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AEC Hot Cells and Related Facilities

Description: Foreward: The primary purpose of this report is to present as an accumulation of basic information on the hot cells constructed to date by the United States Atomic Energy Commission.
Date: May 1958
Creator: Fosdick, Ellery R.
Partner: UNT Libraries Government Documents Department

A Nondestructive Assay System for use in Decommissioning a Plutonium-Handling Facility

Description: Argonne National Laboratory is decommissioning a facility used to fabricate reactor fuel elements. The equipment is contaminated with alpha emitters. The objective of decontamination is to reduce the TRU concentrations below 10 nCi/g of waste. A portable NDA procedure using Na I (TI ) gamma-spectrometric techniques was selected to measure the residual Pu and 2i 1 Am in the glove boxes. Assays were performed at different stages in the decontamination process to estimate the detection system sensitivity and the effectiveness of the cleaning efforts.
Date: July 1979
Creator: Argonne National Laboratory. Special Materials Division. Nondestructive Assay Section.
Partner: UNT Libraries Government Documents Department

Managing the Nuclear Fuel Cycle: Policy Implications of Expanding Global Access to Nuclear Power

Description: This report is intended to provide Members and congressional staff with the background needed to understand the current debate over proposed strategies to redesign the global nuclear fuel cycle. It begins with a look at the motivating factors underlying the resurgent interest in nuclear power, the nuclear power industry's current state of affairs, and the interdependence with the nuclear fuel cycle.
Date: September 3, 2008
Creator: Nikitin, Mary Beth; Andrews, Anthony & Holt, Mark
Partner: UNT Libraries Government Documents Department

20,000 KW Nuclear Power Plant Study for United States Atomic Energy Commission

Description: Introduction: In September of 156, Gilbert Associates, Inc., entered into a contract with the United States of America, acting through the United States Atomic Energy Commission, for the study and preliminary design of a nuclear power plant being considered for integration into a central station power system at an overseas site.
Date: July 7, 1957
Creator: Gilbert Associates, Inc.
Partner: UNT Libraries Government Documents Department

Mission analysis report - deactivation facilities at Hanford

Description: This document examines the portion of the Hanford Site Cleanup Mission that deals with facility deactivation. How facilities get identified for deactivation, how they enter EM-60 for deactivation, programmatic alternatives to perform facility deactivation, the deactivation process itself, key requirements and objectives associated with the deactivation process, and deactivation planning are discussed.
Date: September 27, 1996
Creator: Lund, D. P.
Partner: UNT Libraries Government Documents Department

Managing the Nuclear Fuel Cycle: Policy Implications of Expanding Global Access to Nuclear Power

Description: This report is intended to provide Members and congressional staff with the background needed to understand the current debate over proposed strategies to redesign the global nuclear fuel cycle. It begins with a look at the motivating factors underlying the resurgent interest in nuclear power, the nuclear power industry's current state of affairs, and the interdependence with the nuclear fuel cycle.
Date: March 7, 2008
Creator: Nikitin, Mary Beth; Parillo, Jill Marie; Squassoni, Sharon; Andrews, Anthony & Holt, Mark
Partner: UNT Libraries Government Documents Department

Treatment of Plutonium-Bearing Solutions: a Brief Survey of the DOE Complex

Description: With the abrupt shutdown of some DOE facilities, a significant volume of in-process material was left in place and still requires treatment for interim storage. Because the systems containing these process streams have deteriorated since shutdown, a portable system for treating the solutions may be useful. A brief survey was made of the DOE complex on the need for a portable treatment system to treat plutonium-bearing solutions. A survey was completed to determine (1) the compositions and volumes of solutions and heels present, (2) the methods that have been used to treat these solutions and heels in the past, and (3) the potential problems that exist in removing and treating these solutions. Based on the surveys and on the Defense Nuclear Facilities Safety Board Recommendation 94-1, design criteria for a portable treatment system were generated.
Date: March 1995
Creator: Conner, C.; Chamberlain, D. B.; Chen, L. & Vandegrift, G. F.
Partner: UNT Libraries Government Documents Department

Analysis of facility-monitoring data

Description: This paper discusses techniques for analysis of data collected from nuclear-safeguards facility-monitoring systems. These methods can process information gathered from sensors and make interpretations that are in the best interests of the facility or agency, thereby enhancing safeguards while shortening inspection time.
Date: September 1, 1996
Creator: Howell, J.A.
Partner: UNT Libraries Government Documents Department

Handbook for the implementation of IAEA inspection activities at Department of Energy nuclear facilities

Description: The Nonproliferation Support Program (NSP) in the United States Department of Energy (DOE) Office of Safeguards and Security (OSS) has responsibility for supporting and aiding implementation of international and multilateral programs, agreements, and treaties at domestic facilities. In late 1995, the {open_quotes}Readiness Planning Guide for Nonproliferation Visits{close_quotes} (DOE 470.1-1) was issued to assist DOE sites prepare for the host foreign delegations visiting DOE facilities. Since then, field and head-quarters programs have expressed a need for a document that addresses domestic safeguards and security activities, specifically planning for and hosting International Atomic Energy Agency (IAEA) technical visits and inspections. As a result, OSS/NSP conducted a workshop to prepare a handbook that would contain guidance on domestic safeguards and security preparation and follow-on activities to ensure that this handbook could be utilized by all facilities to improve operational efficiencies and reduce implementation problems. The handbook has been structured to provide detailed background and guidance concerning the obligation, negotiation, inspection, and reporting processes for IAEH safeguards activities in DOE nuclear facilities as well as the lessons-learned by currently inspected facilities and how-we-do-it implementation examples. This paper will present an overview of the preparation and content of this new Handbook.
Date: November 1, 1997
Creator: Zack, N.R.; Thomas, K.E.; Coady, K.J. & Desmond, W.J.
Partner: UNT Libraries Government Documents Department

Preliminary Saturated-Zone Flow Model

Description: This milestone consists of an updated fully 3D model of ground-water flow within the saturated zone at Yucca Mountain, Nevada. All electronic files pertaining to this deliverable have been transferred via ftp transmission to Steve Bodnar (M and O) and the technical data base. The model was developed using a flow and transport simulator, FEHMN, developed at Los Alamos National Laboratory, and represents a collaborative effort between staff from the US Geological Survey and Los Alamos National Laboratory. The model contained in this deliverable is minimally calibrated and represents work in progress. The flow model developed for this milestone is designed to feed subsequent transport modeling studies at Los Alamos which also use the FEHMN software. In addition, a general-application parameter estimation routine, PEST, was used in conjunction with FEHMN to reduce the difference between observed and simulated values of hydraulic head through the adjustment of model variables. This deliverable in large part consists of the electronic files for Yucca Mountain Site saturated-zone flow model as it existed as of 6/6/97, including the executable version of FEHMN (accession no. MOL.19970610.0204) used to run the code on a Sun Ultrasparc I workstation. It is expected that users of the contents of this deliverable be knowledgeable about the oration of FEHMN.
Date: June 10, 1997
Partner: UNT Libraries Government Documents Department

Global nuclear material monitoring with NDA and C/S data through integrated facility monitoring

Description: This paper focuses on a flexible, integrated demonstration of a monitoring approach for nuclear material monitoring. This includes aspects of item signature identification, perimeter portal monitoring, advanced data analysis, and communication as a part of an unattended continuous monitoring system in an operating nuclear facility. Advanced analysis is applied to the integrated nondestructive assay and containment and surveillance data that are synchronized in time. End result will be the foundation for a cost-effective monitoring system that could provide the necessary transparency even in areas that are denied to foreign nationals of both US and Russia should these processes and materials come under full-scope safeguards or bilateral agreements. Monitoring systems of this kind have the potential to provide additional benefits including improved nuclear facility security and safeguards and lower personnel radiation exposures. Demonstration facilities in this paper include VTRAP-prototype, Los Alamos Critical Assemblies Facility, Kazakhstan BM-350 Reactor monitor, DUPIC radiation monitoring, and JOYO and MONJU radiation monitoring.
Date: September 1, 1996
Creator: Howell, J.A.; Menlove, H.O.; Argo, P.; Goulding, C.; Klosterbuer, S. & Halbig, J.
Partner: UNT Libraries Government Documents Department

Repository Safety Strategy: Strategy for Protecting Public Health and Safety after Closure of a Yucca Mountain Repository, Rev. 1

Description: The updated Strategy to Protect Public Health and Safety explains the roles that the natural and engineered systems are expected to play in achieving the objectives of a potential repository system at Yucca Mountain. These objectives are to contain the radionuclides within the waste packages for thousands of years, and to ensure that annual doses to a person living near the site will be acceptably low. This strategy maintains the key assumption of the Site Characterization Plan (DOE 1988) strategy that the potential repository level (horizon) will remain unsaturated. Thus, the strategy continues to rely on the natural attributes of the unsaturated zone for primary protection by providing a setting where waste packages assisted by other engineered barriers are expected to contain wastes for thousands of years. As in the Site Characterization Plan (DOE 1988) strategy, the natural system from the walls of the underground openings (drifts) to the human environment is expected to provide additional defense by reducing the concentrations of any radionuclides released from the waste packages. The updated Strategy to Protect Public Health and Safety is the framework for the integration of site information, repository design and assessment of postclosure performance to develop a safety case for the viability assessment and a subsequent license application. Current site information and a reference design are used to develop a quantitative assessment of performance to be compared with a performance measure. Four key attributes of an unsaturated repository system that are critical to meeting the objectives: (1) Limited water contacting the waste packages; (2) Long waste package lifetime; (3) Slow rate of release of radionuclides from the waste form; and (4) Concentration reduction during transport through engineered and natural barriers.
Date: January 1, 1998
Creator: United States. Department of Energy.
Partner: UNT Libraries Government Documents Department

Remote Manipulation for D&D Exhibiting Teleautonomy and Telecollaboration

Description: The purpose of the work is to enhance remote operations of robotic systems for D&D tasks by extending teleoperation with semi-autonomous functions. The work leverages the $1.2M dual-arm work platform (DAWP) developed with broad participation for the CP5 D&D, as well as 2,000 hr DAWP D&D operational experience. We propose to develop a reactive, agent-based control architecture well suited to unstructured and unpredictable environments, and cobot control technology, which implements a virtual fixture that can be used to guide the application of tools with force-feedback control. Developed methodologies will be implemented using a structured light sensor and cobot hand controller on the dual-arm system.
Date: June 2003
Creator: Park, Young S.; Colgate, J. Edward; Ewing, Thomas F.; Kang, Hyoisig & Peshkin, Michael
Partner: UNT Libraries Government Documents Department

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

Description: Between October 1952 and February 1957, National Lead of Ohio (NLO), a primary contractor for the Atomic Energy Commission (AEC), subcontracted certain uranium machining operations to Alba Craft Laboratory, Incorporated, located at 10-14 West Rose Avenue, Oxford, Ohio. In 1992, personnel from Oak Ridge National Laboratory (ORNL) confirmed the presence of residual radioactive materials from the AEC-related operations in and around the facility in amounts exceeding the applicable Department of Energy (DOE) guidelines. Although the amount of uranium found on the property posed little health hazard if left undisturbed, the levels were sufficient to require remediation to bring radiological conditions into compliance with current guidelines, thus ensuring that the public and the environment are protected. Because it was suspected that uranium may have been used in the past in the immediate vicinity of Alba Craft in a Miami University building a team from ORNL, performed a radiological characterization survey of that structure in January 1994. The survey was conducted at the request of DOE as a precautionary measure to ensure that no radioactive residuals were present at levels exceeding guidelines. The survey included the determination of directly measured radiation levels and the collection of smear samples to detect possible removable alpha and beta-gamma activity levels, and comparison of these data to the guidelines. Results of the survey showed that all measurements were below the applicable guideline limits set by DOE.
Date: April 1, 1996
Creator: Kleinhans, K.R.; Murray, M.E. & Carrier, R.F.
Partner: UNT Libraries Government Documents Department

Advanced conceptual design report: T Plant secondary containment and leak detection upgrades. Project W-259

Description: The T Plant facilities in the 200-West Area of the Hanford site were constructed in the early 1940s to produce nuclear materials in support of national defense activities. T Plant includes the 271-T facility, the 221-T facility, and several support facilities (eg, 2706-T), utilities, and tanks/piping systems. T Plant has been recommended as the primary interim decontamination facility for the Hanford site. Project W-259 will provide capital upgrades to the T Plant facilities to comply with Federal and State of Washington environmental regulations for secondary containment and leak detection. This document provides an advanced conceptual design concept that complies with functional requirements for the T Plant Secondary Containment and Leak Detection upgrades.
Date: May 12, 1995
Creator: Hookfin, J.D.
Partner: UNT Libraries Government Documents Department

Development of an ASTM standard guide on performing vulnerability assessments for nuclear facilities

Description: This paper describes an effort undertaken by subcommittee C26.12 (Safeguards) of the American Society for Testing and Materials (ASTM) to develop a standard guide for performing vulnerability assessments (VAs). VAs are performed to determine the effectiveness of safeguards and security systems for both domestic and international nuclear facilities. These assessments address a range of threats, including theft of nuclear material and sabotage, and use an array of methods. The approach to performing and documenting VAs is varied and is largely dependent upon the tools used to perform them. This diversity can lead to tools being misused, making validation of VAs more difficult. The development of a standard guide for performing VAs would, if generally accepted, alleviate these concerns. ASTM provides a forum for developing guides that includes a high level of peer review to assure that the result is acceptable to all potential users. Additionally, the ASTM is widely recognized for setting standards, and endorsement by the Society may increase the likelihood of acceptance by the nuclear community. The goal of this work is to develop a guide that is independent of the tools being used to perform the VA and applicable to the spectrum of threats described above.
Date: September 1, 1995
Creator: Wilkey, D.D.
Partner: UNT Libraries Government Documents Department

Wet Chemical Oxidation of Organic Waste Using Nitric-Phosphoric Acid Technology

Description: Experimental progress has been made in a wide range of areas which support the continued development of the nitric-phosphoric acid oxidation process for combustible, solid organic wastes. An improved understanding of the overall process operation has been obtained, acid recovery and recycle systems have been studied, safety issues have been addressed, two potential final waste forms have been tested, preliminary mass flow diagrams have been prepared, and process flowsheets have been developed. The flowsheet developed is essentially a closed-loop system which addresses all of the internally generated waste streams. The combined activities aim to provide the basis for building and testing a 250-400 liter pilot-scale unit. Variations of the process now must be evaluated in order to address the needs of the primary customer, SRS Solid Waste Management. The customer is interested in treating job control waste contaminated with Pu-238 for shipment to WIPP. As a result, variations for feed preparation, acid recycle, and final form manufacturing must be considered to provide for simpler processing to accommodate operations in high radiation and contamination environments. The purpose of this program is to demonstrate a nitric-phosphoric acid destruction technology which can treat a heterogeneous waste by oxidizing the solid and liquid organic compounds while decontaminating noncombustible items.
Date: October 6, 1998
Creator: Pierce, R. A.
Partner: UNT Libraries Government Documents Department

Results for the Independent Sampling and Analysis of Used Oil Drums at the Impact Services Facility in Oak Ridge, TN

Description: The U.S. Department of Energy (DOE) requested that Oak Ridge Associated Universities (ORAU), via the Oak Ridge Institute for Science and Education (ORISE) contract, perform independent sampling and analysis of used oils contained within eight 55 gallon drums stored at the former IMPACT Services facility, located at the East Tennessee Technology Park in Oak Ridge, Tennessee. These drums were originally delivered by LATA Sharp Remediation Services (LSRS) to IMPACT Services on January 11, 2011 as part of the Bldg. K-33 demolition project, and the drums plus contents should have been processed as non-hazardous non-radiological waste by IMPACT Services. LSRS received a certificate of destruction on August 29, 2012 (LSRS 2012a). However, IMPACT Services declared bankruptcy and abandoned the site later in 2012, and eight of the original eleven K-33 drums are currently stored at the facility. The content of these drums is the subject of this investigation. The original drum contents were sampled by LSRS in 2010 and analyzed for gross alpha, gross beta, and polychlorinated biphenyls (PCBs), using both compositing and grab sampling techniques. The objective of this 2013 sample and analysis effort was to duplicate, to the extent possible, the 2010 sampling and analysis event to support final disposition decisions. Part of that decision process includes either verifying or refuting the assertion that oils that are currently stored in drums at the IMPACT Services facility originated from Bldg. K-33 equipment.
Date: April 25, 2013
Partner: UNT Libraries Government Documents Department

Enhanced Sulfate Management in HLW Glass Formulations VSL12R2540-1 REV 0

Description: The Low Activity Waste (LAW) tanks that are scheduled to provide the Hanford Tank Waste Treatment and Immobilization Plant (WTP) with waste feeds contain significant amounts of sulfate. The sulfate content in the LAW feeds is sufficiently high that a separate molten sulfate salt phase may form on top of the glass melt during the vitrification process unless suitable glass formulations are employed and sulfate levels are controlled. Since the formation of the salt phase is undesirable from many perspectives, mitigation approaches had to be developed. Considerable progress has been made and reported by the Vitreous State Laboratory (VSL) in enhancing sulfate incorporation into LAW glass melts and developing strategies to manage and mitigate the risks associated with high-sulfate feeds.
Date: November 13, 2012
Creator: Kruger, A. A.; Pegg, Ian L.; Kot, Wing; Gan, Hao & Matlack, Keith S.
Partner: UNT Libraries Government Documents Department