICAL HEALTH LABORATORY from January through June

  15. Radiological Release Event at the Waste Isolation Pilot Plant, February 14, 2014

    Broader source: Energy.gov [DOE]

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

  16. Silver-Mordenite for Radiologic Gas Capture from Complex Streams: Dual

    Office of Scientific and Technical Information (OSTI)

    Catalytic CH3I Decomposition and I Confinement (Journal Article) | SciTech Connect Journal Article: Silver-Mordenite for Radiologic Gas Capture from Complex Streams: Dual Catalytic CH3I Decomposition and I Confinement Citation Details In-Document Search Title: Silver-Mordenite for Radiologic Gas Capture from Complex Streams: Dual Catalytic CH3I Decomposition and I Confinement The effective capture and storage of radiological iodine (129I) remains a strong concern for safe nuclear waste

  17. OFF-SITE SURVEILLANCE ACTIVITIES OF TFE SOUTHWESTERN RADIOLOG1 CAL BEALTH LABORATORY

    Office of Legacy Management (LM)

    SURVEILLANCE ACTIVITIES OF TFE SOUTHWESTERN RADIOLOG1 CAL BEALTH LABORATORY from July through December 1969 - by Environmental Surveillance Southwestern Radiological Health Laboratory ENVIROhMENTAL PROTECTION AGEXCI' February 1971 This surveillance performed under a Xenorandum of Understanding (No. SF 54 373) for the U. S . ATOMIC %I.;Ei?GY COMXESSION OFF-SITE SURVEILLANCE ACTIVITIES OF TRE SQUTmJESTERN RADIOLOGICAL HEALTH LABORATORY from July through December 1969 by Environmental Surveillance

  18. DOE-HDBK-1122-99; Radiological Control Technician Training, Part 5 of 9

    Office of Environmental Management (EM)

    5 of 9 Radiological Control Technician Training Site Academic Training Instructor's Guide Phase I Coordinated and Conducted for Office of Environment, Safety & Health U.S. Department of Energy DOE-HDBK-1122-99 Radiological Control Technician Instructor's Guide ii This page intentionally left blank. DOE-HDBK-1122-99 Radiological Control Technician Instructor's Guide iii Course Developers William Egbert Lawrence Livermore National Laboratory Dave Lent Coleman Research Michael McNaughton Los

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

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    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

  1. DOE-HDBK-1141-2001; Radiological Assessor Training, Instructor's Guide, Part 2 of 5

    Office of Environmental Management (EM)

    5 Radiological Assessor Training DOE-HDBK-1141-2001 Instructor's Guide Office of Environment, Safety & Health U.S. Department of Energy Radiological Assessor Training DOE-HDBK-1141-2001 Instructor's Guide ii This page intentionally left blank. Radiological Assessor Training DOE-HDBK-1141-2001 Instructor's Guide iii Table of Contents Regulatory Documents * (2) ............................................................................ Module1-1 10 CFR Part 835, Background and Focus (3)

  2. Tonopah Test Range Air Monitoring. CY2014 Meteorological, Radiological, and Airborne Particulate Observations

    SciTech Connect (OSTI)

    Nikoloch, George; Shadel, Craig; Chapman, Jenny; Mizell, Steve A.; McCurdy, Greg; Etyemezian, Vicken; Miller, Julianne J.

    2015-10-01

    In 1963, the U.S. Department of Energy (DOE) (formerly the Atomic Energy Commission [AEC]), 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). This test resulted in radionuclide-contaminated soils at Clean Slate I, II, and III. This report documents observations made during ongoing monitoring of radiological, meteorological, and dust conditions at stations installed adjacent to Clean Slate I and Clean Slate III and at the TTR Range Operations Control center. The primary objective of the monitoring effort is to determine if winds blowing across the Clean Slate sites are transporting particles of radionuclide-contaminated soils beyond both the physical and administrative boundaries of the sites. Results for the calendar year (CY) 2014 monitoring are: (1) the gross alpha and gross beta values from the monitoring stations are approximately equivalent to the highest values observed during the CY2014 reporting at the surrounding Community Environmental Monitoring Program (CEMP) stations; (2) only naturally occurring radionuclides were identified in the gamma spectral analyses; (3) the ambient gamma radiation measurements indicate that the average annual gamma exposure is similar at all three monitoring stations and periodic intervals of increased gamma values appear to be associated with storm fronts passing through the area; and (4) the concentrations of both resuspended dust and saltated sand particles generally increase with increasing wind speed. Differences in the observed dust concentrations are likely the result of differences in the soil characteristics immediately adjacent to the monitoring stations. Neither the resuspended particulate radiological analyses nor the ambient gamma radiation measurements suggest wind transport of radionuclide-contaminated soils.

  3. Tonopah Test Range Air Monitoring: CY2013 Meteorological, Radiological, and Airborne Particulate Observations

    SciTech Connect (OSTI)

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

    2014-10-01

    In 1963, the U.S. Department of Energy (DOE) (formerly the Atomic Energy Commission [AEC]), 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). This test resulted in radionuclide-contaminated soils at Clean Slate I, II, and III. This report documents observations made during on-going monitoring of radiological, meteorological, and dust conditions at stations installed adjacent to Clean Slate I and Clean Slate III and at the TTR Range Operations Control center. The primary objective of the monitoring effort is to determine if winds blowing across the Clean Slate sites are transporting particles of radionuclide-contaminated soils beyond both the physical and administrative boundaries of the sites. Results for the calendar year (CY) 2013 monitoring include: (1) the gross alpha and gross beta values from the monitoring stations are approximately equivalent to the highest values observed during the CY2012 reporting at the surrounding Community Environmental Monitoring Program (CEMP) stations (this was the latest documented data available at the time of this writing); (2) only naturally occurring radionuclides were identified in the gamma spectral analyses; (3) the ambient gamma radiation measurements indicate that the average annual gamma exposure is similar at all three monitoring stations and periodic intervals of increased gamma values appear to be associated with storm fronts passing through the area; and (4) the concentrations of both resuspended dust and saltated sand particles generally increase with increasing wind speed. However, differences in the observed dust concentrations are likely due to differences in the soil characteristics immediately adjacent to the monitoring stations. Neither the resuspended particulate radiological analyses nor the ambient gamma radiation measurements suggest wind transport of radionuclide-contaminated soils.

  4. Extension of DOE N 441.1, Radiological Protection for DOE Activities

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

    1998-11-20

    This Notice extends DOE N 441.1, Radiological Protection for DOE Activities, dated 9-30-95 until 6-30-00.

  5. DOE/NV/11718-036 UC-700 FEDERAL RADIOLOGICAL RESPONSE IN THE UNITED STATES

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

    11718-036 UC-700 FEDERAL RADIOLOGICAL RESPONSE IN THE UNITED STATES by Daryl J. Thomé Bechtel Nevada Remote Sensing Laboratory P.O. Box 98521 Las Vegas, Nevada, USA 89193-8521 Bruce W. Hurley, Ph.D. U.S. Department of Energy Nevada Operations Office P.O. Box 98518 Las Vegas, Nevada, USA 89193 ABSTRACT The Federal Radiological Monitoring and Assessment Center (FRMAC) is authorized by the Federal Radiological Emergency Response Plan (FRERP) to coordinate all off-site radiological response

  6. Monitoring activities review of the Radiological Environmental Surveillance Program

    SciTech Connect (OSTI)

    Ritter, P.D.

    1992-03-01

    The 1992 Monitoring Activities Review (MAR) is directed at the Radiological Environment Surveillance Program (RESP) activities at the Radioactive Waste Management Complex (RWMC) of Idaho Engineering Laboratory (INEL). MAR panelists studied RESP documents and discussed their concerns with Environmental Monitoring Unit (EMU) staff and other panel members. These concerns were subsequently consolidated into a collection of recommendations with supporting discussions. Recommendations focus on specific monitoring activities, as well as the overall program. The MAR report also contains pertinent comments that should not require further action.

  7. Federal Radiological Monitoring and Assessment Center Health and Safety Manual

    SciTech Connect (OSTI)

    FRMAC Health and Safety Working Group

    2012-03-20

    This manual is a tool to provide information to all responders and emergency planners and is suggested as a starting point for all organizations that provide personnel/assets for radiological emergency response. It defines the safety requirements for the protection of all emergency responders. The intent is to comply with appropriate regulations or provide an equal level of protection when the situation makes it necessary to deviate. In the event a situation arises which is not addressed in the manual, an appropriate management-level expert will define alternate requirements based on the specifics of the emergency situation. This manual is not intended to pertain to the general public.

  8. RADIOLOGICAL DATA FOR ALARA PLANNING PURPOSES Rev. 1 Contact

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

    RADIOLOGICAL DATA FOR ALARA PLANNING PURPOSES Rev. 1 Contact 1 ft 3 ft 10 ft 25 ft 50 ft 125 ft 100 mR/hr line 5 mR/hr line (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (feet) (feet) Outside of Cask (max) *Unshielded Liner (max) Top of *Unshielded Liner after the cask lid is removed *Unshielded Liner Inside of Cask/Lid Outside of Cask Lifting rig or any other support equipment Does the cask have fixed contamination that may "leach out" during transport (Yes/No)? If yes, please list

  9. Compact cyclone filter train for radiological and hazardous environments

    DOE Patents [OSTI]

    Bench, T.R.

    1998-04-28

    A compact cyclone filter train is disclosed for the removal of hazardous and radiological particles from a gaseous fluid medium. This filter train permits a small cyclone separator to be used in a very small space envelope due to the arrangement of the filter housing adjacent to the separator with the cyclone separator and the filters mounted on a plate. The entire unit will have a hoist connection at the center of gravity so that the entire unit including the separator, the filters, and the base can be lifted and repositioned as desired. 3 figs.

  10. Compact cyclone filter train for radiological and hazardous environments

    DOE Patents [OSTI]

    Bench, Thomas R.

    1998-01-01

    A compact cyclone filter train for the removal of hazardous and radiologi particles from a gaseous fluid medium which permits a small cyclone separator to be used in a very small space envelope due to the arrangement of the filter housing adjacent to the separator with the cyclone separator and the filters mounted on a plate. The entire unit will have a hoist connection at the center of gravity so that the entire unit including the separator, the filters, and the base can be lifted and repositioned as desired.

  11. Radiological Worker Training Power Point Slides for App. A

    Energy Savers [EERE]

    1.1 DOE-HDBK-1130-2008 Overhead 1.1 Regulatory Documents Objectives: * Identify the hierarchy of regulatory documents. * Define the purposes of 10 CFR Parts 820, 830 and 835. * Define the purpose of the DOE Radiological Control Standard. OT 1.2 DOE-HDBK-1130-2008 Overhead 1.2 Regulatory Documents (cont.) Objectives: * Define the terms "shall" and "should" as used in the above documents. * Describe the role of the Defense Nuclear Facilities Safety Board (DNFSB) at DOE sites

  12. Understanding Contamination; Twenty Years of Simulating Radiological Contamination

    SciTech Connect (OSTI)

    Emily Snyder; John Drake; Ryan James

    2012-02-01

    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.

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

    Office of Legacy Management (LM)

    b+^"4-- F Health and Safety Research Division RESULTS OF THE RADIOLOGICAL SURVEY AT 464 DAVISON AVENUE, I4AYWOOD, NEW JERSEY September 1981 Work performed as part of the REMEDIAL ACTION SURVEY AND CERTI FICATION ACTIVITIES OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37830 operated by UNION CARBIDE CORPORATION for the DEPARTMENT OF ENERGY f:. J . , LIST OF FIGURES LIST OF TAELES CONTENTS Page i v INTRODUCTION. 1 SURVEY I.IETHODS. 2 SURVEY RESULTS" 2 0utdoor Survey Results 2

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

    Office of Legacy Management (LM)

    u+'.nop-s' ]._"' Contpact No. tl-7405-eng-25 Health and Safety Research Divlsion RESULTS OF THE RADIOLOGICAL SURVEY AT 467 LATHAI,I STREET, MAYWOOD, NEW JERSEY September 1981 Work perfonned as part of the REMEDIAL ACTION SURVEY AND CERTIFICATION ACTIVITIES OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37830 operated by UNION CARBIDE CORPORATION for the DEPARTI'IENT OF ENERGY CONTENTS Page i v LIST OF FIGURES LIST OF TABLES INTRODUCTION SURVEY METHODS v 1 2 2 2 3 4 5 SURVEY RESUL

  15. OAK RIDGE NATIONAL LABORATORY LABORATORY RESULTS OF THE INDEPENDENT RADIOLOGICAL

    Office of Legacy Management (LM)

    L15 ) pouiuh, _Ols~~~t~~ ^ORNL/RASA-86/70 (LN006V) OAK RIDGE NATIONAL LABORATORY LABORATORY RESULTS OF THE INDEPENDENT RADIOLOGICAL 'i * rf-if nVERIFICATION SURVEY AT 121 AVENUE F, LODI, NEW JERSEY (LN006V) M. G. Yalcintas C. A. Johnson Access to the information in this report is limited to those indicated on the distribution list and to Department of Energy OPfRATED BY and Department of Energy Contractors MARTIN MARIETTA ENERGY SYSTEMS, INC. FOR THE UNITED STATES DEPARTMENT OF ENERGY This

  16. OAK RIDGE NATIONAL LABORATORY LABORATORY RESULTS OF THE INDEPENDENT RADIOLOGICAL

    Office of Legacy Management (LM)

    4q /L~ÂŁe _ *^^.^^^Al~ fl1b /ORNL/RASA-86/69 (LN005V) OAK RIDGE NATIONAL LABORATORY LABORATORY RESULTS OF THE INDEPENDENT RADIOLOGICAL L'ririir g ~VERIFICATION SURVEY AT 3 HANCOCK STREET, LODI, NEW JERSEY (LN005V) M. G. Yalcintas C. A. Johnson Access to the information in this report is limited to those indicated on the distribution list and to Department of Energy OPERATED BY and Department of Energy Contractors MARTIN MARIETTA ENERGY SYSTEMS, INC. FOR THE UNITED STATES DEPARTMENT OF ENERGY

  17. OAK RIDGE NATIONAL LABORATORY RESULTS OF THE INDEPENDENT RADIOLOGICAL

    Office of Legacy Management (LM)

    ornl<^~~ ~~ORNL/RASA-86/64 (MJ18V) orni OAK RIDGE NATIONAL LABORATORY RESULTS OF THE INDEPENDENT RADIOLOGICAL EZ-BBBB - *VERIFICATION SURVEY AT THE BALLOD ASSOCIATES PROPERTY, ROCHELLE PARK, NEW JERSEY (MJ18V) M. G. Yalcintas C. A. Johnson Access to the information in this report is limited to those indicated on the distribution list and to Department of Energy and Department of Energy Contractors OPERATED BY MARTIN MARIETTA ENERGY SYSTEMS, INC. FOR THE UNITED STATES DEPARTMENT OF ENERGY

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

    Office of Legacy Management (LM)

    -I a.d *4dk *-f--l- --- I. ,e-- - .- --_ -- -. ;,. -* " . I . RADIOLOGICAL SCOPING SURVEY OF FO,RMER MONSANTO' FACILITIES (Unit XII and W a rehouse) DAYTON, OHIO Report Date: 4 September 1997 Survey Dak 27 Aitgust 1991 Prepared by: Mark L. Mays, Chief Radiation Safety Branch Sponsored by: M iamisburg Environmental Matigement Reject Office Ohio FTekl Ofice U.S.. Department of Energy Conducted by: %diation Safety Branch Of&e of Environmental Management ggtb Air Base W ing U.S. Departmtnt

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

    Office of Environmental Management (EM)

    DOE-HDBK-1122-99 July 1999 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. 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,

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

    Office of Environmental Management (EM)

    Unit Analysis & Conversion Instructor's Guide 1.02-1 Course Title: Radiological Control Technician Module Title: Unit Analysis & Conversion Module Number: 1.02 Objectives: 1.02.01 Identify the commonly used unit systems of measurement and the base units for mass, length, and time in each system. 1.02.02 Identify the values and abbreviations for SI prefixes. 1.02.03 Given a measurement and the appropriate conversion factor(s) or conversion factor table, convert the measurement to the

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

    Office of Environmental Management (EM)

    Physical Sciences Instructor's Guide 1.03-1 Course Title: Radiological Control Technician Module Title: Physical Sciences Module Number: 1.03 Objectives: 1.03.01 Define the following terms as they relate to physics: a. Work b. Force c. Energy 1.03.02 Identify and describe four forms of energy. 1.03.03 State the Law of Conservation of Energy. 1.03.04 Distinguish between a solid, a liquid, and a gas in terms of shape and volume. 1.03.05 Identify the basic structure of the atom, including the

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

    Office of Environmental Management (EM)

    Nuclear Physics Instructor's Guide 1.04-1 Course Title: Radiological Control Technician Module Title: Nuclear Physics Module Number: 1.04 Objectives: 1.04.01 Identify the definitions of the following terms: a. Nucleon b. Nuclide c. Isotope 1.04.02 Identify the basic principles of the mass-energy equivalence concept. 1.04.03 Identify the definitions of the following terms: a. Mass defect b. Binding energy c. Binding energy per nucleon 1.04.04 Identify the definitions of the following terms: a.

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

    Office of Environmental Management (EM)

    7 Interaction of Radiation with Matter Instructor's Guide 1.07-1 Course Title: Radiological Control Technician Module Title: Interaction of Radiation with Matter Module Number: 1.07 Objectives: 1.07.01 Identify the definitions of the following terms: a. ionization b. excitation c. bremsstrahlung 1.07.02 Identify the definitions of the following terms: a. specific ionization b. linear energy transfer (LET) c. stopping power d. range e. W-value 1.07.03 Identify the two major mechanisms of energy

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

    Office of Environmental Management (EM)

    Biological Effects of Radiation Instructor's Guide 1.08-1 Course Title: Radiological Control Technician Module Title: Biological Effects of Radiation Module Number: 1.08 Objectives: 1.08.01 Identify the function of the following cell structures: a. Cell membrane b. Cytoplasm c. Mitochondria d. Lysosome e. Nucleus f. DNA g. Chromosomes 1.08.02 Identify effects of radiation on cell structures. 1.08.03 Define the law of Bergonie and Tribondeau. 1.08.04 Identify factors which affect the

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

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    Communication Systems Instructor's Guide 2.02-1 Course Title: Radiological Control Technician Module Title: Communication Systems Module Number: 2.02 Objectives: 2.02.01 Explain the importance of good communication. 2.02.02 Identify two methods of communication and be able to determine different types of each. 2.02.03 Describe different types of communication systems. 2.02.04 Describe the FCC and DOE guidelines regarding proper use of communication systems. 2.02.05 Describe general attributes of

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

    Office of Environmental Management (EM)

    Counting Errors and Statistics Instructor's Guide 2.03-1 Course Title: Radiological Control Technician Module Title: Counting Errors and Statistics Module Number: 2.03 Objectives: 2.03.01. Identify five general types of errors that can occur when analyzing radioactive samples, and describe the effect of each source of error on sample measurements. 2.03.02. State two applications of counting statistics in sample analysis. 2.03.03. Define the following terms: a. mode b. median c. mean 2.03.04.

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

    Office of Environmental Management (EM)

    Dosimetry Instructor's Guide 2.04-1 Course Title: Radiological Control Technician Module Title: Dosimetry Module Number: 2.04 Objectives: 2.04.01 Identify the DOE external exposure limits for general employees. 2.04.02 Identify the DOE limits established for the embryo/fetus of a declared pregnant female general employee. L 2.04.03 Identify the administrative exposure control guidelines at your site, including those for the: a. General Employee b. Member of the Public/Minor c. Incidents and

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

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    Instructor's Guide 2.18-1 Course Title: Radiological Control Technician Module Title: Air Sampling Equipment Module Number: 2.18 Objectives: 2.18.01 Identify the factors that affect the operator's selection of a portable air sampler. L 2.18.02 Identify the physical and operating characteristics and the limitation(s) of the Staplex and Radeco portable air samplers. L 2.18.03 Identify the physical and operating characteristics and the limitation(s) of Motor air pumps. L 2.18.04 List the steps for

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

    Office of Environmental Management (EM)

    Unit Analysis & Conversion Study Guide 1.02-1 Course Title: Radiological Control Technician Module Title: Unit Analysis & Conversion Module Number: 1.02 Objectives: 1.02.01 Identify the commonly used unit systems of measurement and the base units for mass, length, and time in each system. 1.02.02 Identify the values and abbreviations for SI prefixes. 1.02.03 Given a measurement and the appropriate conversion factor(s) or conversion factor table, convert the measurement to the specified

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

    Office of Environmental Management (EM)

    Physical Sciences Study Guide 1.03-1 Course Title: Radiological Control Technician Module Title: Physical Sciences Module Number: 1.03 Objectives: 1.03.01 Define the following terms as they relate to physics: a. Work b. Force c. Energy 1.03.02 Identify and describe four forms of energy. 1.03.03 State the Law of Conservation of Energy. 1.03.04 Distinguish between a solid, a liquid, and a gas in terms of shape and volume. 1.03.05 Identify the basic structure of the atom, including the

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

    Office of Environmental Management (EM)

    4 - Nuclear Physics Study Guide 1.04-1 Course Title: Radiological Control Technician Module Title: Nuclear Physics Module Number: 1.04 Objectives: 1.04.01 Identify the definitions of the following terms: a. Nucleon b. Nuclide c. Isotope 1.04.02 Identify the basic principles of the mass-energy equivalence concept. 1.04.03 Identify the definitions of the following terms: a. Mass defect b. Binding energy c. Binding energy per nucleon 1.04.04 Identify the definitions of the following terms: a.

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

    Office of Environmental Management (EM)

    8 Biological Effects of Radiation Study Guide 1.08-1 Course Title: Radiological Control Technician Module Title: Biological Effects of Radiation Module Number: 1.08 Objectives: 1.08.01 Identify the function of the following cell structures: a. Cell membrane b. Cytoplasm c. Mitochondria d. Lysosome e. Nucleus f. DNA g. Chromosomes 1.08.02 Identify effects of radiation on cell structures. 1.08.03 Define the law of Bergonie and Tribondeau. 1.08.04 Identify factors which affect the radiosensitivity

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

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    Number TRNG-0003 Module 1.13 Radiation Detector Theory Study Guide 1.13-1 Course Title: Radiological Control Technician Module Title: Radiation Detector Theory Module Number: 1.13 Objectives: 1.13.01 Identify the three fundamental laws associated with electrical charges. 1.13.02 Identify the definition of current, voltage and resistance and their respective units. 1.13.03 Select the function of the detector and readout circuitry components in a radiation measurement system. 1.13.04 Identify the

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

    Office of Environmental Management (EM)

    Communication Systems Study Guide 2.02-1 Course Title: Radiological Control Technician Module Title: Communication Systems Module Number: 2.02 Objectives: 2.02.01 Explain the importance of good communication. 2.02.02 Identify two methods of communication and be able to determine different types of each. 2.02.03 Describe different types of communication systems. 2.02.04 Describe the FCC and DOE guidelines regarding proper use of communication systems. 2.02.05 Describe general attributes of good

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

    Office of Environmental Management (EM)

    Counting Errors and Statistics Study Guide 2.03-1 Course Title: Radiological Control Technician Module Title: Counting Errors and Statistics Module Number: 2.03 Objectives: 2.03.01. Identify five general types of errors that can occur when analyzing radioactive samples, and describe the effect of each source of error on sample measurements. 2.03.02. State two applications of counting statistics in sample analysis. 2.03.03. Define the following terms: a. mode b. median c. mean 2.03.04. Given a

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

    Office of Environmental Management (EM)

    Dosimetry Study Guide 2.04-1 Course Title: Radiological Control Technician Module Title: Dosimetry Module Number: 2.04 Objectives: 2.04.01 Identify the DOE external exposure limits for general employees. 2.04.02 Identify the DOE limits established for the embryo/fetus of a declared pregnant female general employee. i 2.04.03 Identify the administrative exposure control guidelines at your site, including those for the: a. General employee b. Member of the public/minor c. Incidents and

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

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    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

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

    Office of Environmental Management (EM)

    Study Guide 2.18-1 Course Title: Radiological Control Technician Module Title: Air Sampling Equipment Module Number: 2.18 Objectives: 2.18.01 Identify the factors that affect the operator's selection of a portable air sampler. i 2.18.02 Identify the physical and operating characteristics and the limitation(s) of the Staplex and Radeco portable air samplers. i 2.18.03 Identify the physical and operating characteristics and the limitation(s) of Motor air pumps. i 2.18.04 List the steps for a

  9. DOE-HDBK-1141-2001; Radiological Assessor Training

    Office of Environmental Management (EM)

    41-2001 April 2001 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

  10. DOE-STD-1098-99; Radiological Control

    Office of Environmental Management (EM)

    NOT MEASUREMENT SENSITIVE DOE-STD-1098-99 July 1999 Reaffirmation December 2004 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 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

  11. DOE-STD-1098-99; Radiological Control

    National Nuclear Security Administration (NNSA)

    NOT MEASUREMENT SENSITIVE DOE-STD-1098-99 July 1999 Reaffirmation December 2004 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 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

  12. Final 2011 Supplement Analysis of the 2005 Final SWEIS | National...

    National Nuclear Security Administration (NNSA)

    Office of General Counsel National Environmental Policy Act (NEPA) NEPA Reading Room Final 2011 Supplement Analysis of the 2005 ... Final 2011 Supplement Analysis of the...

  13. NV/YMP radiological control manual, Revision 2

    SciTech Connect (OSTI)

    Gile, A.L.

    1996-11-01

    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.

  14. Radiological Contingency Planning for the Mars Science Laboratory Launch

    SciTech Connect (OSTI)

    Paul P. Guss

    2008-04-01

    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.

  15. Radiological Contingency Planning for the Mars Science Laboratory Launch

    SciTech Connect (OSTI)

    Paul Guss, Robert Augdahl, Bill Nickels, Cassandra Zellers

    2008-04-16

    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.

  16. Radiological approaches in the evaluation of joint disease in children

    SciTech Connect (OSTI)

    Poznanski, A.K.; Conway, J.J.; Shkolnik, A.; Pachman, L.M.

    1987-04-01

    In summary, the newer technologies in radiology have allowed us to visualize more clearly the manifestation of joint disease in children. The presence of small erosions and cartilage damage can be seen much better with magnetic resonance imaging than with any other modality short of arthrography, a much more invasive examination. Joint effusion, although sometimes visualized with conventional radiography, is probably best recognized with ultrasound or magnetic resonance imaging, although it can be detected with computed tomography as well. For the evaluation of avascular necrosis that can be associated with steroid use in joint disease, bone scintigraphy is a simple, sensitive method. Magnetic resonance may be as or more sensitive and gives additional information as well. In the detection of change with time, conventional radiography probably will remain the standard as it is still the simplest, least expensive examination; however, it has many limitations in specific cases. Bone scintigraphy may be of value in selected cases. Although we have still not had enough experience with magnetic resonance imaging to use it as a way of evaluating progress of joint disease, it promises to be the most sensitive radiologic measure of evaluating progress as small anatomical changes can be detected within the cartilage, which cannot be done easily with other means. 27 references.

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

    SciTech Connect (OSTI)

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

    1981-07-23

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

  18. FINAL REPORT VELA UNIFORM PROJECT SPONSORED BY THE ADVANCED RESEARCH PROJECTS AGENCY OF THE

    Office of Legacy Management (LM)

    VUF -1009 FINAL REPORT - VELA UNIFORM PROJECT SPONSORED BY THE ADVANCED RESEARCH PROJECTS AGENCY OF THE DEPARTMENT OF DEFENSE AND THE U. S. ATOMIC ENERGY COMMl SSlON FALLON, NEVADA OCTOBER 26,1963 FINAL REPORT OF OFF-SITE SURVEILLANCE Southwestern Radiological Health Laboratory September 1, 1964 Issuance Date: November 27, 1964 L E G A L N O T I C E This report war preprred a r an account of Government rponrored work. Neither the Unlted Strtor, nor the Commlerlon, nor m y perron acting on behalf

  19. Radiological Instrumentation Assessment for King County Wastewater Treatment Division

    SciTech Connect (OSTI)

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

    2005-05-19

    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.

  20. " Million Housing Units, Final"

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

    Air Conditioning in U.S. Homes, by Housing Unit Type, 2009" " Million Housing Units, Final" ,,"Housing Unit Type" ,,"Single-Family Units",,"Apartments in Buildings With" ,"Total U.S.1 (millions)" ,," Detached"," Attached"," 2 to 4 Units","5 or More Units","Mobile Homes" "Air Conditioning" "Total Homes",113.6,71.8,6.7,9,19.1,6.9 "Air Conditioning Equipment"

  1. Final Technical Report

    SciTech Connect (OSTI)

    Gilbert, Chris

    2014-11-13

    The project, �Capital Investment to Fund Equipment Purchases and Facility Modifications to Create a Sustainable Future for EnergyXchange� served to replace landfill gas energy with alternative energy resources, primarily solar and wood waste. This is the final project closeout report.

  2. Status Update on the NCRP Scientific Committee SC 5-1 Report: Decision Making for Late-Phase Recovery from Nuclear or Radiological Incidents - 13450

    SciTech Connect (OSTI)

    Chen, S.Y.

    2013-07-01

    In August 2008, the U.S. Department of Homeland Security (DHS) issued its final Protective Action Guide (PAG) for radiological dispersal device (RDD) and improvised nuclear device (IND) incidents. This document specifies protective actions for public health during the early and intermediate phases and cleanup guidance for the late phase of RDD or IND incidents, and it discusses approaches to implementing the necessary actions. However, while the PAG provides specific guidance for the early and intermediate phases, it prescribes no equivalent guidance for the late-phase cleanup actions. Instead, the PAG offers a general description of a complex process using a site-specific optimization approach. This approach does not predetermine cleanup levels but approaches the problem from the factors that would bear on the final agreed-on cleanup levels. Based on this approach, the decision-making process involves multifaceted considerations including public health, the environment, and the economy, as well as socio-political factors. In an effort to fully define the process and approach to be used in optimizing late-phase recovery and site restoration following an RDD or IND incident, DHS has tasked the NCRP with preparing a comprehensive report addressing all aspects of the optimization process. Preparation of the NCRP report is a three-year (2010-2013) project assigned to a scientific committee, the Scientific Committee (SC) 5-1; the report was initially titled, Approach to Optimizing Decision Making for Late- Phase Recovery from Nuclear or Radiological Terrorism Incidents. Members of SC 5-1 represent a broad range of expertise, including homeland security, health physics, risk and decision analysis, economics, environmental remediation and radioactive waste management, and communication. In the wake of the Fukushima nuclear accident of 2011, and guided by a recent process led by the White House through a Principal Level Exercise (PLE), the optimization approach has since been expanded to include off-site contamination from major nuclear power plant accidents as well as other nuclear or radiological incidents. The expanded application under the current guidance has thus led to a broadened scope of the report, which is reflected in its new title, Decision Making for Late-Phase Recovery from Nuclear or Radiological Incidents. The NCRP report, which is due for publication in 2013, will substantiate the current DHS guidance by clarifying and elaborating on the processes required for the development and implementation of procedures for optimizing decision making for late-phase recovery, enabling the establishment of cleanup goals on a site-specific basis. The report will contain a series of topics addressing important issues related to the long-term recovery from nuclear or radiological incidents. Special topics relevant to supporting the optimization of the decision-making process will include cost-benefit analysis, radioactive waste management, risk communication, stakeholder interaction, risk assessment, and decontamination approaches and techniques. The committee also evaluated past nuclear and radiological incidents for their relevance to the report, including the emerging issues associated with the Fukushima nuclear accident. Thus, due to the commonality of the late-phase issues (such as the potential widespread contamination following an event), the majority of the information pertaining to the response in the late-phase decision-making period, including site-specific optimization framework and approach, could be used or adapted for use in case of similar situations that are not due to terrorism, such as those that would be caused by major nuclear facility accidents or radiological incidents. To ensure that the report and the NCRP recommendations are current and relevant to the effective implementation of federal guidance, SC 5-1 has actively coordinated with the agencies of interest and other relevant stakeholders throughout the duration of the project. The resulting report will be an important resource to guide those involved in late-phase recovery efforts following a nuclear or radiological incident. (authors)

  3. 2014 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Lewis, Mike

    2015-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  4. 2013 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2014-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  5. 2011 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2012-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  6. 2010 Radiological Monitoring Results Associated with the Advance Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    mike lewis

    2011-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  7. 2012 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2013-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  8. Final Scientific/Technical Report

    SciTech Connect (OSTI)

    Troxell, W; Batchelor, A

    2012-11-28

    Final report for the formation of faculty and education establishing Colorado State's Smart Grid Integration Center

  9. Final Technical Report

    SciTech Connect (OSTI)

    Maxwell, Mike, J., P.E.

    2012-08-30

    The STI product is the Final Technical Report from ReliOn, Inc. for contract award DE-EE0000487: Recovery Act PEM Fuel Cell Systems Providing Emergency Reserve and Backup Power. The program covered the turnkey deployment of 431 ReliOn fuel cell systems at 189 individual sites for AT&T and PG&E with ReliOn functioning as the primary equipment supplier and the project manager. The Final Technical Report provides an executive level summary, a comparison of the actual accomplishments vs. the goals and objectives of the project, as well as a summary of the project activity from the contract award date of August 1, 2009 through the contract expiration date of December 31, 2011. Two photos are included in the body of the report which show hydrogen storage and bulk hydrogen refueling technologies developed as a result of this program.

  10. CX-100 Final Report

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

    SAND2008-4648 Unlimited Release Printed July 2008 Blade System Design Studies Phase II: Final Project Report Derek S. Berry TPI Composites, Inc. 373 Market Street Warren, RI 02885 Abstract This report details the work completed under Phase II of the Sandia National Laboratories Blade System Design Study blade design and manufacturing project; an integrated 9 meter blade design, tooling design and manufacturing, assembly fixture design and fabrication, blade production, blade instrumentation and

  11. DOE Laminar Final Report

    Office of Scientific and Technical Information (OSTI)

    1. Award #: DE-FG02-05ER46250 Institution: Cornell University. 2. Dates: Date of report: August 1, 2013. 3. Title: Transport Phenomena and Interfacial Kinetics in Planar Microfluidic Membraneless Fuel Cells P.I.: Héctor D. Abruña, Chemistry and Chemical Biology, Cornell University co-P.I.: Abraham D. Stroock, Chemical and Biomolecular Engineering, Cornell University 4. Final Report Abstract: Our work is focused on membraneless laminar flow fuel cells, an unconventional fuel cell technology,

  12. Final Environmental Assessment

    National Nuclear Security Administration (NNSA)

    1995 :&,, ' - , i . -- Final Environmental Assessment for Device Assembly - Facility Operations f 3: >fi - , - , ' , 7 - . ' ' , , . I 8 ' , :-<:- L , a . ' ' ' -L. -1 , , ~ e m - . - I ! - , - # 8 , r I I , , , - , . .-- - ' - I S - . ! - , - , Y 2 L - . . 8 : L.-- , r Nevada ' f e s t ~ h e , Nye county, Nevada U. S. Department Of Energy - , 8 - - . 8 - I,, ' - 8 - - , , 8 ENVIRONMENTAL ASSESSMENT for DEVICE ASSEMBLY FACIUTY OPERATIONS MAY 1995 TABLE OF CONTENTS LISTOFFIGURES . . . .

  13. Environmental Management Headquarters Corrective Action Plan- Radiological Release Phase II

    Broader source: Energy.gov [DOE]

    The purpose ofthis Corrective Action Plan (CAP) is to specify U.S. Departme~t of Energy (DOE) actions for addressing Office of Environmental Management (EM) Headquarters (HQ) issues identified in the Accident Investigation Report for the Phase 2: Radiological Release Event at the Waste Isolation Pilot Plant (WIPP) on February 14, 2014. The report identified 24 Conclusions and 40 Judgments of Need (JONs). Six of the Conclusions and five of the JONs were determined to be associated with EM HQ oversight of the operations. As such, EM HQ has taken the action to develop the CAP for those JONs specific to HQ (i.e., JONs 6,30,31 ,37 and 40). This report documents those corrective actions, along with the responsible office and due dates for completing the actions.

  14. Status of ion sources at National Institute of Radiological Sciences

    SciTech Connect (OSTI)

    Kitagawa, A.; Fujita, T.; Goto, A.; Hattori, T.; Hamano, T.; Hojo, S.; Honma, T.; Imaseki, H.; Katagiri, K.; Muramatsu, M.; Sakamoto, Y.; Sekiguchi, M.; Suda, M.; Sugiura, A.; Suya, N.

    2012-02-15

    The National Institute of Radiological Sciences (NIRS) maintains various ion accelerators in order to study the effects of radiation of the human body and medical uses of radiation. Two electrostatic tandem accelerators and three cyclotrons delivered by commercial companies have offered various life science tools; these include proton-induced x-ray emission analysis (PIXE), micro beam irradiation, neutron exposure, and radioisotope tracers and probes. A duoplasmatron, a multicusp ion source, a penning ion source (PIG), and an electron cyclotron resonance ion source (ECRIS) are in operation for these purposes. The Heavy-Ion Medical Accelerator in Chiba (HIMAC) is an accelerator complex for heavy-ion radiotherapy, fully developed by NIRS. HIMAC is utilized not only for daily treatment with the carbon beam but also for fundamental experiments. Several ECRISs and a PIG at HIMAC satisfy various research and clinical requirements.

  15. HAZARDS OF THERMAL EXPANSION FOR RADIOLOGICAL CONTAINER ENGULFED IN FIRE

    SciTech Connect (OSTI)

    Donna Post Guillen

    2013-05-01

    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.

  16. DOE/EA-1499; Radiological/Nuclear Countermeasures Test and Evaluation Complex, Nevada Test Site Final Environmental Assessment

    National Nuclear Security Administration (NNSA)

    Supplement Analysis (SA) for the NTS EIS addressed the increase in activities associated with combating terrorism and counterterrorism training as well as related activities (DOE, 2003). The evaluation in the SA focused on certain areas of the NTS and anticipated sizes of facilities. Although many of the individual components were described in the SA, the scope of the proposed Rad/NucCTEC is substantially greater than anticipated and its location in a previously undisturbed area was not

  17. EA-1148: Final Environmental Assessment | Department of Energy

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

    48: Final Environmental Assessment EA-1148: Final Environmental Assessment Electrometallurgical Treatment Research and Demonstration Project in the Fuel Conditioning Facility at Argonne National Laboratory-West DOE prepard an EA that evaluated the potential environmental impacts associated with the research and demonstration of electrometallurgical technology for treating Experimental Breeder Reactor-II Spent Nuclear Fuel in the Fuel Conditioning Facility at Argonne National Laboratory-West. PDF

  18. Near-Final Agenda

    Office of Environmental Management (EM)

    09 26 2014 Near-Final Agenda Workshop on Estimating the Benefits and Costs of Distributed Energy Technologies September 30 - October 1, 2014 Washington, DC September 30 - Day One 8:00 a.m. Coffee and Registration 8:30 Welcome and Opening Remarks * Overview and purpose of the workshop o Comments by senior DOE Officials o Q&A (time permitting) * Around-the-room introductions 9:00 Framing the Issues * Three presentations on key issues * Facilitated discussion 10:15 BREAK 10:30 Estimating the

  19. Clean Fleet Final Report

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    2 P r o j e c t D e s i g n a n d I m p l e m e n t a t i o n FINAL REPORT December 1995 December 1995 This information was prepared by Battelle Memorial Institute, Columbus Operations, through sponsorship by various companies and associations, the South Coast Air Quality Management District (District), and the California Energy Commission (Commission). Battelle has endeavored to produce a high quality study consistent with its contract commitments. However, because of the research and/or

  20. Clean Fleet Final Report

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    3 V e h i c l e M a i n t e n a n c e a n d D u r a b i l i t y FINAL REPORT December 1995 December 1995 December 1995 This information was prepared by Battelle Memorial Institute, Columbus Operations, through sponsor- ship by various companies and associations, the South Coast Air Quality Management District (District), and the California Energy Commission (Commission). Battelle has endeavored to produce a high quality study consistent with its contract commitments. However, because of the

  1. " Million Housing Units, Final...

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

    "Air Conditioning",94,65.8,28.3,54.6,6.5,3.4,2.2,1.1,5.1,2,13.2,4.7,1.2 "Water Heating",47.1,30.8,16.4,23.9,3.6,1.3,1.1,0.3,3,1,7.7,4.2,1 "Cooking",71.2,48.4,22.8,40.8,5....

  2. " Million Housing Units, Final...

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

    "Air Conditioning",94,22.4,15,4.3,3.1,1.8,5.9,7.4,2.3,3.4,1.7 "Water Heating",47.1,7.6,4.8,0.7,0.8,0.7,2.7,2.8,1,1.4,0.4 "Cooking",71.2,15.4,9.7,1.6,1.9,1.6,4.7...

  3. " Million Housing Units, Final...

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

    "Secondary",26.8,19.7,1.7,1.7,2.1,1.8 "Air Conditioning",94,61.1,5.6,6.3,15.2,5.8 "Water Heating",47.1,27.5,2.3,3.3,8.7,5.2 "Cooking",71.2,46,4,4.8,12.3,4.1 "Other",113.6,71.8,6.7,...

  4. " Million Housing Units, Final...

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

    "Secondary",26.8,4.3,7.4,9.7,5.4 "Air Conditioning",94,16.5,22.4,40.5,14.6 "Water Heating",47.1,5.1,7.6,27.3,7 "Cooking",71.2,10.1,15.4,31.7,13.9 "Other",113.6,20.8,25.9,42....

  5. " Million Housing Units, Final...

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

    ...econdary",26.8,6.5,8.7,4.6,3.9,3.1 "Air Conditioning",94,24.6,30.2,15.1,13.5,10.6 "Water Heating",47.1,14,14.9,7.5,6.2,4.6 "Cooking",71.2,19.6,23.4,11.3,9.7,7.1 ...

  6. " Million Housing Units, Final...

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

    "Secondary",26.8,9.9,9.4,2.5,3.2,1.7 "Air Conditioning",94,30.2,33,10.5,18.3,2.1 "Water Heating",47.1,10.9,17.6,3,13,2.6 "Cooking",71.2,22.9,23.6,6,14.3,4.5 "Other",113.6,38.8,35....

  7. Radiological Risk Assessment for King County Wastewater Treatment Division

    SciTech Connect (OSTI)

    Strom, Daniel J.

    2005-08-05

    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.

  8. ISSUANCE 2015-12-11: Final Rule Regarding Test Procedures for Small, Large,

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

    and Very Large Air-Cooled Commercial Package Air Conditioning and Heating Equipment | Department of Energy 1: Final Rule Regarding Test Procedures for Small, Large, and Very Large Air-Cooled Commercial Package Air Conditioning and Heating Equipment ISSUANCE 2015-12-11: Final Rule Regarding Test Procedures for Small, Large, and Very Large Air-Cooled Commercial Package Air Conditioning and Heating Equipment PDF icon CUAC TP Final Rule.pdf More Documents & Publications ISSUANCE 2015-07-27:

  9. Preliminary report on operational guidelines developed for use in emergency preparedness and response to a radiological dispersal device incident.

    SciTech Connect (OSTI)

    Yu, C.; Cheng, J.-J.; Kamboj, S.; Domotor, S.; Wallo, A.; Environmental Science Division; DOE

    2006-12-15

    This report presents preliminary operational guidelines and supporting work products developed through the interagency Operational Guidelines Task Group (OGT). The report consolidates preliminary operational guidelines, all ancillary work products, and a companion software tool that facilitates their implementation into one reference source document. The report is intended for interim use and comment and provides the foundation for fostering future reviews of the operational guidelines and their implementation within emergency preparedness and response initiatives in the event of a radiological dispersal device (RDD) incident. The report principally focuses on the technical derivation and presentation of the operational guidelines. End-user guidance providing more details on how to apply these operational guidelines within planning and response settings is being considered and developed elsewhere. The preliminary operational guidelines are categorized into seven groups on the basis of their intended application within early, intermediate, and long-term recovery phases of emergency response. We anticipate that these operational guidelines will be updated and refined by interested government agencies in response to comments and lessons learned from their review, consideration, and trial application. This review, comment, and trial application process will facilitate the selection of a final set of operational guidelines that may be more or less inclusive of the preliminary operational guidelines presented in this report. These and updated versions of the operational guidelines will be made available through the OGT public Web site (http://ogcms.energy.gov) as they become finalized for public distribution and comment.

  10. Final Scientific EFNUDAT Workshop

    ScienceCinema (OSTI)

    None

    2011-10-06

    The Final Scientific EFNUDAT Workshop - organized by the CERN/EN-STI group on behalf of n_TOF Collaboration - will be held at CERN, Geneva (Switzerland) from 30 August to 2 September 2010 inclusive.EFNUDAT website: http://www.efnudat.euTopics of interest include: Data evaluationCross section measurementsExperimental techniquesUncertainties and covariancesFission propertiesCurrent and future facilities  International Advisory Committee: C. Barreau (CENBG, France)T. Belgya (IKI KFKI, Hungary)E. Gonzalez (CIEMAT, Spain)F. Gunsing (CEA, France)F.-J. Hambsch (IRMM, Belgium)A. Junghans (FZD, Germany)R. Nolte (PTB, Germany)S. Pomp (TSL UU, Sweden) Workshop Organizing Committee: Enrico Chiaveri (Chairman)Marco CalvianiSamuel AndriamonjeEric BerthoumieuxCarlos GuerreroRoberto LositoVasilis Vlachoudis Workshop Assistant: Géraldine Jean

  11. Final Progress Report

    SciTech Connect (OSTI)

    Josef Michl

    2011-10-31

    In this project we have established guidelines for the design on organic chromophores suitable for producing high triplet yields via singlet fission. We have proven their utility by identifying a chromophore of a structural class that had never been examined for singlet fission before, 1,3-diphenylisobenzofuran, and demonstrating in two independent ways that a thin layer of this material produces a triplet yield of 200% within experimental error. We have also designed a second chromophore of a very different type, again of a structural class that had not been examined for singlet fission before, and found that in a thin layer it produces a 70% triplet yield. Finally, we have enhanced the theoretical understanding of the quantum mechanical nature of the singlet fission process.

  12. Final Scientific EFNUDAT Workshop

    ScienceCinema (OSTI)

    None

    2011-10-06

    The Final Scientific EFNUDAT Workshop - organized by the CERN/EN-STI group on behalf of n_TOF Collaboration - will be held at CERN, Geneva (Switzerland) from 30 August to 2 September 2010 inclusive.EFNUDAT website: http://www.efnudat.euTopics of interest include: Data evaluationCross section measurementsExperimental techniquesUncertainties and covariancesFission propertiesCurrent and future facilities  International Advisory Committee: C. Barreau (CENBG, France)T. Belgya (IKI KFKI, Hungary)E. Gonzalez (CIEMAT, Spain)F. Gunsing (CEA, France)F.-J. Hambsch (IRMM, Belgium)A. Junghans (FZD, Germany)R. Nolte (PTB, Germany)S. Pomp (TSL UU, Sweden) Workshop Organizing Committee: Enrico Chiaveri (Chairman)Marco CalvianiSamuel AndriamonjeEric BerthoumieuxCarlos GuerreroRoberto LositoVasilis Vlachoudis Workshop Assistant: Géraldine Jean

  13. FINAL/ SCIENTIFIC TECHNICAL REPORT

    SciTech Connect (OSTI)

    McDonald, Henry; Singh, Suminderpal

    2006-08-28

    The overall objective of the Chattanooga fuel cell demonstrations project was to develop and demonstrate a prototype 5-kW grid-parallel, solid oxide fuel cell (SOFC) system that co-produces hydrogen, based on Ion America’s technology. The commercial viability of the 5kW SOFC system was tested by transporting, installing and commissioning the SOFC system at the Alternative Energy Laboratory at the University of Tennessee – Chattanooga. The system also demonstrated the efficiency and the reliability of the system running on natural gas. This project successfully contributed to the achievement of DOE technology validation milestones from the Technology Validation section of the Hydrogen, Fuel Cells and Infrastructure Technologies Program Multi-Year Research, Development and Demonstration Plan. Results of the project can be found in the final technical report.

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

    SciTech Connect (OSTI)

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

    2006-07-01

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

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

    SciTech Connect (OSTI)

    Not Available

    1984-08-01

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

  16. Radioactive Waste Management Complex low-level waste radiological performance assessment

    SciTech Connect (OSTI)

    Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

    1994-04-01

    This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected.

  17. Federal Radiological Monitoring and Assessment Center Monitoring Manual Volume 2, Radiation Monitoring and Sampling

    SciTech Connect (OSTI)

    NSTec Aerial Measurement Systems

    2012-07-31

    The FRMAC Monitoring and Sampling Manual, Volume 2 provides standard operating procedures (SOPs) for field radiation monitoring and sample collection activities that are performed by the Monitoring group during a FRMAC response to a radiological emergency.

  18. RPS 11.2 Radiological Work Practices 3/9/95

    Broader source: Energy.gov [DOE]

    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...

  19. 2013 Environmental/Radiological Assistance Directory (ERAD) Presentations

    Broader source: Energy.gov [DOE]

    November 2013 Derived Intervention and Response Levels for Tritium Oxide at the Savannah River Site May 2013 THE MARSAME METHODOLOGY Fundamentals, Benefits, and Applications March 2013 Working to Keep our Shipments Safe, Secure and Economical ANL Facility Decommissioning Training Program January 2013 DOE Corporate Operating Experience Program Radiological Reporting Annual Site Environmental Reports (ASERs) & HSS Environmental and Radiation Protection Performance Dashboards November 2012 Environmental Measurements in an Emergency: This is not a Drill! BGRR D&D Presentation for the DOE ERAD Working Group September 2012 Development of Authorized Limits for Portsmouth Oil Inventory Disposition Development of Authorized Limits for Portsmouth Oil Inventory Disposition Development of Authorized Limits for Portsmouth Oil Inventory Disposition Clearance of Real and Personal Property Under DOE Radiation Protection Directive DOE Order 458.1 June 2012 RESRAD Codes for ERAD June 27, 2012 Florida International University (FIU) D&D Knowledge Management Information Tool, June 27, 2012 May 2012 Integrated Cloud Based Environmental Data Management System DOE Order 458.1, Radiation Protection of the Public and the Environment

  20. Radiological Impact Assessment (RIA) following a postulated accident in PHWRS

    SciTech Connect (OSTI)

    Soni, N.; Kansal, M.; Rammohan, H. P.; Malhotra, P. K.

    2012-07-01

    Radiological Impact Assessment (RIA) following postulated accident i.e Loss of Coolant Accident (LOCA) with failed Emergency Core Cooling System (ECCS), performed as part of the reactor safety analysis of a typical 700 MWe Indian Pressurized Heavy Water Reactor(PHWR). The rationale behind the assessment is that the public needs to be protected in the event that the postulated accident results in radionuclide release outside containment. Radionuclides deliver dose to the human body through various pathways namely, plume submersion, exposure due to ground deposition, inhalation and ingestion. The total exposure dose measured in terms of total effective dose equivalent (TEDE) is the sum of doses to a hypothetical adult human at exclusion zone boundary by all the exposure pathways. The analysis provides the important inputs to decide upon the type of emergency counter measures to be adopted during the postulated accident. The importance of the various pathways in terms of contribution to the total effective dose equivalent(TEDE) is also assessed with respect to time of exposure. Inhalation and plume gamma dose are the major contributors towards TEDE during initial period of accident whereas ingestion and ground shine dose start dominating in TEDE in the extended period of exposure. Moreover, TEDE is initially dominated by I-131, Kr-88, Te-132, I-133 and Sr-89, whereas, as time progresses, Xe-133,I-131 and Te-132 become the main contributors. (authors)

  1. Method and apparatus for laser-controlled proton beam radiology

    DOE Patents [OSTI]

    Johnstone, Carol J.

    1998-01-01

    A proton beam radiology system provides cancer treatment and proton radiography. The system includes an accelerator for producing an H.sup.- beam and a laser source for generating a laser beam. A photodetachment module is located proximate the periphery of the accelerator. The photodetachment module combines the H.sup.- beam and laser beam to produce a neutral beam therefrom within a subsection of the H.sup.- beam. The photodetachment module emits the neutral beam along a trajectory defined by the laser beam. The photodetachment module includes a stripping foil which forms a proton beam from the neutral beam. The proton beam is delivered to a conveyance segment which transports the proton beam to a patient treatment station. The photodetachment module further includes a laser scanner which moves the laser beam along a path transverse to the cross-section of the H.sup.- beam in order to form the neutral beam in subsections of the H.sup.- beam. As the scanning laser moves across the H.sup.- beam, it similarly varies the trajectory of the proton beam emitted from the photodetachment module and in turn varies the target location of the proton beam upon the patient. Intensity modulation of the proton beam can also be achieved by controlling the output of the laser.

  2. Environmental Management Headquarters Corrective Action Plan- Radiological Release Phase I

    Broader source: Energy.gov [DOE]

    The purpose of this Corrective Action Plan (CAP) is to specify U.S. Department of Energy (DOE) actions for addressing Office of Environmental Management (EM) Headquarters (HQ) issues identified in the Accident Investigation Report for the Phase 1: Radiological Release Event at the Waste Isolation Pilot Plant (WIPP) on February 14, 2014. The report identified 31 Conclusions and 47 Judgments of Need (JON). Twelve of the Conclusions and ten of the JONs were determined to be associated with DOE HQ oversight of the operations. As such, EM HQ has taken the action to develop the CAP for those JONs specific to HQ (i.e., JONs 11, 13, 23, 25, 26, 32, 44-47). This report documents those corrective actions, along with the responsible office and due dates for completing the actions. The overall approval process for the CAPs associated with this event will involve both the Carlsbad Field Office (CBFO) and EM HQ offices. Specifically, CBFO will approve the NWP CAP (with EM HQ concurrence); EM HQ Office of Safety, Security, and Quality Programs (EM-40) will approve the CBFO CAP; and the Assistant Secretary for the Office of Environmental Management (EM-1) will approve the EM HQ CAP.

  3. Method and apparatus for laser-controlled proton beam radiology

    DOE Patents [OSTI]

    Johnstone, C.J.

    1998-06-02

    A proton beam radiology system provides cancer treatment and proton radiography. The system includes an accelerator for producing an H{sup {minus}} beam and a laser source for generating a laser beam. A photodetachment module is located proximate the periphery of the accelerator. The photodetachment module combines the H{sup {minus}} beam and laser beam to produce a neutral beam therefrom within a subsection of the H{sup {minus}} beam. The photodetachment module emits the neutral beam along a trajectory defined by the laser beam. The photodetachment module includes a stripping foil which forms a proton beam from the neutral beam. The proton beam is delivered to a conveyance segment which transports the proton beam to a patient treatment station. The photodetachment module further includes a laser scanner which moves the laser beam along a path transverse to the cross-section of the H{sup {minus}} beam in order to form the neutral beam in subsections of the H{sup {minus}} beam. As the scanning laser moves across the H{sup {minus}} beam, it similarly varies the trajectory of the proton beam emitted from the photodetachment module and in turn varies the target location of the proton beam upon the patient. Intensity modulation of the proton beam can also be achieved by controlling the output of the laser. 9 figs.

  4. Title XVII Final Rule | Department of Energy

    Energy Savers [EERE]

    Final Rule Title XVII Final Rule PDF icon Title XVII Final Rule More Documents & Publications Final Rule (December 4, 2009) Notice of Proposed Rulemaking (August 6, 2009) Final Rule (October 23, 2007)

  5. " Million Housing Units, Final...

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

    "Air Conditioning",94,40.5,21.2,2.8,3.4,6.7,3.2,5.1,6.9,2.4,4.5,12.4,8.2,4.1 "Water Heating",47.1,27.3,16.1,1.8,1.8,6.2,2.2,4.2,5,1.8,3.1,6.2,4,2.3 "Cooking",71.2,31.7,17.9,2....

  6. " Million Housing Units, Final...

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

    ...,3.5,2.9,3.9,3.8,3.8,3 "Air Conditioning",94,10.5,4,10.6,10.5,15.1,14.1,14.7,14.4 "Water Heating",47.1,4.1,1.7,3.8,4.4,8.4,9.2,8,7.5 "Cooking",71.2,7,2.6,6.7,7.8,12.6,11.9,11.4,11....

  7. " Million Housing Units, Final...

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

    ...5,3.6,2.5,1.5,3.1,3.5 "Air Conditioning",94,18.3,22.3,17.9,11.9,8.1,5.1,10.4,12.8 "Water Heating",47.1,11.4,12.8,8.9,5.6,3.2,1.7,3.5,8.2 "Cooking",71.2,14.2,17.1,13.4,9.2,6,3.5,7.7...

  8. " Million Housing Units, Final...

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

    "Air Conditioning",94,14.6,5.7,2.4,0.9,1.4,3.3,2.1,1.2,8.9,6.9,2.1 "Water Heating",47.1,7,2.5,0.9,0.3,0.6,1.6,1.2,0.4,4.5,1.4,3.1 "Cooking",71.2,13.9,5.1,3,1.4,1.6,2...

  9. " Million Housing Units, Final...

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

    ...3,1.3,0.6,0.7,2.9,1,1.5,0.4 "Air Conditioning",94,16.5,3.9,1.9,2,12.6,5.3,4.4,2.9 "Water Heating",47.1,5.1,1.4,0.5,0.9,3.7,1.2,2.1,0.4 "Cooking",71.2,10.1,3.6,1.4,2.3,6.5,2.3,3.2,1 ...

  10. Southwestern Radiological Health Laboratory U. S. Department of Health, Education and Welfare

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

    the Southwestern Radiological Health Laboratory U. S. Department of Health, Education and Welfare Public Health Service . Environmental Health Service May 1970 OFF-SITE SURVEILLANCE ACTIVITIES OF THE SOUTHWESTERN RADIOLOGICAL HEALTH LABORATORY from July through December 1967 This surveillance performed under a Memorandum of Understanding (No. SF 54 373) for the U. S. ATOMIC ENERGY COMMISSION TABLEOFCONTENTS ABSTRACT TABLE OF CONTENTS LIST OF TABLES LIST OF FIGURES I. INTRODUCTION II. OPERATIONAL

  11. RESRAD Family of Codes - A Suite of Tools for Environmental Radiological Dose Assessment

    Office of Environmental Management (EM)

    RESRAD Family of Codes - A Suite of Tools for Environmental Radiological Dose Assessment Charley Yu, PhD, CHP RESRAD Program Manager Environmental Science Division Argonne National Laboratory, Argonne, IL Presented at Environmental Radiological Assistance Directory Web Conference June 27, 2012 Presentation Outline  RESRAD Family of Codes Overview  Brief Overview of the RESRAD Methodology  RESRAD-BUILD Overview  RESRAD-OFFSITE Overview  RESRAD-BIOTA Overview  Summary 2 RESRAD

  12. SWKHL-&Slr OFF-SITE SURVEILLANCE ACTIVITIES OF THE SOUTHWESTERN RADIOLOGICAL HEALTH LABORATORY

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

    SWKHL-&Slr OFF-SITE SURVEILLANCE ACTIVITIES OF THE SOUTHWESTERN RADIOLOGICAL HEALTH LABORATORY from January through June 1968 bY Environmental Surveillance Western Environmental Research Laboratory ENVIRONMENTAL PROTECTION AGENCY . Published January 1972 This surveillance performed under a Memorandum of Understanding (No. SF 54 373) for the U. S. ATOMIC ENERGY COMMISSION SWRKL-81r OFF-SITE SURVEILLANCE ACTIVITIES OF THE SOUTHWESTERN RADIOLOGICAL HEALTH LABORATORY from January through June

  13. SWRHL-108r OFF-SITE SURVEILLANCE ACTIVITIES OF THE SOUTHWESTERN RADIOLOGICAL HEALTH LABORATORY

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

    gyg?- SWRHL-108r OFF-SITE SURVEILLANCE ACTIVITIES OF THE SOUTHWESTERN RADIOLOGICAL HEALTH LABORATORY from January through June 1970 Environmental Surveillance Western Environmental Research Laboratory ENVIRONMENTAL PROTECTION AGENCY Published August 1972 This surveillance performed under a Memorandum of Understanding (No. SF 54 373) for the U.S. ATOMIC ENERGY COMMISSION -- SWRH?-108r OFF-SITE SURVEILLANCE ACTIVITIES OF THE SOUTHWESTERN RADIOLOGICAL HEALTH LABORATORY from January through June

  14. SWRHL-47r OFF-SITE SURVEILLANCE ACTIVITIES OF THE SOUTHWESTERN RADIOLOGICAL HEALTH LABORATORY

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

    47r OFF-SITE SURVEILLANCE ACTIVITIES OF THE SOUTHWESTERN RADIOLOGICAL HEALTH LABORATORY from January through June 1967 bY Environmental Surveillance Southwestern Radiological Health Laboratory U. S. Department of Health, Education, and Welfare' Public Health Service Environmental Health Service March 1970 This surveillance performed under a Memorandum of Understanding (No. SF 54 373) for the U. S. MOMIC ENERGY COMMISSION SWRHL-47r OFF -SITE SURVEILLANCE ACTIVITIES OF THE SOU IHWESTERN

  15. Hospital Triage in the First 24 Hours after a Nuclear or Radiological Disaster

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

    Hospital Triage in the First 24 Hours after a Nuclear or Radiological Disaster Berger, ME; Leonard, RB; Ricks, RC; Wiley, AL; Lowry, PC; Flynn, DF Abstract: This article addresses the problems emergency physicians would face in the event of a nuclear or radiological catastrophe. It presents information about what needs to be done so that useful information will be gathered and reasonable decisions made in the all important triage period. A brief introductory explanation of radiation injury is

  16. FEDERAL RADIOLOGICAL MONITORING AND ASSESSMENT CENTER ADVANCE PARTY PHASE RESPONSE ACTIONS

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

    FEDERAL RADIOLOGICAL MONITORING AND ASSESSMENT CENTER ADVANCE PARTY PHASE RESPONSE ACTIONS Bruce Hurley, Ph.D. U.S. Department of Energy Nevada Operations Office P.O. Box 98518 Las Vegas, Nevada 89102 (702) 295-1284 Daryl Thome' Bechtel Nevada Remote Sensing Laboratory P.O. Box 98521 Las Vegas, Nevada 89193 (702) 295-8780 SUMMARY Federal Radiological Monitoring and Assessment Center (FRMAC) response actions are carried out in Advance Party and Main Party phases of deployment. Response activities

  17. Don Haward joins WIPP as manager of radiological control and emergency preparedness

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (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 Harward as manager of Radiological Control and Emergency Preparedness at the Waste Isolation Pilot Plant (WIPP). Westinghouse is the management and operating contractor for the U.S. Department of Energy's Carlsbad Area Office at WIPP. "Don comes to the division with many years of experience in radiation safety and

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

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

    Incident Commanders | Department of Energy Unified Resolve 2014: A Proof of Concept for Radiological Support to Incident Commanders Unified Resolve 2014: A Proof of Concept for Radiological Support to Incident Commanders Daniel Blumenthal*, U.S. Department of Energy ; John Crapo, Oak Ridge Institute for Science and Education; Gerard Vavrina, U.S. Department of Energy; Katharine McLellan McLellan, U.S. Department of Energy; Michael J. Gresalfi, Oak Ridge National Laboratory Abstract: In

  19. Guide of Good Practices for Occupational Radiological Protection in Uranium Facilities

    Office of Environmental Management (EM)

    36-2009 July 2009 DOE STANDARD GUIDE OF GOOD PRACTICES FOR OCCUPATIONAL RADIOLOGICAL PROTECTION IN URANIUM FACILITIES U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1136-2009 Guide of Good Practices for Occupational Radiological Protection in Uranium Facilities i This document is available on the Department of Energy Technical Standards Program Web Site at

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

    Office of Legacy Management (LM)

    Health and Safety Research Division RESULTS FROM A RADIOLOGICAL SURVEY ON YARDEORO AVENUE, ALBANY, AND CENTRAL AVENUE,, COLONIE, NEW YORK PROPERTIES AL013 - AL028 July 1984 Work performed as part of the RADIOLOGICAL SURVEY ACTIVITIES PROGRAM OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37831 operated by MARTIN MARIETTA ENERGY SYSTEMS, INC. for the U.S. DEPARTMENT OF ENERGY under Contract No. DE-AC05840R21400 _- _^." .-. ..-.- _---.--_ -... .- Fk. 3 ,=. Y)*cx gs 1 XEC @ d +I? ,%r $ g

  1. PRELIMINqRY RADIOLOGICAL SURVEY REPORT OF THE FORMER STATEN ISLAND WAREHOUSE SITE

    Office of Legacy Management (LM)

    pJ y, 22/4 PRELIMINqRY RADIOLOGICAL SURVEY REPORT OF THE FORMER STATEN ISLAND WAREHOUSE SITE (ARCHER-DANIELS MIOLANO COMPANY) AT PORT RICHMOND, NEW YORK ./ Work performed by the Health and Safety Research Division Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 . . ' October 1980 OAK RIDGE NATIONAL LABORATORY operated by UNION CARBIDE CORPORATION for the DEPARTMENT OF ENERGY as part of the Former1 y Uti 1 i ted Sites-- Remedial Action Program PRELIMINARY RADIOLOGICAL SURVEY REPORT OF

  2. DOE-HDBK-1141-2001; Radiological Assessor Training, Student's Guide, Part 4 of 5

    Office of Environmental Management (EM)

    Assessor Training DOE-HDBK-1141-2001 Student's Guide Office of Environment, Safety & Health U.S. Department of Energy Radiological Assessor Training DOE-HDBK-1141-2001 Student's Guide ii This page intentionally left blank. Radiological Assessor Training DOE-HDBK-1141-2001 Student's Guide iii Table of Contents Regulatory Documents..................................................................................... Module1-1 10 CFR Part 835, Background and

  3. DOE-HDBK-1143-2001; Radiological Control Training for Supervisors - Student's Guide

    Office of Environmental Management (EM)

    43-2001 Student's Guide Notes I. Introduction II. Problem analysis Supervisors of radiological workers are often faced with critical decisions. Providing a model for strategic decision making will ensure that these critical decisions are made in an efficient, rational manner. Module 6-1 Radiological Control Training for Supervisors DOE-HDBK-1143-2001 Student's Guide Notes A. Stating the mission In making decisions, the organization's mission and resultant goals should always be considered.

  4. Final Technical Report

    SciTech Connect (OSTI)

    Alexander Pigarov

    2012-06-05

    This is the final report for the Research Grant DE-FG02-08ER54989 'Edge Plasma Simulations in NSTX and CTF: Synergy of Lithium Coating, Non-Diffusive Anomalous Transport and Drifts'. The UCSD group including: A.Yu. Pigarov (PI), S.I. Krasheninnikov and R.D. Smirnov, was working on modeling of the impact of lithium coatings on edge plasma parameters in NSTX with the multi-species multi-fluid code UEDGE. The work was conducted in the following main areas: (i) improvements of UEDGE model for plasma-lithium interactions, (ii) understanding the physics of low-recycling divertor regime in NSTX caused by lithium pumping, (iii) study of synergistic effects with lithium coatings and non-diffusive ballooning-like cross-field transport, (iv) simulation of experimental multi-diagnostic data on edge plasma with lithium pumping in NSTX via self-consistent modeling of D-Li-C plasma with UEDGE, and (v) working-gas balance analysis. The accomplishments in these areas are given in the corresponding subsections in Section 2. Publications and presentations made under the Grant are listed in Section 3.

  5. Final Technical Report

    SciTech Connect (OSTI)

    Alexander Fridman

    2005-06-01

    This DOE project DE-FC36-04GO14052 ''Plasma Pilot Plant Test for Treating VOC Emissions from Wood Products Plants'' was conducted by Drexel University in cooperation with Georgia-Pacific (G-P) and Kurchatov Institute (KI). The objective of this project was to test the Plasma Pilot Plant capabilities in wood industry. The final goal of the project was to replace the current state-of-the-art, regenerative thermal oxidation (RTO) technology by Low-Temperature Plasma Technology (LTPT) in paper and wood industry for Volatile Organic Components (VOC) destruction in High Volume Low Concentration (HVLC) vent emissions. MetPro Corporation joined the team as an industrial partner from the environmental control business and a potential leader for commercialization. Concurrent Technology Corporation (CTC) has a separate contract with DOE for this technology evaluation. They prepared questionnaires for comparison of this technology and RTO, and made this comparison. These data are presented in this report along with the description of the technology itself. Experiments with the pilot plant were performed with average plasma power up to 3.6 kW. Different design of the laboratory and pilot plant pulsed coronas, as well as different analytical methods revealed many new peculiarities of the VOC abatement process. The work reported herein describes the experimental results for the VOCs removal efficiency with respect to energy consumption, residence time, water effect and initial concentration.

  6. Final Technical Report

    SciTech Connect (OSTI)

    Velasco, Mayda

    2013-11-01

    This work is focused on the design and construction of novel beam diagnostic and instrumentation for charged particle accelerators required for the next generation of linear colliders. Our main interest is in non-invasive techniques. The Northwestern group of Velasco has been a member of the CLIC Test Facility 3 (CTF3) collaboration since 2003, and the beam instrumentation work is developed mostly at this facility1. This 4 kW electron beam facility has a 25-170 MeV electron LINAC. CTF3 performed a set of dedicated measurements to finalize the development of our RF-Pickup bunch length detectors. The RF-pickup based on mixers was fully commissioned in 2009 and the RF-pickup based on diodes was finished in time for the 2010-11 data taking. The analysis of all the data taken in by the summer of 2010 was finish in time and presented at the main conference of the year, LINAC 2010 in Japan.

  7. Session 70 - Panel: Consequence Management of a Radiological Dispersion Device

    SciTech Connect (OSTI)

    Demmer, Rick; Lenox, Dave; Wilson, Pete; Schumann, Jean; Honerlah, Hans; Chen, S.Y.; Gwiazdowski, Gene

    2006-07-01

    This was an unusual panel session in that the panelists did not give presentations but responded to a tabletop exercise where they postulated decisions necessary after radiological dispersal device detonation event (dirty bomb). Articles in the daily WM'06 newsletter sought to prepare the participants for a simulated exercise involving the sighting of a known terrorist and the theft of radiological materials. During the slide presentation (in the form of a developing television news broadcast) the audience played decision makers and their 'votes' were tallied for multiple choice decisions and questions. After that was completed, the expert panel was asked to give their best responses for those decisions. The audience was allowed to ask questions and to give opinions as the panel responded. During the exercise the session co-chairs alternated announcing the events as they unfolded in the exercise and polled the audience using multiple-choice options for decisions to be made during the event. The answers to those questions were recorded and compared to the panelists' answers. The event chronology and decisions (audience questions) are shown in this report. - An explosion was reported at the Tucson International Airport (9:35 am). 1. Who is in charge? - Witnesses report 10-20 fatalities, 50 injured and massive damage to the airport, no cause determined yet (9:55 am). 2. IC's Next Action Should Be? - KRAD (local television station) Investigative News Reporters interviewed witnesses that observed a 25 foot U-Haul truck pull up onto the departure ramp just moments before the explosion (10:02 am). Terrorism has not been ruled out. 3. When is the incident declared a potential crime scene? - City of Tucson IC has ordered an evacuation of the airport to a holding area at a nearby long term parking area (10:10 am). No information has been given as to why the evacuation took place. The explosion is suspected to contain chemical, biological or radiological agents. County and State emergency operations centers have been activated. 4. Terrorism is suspected; next action is? - KRAD News has just learned that elevated levels of radiation have been detected at the airport and by the University of Arizona remote detectors (10:17 am). A 'dirty bomb' is now suspected. 5. What should the IC do next? - KRAD reporters have learned that dose rates are approximately 7.5 mR/hr gamma radiation in the short-term parking area (10:28 am). Experts attending a conference at the Tucson Convention Center state that these levels are not life threatening, but well above acceptable levels. 6. What does the IC do next? 7. Who is the coordinating agency? - Forensics indicate that the radioactive material used in the explosion at the Tucson Airport is apparently a mixture of high jacked low level waste from a nuclear facility and stolen radiation sources for medical or industrial purposes (11:21 am). The origin of the waste material is from an audience member's plant (assume it is your own material). 8. Who is responsible for surveys and characterization? 9. Who is responsible for the decontamination? 10. Where are the injured and contaminated victims treated? KRAD learned from the University of Arizona that the plume from the 'dirty bomb' elevated radiation levels above approved levels over a 3 square mile area downwind of the Tucson Airport (1:13 pm). People in the affected area are checking in at emergency rooms at the hospital to learn if they're in danger of radiation health affects. Gridlock has set in as panicked people are either leaving the area or headed for emergency rooms. 11. What should be done to help mitigate fears? DHS raises the National Terrorism Alert to Code Red (late afternoon). 12. What should your nuclear facility do next? 13. KRAD reporter contacts you at your nuclear facility and asks, 'Since title to the waste remains with your company, will your company cover the cost of the terrorist event including all decontamination and medical expenses? The results of the question were very interesting and stimulated quite a bit of discussion am

  8. Conditions and Requirements

    Broader source: Energy.gov [DOE]

    Conditions and requirements for Energy Efficiency and Renewable Energy (EERE) Postdoctoral Research Awards are spelled out below:

  9. MTX final report

    SciTech Connect (OSTI)

    Hooper, E.B.; Allen, S.L.; Brown, M.D.; Byers, J.A.; Casper, T.A.; Cohen, B.I.; Cohen, R.H.; Fenstermacher, M.E.; Foote, J.H.; Hoshino, K.

    1994-01-01

    The MTX experiment was proposed in 1986 to apply high frequency microwaves generated by a free-electron laser (FEL) to electron cyclotron resonance heating (ECRH) in a high field, high density tokamak. As the absorption of microwaves at the electron cyclotron resonance requires high frequencies, the opportunity of applying a free-electron laser has appeal as the device is not limited to frequencies in the microwave or long millimeter wavelength regions, in contrast to many other sources. In addition, the FEL is inherently a high power source of microwaves, which would permit single units of 10 MW or more, optimum for reactors. Finally, it was recognized early in the study of the application of the FEL based on the induction linear accelerator, that the nonlinear effects associated with the intense pulses of microwaves naturally generated would offer several unique opportunities to apply ECRH to current drive, MHD control, and other plasma effects. It was consequently decided to adapt the induction accelerator based FEL to heating and controlling the tokamak, and to conduct experiments on the associated physics. To this end, the Alcator C tokamak was moved from the Massachusetts Institute of Technology (MIT) to the Lawrence Livermore National Laboratory where it was installed in Building 431 and operated from March, 1989, until the conclusion of the experiment in October, 1992. The FEL, based on the ETA-11 accelerator and IMP wiggler was brought into operation by the LLNL Electron Beam Group and power injected into the tokamak during an experimental run in the Fall, 1989. Following an upgrade by the MTX group, a second experimental run was made lasting from the Winter, 1992 through the end of the experiment. Significant contributions to the ECRH experiments were made by the Japan Atomic Energy Research Institute (JAERI).

  10. LIVE_NSB_final.wmv

    ScienceCinema (OSTI)

    None

    2010-09-01

    National Science Bowl finals and awards at the National Building Museum in Washington D.C. Monday 5/3/2010

  11. Final Meeting Summary Page 1

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

    9, 2012 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD RIVER AND PLATEAU COMMITTEE August 9, 2012 Richland, WA Topics in this Meeting Summary Opening ......................................................................................................................................................... 1 Committee Business ...................................................................................................................................... 4 Attachments

  12. EA-1637: Final Environmental Assessment

    Broader source: Energy.gov [DOE]

    10 CFR 431 Energy Conservation Program for Commerical and Industrial Equipment: Packaged Terminal Air Conditioner and Packaged Terminal Heat Pump Energy Conservation Standards; Final Rule

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

    SciTech Connect (OSTI)

    Jeremy Gwin and Douglas Frenette

    2010-09-30

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

  14. Development and operativity of a real-time radiological monitoring network centered on the nuclear power plant of Almaraz (Spain)

    SciTech Connect (OSTI)

    Baeza, A.; Miro, C.; Puerto, J.A. del; Rio, M. del; Ortiz, F.; Paniagua, J.M.

    1993-12-01

    This work presents the hardware and software characteristics of the environmental surveillance radiological network that has been installed around the nuclear power station of Almaraz (Spain). A description is given of the program RADLINE which allows radiological data to be logged in real time, and a study is made of the operativity of the network and the methodology followed in establishing the radiological pre-alert and alert levels.

  15. Hydrothermal reaction of fly ash. Final report

    SciTech Connect (OSTI)

    Brown, P.W.

    1994-12-31

    The reactions which occur when fly ash is treated under hydrothermal conditions were investigated. This was done for the following primary reasons. The first of these is to determine the nature of the phases that form to assess the stabilities of these phases in the ambient environment and, finally, to assess whether these phases are capable of sequestering hazardous species. The second reason for undertaking this study was whether, depending on the composition of the ash and the presence of selected additives, it would be possible under hydrothermal conditions to form compounds which have cementitious properties. Formation of four classes of compounds, which bracket likely fly ash compositional ranges, were selected for study. The classes are calcium silicate hydrates, calcium selenates, and calcium aluminosulfates, and silicate-based glasses. Specific compounds synthesized were determined and their stability regions assessed. As part of stability assessment, the extent to which selected hazardous species are sequestered was determined. Finally, the cementing properties of these compounds were established. The results obtained in this program have demonstrated that mild hydrothermal conditions can be employed to improve the reactivity of fly ash. Such improvements in reactivity can result in the formation of monolithic forms which may exhibit suitable mechanical properties for selected applications as building materials. If the ashes involved are considered hazardous, the mechanical properties exhibited indicated the forms could be handled in a manner which facilitates their disposal.

  16. Final Project Report

    SciTech Connect (OSTI)

    Carrick M. Eggleston

    2003-12-12

    This report provides a description of the main accomplishments of the EMSP funded research, including products such as conference presentations and publications (including those still in preparation). The purpose of this study was to better understand the chemical interactions between dissolved aqueous contaminants and carbonate minerals occurring as coatings on mineral grains in the vadose zone beneath the Hanford reserve. This information is important for construction of improved reactive transport models intended to predict the subsurface migration of contaminants. We made improvements to the hydrothermal atomic force microscope (HAFM) design to be used in this project. The original HAFM was built with funding from the U.S. DOE, Office of Basic Energy Sciences. Improvements include operating limits of 70 bars and 170 C, from an original limit of 12 bars and 150 C. This product is patented. We completed a series of studies of magnesite, MgCO3, because this mineral is structurally equivalent to calcite but reacts much more slowly, allowing us to study carbonate reactivity under pH conditions (i.e., low pH) that are much more problematic for studies of calcite but which are nevertheless relevant to in-situ conditions. We found that dissolving magnesite exhibits a dramatic change in step orientation, and therefore etch pit shape, as pH is lowered through 4.2 to 3 and 2. This change in step orientation is NOT accompanied by an increase in step velocity with decreasing pH. We also found that, after growing magnesite on a magnesite substrate, the newly grown magnesite dissolved much more readily than the underlying substrate magnesite, and exhibited far larger etch pit densities. This effect may have been related to the rate of growth or to the presence of an Fe impurity in the growth solutions. We studied the dissolution of magnesite and calcite (104) surfaces under a wider variety of conditions with a new hydrodynamically defined hydro thermal AFM fluid cell, and we have observed the precipitation of a strontium-containing carbonate phase on dissolving calcite. We have applied the advection-diffusion equation coupled to proposed homogeneous and heterogeneous kinetic models to test rate laws for dissolution observed by HAFM. Our main conclusions in the magnesite studies are that step density, rather than step velocity, is a strong function of pH near the surface and that the step orientation is sensitive to pH. In these studies, we definitively demonstrate that diffusive mass transport is only important at very low fluid velocities for magnesite, but that studies of calcite dissolution are generally in the mixed transport-kinetics controlled regime (even at high fluid velocities) where quantitative information can only be obtained by accounting for the transport components. We also have found that alkaline earth carbonate secondary precipitate formation on calcite surfaces significantly alters the net flux o f Ca2+ and may passivate the CaCO3 surface from further reaction. The research has so far resulted in 5 conference presentations and 3 published journal articles, with several manuscripts still in preparation. The project supported graduate student Briana Deeds and postdoctoral researcher Steven R. Higgins.

  17. Decontamination of hot cells K-1, K-3, M-1, M-3, and A-1, M-Wing, Building 200: Project final report Argonne National Laboratory-East

    SciTech Connect (OSTI)

    Cheever, C.L.; Rose, R.W.

    1996-09-01

    The purpose of this project was to remove radioactively contaminated materials and equipment from the hot cells, to decontaminate the hot cells, and to dispose of the radioactive waste. The goal was to reduce stack releases of Rn-220 and to place the hot cells in an emptied, decontaminated condition with less than 10 {micro}Sv/h (1 mrem/h) general radiation background. The following actions were needed: organize and mobilize a decontamination team; prepare decontamination plans and procedures; perform safety analyses to ensure protection of the workers, public, and environment; remotely size-reduce, package, and remove radioactive materials and equipment for waste disposal; remotely decontaminate surfaces to reduce hot cell radiation background levels to allow personnel entries using supplied air and full protective suits; disassemble and package the remaining radioactive materials and equipment using hands-on techniques; decontaminate hot cell surfaces to remove loose radioactive contaminants and to attain a less than 10 {micro}Sv/h (1 mrem/h) general background level; document and dispose of the radioactive and mixed waste; and conduct a final radiological survey.

  18. Final Report Strings 2014

    SciTech Connect (OSTI)

    Witten, Edward

    2015-10-21

    DOE Final Report “Strings 2014” PI: Edward Witten, Institute for Advanced Study, Princeton, NJ 08540 CO-PI: Igor Klebanov, Princeton University, Princeton, NJ 08540 DOE Grant Number: DE-SC0011919 The Strings 2014 meeting was held at Princeton University in June 2014, co-sponsored by Princeton University and the Institute for Advanced Study. Plenary lectures at Strings 2014 were held in Richardson Auditorium of Princeton University. This comfortable and spacious facility easily accommodated the 616 participants registered participants at Strings 2014. The rental fee for the auditorium was $11,000. This grant provided $5,500 from the Department of Energy to pay for one-half of the cost of the facility rental and videotaping. Speakers were supported with funds from the National Science Foundation Clay Mathematics Institute, the Institute for Advanced Study and Princeton University. The organization of Strings 2014 consisted of an International Organizing Committee of 60 prominent scientists around the world, and a Local Advisory Committee consisting of an additional 15 distinguished scientists from neighboring institutions. Additionally, the Local Organizing Committee assisted them with about 15 members (mostly faculty at Princeton University and the Institute for Advanced Study). These groups (which are listed at the end of this narrative) offered important input concerning the selection of speakers and helped to ensure that the speakers were selected from the broadest possible pool. The conference was held on June 23-7 at Princeton University and the Institute for Advanced Study. The 616 registered participants included 272 participants from the United States and 344 from 32 institutions outside of the U.S. We believe that we were successful at providing a stimulating and up-to-date overview of research in string theory and its relations to other areas of physics and mathematics, ranging from geometry to quantum field theory, condensed matter physics, and more. There were a total of 45 plenary speakers and 27 speakers at parallel sessions. (Parallel sessions were held at the Institute for Advanced Study.) Overall the speakers did an excellent job of presenting their topics and some presented surprising and novel results. The talks at Strings 2014 were videotaped and are available on the conference website: http://physics.princeton.edustrings2014/Talk_titles.shtml. One important facet of Strings 2014 and one of the reasons it was so well-attended was that it had a strong educational component. The week before the meeting, there was a summer school, Prospects in Theoretical Physics (PiTP), held at the Institute for Advanced Study on the subject of string theory. 260 graduate students attended both PiTP and Strings 2014. The group consisted of 25 females and 235 males; 208 graduate students and 52 postdocs. 129 participants were from the United States, and 131 participants came from institutions in 25 countries outside of the U.S. The Institute for Advanced Study substantially subsidized the summer school for students. Over two dozen students had the chance to give short (six minute) talks at the “gong shows” that were held at PiTP and Strings 2014, and nearly 60 students and postdocs made poster presentations at Strings 2014.

  19. Final Technical Progress Report

    SciTech Connect (OSTI)

    J.Y. Hwang; R.C. Greenlund

    2002-12-31

    Michigan Technological University has demonstrated major inroads in establishing the viability of utilizing aluminum smelting by-product waste materials in lightweight concrete product applications. The research identified key elements of producing various forms of lightweight concrete products through utilizing various procedures and mixture components with the by-product materials. A process was developed through pilot plant testing that results in additional aluminum recovery at finer sizes, a clean returnable salt product through spray drying technology, and a low-salt-content oxide product with enough aluminum metal content that it can be used to form lightweight cementitious mixtures. Having three distinct products aids in generating favorable process economics. Revenue projections from aluminum recovery and salt recovery are enough to cover processing costs and create a cost-free oxide product to market for lightweight concrete applications. This supply side commercialization strategy offers aluminum by-product recyclers a potentially no cost product, which has been demonstrated through this project to create desirable and marketable lightweight concrete products of various forms. Environmental benefits to the public are tremendous. At best, all dross and salt cake materials have the potential to be completely recycled and utilized. At worst, disposal sites would see a reduced amount of material: a post processed oxide product with little salt and no hydrogen sulfide or ammonia gas generating capability, which, if isolated from high alkali conditions, would pose no reactivity concerns. The US aluminum industry has historically, along with the steel industry, been a leader in recycling metal. The findings from this project, increased metal recovery, improved salt recycling, and demonstrated end uses for oxide residues, will go a long way in helping the aluminum industry obtain 100% material utilization and zero discharge.

  20. Final ECR 2008 Report | Department of Energy

    Energy Savers [EERE]

    Final ECR 2008 Report Final ECR 2008 Report Final ECR 2008 Report PDF icon Environmental Conflict Resolution Third Annual Report January 2009 More Documents & Publications Environmental Conflict Resolution 2009 ECR FINAL REPORT 2010 test

  1. Bridge Condition Assessment

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

    Condition and Performance Assessment Background How bridges respond to extreme loading conditions, such as during high winds and severe storms, and to the effects of aging, such as corrosion- and fatigue-induced cracking, is a major concern for the Federal Highway Administration (FHWA). The FHWA is working to ensure that highway structures are safe and reliable under all service conditions, including potential structural, environmental, and human-generated threats. Role of High-Performance

  2. Final Technical Report

    SciTech Connect (OSTI)

    Stenzel, Reiner; Urrutia, J. Manuel

    2009-09-08

    The nonlinear physics of electron magnetohydrodynamics (EMHD) in plasmas. Time-varying wave magnetic field exceeding the background magnetic field produces highly nonlinear whistler mode since the wave dispersion depends on the total magnetic field. There exists no theory for such whistler modes. The present experimental work is the first one to explore this regime of nonlinear whistlers. A field-reversed configuration has been found which has the same vortex topology as an MHD spheromak, termed a whistler spheromak. Whistler mirrors have compressed and twisted field lines propagating in the whistler mode. Their helicity properties have been studied. Whistler spheromaks and mirrors have different propagation and damping characteristics. Wave collisions have been studied. Head-on collisions of two whistler spheromaks form a stationary field-reversed configuration (FRC) without helicity. When whistler spheromaks are excited the toroidal current flows mainly in the toroidal null line. It is only carried by electrons since ion currents and displacement currents are negligible. A change in the poloidal (axial) magnetic field induces a toroidal electric field which drives the current. Magnetic energy is dissipated and converted into electron kinetic energy. This process is called magnetic reconnection in 2D geometries, which are simplifications for theoretical convenience but rarely occur in nature. A crucial aspect of reconnection is its rate, determined by the electron collisionality. Regular Coulomb collisions can rarely account for the observed reconnection rates. In the present experiments we have also observed fast reconnection and explained it by electron transit time damping in the finite-size null layer. Electrons move faster than a whistler spheromak, hence transit through the toroidal null line where they are freely accelerated. The transit time is essentially the collision time but no particle collisions are required. Strong electron heating and visible light emissions are only observed in whistler spheromaks and FRCs but not in mirrors or asymmetric configurations lacking magnetic null lines. The collisionless electron energization in a toroidal null line usually produces non-Maxwellian distributions. Off the null axis electrons gain more perpendicular than parallel energy. Distributions with T{sub {perpendicular}} > T{sub {parallel}} lead to whistler instabilities which have been observed. A whistler spheromak is a source of high-frequency whistler emissions. These are usually small amplitude whistlers propagating in a complicated background magnetic field. The waves are emitted from a moving source. High frequency whistlers propagate faster than the spheromak, thus partly move ahead of it and partly in the reverse direction. In test wave experiments wave growth opposite to the direction of the hot electron flow has been observed, confirming that Doppler-shifted cyclotron resonance instabilities account for the emission process. Propagating whistler mirrors produce no significant instabilities except when they interact with other fields which exhibit null lines. For example, a whistler mirror has been launched against a stationary FRC, resulting in strong FRC heating and whistler instabilities. In the whistler mirror configuration the antenna near-zone field produces a toroidal null line outside the coil which can also become a source for whistler emissions. Finally, nonlinear EMHD research has been extended to initially unmagnetized plasmas where a new nonlinear skin depth has been discovered. When a small-amplitude oscillating magnetic field is applied to a plasma the field penetration is governed by the skin depth, collisional or collisionless depending on frequency, collision frequency and plasma frequency. However, when the magnetic field increases the electrons become magnetized and the field penetration occurs in the whistler mode if the cyclotron frequency exceeds the oscillating frequency. This phenomenon has been observed. A loop antenna creates a dipole field which is frozen into the plasma for a half cycle and becomes the background field for the wave launched by the next half cycle. The field topology consists of field-reversed dipoles of decreasing strength with distance. The propagation region depends on field amplitude but not on the skin depth. Our research has been published in 13 scientific papers.

  3. Method and apparatus for in-cell vacuuming of radiologically contaminated materials

    DOE Patents [OSTI]

    Spadaro, Peter R.; Smith, Jay E.; Speer, Elmer L.; Cecconi, Arnold L.

    1987-01-01

    A vacuum air flow operated cyclone separator arrangement for collecting, handling and packaging loose contaminated material in accordance with acceptable radiological and criticality control requirements. The vacuum air flow system includes a specially designed fail-safe prefilter installed upstream of the vacuum air flow power supply. The fail-safe prefilter provides in-cell vacuum system flow visualization and automatically reduces or shuts off the vacuum air flow in the event of an upstream prefilter failure. The system is effective for collecting and handling highly contaminated radiological waste in the form of dust, dirt, fuel element fines, metal chips and similar loose material in accordance with radiological and criticality control requirements for disposal by means of shipment and burial.

  4. The Importance of Curriculum-Based Training and Assessment in Interventional Radiology

    SciTech Connect (OSTI)

    Belli, Anna-Maria; Reekers, Jim A.; Lee, Michael

    2013-10-30

    Physician performance and outcomes are being scrutinised by health care providers to improve patient safety and cost efficiency. Patients are best served by physicians who have undergone appropriate specialist training and assessment and perform large numbers of cases to maintain their skills. The Cardiovascular and Interventional Radiological Society of Europe has put into place a curriculum for training in interventional radiology (IR) and a syllabus with an examination, the European Board of Interventional Radiology, providing evidence of attainment of an appropriate and satisfactory skill set for the safe practice of IR. This curriculum is appropriate for IR where there is a high volume of image-guided procedures in vascular and nonvascular organ systems with cross-use of minimally invasive techniques in patients with a variety of disease processes. Other specialties may require different, longer, and more focused training if their experience is “diluted” by the need to master a different skill set.

  5. SPECIAL TERMS AND CONDITIONS FOR USE IN MOST GRANTS AND COOPERATIVE

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

    ... The final version of the Research Terms and Conditions and ... Applicationproposal as approved by DOE. f. National Policy ... the purpose for which the grant or cooperative agreement ...

  6. Decision Support Tool for the Management of Debris from Radiological Dispersal Devices and Other Incidents of National Significance

    SciTech Connect (OSTI)

    Lemieux, P.; Thorneloe, S.; Hayes, C.; Rodgers, M.; Christman, R.

    2008-07-01

    Unique challenges exist for the handling, transport, and disposal of debris resulting from homeland security incidents, disasters or other national emergencies. Access to guidance to facilitate decision making to ensure the safe and timely disposal of debris is critical to helping restore a community or region and prevent further contamination or spread of disease. For a radiological dispersal device (RDD), proper characterization of the quantity, properties, and level of contamination of debris can have a significant impact on cleanup costs and timelines. A suite of decision support tools (DSTs) is being developed by the U.S. EPA's Office of Research and Development to assist individuals responsible for making decisions associated with handling, transport, and disposal of such debris. The DSTs are location-specific to help identify specific facilities and contacts for making final disposal decisions. The DSTs provide quick reference to technical information, regulations, and other information to provide decision makers with assistance in guiding disposal decisions that are important for the protection of public health, first responders, and the environment. These tools are being developed in partnership with other U.S. government agencies, EPA program offices, industry, and state and local emergency response programs. (authors)

  7. Condition Assessment Information System

    Energy Science and Technology Software Center (OSTI)

    2002-09-16

    CAIS2000 records, tracks and cost maintenance deficiencies associated with condition assessments of real property assets. Cost information is available for 39,000 items in the currenht RS Means, Facilities Construction Manual. These costs can, in turn, be rolled by by asset to produce the summary condition of an asset or site.

  8. Advanced Distillation Final Report

    SciTech Connect (OSTI)

    Maddalena Fanelli; Ravi Arora; Annalee Tonkovich; Jennifer Marco; Ed Rode

    2010-03-24

    The Advanced Distillation project was concluded on December 31, 2009. This U.S. Department of Energy (DOE) funded project was completed successfully and within budget during a timeline approved by DOE project managers, which included a one year extension to the initial ending date. The subject technology, Microchannel Process Technology (MPT) distillation, was expected to provide both capital and operating cost savings compared to conventional distillation technology. With efforts from Velocys and its project partners, MPT distillation was successfully demonstrated at a laboratory scale and its energy savings potential was calculated. While many objectives established at the beginning of the project were met, the project was only partially successful. At the conclusion, it appears that MPT distillation is not a good fit for the targeted separation of ethane and ethylene in large-scale ethylene production facilities, as greater advantages were seen for smaller scale distillations. Early in the project, work involved flowsheet analyses to discern the economic viability of ethane-ethylene MPT distillation and develop strategies for maximizing its impact on the economics of the process. This study confirmed that through modification to standard operating processes, MPT can enable net energy savings in excess of 20%. This advantage was used by ABB Lumus to determine the potential impact of MPT distillation on the ethane-ethylene market. The study indicated that a substantial market exists if the energy saving could be realized and if installed capital cost of MPT distillation was on par or less than conventional technology. Unfortunately, it was determined that the large number of MPT distillation units needed to perform ethane-ethylene separation for world-scale ethylene facilities, makes the targeted separation a poor fit for the technology in this application at the current state of manufacturing costs. Over the course of the project, distillation experiments were performed with the targeted mixture, ethane-ethylene, as well as with analogous low relative volatility systems: cyclohexane-hexane and cyclopentane-pentane. Devices and test stands were specifically designed for these efforts. Development progressed from experiments and models considering sections of a full scale device to the design, fabrication, and operation of a single-channel distillation unit with integrated heat transfer. Throughout the project, analytical and numerical models and Computational Fluid Dynamics (CFD) simulations were validated with experiments in the process of developing this platform technology. Experimental trials demonstrated steady and controllable distillation for a variety of process conditions. Values of Height-to-an-Equivalent Theoretical Plate (HETP) ranging from less than 0.5 inch to a few inches were experimentally proven, demonstrating a ten-fold performance enhancement relative to conventional distillation. This improvement, while substantial, is not sufficient for MPT distillation to displace very large scale distillation trains. Fortunately, parallel efforts in the area of business development have yielded other applications for MPT distillation, including smaller scale separations that benefit from the flowsheet flexibility offered by the technology. Talks with multiple potential partners are underway. Their outcome will also help determine the path ahead for MPT distillation.

  9. FinalProgramReportfinal.doc

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

    November 8, 2004 Paul Wambach EH-53/270 Corporate Square Building U. S. Department of Energy 1000 Independence Avenue, SW Germantown, MD 20585-0270 CONTRACT NO. DE-AC05-00OR22750: FY04 FINAL REPORT FOR THE FORMER RADIATION WORKER MEDICAL SURVEILLANCE PROGRAM AT ROCKY FLATS The enclosed subject final report prepared by Joe M. Aldrich is submitted as stated in the Fiscal Year 2004 Field Work Proposal for the Former Radiation Worker Medical Surveillance Program at Rocky Flats. This is the final

  10. Hawaii Clean Energy Final PEIS

    Office of Environmental Management (EM)

    A 1 2 Public Notices 3 Notices about the Draft Programmatic EIS Appendix A Hawai i Clean Energy Final PEIS A-1 September 2015 DOE/EIS-0459 The following Notice of Availability appeared in the Federal Register on April 18, 2014. Appendix A Hawai i Clean Energy Final PEIS A-2 September 2015 DOE/EIS-0459 Appendix A Hawai i Clean Energy Final PEIS A-3 September 2015 DOE/EIS-0459 DOE-Hawaii placed the following advertisement in The Garden Island on May 5 and 9, 2014. Appendix A Hawai i Clean Energy

  11. Appendix B - Chemical and Radiological Inventories for the CEMRC, pages 1-4

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

    B-1 APPENDIX B CHEMICAL AND RADIOLOGICAL INVENTORIES FOR THE CEMRC The current inventories of chemicals and radiological materials at the Carlsbad Environmental Monitoring and Research Center (CEMRC) are provided in Tables B-1 and B-2, respectively. These tables were provided by Joel Webb, Director of the CEMRC, New Mexico State University (Webb 2002). Table B-1. Onsite CEMRC Chemical Inventory Chemical Name Amount Units SARA Limit Acetic Acid, Glacial 5,400 mL NA a Acetone 38 L NA AA Modifier

  12. DOE, Westinghouse to Partner with NMJC To Train Radiological and Waste Handling Technicians

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (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 presented a check for $70,000 to New Mexico Junior College (NMJC) to initiate a new program to train and certify radiological and waste handling technicians. Dr. Steve McCleery, President of NMJC, accepted the check from Dr. Chuan-Fu Wu, Senior Technical Advisor for the U.S. Department of Energy's Carlsbad Field Office, and

  13. DOE-HDBK-1141-2001; Radiological Assessor Training, Overheads, Part 3 of 5

    Office of Environmental Management (EM)

    Assessor Training DOE-HDBK-1141-2001 Overheads Office of Environment, Safety & Health U.S. Department of Energy Radiological Assessor Training DOE-HDBK-1141-2001 Overheads ii This page intentionally left blank. OT 1.1 DOE-HDBK-1141-2001 Overhead 1.1 Regulatory Documents Objectives: * Identify the hierarchy of regulatory documents. * Define the purpose of 10 CFR Part 835. * Define the purpose of the DOE Radiological Control Standard. OT 1.2 DOE-HDBK-1141-2001 Overhead 1.2 Regulatory Documents

  14. DOE-HDBK-1143-2001; Radiological Control Training for Supervisors - Overheads

    Office of Environmental Management (EM)

    Control Training for Supervisors DOE-HDBK-1143-2001 Overheads Office of Environment, Safety & Health U.S. Department of Energy Radiological Control Training for Supervisors DOE-HDBK-1143-2001 Overheads This page intentionally left blank. ii OT 1.1 DOE-HDBK-1143-2001 Overhead 1.1 Regulatory Documents Objectives: * Identify the hierarchy of regulatory documents. * Define the purposes of 10 CFR Parts 820, 830 and 835. * Define the purpose of the DOE Radiological Control Standard. OT 1.2

  15. Improving Site-Specific Radiological Performance Assessments - 13431

    SciTech Connect (OSTI)

    Tauxe, John; Black, Paul; Catlett, Kate; Lee, Robert; Perona, Ralph; Stockton, Tom; Sully, Mike

    2013-07-01

    An improved approach is presented for conducting complete and defensible radiological site-specific performance assessments (PAs) to support radioactive waste disposal decisions. The basic tenets of PA were initiated some thirty years ago, focusing on geologic disposals and evaluating compliance with regulations. Some of these regulations were inherently probabilistic (i.e., addressing uncertainty in a quantitative fashion), such as the containment requirements of the U.S. Environmental Protection Agency's (EPA's) 40 CFR 191, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, Chap. 191.13 [1]. Methods of analysis were developed to meet those requirements, but at their core early PAs used 'conservative' parameter values and modeling approaches. This limited the utility of such PAs to compliance evaluation, and did little to inform decisions about optimizing disposal, closure and long-term monitoring and maintenance, or, in general, maintaining doses 'as low as reasonably achievable' (ALARA). This basic approach to PA development in the United States was employed essentially unchanged through the end of the 20. century, principally by the U.S. Department of Energy (DOE). Performance assessments developed in support of private radioactive waste disposal operations, regulated by the U.S. Nuclear Regulatory Commission (NRC) and its agreement states, were typically not as sophisticated. Discussion of new approaches to PA is timely, since at the time of this writing, the DOE is in the midst of revising its Order 435.1, Radioactive Waste Management [2], and the NRC is revising 10 CFR 61, Licensing Requirements for Land Disposal of Radioactive Waste [3]. Over the previous decade, theoretical developments and improved computational technology have provided the foundation for integrating decision analysis (DA) concepts and objective-focused thinking, plus a Bayesian approach to probabilistic modeling and risk analysis, to guide improvements in PA. This decision-making approach, [4, 5, 6] provides a transparent formal framework for using a value- or objective-focused approach to decision-making. DA, as an analytical means to implement structured decision making, provides a context for both understanding how uncertainty affects decisions and for targeting uncertainty reduction. The proposed DA approach improves defensibility and transparency of decision-making. The DA approach is fully consistent with the need to perform realistic modeling (rather than conservative modeling), including evaluation of site-specific factors. Instead of using generic stylized scenarios for radionuclide fate and transport and for human exposures to radionuclides, site-specific scenarios better represent the advantages and disadvantages of alternative disposal sites or engineered designs, thus clarifying their differences as well as providing a sound basis for evaluation of site performance. The full DA approach to PA is described, from explicitly incorporating societal values through stakeholder involvement to model building. Model building involves scoping by considering features, events, processes, and exposure scenarios (FEPSs), development of a conceptual site model (CSM), translation into numerical models and subsequent computation, and model evaluation. These are implemented in a cycle of uncertainty analysis, sensitivity analysis and value of information analysis so that uncertainty can be reduced until sufficient confidence is gained in the decisions to be made. This includes the traditional focus on hydrogeological processes, but also places emphasis on other FEPSs such as biotically-induced transport and human exposure phenomena. The significance of human exposure scenarios is emphasized by modifying the traditional acronym 'FEPs' to include them, hence 'FEPSs'. The radioactive waste community is also recognizing that disposal sites are to be considered a national (or even global) resource. As such, there is a pressing need to optimize their utility withi

  16. Final Meeting Summary Page 1

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

    November 12, 2014 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD RIVER AND PLATEAU COMMITTEE November 12, 2014 Richland, WA Topics in this Meeting Summary Opening ......................................................................................................................................................... 1 100 F-Area Record of Decision .................................................................................................................... 1 Central Plateau Inner Area Cleanup

  17. Final Meeting Summary Page 1

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

    November 13, 2014 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD TANK WASTE COMMITTEE November 13, 2014 Richland, WA Topics in this Meeting Summary Opening ......................................................................................................................................................... 1 Tank Farm Vapor Issues (joint w/ HSEP) .................................................................................................... 1 Direct Feed Low-Activity Waste Treatment

  18. Final Meeting Summary Page 1

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

    7, 2015 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD TANK WASTE COMMITTEE January 7, 2015 Richland, WA Topics in this Meeting Summary Opening ......................................................................................................................................................... 1 Risk-Based Retrieval, Treatment, and Closure ............................................................................................. 1 Waste Management Area C Performance Assessment

  19. Final Meeting Summary Page 1

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

    March 10, 2015 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD RIVER AND PLATEAU COMMITTEE March 10, 2015 Richland, WA Topics in this Meeting Summary Opening ......................................................................................................................................................... 1 Central Plateau Inner Area Guidelines .......................................................................................................... 1 2014/15 Budget and RL Cleanup, Lifecycle

  20. Final Meeting Summary Page 1

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

    March 11, 2015 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD TANK WASTE COMMITTEE March 11, 2015 Richland, WA Topics in this Meeting Summary Opening ......................................................................................................................................................... 1 Cesium Treatment and Disposition Issue Manager Update .......................................................................... 2 Waste Treatment Plant Issue Manager Update