National Library of Energy BETA

Sample records for decommissioning cxs applied

  1. Decommissioning Documents | Department of Energy

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

    Decommissioning Documents PDF icon Decommissioning Documents More Documents & Publications Decommissioning Benchmarking Study Final Report Decommissioning Handbook ...

  2. Supercomputer decommissioning

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

    submit Roadrunner supercomputer: Rest in pieces Decommissioning a classified computer into hardware "mulch." May 1, 2013 The Roadrunner supercomputer broke the petaflop...

  3. Decommissioning Handbook

    Broader source: Energy.gov [DOE]

    The Decommissioning Handbook has been developed to incorporate examples and lessons learned, and to illustrate practices and procedures for implementing each step of the LCAM Decommissioing...

  4. Decommissioning Handbook

    SciTech Connect (OSTI)

    Not Available

    1994-03-01

    The Decommissioning Handbook is a technical guide for the decommissioning of nuclear facilities. The decommissioning of a nuclear facility involves the removal of the radioactive and, for practical reasons, hazardous materials to enable the facility to be released and not represent a further risk to human health and the environment. This handbook identifies and technologies and techniques that will accomplish these objectives. The emphasis in this handbook is on characterization; waste treatment; decontamination; dismantling, segmenting, demolition; and remote technologies. Other aspects that are discussed in some detail include the regulations governing decommissioning, worker and environmental protection, and packaging and transportation of the waste materials. The handbook describes in general terms the overall decommissioning project, including planning, cost estimating, and operating practices that would ease preparation of the Decommissioning Plan and the decommissioning itself. The reader is referred to other documents for more detailed information. This Decommissioning Handbook has been prepared by Enserch Environmental Corporation for the US Department of Energy and is a complete restructuring of the original handbook developed in 1980 by Nuclear Energy Services. The significant changes between the two documents are the addition of current and the deletion of obsolete technologies and the addition of chapters on project planning and the Decommissioning Plan, regulatory requirements, characterization, remote technology, and packaging and transportation of the waste materials.

  5. Supercomputer decommissioning

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

    Supercomputer decommissioning Community Connections: Your link to news and opportunities from Los Alamos National Laboratory Latest Issue:May 2016 all issues All Issues » submit Roadrunner supercomputer: Rest in pieces Decommissioning a classified computer into hardware "mulch." May 1, 2013 The Roadrunner supercomputer broke the petaflop barrier The Roadrunner supercomputer broke the petaflop barrier. Contact Editor Linda Anderman Email Community Programs Office Kurt Steinhaus Email

  6. Decommissioning handbook

    SciTech Connect (OSTI)

    Manion, W.J.; LaGuardia, T.S.

    1980-11-01

    This document is a compilation of information pertinent to the decommissioning of surplus nuclear facilities. This handbook is intended to describe all stages of the decommissioning process including selection of the end product, estimation of the radioactive inventory, estimation of occupational exposures, description of the state-of-the-art in re decontamination, remote csposition of wastes, and estimation of program costs. Presentation of state-of-the-art technology and data related to decommissioning will aid in consistent and efficient program planning and performance. Particular attention is focused on available technology applicable to those decommissioning activities that have not been accomplished before, such as remote segmenting and handling of highly activated 1100 MW(e) light water reactor vessel internals and thick-walled reactor vessels. A summary of available information associated with the planning and estimating of a decommissioning program is also presented. Summarized in particular are the methodologies associated with the calculation and measurement of activated material inventory, distribution, and surface dose level, system contamination inventory and distribution, and work area dose levels. Cost estimating techniques are also presented and the manner in which to account for variations in labor costs as impacting labor-intensive work activities is explained.

  7. Chapter 20 - Uranium Enrichment Decontamination & Decommissioning Fund

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

    0. Uranium Enrichment Decontamination and Decommissioning Fund 20-1 CHAPTER 20 URANIUM ENRICHMENT DECONTAMINATION AND DECOMMISSIONING FUND 1. INTRODUCTION. a. Purpose. To establish policies and procedures for the financial management, accounting, budget preparation, cash management of the Uranium Enrichment Decontamination and Decommissioning Fund, referred to hereafter as the Fund. b. Applicability. This chapter applies to all Departmental elements, including the National Nuclear Security

  8. Decommissioning Plan RM

    Broader source: Energy.gov [DOE]

    The Decommissioning Plan Review (DPR) Module is a tool that assists DOE federal project review teams in evaluating the adequacy of the decommissioning plan prior to approval of the associated CD.

  9. Deactivation & Decommissioning Knowledge Management Information...

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

    Knowledge Management Information Tool (D&D KM-IT) Deactivation & Decommissioning Knowledge Management Information Tool (D&D KM-IT) Deactivation & Decommissioning Knowledge ...

  10. Decommissioning Benchmarking Study Final Report

    Broader source: Energy.gov [DOE]

    DOE's former Office of Environmental Restoration (EM-40) conducted a benchmarking study of its decommissioning program to analyze physical activities in facility decommissioning and to determine...

  11. Decommissioning Unit Cost Data

    SciTech Connect (OSTI)

    Sanford, P. C.; Stevens, J. L.; Brandt, R.

    2002-02-26

    The Rocky Flats Closure Site (Site) is in the process of stabilizing residual nuclear materials, decommissioning nuclear facilities, and remediating environmental media. A number of contaminated facilities have been decommissioned, including one building, Building 779, that contained gloveboxes used for plutonium process development but did little actual plutonium processing. The actual costs incurred to decommission this facility formed much of the basis or standards used to estimate the decommissioning of the remaining plutonium-processing buildings. Recent decommissioning activities in the first actual production facility, Building 771, implemented a number of process and procedural improvements. These include methods for handling plutonium contaminated equipment, including size reduction, decontamination, and waste packaging, as well as management improvements to streamline planning and work control. These improvements resulted in a safer working environment and reduced project cost, as demonstrated in the overall project efficiency. The topic of this paper is the analysis of how this improved efficiency is reflected in recent unit costs for activities specific to the decommissioning of plutonium facilities. This analysis will allow the Site to quantify the impacts on future Rocky Flats decommissioning activities, and to develop data for planning and cost estimating the decommissioning of future facilities. The paper discusses the methods used to collect and arrange the project data from the individual work areas within Building 771. Regression and data correlation techniques were used to quantify values for different types of decommissioning activities. The discussion includes the approach to identify and allocate overall project support, waste management, and Site support costs based on the overall Site and project costs to provide a ''burdened'' unit cost. The paper ultimately provides a unit cost basis that can be used to support cost estimates for decommissioning at other facilities with similar equipment and labor costs. It also provides techniques for extracting information from limited data using extrapolation and interpolation techniques.

  12. Piqua, Ohio, Decommissioned Reactor Site

    Office of Legacy Management (LM)

    Piqua, Ohio, Decommissioned Reactor Site This fact sheet provides information about the Piqua, Ohio, Decommissioned Reactor. This site is managed by the U.S. Department of Energy Office of Legacy Management under the DOE Defense Decontamination and Decommissioning (D&D) Program. Location of the Piqua Decommissioned Reactor Site Description and History The Piqua, Ohio, Decommissioned Reactor site is located in southwestern Ohio in the city of Piqua on the east bank of the Great Miami River,

  13. Apply

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

    Applied Studies and Technology (AS&T) Applied Studies and Technology (AS&T) Applied Studies and Technology (AS&T) DOE established the Environmental Sciences Laboratory (ESL) in Grand Junction, Colorado, in 1991 to support its programs. ESL scientists perform applied research and laboratory-scale demonstrations of soil and groundwater remediation and treatment technologies. Capabilities Installation, monitoring, and operation of permeable reactive barriers Research of permeable

  14. Apply

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

    Apply Application Process Bringing together top space science students with internationally recognized researchers at Los Alamos in an educational and collaborative atmosphere. ...

  15. Portsmouth Decommissioning and Decontamination Project Director...

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

    Decommissioning and Decontamination Project Director's Final Findings and Order Portsmouth Decommissioning and Decontamination Project Director's Final Findings and Order...

  16. Factors Impacting Decommissioning Costs - 13576

    SciTech Connect (OSTI)

    Kim, Karen; McGrath, Richard

    2013-07-01

    The Electric Power Research Institute (EPRI) studied United States experience with decommissioning cost estimates and the factors that impact the actual cost of decommissioning projects. This study gathered available estimated and actual decommissioning costs from eight nuclear power plants in the United States to understand the major components of decommissioning costs. Major costs categories for decommissioning a nuclear power plant are removal costs, radioactive waste costs, staffing costs, and other costs. The technical factors that impact the costs were analyzed based on the plants' decommissioning experiences. Detailed cost breakdowns by major projects and other cost categories from actual power plant decommissioning experiences will be presented. Such information will be useful in planning future decommissioning and designing new plants. (authors)

  17. Site decommissioning management plan

    SciTech Connect (OSTI)

    Fauver, D.N.; Austin, J.H.; Johnson, T.C.; Weber, M.F.; Cardile, F.P.; Martin, D.E.; Caniano, R.J.; Kinneman, J.D.

    1993-10-01

    The Nuclear Regulatory Commission (NRC) staff has identified 48 sites contaminated with radioactive material that require special attention to ensure timely decommissioning. While none of these sites represent an immediate threat to public health and safety they have contamination that exceeds existing NRC criteria for unrestricted use. All of these sites require some degree of remediation, and several involve regulatory issues that must be addressed by the Commission before they can be released for unrestricted use and the applicable licenses terminated. This report contains the NRC staff`s strategy for addressing the technical, legal, and policy issues affecting the timely decommissioning of the 48 sites and describes the status of decommissioning activities at the sites.

  18. Decommissioning Implementation Guide

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

    1999-09-02

    The Department of Energy (DOE) faces an enormous task in the disposition of the nation's excess facilities. Many of these facilities are large and complex and contain potentially hazardous substances. As DOE facilities complete mission operations and are declared excess, they pass into a transition phase which ultimately prepares them for disposition. The disposition phase of a facility's life-cycle usually includes deactivation, decommissioning, and surveillance and maintenance (S&M) activities.

  19. Recordkeeping in the decommissioning process

    SciTech Connect (OSTI)

    Boing, L. E.

    2000-02-29

    In the US, there are two sets of key decommissioning records clearly identified -- those that are essential for planning the D and D of a facility and then those that are the result of the decommissioning process itself. In some cases, the regulatory authorities require and in others advise the licensees of the records that may be useful or which are required to be kept from the decommissioning. In the remainder of the paper, the author attempts to highlight some important aspects of decommissioning recordkeeping.

  20. International Research Reactor Decommissioning Project

    SciTech Connect (OSTI)

    Leopando, Leonardo; Warnecke, Ernst

    2008-01-15

    Many research reactors have been or will be shut down and are candidates for decommissioning. Most of the respective countries neither have a decommissioning policy nor the required expertise and funds to effectively implement a decommissioning project. The IAEA established the Research Reactor Decommissioning Demonstration Project (R{sup 2}D{sup 2}P) to help answer this need. It was agreed to involve the Philippine Research Reactor (PRR-1) as model reactor to demonstrate 'hands-on' experience as it is just starting the decommissioning process. Other facilities may be included in the project as they fit into the scope of R{sup 2}D{sup 2}P and complement to the PRR-1 decommissioning activities. The key outcome of the R{sup 2}D{sup 2}P will be the decommissioning of the PRR-1 reactor. On the way to this final goal the preparation of safety related documents (i.e., decommissioning plan, environmental impact assessment, safety analysis report, health and safety plan, cost estimate, etc.) and the licensing process as well as the actual dismantling activities could provide a model to other countries involved in the project. It is expected that the R{sup 2}D{sup 2}P would initiate activities related to planning and funding of decommissioning activities in the participating countries if that has not yet been done.

  1. Decommissioning Plan RM

    Office of Environmental Management (EM)

    Decommissioning Plan Review Module March 2010 CD-0 O 0 C OFFICE OF D C CD-1 F ENVIRO Standard R Decomm Rev Critical Decisi CD-2 M ONMENTAL Review Plan missioning view Module ion (CD) Ap CD March 2010 L MANAGE n (SRP) g Plan e plicability D-3 EMENT CD-4 Post Oper ration Standard Review Plan, 2 nd Edition, March 2010 i FOREWORD The Standard Review Plan (SRP) 1 provides a consistent, predictable corporate review framework to ensure that issues and risks that could challenge the success of Office of

  2. Decontamination & decommissioning focus area

    SciTech Connect (OSTI)

    1996-08-01

    In January 1994, the US Department of Energy Office of Environmental Management (DOE EM) formally introduced its new approach to managing DOE`s environmental research and technology development activities. The goal of the new approach is to conduct research and development in critical areas of interest to DOE, utilizing the best talent in the Department and in the national science community. To facilitate this solutions-oriented approach, the Office of Science and Technology (EM-50, formerly the Office of Technology Development) formed five Focus AReas to stimulate the required basic research, development, and demonstration efforts to seek new, innovative cleanup methods. In February 1995, EM-50 selected the DOE Morgantown Energy Technology Center (METC) to lead implementation of one of these Focus Areas: the Decontamination and Decommissioning (D & D) Focus Area.

  3. Status of the NRC Decommissioning Program

    SciTech Connect (OSTI)

    Orlando, D. A.; Camper, L.; Buckley, J.; Pogue, E.; Banovac, K.

    2003-02-24

    On July 21, 1997, the U.S. Nuclear Regulatory Commission (NRC) published the final rule on Radiological Criteria for License Termination (the License Termination Rule or LTR) as Subpart E to 10 CFR Part 20. NRC regulations require that materials licensees submit Decommissioning Plans to support the decommissioning of its facility if it is required by license condition, or if the procedures and activities necessary to carry out the decommissioning have not been approved by NRC and these procedures could increase the potential health and safety impacts to the workers or the public. NRC regulations also require that reactor licensees submit Post-shutdown Decommissioning Activities Reports and License Termination Plans to support the decommissioning of nuclear power facilities. This paper provides an update on the status of the NRC's decommissioning program that was presented during WM'02. It discusses the staff's current efforts to streamline the decommissioning process, current issues being faced in the decommissioning program, such as partial site release and restricted release of sites, as well as the status of the decommissioning of complex sites and those listed in the Site Decommissioning Management Plan. The paper discusses the status of permanently shut-down commercial power reactors and the transfer of complex decommissioning sites and sites listed on the SDMP to Agreement States. Finally the paper provides an update of the status of various tools and guidance the NRC is developing to assist licensees during decommissioning, including an effort to consolidate and risk-inform decommissioning guidance.

  4. Is Entombment an Acceptable Option for Decommissioning? An International Perspective - 13488

    SciTech Connect (OSTI)

    Belencan, Helen; Nys, Vincent; Guskov, Andrey; Francois, Patrice; Watson, Bruce; Ljubenov, Vladan

    2013-07-01

    Selection of a decommissioning strategy is one of the key steps in the preparation for decommissioning of nuclear facilities and other facilities using radioactive material. Approaches being implemented or considered by Member States include immediate dismantling, deferred dismantling and entombment. Other options or slight modifications of these strategies are also possible. Entombment has been identified in the current International Atomic Energy Agency (IAEA) Safety Standards as one of the three basic decommissioning strategies and has been defined as a decommissioning strategy by which radioactive contaminants are encased in a structurally long lived material until radioactivity decays to a level permitting the unrestricted release of the facility, or release with restrictions imposed by the regulatory body. Although all three strategies have been considered, in principle, applicable to all facilities, their application to some facilities may not be appropriate owing to political concerns, safety or environmental requirements, technical considerations, local conditions or financial considerations. The IAEA is currently revising the decommissioning Safety Standards and one of the issues widely discussed has been the applicability of entombment in the context of decommissioning and its general objective to enable removal of regulatory control from the decommissioned facility. The IAEA recently established a consultancy to collect and discuss experience and lessons learned from entombment projects, to identify regulatory requirements and expectations for applying entombment as a decommissioning option strategy, in compliance with the internationally agreed standards. (authors)

  5. Portsmouth Decontamination & Decommissioning | Department of Energy

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

    Decontamination & Decommissioning Portsmouth Decontamination & Decommissioning The Decontamination & Decommissioning (D&D) Program at the Portsmouth Site addresses potential future demolition and disposal of approximately 415 facilities (including buildings, utilities, systems, ponds and infrastructure units) currently identified on the Portsmouth site. This includes the three Gaseous Diffusion Process buildings that housed the process equipment and span the size of 158 football

  6. CX-012628: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    Deactivation and Decommissioning of 711-L CX(s) Applied: B1.23Date: 41793 Location(s): South CarolinaOffices(s): Savannah River Operations Office

  7. STATUS OF THE NRC'S DECOMMISSIONING PROGRAM

    SciTech Connect (OSTI)

    Orlando, D. A.; Camper, L. W.; Buckley, J.

    2002-02-25

    On July 21, 1997, the U.S. Nuclear Regulatory Commission published the final rule on Radiological Criteria for License Termination (the License Termination Rule) as Subpart E to 10 CFR Part 20. NRC regulations require that materials licensees submit Decommissioning Plans to support the decommissioning of its facility if it is required by license condition, or if the procedures and activities necessary to carry out the decommissioning have not been approved by NRC and these procedures could increase the potential health and safety impacts to the workers or the public. NRC regulations also require that reactor licensees submit Post-shutdown Decommissioning Activities Reports and License Termination Plans to support the decommissioning of nuclear power facilities. This paper provides an update on the status of the NRC's decommissioning program. It discusses the status of permanently shut-down commercial power reactors, complex decommissioning sites, and sites listed in the Site Decommissioning Management Plan. The paper provides the status of various tools and guidance the NRC is developing to assist licensees during decommissioning, including a Standard Review Plan for evaluating plans and information submitted by licensees to support the decommissioning of nuclear facilities and the D and D Screen software for determining the potential doses from residual radioactivity. Finally, it discusses the status of the staff's current efforts to streamline the decommissioning process.

  8. Assessment of foreign decommissioning technology with potential application to US decommissioning needs

    SciTech Connect (OSTI)

    Allen, R.P.; Konzek, G.J.; Schneider, K.J.; Smith, R.I.

    1987-09-01

    This study was conducted by the Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE) to identify and technically assess foreign decommissioning technology developments that may represent significant improvements over decommissioning technology currently available or under development in the United States. Technology need areas for nuclear power reactor decommissioning operations were identified and prioritized using the results of past light water reactor (LWR) decommissioning studies to quantitatively evaluate the potential for reducing cost and decommissioning worker radiation dose for each major decommissioning activity. Based on these identified needs, current foreign decommissioning technologies of potential interest to the US were identified through personal contacts and the collection and review of an extensive body of decommissioning literature. These technologies were then assessed qualitatively to evaluate their uniqueness, potential for a significant reduction in decommissioning costs and/or worker radiation dose, development status, and other factors affecting their value and applicability to US needs.

  9. Technology, Safety and Costs of Decommissioning Nuclear Reactors At Multiple-Reactor Stations

    SciTech Connect (OSTI)

    Wittenbrock, N. G.

    1982-01-01

    Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWRs) and large (1155-MWe) boiling water reactors {BWRs) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite nuclear waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services. Five scenarios for decommissioning reactors at a multiple-reactor station are investigated. The number of reactors on a site is assumed to be either four or ten; nuclear waste disposal is varied between immediate offsite disposal, interim onsite storage, and immediate onsite disposal. It is assumed that the decommissioned reactors are not replaced in one scenario but are replaced in the other scenarios. Centralized service facilities are provided in two scenarios but are not provided in the other three. Decommissioning of a PWR or a BWR at a multiple-reactor station probably will be less costly and result in lower radiation doses than decommissioning an identical reactor at a single-reactor station. Regardless of whether the light water reactor being decommissioned is at a single- or multiple-reactor station: • the estimated occupational radiation dose for decommissioning an LWR is lowest for SAFSTOR and highest for DECON • the estimated cost of decommissioning a PWR is lowest for ENTOMB and highest for SAFSTOR • the estimated cost of decommissioning a BWR is lowest for OECON and highest for SAFSTOR. In all cases, SAFSTOR has the lowest occupational radiation dose and the highest cost.

  10. Deactivation and Decommissioning | Department of Energy

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

    Services » Deactivation and Decommissioning Deactivation and Decommissioning TA-21-286 being demolished TA-21-286 being demolished The EM-LA Deactivation and Decommissioning (D&D) Team is dedicated to demolishing, deactivating and disposing material from historical buildings at Los Alamos National Laboratory. Current workscope is focused on Technical Area 21 (TA-21), one of the early sites of the Manhattan Project and Cold War-era work conducted at LANL. TA-21 was the location of the

  11. Portsmouth Decommissioning and Decontamination Project Director's Final

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

    Findings and Order | Department of Energy Decommissioning and Decontamination Project Director's Final Findings and Order Portsmouth Decommissioning and Decontamination Project Director's Final Findings and Order Portsmouth Decommissioning and Decontamination (D&D) Project Director's Final Findings and Order defines the steps for identifying a range of technical alternatives for the D&D and waste disposition components of the project, and reaching formal decisions on how best to

  12. Power Burst Facility (PBF) Reactor Reactor Decommissioning

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

    to ensure it protects the environment. Decommissioning of older, unused facilities saves money from on-going maintenance and utility requirements. Editorial Date September 25...

  13. Decommissioning abandoned roads to protect fish

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

    Decommissioning-abandoned-roads-to-protect-fish Sign In About | Careers | Contact | Investors | bpa.gov Search News & Us Expand News & Us Projects & Initiatives Expand Projects...

  14. In-Situ Decommissioning | Department of Energy

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

    In-Situ Decommissioning (ISD) is the permanent entombment of a facility that contains residual radiological andor chemical contamination. The ISD approach is a cost-effective ...

  15. Uranium Enrichment Decontamination and Decommissioning Fund's...

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

    Uranium Enrichment Decontamination and Decommissioning Fund's Fiscal Year 2008 and 2007 Financial Statement Audit, OAS-FS-10-05 Uranium Enrichment Decontamination and...

  16. Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) |

    Energy Savers [EERE]

    Department of Energy Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) As the DOE complex sites

  17. Idaho Site Closes Out Decontamination and Decommissioning Project...

    Office of Environmental Management (EM)

    Site Closes Out Decontamination and Decommissioning Project about 440 Million under Cost Idaho Site Closes Out Decontamination and Decommissioning Project about 440 Million under...

  18. Nuclear Decommissioning Authority of the United Kingdom NDA ...

    Open Energy Info (EERE)

    Decommissioning Authority of the United Kingdom NDA Jump to: navigation, search Name: Nuclear Decommissioning Authority of the United Kingdom (NDA) Place: Cumbria, England, United...

  19. STANDARD OPERATING PROTOCOLS FOR DECOMMISSIONING

    SciTech Connect (OSTI)

    Foss, D. L.; Stevens, J. L.; Gerdeman, F. W.

    2002-02-25

    Decommissioning projects at Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) sites are conducted under project-specific decision documents, which involve extensive preparation time, public comment periods, and regulatory approvals. Often, the decision documents must be initiated at least one year before commencing the decommissioning project, and they are expensive and time consuming to prepare. The Rocky Flats Environmental Technology Site (RFETS) is a former nuclear weapons production plant at which hazardous substances and wastes were released or disposed during operations. As a result of the releases, RFETS was placed on the National Priorities List in 1989, and is conducting cleanup activities under a federal facilities compliance agreement. Working closely with interested stakeholders and state and federal regulatory agencies, RFETS has developed and implemented an improved process for obtaining the approvals. The key to streamlining the approval process has been the development of sitewide decision documents called Rocky Flats Cleanup Agreement Standard Operating Protocols or ''RSOPs.'' RSOPs have broad applicability, and could be used instead of project-specific documents. Although no two decommissioning projects are exactly the same and they may vary widely in contamination and other hazards, the basic steps taken for cleanup are usually similar. Because of this, using RSOPs is more efficient than preparing a separate project-specific decision documents for each cleanup action. Over the Rocky Flats cleanup life cycle, using RSOPs has the potential to: (1) Save over 5 million dollars and 6 months on the site closure schedule; (2) Eliminate preparing one hundred and twenty project-specific decision documents; and (3) Eliminate writing seventy-five closure description documents for hazardous waste unit closure and corrective actions.

  20. Comparative Evaluation of Cutting Methods of Activated Concrete from Nuclear Power Plant Decommissioning - 13548

    SciTech Connect (OSTI)

    Kim, HakSoo; Chung, SungHwan; Maeng, SungJun

    2013-07-01

    The amount of radioactive wastes from decommissioning of a nuclear power plant varies greatly depending on factors such as type and size of the plant, operation history, decommissioning options, and waste treatment and volume reduction methods. There are many methods to decrease the amount of decommissioning radioactive wastes including minimization of waste generation, waste reclassification through decontamination and cutting methods to remove the contaminated areas. According to OECD/NEA, it is known that the radioactive waste treatment and disposal cost accounts for about 40 percentage of the total decommissioning cost. In Korea, it is needed to reduce amount of decommissioning radioactive waste due to high disposal cost, about $7,000 (as of 2010) per a 200 liter drum for the low- and intermediate-level radioactive waste (LILW). In this paper, cutting methods to minimize the radioactive waste of activated concrete were investigated and associated decommissioning cost impact was assessed. The cutting methods considered are cylindrical and volume reductive cuttings. The study showed that the volume reductive cutting is more cost-effective than the cylindrical cutting. Therefore, the volume reductive cutting method can be effectively applied to the activated bio-shield concrete. (authors)

  1. Implementing 'Continuous Improvement' in the U.S. Nuclear Regulatory Commission's Decommissioning Program

    SciTech Connect (OSTI)

    Orlando, D. A.; Buckley, J. T.; Johnson, R. L.; Gillen, D. M.

    2006-07-01

    The United States Nuclear Regulatory Commission's (US NRC's) comprehensive decommissioning program encompasses the decommissioning of all US NRC licensed facilities, ranging from the termination of routine licenses for sealed sources, to the closure of complex materials sites and nuclear power reactor facilities. Of the approximately 200 materials licenses that are terminated each year, most are routine and require little, if any, remediation to meet the US NRC unrestricted release criteria. However, some present technical and policy challenges that require large expenditures of resources, including a few complex materials sites that have requested license termination under the restricted-use provisions of 10 CFR 20.1403. Fiscal constraints to reduce budgeted resources in the decommissioning program, as well as concerns over the time to complete the decommissioning process have led to actions to improve the program and use resources more efficiently. In addition, the US NRC's Strategic Plan requires efforts to identify and implement improvements to US NRC programs in order to improve efficiency, effectiveness, timeliness, and openness, of the US NRC's activities, while maintaining the necessary focus on safety. Decommissioning regulations, and more recently the analysis of several issues associated with implementing those regulations, also have been significant catalysts for improvements in the decommissioning program. Actions in response to these catalysts have resulted in a program focused on the management of complex sites in a comprehensive, consistent, and risk-informed manner, as opposed to the past practice of focusing on sites deemed to be problematic. This paper describes the current status of the decommissioning of US NRC-licensed nuclear facilities, including an overview of recent decommissioning project completion efforts. It provides a detailed summary of past, current, and future improvements in the US NRC decommissioning program including the significant improvements implemented since 2000, and ongoing improvement efforts. Finally, the paper discusses how these efforts have been applied at specific sites and have contributed to the improvement in the decommissioning process at nuclear facilities, typically resulting in a reduction in the length of time needed for the decommissioning project or the reduction in the amount of US NRC and licensee resources necessary to complete a project. (authors)

  2. FY 2000 Deactivation and Decommissioning Focus Area Annual Report

    SciTech Connect (OSTI)

    2001-03-01

    This document describes activities of the Deactivation and Decommissioning Focus Area for the past year.

  3. In-Situ Decommissioning: A Strategy for Environmental Management |

    Energy Savers [EERE]

    Department of Energy In-Situ Decommissioning: A Strategy for Environmental Management In-Situ Decommissioning: A Strategy for Environmental Management In-Situ Decommissioning (ISD) is an effective decommissioning practice offering a safe and environmentally-favorable alternative to completely demolishing a facility and transporting its debris elsewhere for disposal. Regulatory approval to decommission a facility through ISD is authorized primarily by the Environmental Protection Agency under

  4. Technology Requirements for In-Situ Decommissioning Workshop Report |

    Energy Savers [EERE]

    Department of Energy Services » Site & Facility Restoration » Deactivation & Decommissioning (D&D) » D&D Workshops » Technology Requirements for In-Situ Decommissioning Workshop Report Technology Requirements for In-Situ Decommissioning Workshop Report In recognition of the increasing attention being focused on In Situ Decommissioning (ISD or entombment) as an acceptable and beneficial decommissioning end state, EM is developing guidance for the implementation of ISD of

  5. Pipeline Decommissioning Trial AWE Berkshire UK - 13619

    SciTech Connect (OSTI)

    Agnew, Kieran

    2013-07-01

    This Paper details the implementation of a 'Decommissioning Trial' to assess the feasibility of decommissioning the redundant pipeline operated by AWE located in Berkshire UK. The paper also presents the tool box of decommissioning techniques that were developed during the decommissioning trial. Constructed in the 1950's and operated until 2005, AWE used a pipeline for the authorised discharge of treated effluent. Now redundant, the pipeline is under a care and surveillance regime awaiting decommissioning. The pipeline is some 18.5 km in length and extends from AWE site to the River Thames. Along its route the pipeline passes along and under several major roads, railway lines and rivers as well as travelling through woodland, agricultural land and residential areas. Currently under care and surveillance AWE is considering a number of options for decommissioning the pipeline. One option is to remove the pipeline. In order to assist option evaluation and assess the feasibility of removing the pipeline a decommissioning trial was undertaken and sections of the pipeline were removed within the AWE site. The objectives of the decommissioning trial were to: - Demonstrate to stakeholders that the pipeline can be removed safely, securely and cleanly - Develop a 'tool box' of methods that could be deployed to remove the pipeline - Replicate the conditions and environments encountered along the route of the pipeline The onsite trial was also designed to replicate the physical prevailing conditions and constraints encountered along the remainder of its route i.e. working along a narrow corridor, working in close proximity to roads, working in proximity to above ground and underground services (e.g. Gas, Water, Electricity). By undertaking the decommissioning trial AWE have successfully demonstrated the pipeline can be decommissioned in a safe, secure and clean manor and have developed a tool box of decommissioning techniques. The tool box of includes; - Hot tapping - a method of breaching the pipe while maintaining containment to remove residual liquids, - Crimp and shear - remote crimping, cutting and handling of pipe using the excavator - Pipe jacking - a way of removing pipes avoiding excavations and causing minimal disturbance and disruption. The details of the decommissioning trial design, the techniques employed, their application and effectiveness are discussed and evaluated here in. (authors)

  6. Deactivation, Decontamination and Decommissioning Project Summaries

    SciTech Connect (OSTI)

    Peterson, David Shane; Webber, Frank Laverne

    2001-07-01

    This report is a compilation of summary descriptions of Deactivation, Decontamination and Decommissioning, and Surveillance and Maintenance projects planned for inactive facilities and sites at the INEEL from FY-2002 through FY-2010. Deactivations of contaminated facilities will produce safe and stable facilities requiring minimal surveillance and maintenance pending further decontamination and decommissioning. Decontamination and decommissioning actions remove contaminated facilities, thus eliminating long-term surveillance and maintenance. The projects are prioritized based on risk to DOE-ID, the public, and the environment, and the reduction of DOE-ID mortgage costs and liability at the INEEL.

  7. Decommissioning Under CERCLA Information Sheet | Department of...

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

    Decommissioning Under CERCLA Information Sheet This Question and Answer (Q&A) Sheet ... This Q&A Sheet is presented in four parts. The first part presents the bottom line: what ...

  8. Systematic Approach for Decommissioning Planning and Estimating

    SciTech Connect (OSTI)

    Dam, A. S.

    2002-02-26

    Nuclear facility decommissioning, satisfactorily completed at the lowest cost, relies on a systematic approach to the planning, estimating, and documenting the work. High quality information is needed to properly perform the planning and estimating. A systematic approach to collecting and maintaining the needed information is recommended using a knowledgebase system for information management. A systematic approach is also recommended to develop the decommissioning plan, cost estimate and schedule. A probabilistic project cost and schedule risk analysis is included as part of the planning process. The entire effort is performed by a experienced team of decommissioning planners, cost estimators, schedulers, and facility knowledgeable owner representatives. The plant data, work plans, cost and schedule are entered into a knowledgebase. This systematic approach has been used successfully for decommissioning planning and cost estimating for a commercial nuclear power plant. Elements of this approach have been used for numerous cost estimates and estimate reviews. The plan and estimate in the knowledgebase should be a living document, updated periodically, to support decommissioning fund provisioning, with the plan ready for use when the need arises.

  9. DOE Policy on Decommissioning DOE Facilities Under CERCLA | Department...

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

    POLICY ON DECOMMISSIONING DOE FACILITIES UNDER CERCLA This policy is the result of a joint effort by EPA and DOE to develop an approach to decommissioning that ensures protection ...

  10. Uranium enrichment decontamination and decommissioning fund, 1995 report

    SciTech Connect (OSTI)

    1996-11-01

    This report describes strategies for the decontamination and decommissioning of gaseous diffusion plants. Progress in remedial action activities are discussed.

  11. ORISE: Applied health physics projects

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

    Applied health physics projects The Oak Ridge Institute for Science and Education (ORISE) provides applied health physics services to government agencies needing technical support for decommissioning projects. Whether the need is assistance with the development of technical basis documents or advice on how to identify, measure and assess the presence of radiological materials, ORISE can help determine the best course for an environmental cleanup project. Our key areas of expertise include fuel

  12. Decontamination, decommissioning, and vendor advertorial issue, 2006

    SciTech Connect (OSTI)

    Agnihotri, Newal (ed.)

    2006-07-15

    The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Major articles/reports in this issue include: NPP Krsko revised decommissioning program, by Vladimir Lokner and Ivica Levanat, APO d.o.o., Croatia, and Nadja Zeleznik and Irena Mele, ARAO, Slovenia; Supporting the renaissance, by Marilyn C. Kray, Exelon Nuclear; Outage world an engineer's delight, by Tom Chrisopher, Areva, NP Inc.; Optimizing refueling outages with R and D, by Ross Marcoot, GE Energy; and, A successful project, by Jim Lash, FirstEnergy.

  13. Sodium Reactor Experiment decommissioning. Final report

    SciTech Connect (OSTI)

    Carroll, J.W.; Conners, C.C.; Harris, J.M.; Marzec, J.M.; Ureda, B.F.

    1983-08-15

    The Sodium Reactor Experiment (SRE) located at the Rockwell International Field Laboratories northwest of Los Angeles was developed to demonstrate a sodium-cooled, graphite-moderated reactor for civilian use. The reactor reached full power in May 1958 and provided 37 GWh to the Southern California Edison Company grid before it was shut down in 1967. Decommissioning of the SRE began in 1974 with the objective of removing all significant radioactivity from the site and releasing the facility for unrestricted use. Planning documentation was prepared to describe in detail the equipment and techniques development and the decommissioning work scope. A plasma-arc manipulator was developed for remotely dissecting the highly radioactive reactor vessels. Other important developments included techniques for using explosives to cut reactor vessel internal piping, clamps, and brackets; decontaminating porous concrete surfaces; and disposing of massive equipment and structures. The documentation defined the decommissioning in an SRE dismantling plan, in activity requirements for elements of the decommissioning work scope, and in detailed procedures for each major task.

  14. DOE Awards New York Decommissioning Services Contract

    Broader source: Energy.gov [DOE]

    West Valley, NY -- The Department of Energy (DOE) today awarded a contract to CH2M Hill-B&W West Valley of Englewood, Colorado, for the Phase I Decommissioning and Facility Disposition activities at the West Valley Demonstration Project (WVDP).

  15. University of Virginia Reactor Facility Decommissioning Results

    SciTech Connect (OSTI)

    Ervin, P. F.; Lundberg, L. A.; Benneche, P. E.; Mulder, R. U.; Steva, D. P.

    2003-02-24

    The University of Virginia Reactor Facility started accelerated decommissioning in 2002. The facility consists of two licensed reactors, the CAVALIER and the UVAR. This paper will describe the progress in 2002, remaining efforts and the unique organizational structure of the project team.

  16. Decontamination and decommissioning focus area. Technology summary

    SciTech Connect (OSTI)

    1995-06-01

    This report presents details of the facility deactivation, decommissioning, and material disposition research for development of new technologies sponsored by the Department of Energy. Topics discussed include; occupational safety, radiation protection, decontamination, remote operated equipment, mixed waste processing, recycling contaminated metals, and business opportunities.

  17. Nuclear facility decommissioning and site remedial actions: a selected bibliography

    SciTech Connect (OSTI)

    Owen, P.T.; Knox, N.P.; Fielden, J.M.; Johnson, C.A.

    1982-09-01

    This bibliography contains 693 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. Foreign, as well as domestic, literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Uranium Mill Tailings Remedial Action Program, Grand Junction Remedial Action Program, and Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General Studies. The references within each chapter are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for (1) author; (2) corporate affiliation; (3) title; (4) publication description; (5) geographic location; and (6) keywords. An appendix of 202 bibliographic references without abstracts or indexes has been included in this bibliography. This appendix represents literature identified but not abstracted due to time constraints.

  18. NMSS handbook for decommissioning fuel cycle and materials licensees

    SciTech Connect (OSTI)

    Orlando, D.A.; Hogg, R.C.; Ramsey, K.M.

    1997-03-01

    The US Nuclear Regulatory Commission amended its regulations to set forth the technical and financial criteria for decommissioning licensed nuclear facilities. These regulations were further amended to establish additional recordkeeping requirements for decommissioning; to establish timeframes and schedules for the decommissioning; and to clarify that financial assurance requirements must be in place during operations and updated when licensed operations cease. Reviews of the Site Decommissioning Management Plan (SDMP) program found that, while the NRC staff was overseeing the decommissioning program at nuclear facilities in a manner that was protective of public health and safety, progress in decommissioning many sites was slow. As a result NRC determined that formal written procedures should be developed to facilitate the timely decommissioning of licensed nuclear facilities. This handbook was developed to aid NRC staff in achieving this goal. It is intended to be used as a reference document to, and in conjunction with, NRC Inspection Manual Chapter (IMC) 2605, ``Decommissioning Inspection Program for Fuel Cycle and Materials Licensees.`` The policies and procedures discussed in this handbook should be used by NRC staff overseeing the decommissioning program at licensed fuel cycle and materials sites; formerly licensed sites for which the licenses were terminated; sites involving source, special nuclear, or byproduct material subject to NRC regulation for which a license was never issued; and sites in the NRC`s SDMP program. NRC staff overseeing the decommissioning program at nuclear reactor facilities subject to regulation under 10 CFR Part 50 are not required to use the procedures discussed in this handbook.

  19. Management of Decommissioning on a Multi-Facility Site (Conference) |

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect Conference: Management of Decommissioning on a Multi-Facility Site Citation Details In-Document Search Title: Management of Decommissioning on a Multi-Facility Site The management of the decommissioning of multi-facility sites may be inadequate or inappropriate if based on approaches and strategies developed for sites consisting of only a single facility. The varied nature of activities undertaken, their interfaces and their interdependencies are likely to complicate the

  20. DOE Policy on Decommissioning DOE Facilities Under CERCLA | Department of

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

    Energy DOE Policy on Decommissioning DOE Facilities Under CERCLA DOE Policy on Decommissioning DOE Facilities Under CERCLA In May 1995, the Department of Energy (DOE) issued a policy in collaboration with the Environmental Protection Agency (EPA) for decommissioning surplus DOE facilities consistent with the requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). This policy ensures protection of the environment, worker health and public health,

  1. Fossil plant decommissioning: Tracking deferred costs in a competitive market

    SciTech Connect (OSTI)

    Ferguson, J.S.

    1995-06-15

    Widespread concern over nuclear plant decommissioning has triggered similar interest in the decommissioning of fossil-fired steam generating stations. This rising interest stems in part from the emergence of a competitive market in electric generation, which, among other things, threatens impairment of assets. Fossil decommissioning issues are not nearly as contentious as those that attend nuclear plants. Nevertheless, the magnitude of cost estimates for fossil decommissioning, when expressed as a percentage of station investment, is high enough to demand attention from accountants and regulators.

  2. BONUS, Puerto Rico, Decommissioned Reactor Site Fact Sheet

    Office of Legacy Management (LM)

    information about the Defense Decontamination and Decommissioning Program Boiling Nuclear Superheater (BONUS) reactor located northwest of Rincn, Puerto Rico. The site is...

  3. Role of decommissioning plan and its progress for the PUSPATI...

    Office of Scientific and Technical Information (OSTI)

    At international level, IAEA recognizes the absence of Decommissioning Plan as one of the ... national contribution at the international level, as well as meeting the ...

  4. Decommissioning of U.S. Uranium Production Facilities

    Reports and Publications (EIA)

    1995-01-01

    This report analyzes the uranium production facility decommissioning process and its potential impact on uranium supply and prices. 1995 represents the most recent publication year.

  5. HEAVY WATER COMPONENTS TEST REACTOR DECOMMISSIONING

    SciTech Connect (OSTI)

    Austin, W.; Brinkley, D.

    2011-10-13

    The Heavy Water Components Test Reactor (HWCTR) Decommissioning Project was initiated in 2009 as a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Removal Action with funding from the American Recovery and Reinvestment Act (ARRA). This paper summarizes the history prior to 2009, the major D&D activities, and final end state of the facility at completion of decommissioning in June 2011. The HWCTR facility was built in 1961, operated from 1962 to 1964, and is located in the northwest quadrant of the Savannah River Site (SRS) approximately three miles from the site boundary. The HWCTR was a pressurized heavy water test reactor used to develop candidate fuel designs for heavy water power reactors. In December of 1964, operations were terminated and the facility was placed in a standby condition as a result of the decision by the U.S. Atomic Energy Commission to redirect research and development work on heavy water power reactors to reactors cooled with organic materials. For about one year, site personnel maintained the facility in a standby status, and then retired the reactor in place. In the early 1990s, DOE began planning to decommission HWCTR. Yet, in the face of new budget constraints, DOE deferred dismantlement and placed HWCTR in an extended surveillance and maintenance mode. The doors of the reactor facility were welded shut to protect workers and discourage intruders. In 2009 the $1.6 billion allocation from the ARRA to SRS for site footprint reduction at SRS reopened the doors to HWCTR - this time for final decommissioning. Alternative studies concluded that the most environmentally safe, cost effective option for final decommissioning was to remove the reactor vessel, both steam generators, and all equipment above grade including the dome. The transfer coffin, originally above grade, was to be placed in the cavity vacated by the reactor vessel and the remaining below grade spaces would be grouted. Once all above equipment including the dome was removed, a concrete cover was to be placed over the remaining footprint and the groundwater monitored for an indefinite period to ensure compliance with environmental regulations.

  6. Policy on Decommissioning of Department of Energy Facilities Under the

    Energy Savers [EERE]

    Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) | Department of Energy Policy on Decommissioning of Department of Energy Facilities Under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Policy on Decommissioning of Department of Energy Facilities Under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Purpose This Policy establishes the approach agreed upon by the Department of Energy (DOE) and

  7. Study on the financing mechanism and management for decommissioning of nuclear installations in Malaysia

    SciTech Connect (OSTI)

    Saleh, Lydia Ilaiza Ryong, Kim Tae

    2015-04-29

    The whole cycle of the decommissioning process development of repository requires the relevant bodies to have a financial system to ensure that it has sufficient funds for its whole life cycle (over periods of many decades). Therefore, the financing mechanism and management system shall respect the following status: the national position, institutional and legislative environment, technical capabilities, the waste origin, ownership, characteristics and inventories. The main objective of the studies is to focus on the cost considerations, alternative funding managements and mechanisms, technical and non-technical factors that may affect the repository life-cycle costs. As a conclusion, the outcomes of this paper is to make a good recommendation and could be applied to the national planners, regulatory body, engineers, or the managers, to form a financial management plan for the decommissioning of the Nuclear Installation.

  8. Environmental Impact Assessment (EIA) Process of V1 NPP Decommissioning

    SciTech Connect (OSTI)

    Matejovic, Igor; Polak, Vincent

    2007-07-01

    Through the adoption of Governmental Resolution No. 801/99 the Slovak Republic undertook a commitment to shutdown units 1 and 2 of Jaslovske Bohunice V 1 NPP (WWER 230 reactor type) in 2006 and 2008 respectively. Therefore the more intensive preparation of a decommissioning documentation has been commenced. Namely, the VI NPP Conceptual Decommissioning Plan and subsequently the Environmental Impact Assessment Report of VI NPP Decommissioning were developed. Thus, the standard environmental impact assessment process was performed and the most suitable alternative of V1 NPP decommissioning was selected as a basis for development of further decommissioning documents. The status and main results of the environmental impact assessment process and EIA report are discussed in more detail in this paper. (authors)

  9. CX-008145: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Reclamation of Decommissioned Batteries, Test Satellites, and Facilities CX(s) Applied: B1.3, B6.1 Date: 08/06/2011 Location(s): Wyoming Offices(s): RMOTC

  10. CX-008288: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Decommissioning of the Appliance Testing and Evaluation Center in Morgantown CX(s) Applied: B3.6 Date: 05/01/2012 Location(s): West Virginia Offices(s): National Energy Technology Laboratory

  11. CX-007821: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Routine Activities at the Site A/Plot M, Illinois, Decommissioned Reactor Site CX(s) Applied: B1.3, B3.1 Date: 02/09/2012 Location(s): Illinois Offices(s): Legacy Management

  12. CX-002606: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Decommissioning of Room 94-03CX(s) Applied: B3.6Date: 12/11/2009Location(s): Pittsburgh, PennsylvaniaOffice(s): Fossil Energy, National Energy Technology Laboratory

  13. CX-007811: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    "Decommission Ground Water Monitoring Well Located on Bonneville Power Administration (BPA) Fee-owned Property CX(s) Applied: B3.1 Date: 12/14/2011 Location(s): Washington Offices(s): Bonneville Power Administration"

  14. CX-011212: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Decommissioning of Shallow Injection Wells at the Advanced Test Reactor Complex CX(s) Applied: B5.3 Date: 08/29/2013 Location(s): Idaho Offices(s): Idaho Operations Office

  15. CX-011715: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    Bayou Choctaw Cavern 20 Decommissioning (Long Term Actions) CX(s) Applied: B1.28 Date: 01/10/2014 Location(s): Louisiana Offices(s): Strategic Petroleum Reserve Field Office

  16. CX-012468: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    TGA Reactor - Decommissioning (Building 84, Room 212 South) CX(s) Applied: B3.6Date: 41876 Location(s): PennsylvaniaOffices(s): National Energy Technology Laboratory

  17. CX-007753: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Routine Activities at the Piqua, Ohio, Decommissioned Reactor Site CX(s) Applied: B1.3, B3.1 Date: 01/18/2012 Location(s): Ohio Offices(s): Legacy Management

  18. Nuclear facility decommissioning and site remedial actions

    SciTech Connect (OSTI)

    Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

    1990-09-01

    The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies.

  19. Lessons learnt from Ignalina NPP decommissioning project

    SciTech Connect (OSTI)

    NAISSE, Jean-Claude

    2007-07-01

    The Ignalina Nuclear Power Plant (INPP) is located in Lithuania, 130 km north of Vilnius, and consists of two 1500 MWe RBMK type units, commissioned respectively in December 1983 and August 1987. On the 1. of May 2004, the Republic of Lithuania became a member of the European Union. With the protocol on the Ignalina Nuclear Power in Lithuania which is annexed to the Accession Treaty, the Contracting Parties have agreed: - On Lithuanian side, to commit closure of unit 1 of INPP before 2005 and of Unit 2 by 31 December 2009; - On European Union side, to provide adequate additional Community assistance to the efforts of Lithuania to decommission INPP. The paper is divided in two parts. The first part describes how, starting from this agreement, the project was launched and organized, what is its present status and which activities are planned to reach the final ambitious objective of a green field. To give a global picture, the content of the different projects that were defined and the licensing process will also be presented. In the second part, the paper will focus on the lessons learnt. It will explain the difficulties encountered to define the decommissioning strategy, considering both immediate or differed dismantling options and why the first option was finally selected. The paper will mention other challenges and problems that the different actors of the project faced and how they were managed and solved. The paper will be written by representatives of the Ignalina NPP and of the Project Management Unit. (author)

  20. Nuclear facility decommissioning and site remedial actions

    SciTech Connect (OSTI)

    Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

    1989-09-01

    The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords.

  1. Overview of Remote Handling Equipment Used for the NPP A1 Decommissioning - 12141

    SciTech Connect (OSTI)

    Kravarik, K.; Medved, J.; Pekar, A.; Stubna, M.; Michal, V.; Vargovcik, L.

    2012-07-01

    The first Czechoslovak NPP A1 was in operation from 1972 to 1977 and it was finally shutdown due to an accident (level 4 according to the INES). The presence of radioactive, toxic or hazardous materials limits personnel access to facilities and therefore it is necessary to use remote handling technologies for some most difficult characterization, retrieval, decontamination and dismantling tasks. The history of remote handling technologies utilization started in nineties when the spent nuclear fuel, including those fuel assemblies damaged during the accident, was prepared for the transport to Russia. Subsequent significant development of remote handling equipment continued during implementation of the NPP A1 decommissioning project - Stage I and ongoing Stage II. Company VUJE, Inc. is the general contractor for both mentioned stages of the decommissioning project. Various remote handling manipulators and robotics arms were developed and used. It includes remotely controlled vehicle manipulator MT-15 used for characterisation tasks in hostile and radioactive environment, special robust manipulator DENAR-41 used for the decontamination of underground storage tanks and multi-purposes robotics arms MT-80 and MT-80A developed for variety of decontamination and dismantling tasks. The heavy water evaporator facility dismantling is the current task performed remotely by robotics arm MT-80. The heavy water evaporator is located inside the main production building in the room No. 220 where loose surface contamination varies from 10 Bq/cm{sup 2} to 1x10{sup 3} Bq/cm{sup 2}, dose rate is up to 1.5 mGy/h and the feeding pipeline contained liquid RAW with high tritium content. Presented manipulators have been designed for broad range of decommissioning tasks. They are used for recognition, sampling, waste retrieval from large underground tanks, decontamination and dismantling of technological equipments. Each of the mentioned fields claims specific requirements on design of manipulator, their operation and control systems as well as tools of manipulators. Precise planning of decontamination and dismantling tasks is necessary for its successful performance by remotely controlled manipulator. The example of the heavy water evaporator demonstrates typical procedure for decommissioning of contaminated technological equipment by remotely controlled manipulators - planning of decommissioning tasks, preparatory tasks, modification of applied tools and design of specific supporting constructions for manipulator and finally decontamination and dismantling themselves. Due to the particularly demanding conditions in highly contaminated A1 NPP, a team of experts with special know-how in the field of decommissioning has grown up, and unique technological equipment enabling effective and safe work in environment with a high radiation level has been developed. (authors)

  2. Decommissioning Plan of the Musashi Reactor and Its Progress

    SciTech Connect (OSTI)

    Tanzawa, Tomio

    2008-01-15

    The Musashi Reactor is a TRIGA-II, tank-type research reactor, as shown in Table 1. The reactor had been operated at maximum thermal power level of 100 kW since first critical, January 30, 1963. Reactor operation was shut down due to small leakage of water from the reactor tank on December 21,1989. After shutdown, investigation of the causes, making plan of repair and discussions on restart or decommissioning had been done. Finally, decision of decommissioning was made in May, 2003. The initial plan of the decommissioning was submitted to the competent authority in January, 2004. Now, the reactor is under decommissioning. The plan of decommissioning and its progress are described. In conclusion: considering the status of undertaking plan of the waste disposal facility for the low level radioactive waste from research reactors, the phased decommissioning was selected for the Musashi Reactor. First phase of the decommissioning activities including the actions of permanent shutdown and delivering the spent nuclear fuels to US DOE was completed.

  3. Release and disposal of materials during decommissioning of Siemens MOX fuel fabrication plant at Hanau, Germany

    SciTech Connect (OSTI)

    Koenig, Werner; Baumann, Roland

    2007-07-01

    In September 2006, decommissioning and dismantling of the Siemens MOX Fuel Fabrication Plant in Hanau were completed. The process equipment and the fabrication buildings were completely decommissioned and dismantled. The other buildings were emptied in whole or in part, although they were not demolished. Overall, the decommissioning process produced approximately 8500 Mg of radioactive waste (including inactive matrix material); clearance measurements were also performed for approximately 5400 Mg of material covering a wide range of types. All the equipment in which nuclear fuels had been handled was disposed of as radioactive waste. The radioactive waste was conditioned on the basis of the requirements specified for the projected German final disposal site 'Schachtanlage Konrad'. During the pre-conditioning, familiar processes such as incineration, compacting and melting were used. It has been shown that on account of consistently applied activity containment (barrier concept) during operation and dismantling, there has been no significant unexpected contamination of the plant. Therefore almost all the materials that were not a priori destined for radioactive waste were released without restriction on the basis of the applicable legal regulations (chap. 29 of the Radiation Protection Ordinance), along with the buildings and the plant site. (authors)

  4. Safety Oversight of Decommissioning Activities at DOE Nuclear Sites

    SciTech Connect (OSTI)

    Zull, Lawrence M.; Yeniscavich, William

    2008-01-15

    The Defense Nuclear Facilities Safety Board (Board) is an independent federal agency established by Congress in 1988 to provide nuclear safety oversight of activities at U.S. Department of Energy (DOE) defense nuclear facilities. The activities under the Board's jurisdiction include the design, construction, startup, operation, and decommissioning of defense nuclear facilities at DOE sites. This paper reviews the Board's safety oversight of decommissioning activities at DOE sites, identifies the safety problems observed, and discusses Board initiatives to improve the safety of decommissioning activities at DOE sites. The decommissioning of former defense nuclear facilities has reduced the risk of radioactive material contamination and exposure to the public and site workers. In general, efforts to perform decommissioning work at DOE defense nuclear sites have been successful, and contractors performing decommissioning work have a good safety record. Decommissioning activities have recently been completed at sites identified for closure, including the Rocky Flats Environmental Technology Site, the Fernald Closure Project, and the Miamisburg Closure Project (the Mound site). The Rocky Flats and Fernald sites, which produced plutonium parts and uranium materials for defense needs (respectively), have been turned into wildlife refuges. The Mound site, which performed R and D activities on nuclear materials, has been converted into an industrial and technology park called the Mound Advanced Technology Center. The DOE Office of Legacy Management is responsible for the long term stewardship of these former EM sites. The Board has reviewed many decommissioning activities, and noted that there are valuable lessons learned that can benefit both DOE and the contractor. As part of its ongoing safety oversight responsibilities, the Board and its staff will continue to review the safety of DOE and contractor decommissioning activities at DOE defense nuclear sites.

  5. Constructing Predictive Estimates for Worker Exposure to Radioactivity During Decommissioning: Analysis of Completed Decommissioning Projects - Master Thesis

    SciTech Connect (OSTI)

    Dettmers, Dana Lee; Eide, Steven Arvid

    2002-10-01

    An analysis of completed decommissioning projects is used to construct predictive estimates for worker exposure to radioactivity during decommissioning activities. The preferred organizational method for the completed decommissioning project data is to divide the data by type of facility, whether decommissioning was performed on part of the facility or the complete facility, and the level of radiation within the facility prior to decommissioning (low, medium, or high). Additional data analysis shows that there is not a downward trend in worker exposure data over time. Also, the use of a standard estimate for worker exposure to radioactivity may be a best estimate for low complete storage, high partial storage, and medium reactor facilities; a conservative estimate for some low level of facility radiation facilities (reactor complete, research complete, pits/ponds, other), medium partial process facilities, and high complete research facilities; and an underestimate for the remaining facilities. Limited data are available to compare different decommissioning alternatives, so the available data are reported and no conclusions can been drawn. It is recommended that all DOE sites and the NRC use a similar method to document worker hours, worker exposure to radiation (person-rem), and standard industrial accidents, injuries, and deaths for all completed decommissioning activities.

  6. DOE-EM'S In-Situ Decommissioning Strategy

    SciTech Connect (OSTI)

    Negin, C.A.; Urland, C.S.; Szilagyi, A.P.

    2008-07-01

    This paper addressed the current status of decommissioning projects within the Department of Energy (DOE) that have an end state of permanent entombment, referred to as in-situ decommissioning (ISD). The substance of a Department of Energy, Office of Environmental Management (DOE-EM) review of ISD and the development of a strategy are summarized. The strategy first recognizes ISD as a viable decommissioning end state; secondly addresses the integration of this approach within the external and internal regulatory regimes; subsequently identifies tools that need developing; and finally presents guidance for implementation. The overall conclusion is that ISD is a viable mode of decommissioning that can be conducted within the existing structure of rules and regulations. (author)

  7. FAQS Job Task Analyses - Deactivation and Decommissioning | Department of

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

    Energy FAQS Job Task Analyses - Deactivation and Decommissioning FAQS Job Task Analyses - Deactivation and Decommissioning FAQS Job Task Analyses are performed on the Function Area Qualification Standards. The FAQS Job Task Analyses consists of: Developing a comprehensive list of tasks that define the job such as the duties and responsibilities which include determining their levels of importance and frequency. Identifying and evaluating competencies. Last step is evaluating linkage between

  8. Brookhaven Lab Completes Decommissioning of Graphite Research Reactor:

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

    Reactor core and associated structures successfully removed; waste shipped offsite for disposal | Department of Energy Brookhaven Lab Completes Decommissioning of Graphite Research Reactor: Reactor core and associated structures successfully removed; waste shipped offsite for disposal Brookhaven Lab Completes Decommissioning of Graphite Research Reactor: Reactor core and associated structures successfully removed; waste shipped offsite for disposal September 1, 2012 - 12:00pm Addthis The

  9. 3-D Model for Deactivation & Decommissioning | Department of Energy

    Energy Savers [EERE]

    -D Model for Deactivation & Decommissioning 3-D Model for Deactivation & Decommissioning The design and production of 3-D scale models that replicate the highly contaminated structures within the nuclear facility would provide a significant improvement in visualization of the work space, which would give managers and supervisors a more powerful tool for planning and communicating safety issues and work sequences to personnel executing the physical D&D tasks. PDF icon 3-D Model for

  10. Deactivation & Decommissioning (D&D) | Department of Energy

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

    Deactivation & Decommissioning (D&D) Deactivation & Decommissioning (D&D) American Recovery and Reinvestment Act workers at the Savannah River Site imploded the 455-foot-tall K Reactor Cooling Tower in May 2010. The project was completed safely and contributed 36.5 square miles to the site's total footprint reduction. On August 3, 2013, contractors and the Oak Ridge Office of Environmental Management successfully completed the explosive demolition of the K-1206-F Fire Water

  11. FAQS Qualification Card - Deactivation and Decommissioning | Department of

    Energy Savers [EERE]

    Energy Deactivation and Decommissioning FAQS Qualification Card - Deactivation and Decommissioning A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA). For each

  12. In-Situ Decommissioning: A Strategy for Environmental Management

    Office of Environmental Management (EM)

    Situ Decommissioning A Strategy for Environmental Management Reducing the Footprint of the Cold War For over a decade, the Department of Energy has focused on reducing the footprint of 60 years of nuclear research and weapons testing and production. While these facilities are no longer needed, they exist with varying degrees of radiation contamination from years of operation. Deactivation & Decommissioning (D&D) is the process of closing down a nuclear facility and placing it in a state

  13. PROJECT MANGEMENT PLAN EXAMPLES Deactivation to Decommissioning Transition

    Office of Environmental Management (EM)

    to Decommissioning Transition Example Example 80 1.5 OPERATIONAL TRANSITION AND DEACTIVATION STRATEGY According to the U.S. Department of Energy (DOE) Order 430.1A Life Cycle Asset Management (LCAM), the life cycle of a facility makes several transitions over the course of it's existence. The typical stages or phases include operation, (standby), deactivation, S&M, decontamination and decommissioning (D&D). The life cycle phases may occur as a straight through process or with long

  14. Progress and experiences from the decommissioning of the Eurochemic reprocessing plant

    SciTech Connect (OSTI)

    Gills, R.; Lewandowski, P.; Ooms, B.; Reusen, N.; Van Laer, W.; Walthery, R.

    2007-07-01

    Belgoprocess started the industrial decommissioning of the main process building of the former EUROCHEMIC reprocessing plant in 1990, after completion of a pilot project in which two buildings were emptied and decontaminated to background levels. The remaining structures were demolished and the concrete debris was disposed of as industrial waste and green field conditions restored. The Eurochemic reprocessing plant operated from 1966 to 1974 to process fuel from power reactors and research reactors. The main building is a large concrete structure, comprising a surface area of 55,000 m{sup 2}, concrete volume 12,500 m{sup 3}, and 1,500 Mg of metal components. The building is divided into multiple cells. About 106 individual cell structures have to be dismantled, involving the removal and decontamination of equipment from each cell, the decontamination of the cell walls, ceilings and floors, the dismantling of the ventilation system. Most of the work involves hands-on operations under protective clothing tailored to each specific task. Tool automation and automatic positioning systems are successfully applied. In view of the final demolition of the main process building, the main process building is divided into three parts - each part is isolated from the others. In the middle of 2008, after the removal of the NDA-IPAN/GEA installation, the eastern part will be demolished. The paper presents a status overview of the decommissioning and decontamination activities at the main process building of the former Eurochemic reprocessing plant on the nuclear site of Dessel in Belgium. The specific BELGOPROCESS approach will be highlighted, in which the decommissioning activities are carried out on an industrial scale with special emphasis on cost minimisation, the use of technology on an industrial representative scale and the specific alpha contamination of equipment and building surfaces, requiring that the decommissioning work is done with adequate protective clothing. Also specific breathing and cooling air systems have been provided to allow the operators to carry out the decommissioning tasks in acceptable working conditions. (authors)

  15. Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities

    SciTech Connect (OSTI)

    MC Bierschbach; DR Haffner; KJ Schneider; SM Short

    2002-12-01

    Cost information is developed for the conceptual decommissioning of non-fuel-cycle nuclear facilities that represent a significant decommissioning task in terms of decontamination and disposal activities. This study is a re-evaluation of the original study (NUREG/CR-1754 and NUREG/CR-1754, Addendum 1). The reference facilities examined in this study are the same as in the original study and include: a laboratory for the manufacture of {sup 3}H-labeled compounds; a laboratory for the manufacture of {sup 14}C-labeled compounds; a laboratory for the manufacture of {sup 123}I-labeled compounds; a laboratory for the manufacture of {sup 137}Cs sealed sources; a laboratory for the manufacture of {sup 241}Am sealed sources; and an institutional user laboratory. In addition to the laboratories, three reference sites that require some decommissioning effort were also examined. These sites are: (1) a site with a contaminated drain line and hold-up tank; (2) a site with a contaminated ground surface; and (3) a tailings pile containing uranium and thorium residues. Decommissioning of these reference facilities and sites can be accomplished using techniques and equipment that are in common industrial use. Essentially the same technology assumed in the original study is used in this study. For the reference laboratory-type facilities, the study approach is to first evaluate the decommissioning of individual components (e.g., fume hoods, glove boxes, and building surfaces) that are common to many laboratory facilities. The information obtained from analyzing the individual components of each facility are then used to determine the cost, manpower requirements and dose information for the decommissioning of the entire facility. DECON, the objective of the 1988 Rulemaking for materials facilities, is the decommissioning alternative evaluated for the reference laboratories because it results in the release of the facility for restricted or unrestricted use as soon as possible. For a facility, DECON requires that contaminated components either be: (1) decontaminated to restricted or unrestricted release levels or (2) packaged and shipped to an authorized disposal site. This study considers unrestricted release only. The new decommissioning criteria of July 1997 are too recent for this study to include a cost analysis of the restricted release option, which is now allowed under these new criteria. The costs of decommissioning facility components are generally estimated to be in the range of $140 to $27,000, depending on the type of component, the type and amount of radioactive contamination, the remediation options chosen, and the quantity of radioactive waste generated from decommissioning operations. Estimated costs for decommissioning the example laboratories range from $130,000 to $205,000, assuming aggressive low-level waste (LLW) volume reduction. If only minimal LLW volume reduction is employed, decommissioning costs range from $150,000 to $270,000 for these laboratories. On the basis of estimated decommissioning costs for facility components, the costs of decommissioning typical non-fuel-cycle laboratory facilities are estimated to range from about $25,000 for the decommissioning of a small room containing one or two fume hoods to more than $1 million for the decommissioning of an industrial plant containing several laboratories in which radiochemicals and sealed radioactive sources are prepared. For the reference sites of this study, the basic decommissioning alternatives are: (1) site stabilization followed by long-term care and (2) removal of the waste or contaminated soil to an authorized disposal site. Cost estimates made for decommissioning three reference sites range from about $130,000 for the removal of a contaminated drain line and hold-up tank to more than $23 million for the removal of a tailings pile that contains radioactive residue from ore-processing operations in which tin slag is processed for the recovery of rare metals. Total occupational radiation doses generally range from 0.00007 person-rem to 13 person-rem for decommissioning the laboratory facilities of this study. The results of this study are: (1) decommissioning costs have continued to increase since publication of the original study, due primarily to rapidly escalating costs for disposal of radioactive wastes at the available LLW burial sites; (2) these swiftly increasing LLW disposal costs provide a significant incentive for NRC licensees to effectively manage LLW generation, treatment, and disposal from decommissioning activities; and (3) decommissioning costs have increased on the order of 34% to 66% since the Final Decommissioning Rule was issued in 1988, due in large part to the 3.5-fold increase in burial costs.

  16. Development of a Preliminary Decommissioning Plan Following the International Structure for Decommissioning Costing (ISDC) of Nuclear Installations - 13361

    SciTech Connect (OSTI)

    Moshonas Cole, Katherine; Dinner, Julia; Grey, Mike; Daniska, Vladimir

    2013-07-01

    The International Structure for Decommissioning Costing (ISDC) of Nuclear Installations, published by OECD/NEA, IAEA and EC is intended to provide a uniform list of cost items for decommissioning projects and provides a standard format that permits international cost estimates to be compared. Candesco and DECOM have used the ISDC format along with two costing codes, OMEGA and ISDCEX, developed from the ISDC by DECOM, in three projects: the development of a preliminary decommissioning plan for a multi-unit CANDU nuclear power station, updating the preliminary decommissioning cost estimates for a prototype CANDU nuclear power station and benchmarking the cost estimates for CANDU against the cost estimates for other reactor types. It was found that the ISDC format provides a well defined and transparent basis for decommissioning planning and cost estimating that assists in identifying gaps and weaknesses and facilitates the benchmarking against international experience. The use of the ISDC can also help build stakeholder confidence in the reliability of the plans and estimates and the adequacy of decommissioning funding. (authors)

  17. An overview of U.S. decommissioning experience -- A basic introduction

    SciTech Connect (OSTI)

    Boing, L.E.

    1998-03-09

    This paper presents an overview of the US experiences in the decommissioning technical area. Sections included are: (1) an overview of the magnitude of the problem, (2) a review of the US decommissioning process, (3) regulation of decommissioning, (4) regulatory and funding requirements for decommissioning, and (5) a general overview of all on-going and completed decommissioning projects to date in the US. The final section presents a review of some issues in the decommissioning area currently being debated in the technical specialists community.

  18. Performance and review of safety assessment for decommissioning

    SciTech Connect (OSTI)

    Percival, K.; Thierfeldt, S.; Joubert, A.; Kaulard, J.; Manson, P.; Ferch, R.; Batandjieva, B.

    2007-07-01

    Available in abstract form only. Full text of publication follows: Safety assessment is required by national and international safety standards to be performed for all stages of life cycle of facilities that are using radioactive material. It is required to be performed by operators and reviewed by regulators in support of a decommissioning plan for every facility before decommissioning commences. With the growing amount of decommissioning activities world-wide, the need for assistance to Member States in development and review of such assessments was highlighted in the Berlin Conference in 2002 and reflected in the International Action Plan on Decommissioning of Nuclear Facilities, approved by the International Atomic Energy Agency (IAEA) Board of Governors in 2004. In order to respond to this need, the IAEA initiated an international project on Evaluation and Demonstration of Safety during Decommissioning of Nuclear Facilities (DeSa Project) in the same year. More than fifty experts from over thirty Member States have been working over the last three years on (i) the establishment of a harmonized safety assessment methodology for decommissioning; (ii) development of recommendations for a regulatory approach and procedure for review of such assessments; (iii) development of recommendations on the application of the graded approach to development and review of safety assessments; and (iv) application of the methodology, the regulatory review procedure and graded approach recommendations to three test cases - safety assessment for decommissioning of a nuclear power plant (NPP), a research reactor and a nuclear laboratory. This paper presents the current status of the DeSa project work, the consensus achieved, the main preliminary outcomes and lessons learned. The project results are envisaged to be presented and discussed at the 4. Joint DeSa meeting in October 2007 in Vienna, where the scope and objectives of a follow- up project will be also discussed. (authors)

  19. Mobile workstation for decontamination and decommissioning operations

    SciTech Connect (OSTI)

    Whittaker, W.L.; Osborn, J.F.; Thompson, B.R.

    1993-10-01

    This project is an interdisciplinary effort to develop effective mobile worksystems for decontamination and decommissioning (D&D) of facilities within the DOE Nuclear Weapons Complex. These mobile worksystems will be configured to operate within the environmental and logistical constraints of such facilities and to perform a number of work tasks. Our program is designed to produce a mobile worksystem with capabilities and features that are matched to the particular needs of D&D work by evolving the design through a series of technological developments, performance tests and evaluations. The project has three phases. In this the first phase, an existing teleoperated worksystem, the Remote Work Vehicle (developed for use in the Three Mile Island Unit 2 Reactor Building basement), was enhanced for telerobotic performance of several D&D operations. Its ability to perform these operations was then assessed through a series of tests in a mockup facility that contained generic structures and equipment similar to those that D&D work machines will encounter in DOE facilities. Building upon the knowledge gained through those tests and evaluations, a next generation mobile worksystem, the RWV II, and a more advanced controller will be designed, integrated and tested in the second phase, which is scheduled for completion in January 1995. The third phase of the project will involve testing of the RWV II in the real DOE facility.

  20. Regulatory process for decommissioning nuclear power reactors. Final report

    SciTech Connect (OSTI)

    1998-03-01

    This report provides regulatory guidance for utilities consistent with the changes in the decommissioning rule, 10 CFR50.82 as revised in July 1996. The purpose of this report is to explain the new rule in the context of related industry experience and to provide practical guidance to licensees contemplating or implementing a shutdown. Because the regulatory process is still rapidly evolving, this report reflects only a current status of the acceptable methods and practices derived from a review of the current regulations, guidance documents and industry experience for decommissioning a nuclear power reactor. EPRI anticipates periodic updates of this document to incorporate various utility experiences with decommissioning, and also to reflect any regulatory changes. The report provides a summary of ongoing federal agency and industry activities and the regulatory requirements that are currently applicable, or no longer applicable, to nuclear power plants at the time of permanent shutdown through the early decommissioning stage. The report describes the major components of a typical decommissioning action plan, providing industry experience and guidance for licensees considering or implementing permanent shutdown.

  1. Statement of Intent No. 2 between DOE and the Nuclear Decommissioning

    Energy Savers [EERE]

    Authority | Department of Energy Statement of Intent No. 2 between DOE and the Nuclear Decommissioning Authority Statement of Intent No. 2 between DOE and the Nuclear Decommissioning Authority Statement of Intent No. 2 between DOE and the Nuclear Decommissioning Authority in the United Kingdom of Great Britain and Northern Ireland for exchange of information concerning management of radioactive waste. PDF icon Statement of Intent No. 2 between DOE and the Nuclear Decommissioning Authority

  2. Confidentiality Agreement between the Nuclear Decommissioning Authority and US Department of Energy

    Broader source: Energy.gov [DOE]

    Confidentiality Agreement between the Nuclear Decommissioning Authority in UK and US Department of Energy

  3. Technology needs for decommissioning and decontamination

    SciTech Connect (OSTI)

    Bundy, R.D.; Kennerly, J.M.

    1993-12-01

    This report summarizes the current view of the most important decontamination and decommissioning (D & D) technology needs for the US Department of Energy facilities for which the D & D programs are the responsibility of Martin Marietta Energy Systems, Inc. The source of information used in this assessment was a survey of the D & D program managers at each facility. A summary of needs presented in earlier surveys of site needs in approximate priority order was supplied to each site as a starting point to stimulate thinking. This document reflects a brief initial assessment of ongoing needs; these needs will change as plans for D & D are finalized, some of the technical problems are solved through successful development programs, and new ideas for D and D technologies appear. Thus, this assessment should be updated and upgraded periodically, perhaps, annually. This assessment differs from others that have been made in that it directly and solely reflects the perceived need for new technology by key personnel in the D & D programs at the various facilities and does not attempt to consider the likelihood that these technologies can be successfully developed. Thus, this list of technology needs also does not consider the cost, time, and effort required to develop the desired technologies. An R & D program must include studies that have a reasonable chance for success as well as those for which there is a high need. Other studies that considered the cost and probability of successful development as well as the need for new technology are documented. However, the need for new technology may be diluted in such studies; this document focuses only on the need for new technology as currently perceived by those actually charged with accomplishing D & D.

  4. DEACTIVATION AND DECOMMISSIONING PLANNING AND ANALYSIS WITH GEOGRAPHIC INFORMATION SYSTEMS

    SciTech Connect (OSTI)

    Bollinger, J; William Austin, W; Larry Koffman, L

    2007-09-17

    From the mid-1950's through the 1980's, the U.S. Department of Energy's Savannah River Site produced nuclear materials for the weapons stockpile, for medical and industrial applications, and for space exploration. Although SRS has a continuing defense-related mission, the overall site mission is now oriented toward environmental restoration and management of legacy chemical and nuclear waste. With the change in mission, SRS no longer has a need for much of the infrastructure developed to support the weapons program. This excess infrastructure, which includes over 1000 facilities, will be decommissioned and demolished over the forthcoming years. Dispositioning facilities for decommissioning and deactivation requires significant resources to determine hazards, structure type, and a rough-order-of-magnitude estimate for the decommissioning and demolition cost. Geographic information systems (GIS) technology was used to help manage the process of dispositioning infrastructure and for reporting the future status of impacted facilities.

  5. ADVANTAGES, DISADVANTAGES, AND LESSONS LEARNED FROM MULTI-REACTOR DECOMMISSIONING PROJECTS

    SciTech Connect (OSTI)

    Morton, M.R.; Nielson, R.R.; Trevino, R.A.

    2003-02-27

    This paper discusses the Reactor Interim Safe Storage (ISS) Project within the decommissioning projects at the Hanford Site and reviews the lessons learned from performing four large reactor decommissioning projects sequentially. The advantages and disadvantages of this multi-reactor decommissioning project are highlighted.

  6. Integration of improved decontamination and characterization technologies in the decommissioning of the CP-5 research reactor

    SciTech Connect (OSTI)

    Bhattacharyya, S. K.; Boing, L. E.

    2000-02-17

    The aging of research reactors worldwide has resulted in a heightened awareness in the international technical decommissioning community of the timeliness to review and address the needs of these research institutes in planning for and eventually performing the decommissioning of these facilities. By using the reactors already undergoing decommissioning as test beds for evaluating enhanced or new/innovative technologies for decommissioning, it is possible that new techniques could be made available for those future research reactor decommissioning projects. Potentially, the new technologies will result in: reduced radiation doses to the work force, larger safety margins in performing decommissioning and cost and schedule savings to the research institutes in performing the decommissioning of these facilities. Testing of these enhanced technologies for decontamination, dismantling, characterization, remote operations and worker protection are critical to furthering advancements in the technical specialty of decommissioning. Furthermore, regulatory acceptance and routine utilization for future research reactor decommissioning will be assured by testing and developing these technologies in realistically contaminated environments prior to use in the research reactors. The decommissioning of the CP-5 Research Reactor is currently in the final phase of dismantlement. In this paper the authors present results of work performed at Argonne National Laboratory (ANL) in the development, testing and deployment of innovative and/or enhanced technologies for the decommissioning of research reactors.

  7. Decommissioning experience from the Experimental Breeder Reactor-II.

    SciTech Connect (OSTI)

    Henslee, S.P.; Rosenberg, K.E.

    2002-03-28

    Consistent with the intent of this International Atomic Energy Agency technical meeting, decommissioning operating experience and contributions to the preparation for the Coordinated Research Project from Experimental Breeder Reactor-II activities will be discussed. This paper will review aspects of the decommissioning activities of the Experimental Breeder Reactor-II, make recommendations for future decommissioning activities and reactor system designs and discuss relevant areas of potential research and development. The Experimental Breeder Reactor-II (EBR-II) was designed as a 62.5 MWt, metal fueled, pool reactor with a conventional 19 MWe power plant. The productive life of the EBR-II began with first operations in 1964. Demonstration of the fast reactor fuel cycle, serving as an irradiation facility, demonstration of fast reactor passive safety and lastly, was well on its way to close the fast breeder fuel cycle for the second time when the Integral Fast Reactor program was prematurely ended in October 1994 with the shutdown of the EBR-II. The shutdown of the EBR-II was dictated without an associated planning phase that would have provided a smooth transition to shutdown. Argonne National Laboratory and the U.S. Department of Energy arrived at a logical plan and sequence for closure activities. The decommissioning activities as described herein fall into in three distinct phases.

  8. Recent Trends in the Adequacy of Nuclear Plant Decommissioning Funding

    SciTech Connect (OSTI)

    Williams, D. G.

    2002-02-26

    Concerned about the potential cost and sufficiency of funds to decommission the nation's nuclear power plants, the Congress asked the U.S. General Accounting Office (GAO) to assess the adequacy, as of December 31, 1997, of electric utilities'; funds to eventually decommission their plants. GAO's report (GAO/RCED-99-75) on this issue addressed three alternative assumption scenarios--baseline (most likely), optimistic, and pessimistic; and was issued in May 1999. This paper updates GAO's baseline assessment of fund adequacy in 1997, and extends the analysis through 2000. In 2000, we estimate that the present value cost to decommission the nation's nuclear plants is about $35 billion; utility fund balances are about $29 billion. Both our two measures of funding adequacy for utilities are on average not only much above ideal levels, but also overall have greatly improved since 1997. However, certain utilities still show less than ideal fund balances and annual contributions. We suggest that the range of these results among the individual utilities is a more important policy measure to assess the adequacy of decommissioning funding than is the funding adequacy for the industry as a whole.

  9. Korea Research Reactor -1 & 2 Decommissioning Project in Korea

    SciTech Connect (OSTI)

    Park, S. K.; Chung, U. S.; Jung, K. J.; Park, J. H.

    2003-02-24

    Korea Research Reactor 1 (KRR-1), the first research reactor in Korea, has been operated since 1962, and the second one, Korea Research Reactor 2 (KRR-2) since 1972. The operation of both of them was phased out in 1995 due to their lifetime and operation of the new and more powerful research reactor, HANARO (High-flux Advanced Neutron Application Reactor; 30MW). Both are TRIGA Pool type reactors in which the cores are small self-contained units sitting in tanks filled with cooling water. The KRR-1 is a TRIGA Mark II, which could operate at a level of up to 250 kW. The second one, the KRR-2 is a TRIGA Mark III, which could operate at a level of up 2,000 kW. The decontamination and decommissioning (D & D) project of these two research reactors, the first D & D project in Korea, was started in January 1997 and will be completed to stage 3 by 2008. The aim of this decommissioning program is to decommission the KRR-1 & 2 reactors and to decontaminate the residual building structure s and the site to release them as unrestricted areas. KAERI (Korea Atomic Energy Research Institute) submitted the decommissioning plan and the environmental impact assessment reports to the Ministry of Science and Technology (MOST) for the license in December 1998, and was approved in November 2000.

  10. Nuclear facility decommissioning and site remedial actions. Volume 6. A selected bibliography

    SciTech Connect (OSTI)

    Owen, P.T.; Michelson, D.C.; Knox, N.P.

    1985-09-01

    This bibliography of 683 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the sixth in a series of annual reports prepared for the US Department of Energy's Remedial Action Programs. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's remedial action program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Facilities Contaminated with Natural Radioactivity; (5) Uranium Mill Tailings Remedial Action Program; (6) Grand Junction Remedial Action Program; (7) Uranium Mill Tailings Management; (8) Technical Measurements Center; and (9) General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 7 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate affiliation or by publication description.

  11. Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 5

    SciTech Connect (OSTI)

    Owen, P.T.; Knox, N.P.; Chilton, B.D.; Baldauf, M.F.

    1984-09-01

    This bibliography of 756 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fifth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; (6) Uranium Mill Tailings Management; and (7) Technical Measurements Center. Chapter sections for chapters 1, 2, 4, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. The Appendix contains a list of frequently used acronyms.

  12. Applied ALARA techniques

    SciTech Connect (OSTI)

    Waggoner, L.O.

    1998-02-05

    The presentation focuses on some of the time-proven and new technologies being used to accomplish radiological work. These techniques can be applied at nuclear facilities to reduce radiation doses and protect the environment. The last reactor plants and processing facilities were shutdown and Hanford was given a new mission to put the facilities in a safe condition, decontaminate, and prepare them for decommissioning. The skills that were necessary to operate these facilities were different than the skills needed today to clean up Hanford. Workers were not familiar with many of the tools, equipment, and materials needed to accomplish:the new mission, which includes clean up of contaminated areas in and around all the facilities, recovery of reactor fuel from spent fuel pools, and the removal of millions of gallons of highly radioactive waste from 177 underground tanks. In addition, this work has to be done with a reduced number of workers and a smaller budget. At Hanford, facilities contain a myriad of radioactive isotopes that are 2048 located inside plant systems, underground tanks, and the soil. As cleanup work at Hanford began, it became obvious early that in order to get workers to apply ALARA and use hew tools and equipment to accomplish the radiological work it was necessary to plan the work in advance and get radiological control and/or ALARA committee personnel involved early in the planning process. Emphasis was placed on applying,ALARA techniques to reduce dose, limit contamination spread and minimize the amount of radioactive waste generated. Progress on the cleanup has,b6en steady and Hanford workers have learned to use different types of engineered controls and ALARA techniques to perform radiological work. The purpose of this presentation is to share the lessons learned on how Hanford is accomplishing radiological work.

  13. Decommissioning of the BR3 reactor: status and perspectives

    SciTech Connect (OSTI)

    Noynaert, L.; Verstraeten, I.

    2007-07-01

    The BR3 plant at Mol in Belgium built at the end of the fifties was the first PWR plant built outside the USA. The reactor had a small net power output (10 MWe) but comprised all the loops and features of a commercial PWR plant. The BR3 plant was operated with the main objective of testing advanced PWR fuels under irradiation conditions similar to those encountered in large commercial PWR plants. The reactor was started in 1962 and shut down in 1987 after 25 years of continuous operation. Since 1989, SCK.CEN is decommissioning the BR3 PWR research reactor. The dismantling of the metallic components including reactor pressure vessel and internals is completed and extensively reported in the literature. The dismantling of auxiliary components and the decontamination of parts of the infrastructure are now going on. The decommissioning progress is continuously monitored and costs and strategy are regularly reassessed. The first part of the paper describes the main results and lessons learned from the reassessment exercises performed in 1994, 1999, 2004 and 2007. Impacts of changes in legal framework on the decommissioning costs will be addressed. These changes concern e.g. licensing aspects, clearance levels, waste management... The middle part of the paper discusses the management of activated and/or contaminated concrete. The costing exercise performed in 1995 highlighted that the management of activated and contaminated concrete is the second main cost item after the dismantling of the reactor pressure vessel and internals. Different possible solutions were studied. These are evacuation as radioactive waste with or without supercompaction, recycling this 'radioactive' grout or concrete for conditioning of radioactive waste e.g. conditioning of metallic waste. The paper will give the results of the cost-benefit analysis made to select the solution retained. The last part of the paper will discuss the end goal of the decommissioning of the BR3. In the final decommissioning plan approved by ONDRAF/NIRAS, it was mentioned that the final goal of the BR3 decommissioning will be the 'green field' unless opportunities for reuse of the BR3 site will occur during decommissioning. A strategy of partial reuse of the BR3 facility is proposed and being discussed with the main stakeholders. The paper will give the present state of the discussion. (authors)

  14. Draft principles, policy, and acceptance criteria for decommissioning of U.S. Department of Energy contaminated surplus facilities and summary of international decommissioning programs

    SciTech Connect (OSTI)

    Singh, B.K.; Gillette, J.; Jackson, J.

    1994-12-01

    Decommissioning activities enable the DOE to reuse all or part of a facility for future activities and reduce hazards to the general public and any future work force. The DOE Office of Environment, Health and Safety has prepared this document, which consists of decommissioning principles and acceptance criteria, in an attempt to establish a policy that is in agreement with the NRC policy. The purpose of this document is to assist individuals involved with decommissioning activities in determining their specific responsibilities as identified in Draft DOE Order 5820.DDD, ``Decommissioning of US Department of Energy Contaminated Surplus Facilities`` (Appendix A). This document is not intended to provide specific decommissioning methodology. The policies and principles of several international decommissioning programs are also summarized. These programs are from the IAEA, the NRC, and several foreign countries expecting to decommission nuclear facilities. They are included here to demonstrate the different policies that are to be followed throughout the world and to allow the reader to become familiar with the state of the art for environment, safety, and health (ES and H) aspects of nuclear decommissioning.

  15. Capturing Process Knowledge for Facility Deactivation and Decommissioning

    Office of Environmental Management (EM)

    Tech Assistance Savannah River National Laboratory- Assess Adequacy of Process Knowledge for D&D Guidance for Determining Adequacy of Process Knowledge Page 1 of 2 Savannah River National Laboratory South Carolina Capturing Process Knowledge for Facility Deactivation and Decommissioning Challenge The Office of Environmental Management (EM) is responsible for the disposition of a vast number of facilities at numerous sites around the country which have been declared excess to current mission

  16. TECHNOLOGY REQUIREMENTS FOR IN SITU DECOMMISSIONING WORKSHOP REPORT

    SciTech Connect (OSTI)

    Jannik, T.; Lee, P.; Gladden, J.; Langton, C.; Serrato, M.; Urland, C.; Reynolds, E.

    2009-06-30

    In recognition of the increasing attention being focused on In Situ Decommissioning (ISD or entombment) as an acceptable and beneficial decommissioning end state, the Department of Energy's (DOE) Office of Environmental Management (EM) is developing guidance for the implementation of ISD of excess facilities within the DOE complex. Consistent with the overarching DOE goals for increased personnel and environmental safety, reduced technical uncertainties and risks, and overall gains in efficiencies and effectiveness, EM's Office of Deactivation and Decommissioning and Facility Engineering (EM-23) initiated efforts to identify the technical barriers and technology development needs for the optimal implementation of ISD. Savannah River National Laboratory (SRNL), as the EM Corporate Laboratory, conducted an ISD Technology Needs Workshop to identify the technology needs at DOE sites. The overall goal of the workshop was to gain a full understanding of the specific ISD technical challenges, the technologies available, and those needing development. The ISD Workshop was held December 9-10, 2008 in Aiken, SC. Experienced decommissioning operations personnel from Richland Operations Office (RL), Idaho National Laboratory (INL) and Savannah River Site (SRS) along with scientists and engineers specific expertise were assembled to identify incremental and 'game changing' solutions to ISD technology challenges. The workshop and follow-up activities yielded 14 technology needs statements and the recommendation that EM-23 prioritize and pursue the following specific technology development and deployment actions. For each action, the recommended technology acquisition mechanisms (competitive solicitation (CS) or direct funding (TCR)) are provided. Activities that are time critical for ISD projects, or require unique capabilities that reside in the DOE Laboratory system will be funded directly to those institutions. Activities that have longer lead times and where the private sector, universities or other agencies are expected to have greater expertise will be accomplished through an open, competitive solicitation process. Several areas will require joint efforts from the two classes of resources.

  17. A NOVEL APPROACH TO SPENT FUEL POOL DECOMMISSIONING

    SciTech Connect (OSTI)

    R. L. Demmer

    2011-04-01

    The Idaho National Laboratory (INL) has been at the forefront of developing methods to reduce the cost and schedule of deactivating spent fuel pools (SFP). Several pools have been deactivated at the INL using an underwater approach with divers. These projects provided a basis for the INL cooperation with the Dresden Nuclear Power Station Unit 1 SFP (Exelon Generation Company) deactivation. It represents the first time that a commercial nuclear power plant (NPP) SFP was decommissioned using this underwater coating process. This approach has advantages in many aspects, particularly in reducing airborne contamination and allowing safer, more cost effective deactivation. The INL pioneered underwater coating process was used to decommission three SFPs with a total combined pool volume of over 900,000 gallons. INL provided engineering support and shared project plans to successfully initiate the Dresden project. This report outlines the steps taken by INL and Exelon to decommission SFPs using the underwater coating process. The rationale used to select the underwater coating process and the advantages and disadvantages are described. Special circumstances are also discussed, such as the use of a remotely-operated underwater vehicle to visually and radiologically map the pool areas that were not readily accessible. A larger project, the INTEC-603 SFP in-situ (grouting) deactivation, is reviewed. Several specific areas where special equipment was employed are discussed and a Lessons Learned evaluation is included.

  18. The Regulatory Challenges of Decommissioning Nuclear Power Plants in Korea - 13101

    SciTech Connect (OSTI)

    Lee, Jungjoon; Ahn, Sangmyeon; Choi, Kyungwoo; Kim, Juyoul; Kim, Juyub

    2013-07-01

    As of 2012, 23 units of nuclear power plants are in operation, but there is no experience of permanent shutdown and decommissioning of nuclear power plant in Korea. It is realized that, since late 1990's, improvement of the regulatory framework for decommissioning has been emphasized constantly from the point of view of International Atomic Energy Agency (IAEA)'s safety standards. And it is known that now IAEA prepare the safety requirement on decommissioning of facilities, its title is the Safe Decommissioning of Facilities, General Safety Requirement Part 6. According to the result of IAEA's Integrated Regulatory Review Service (IRRS) mission to Korea in 2011, it was recommended that the regulatory framework for decommissioning should require decommissioning plans for nuclear installations to be constructed and operated and these plans should be updated periodically. In addition, after the Fukushima nuclear disaster in Japan in March of 2011, preparedness for early decommissioning caused by an unexpected severe accident became also important issues and concerns. In this respect, it is acknowledged that the regulatory framework for decommissioning of nuclear facilities in Korea need to be improved. First of all, we identify the current status and relevant issues of regulatory framework for decommissioning of nuclear power plants compared to the IAEA's safety standards in order to achieve our goal. And then the plan is to be established for improvement of regulatory framework for decommissioning of nuclear power plants in Korea. After dealing with it, it is expected that the revised regulatory framework for decommissioning could enhance the safety regime on the decommissioning of nuclear power plants in Korea in light of international standards. (authors)

  19. Development of a Remote Monitoring Sensor Network for In-Situ Decommissioned Structures

    Office of Environmental Management (EM)

    10-01666, Revision 0 Key Words: in situ decommissioning sensor remote monitoring end state Retention: Permanent DEVELOPMENT OF A REMOTE MONITORING SENSOR NETWORK FOR IN SITU DECOMMISSIONED STRUCTURES Panel Report November 2010 Savannah River National Laboratory Savannah River Nuclear Solutions Aiken, SC 29808 Prepared for the U.S. Department of Energy Under Contract Number DE-AC09-08SR22470 Development of a Remote Monitoring Sensor Network Page 2 of 34 for In Situ Decommissioned Structures

  20. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Appendices. Volume 2

    SciTech Connect (OSTI)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Appendices are presented concerning the evaluations of decommissioning financing alternatives; reference site description; reference BWR facility description; radiation dose rate and concrete surface contamination data; radionuclide inventories; public radiation dose models and calculated maximum annual doses; decommissioning methods; generic decommissioning information; immediate dismantlement details; passive safe storage, continuing care, and deferred dismantlement details; entombment details; demolition and site restoration details; cost estimating bases; public radiological safety assessment details; and details of alternate study bases.

  1. Statement of Intent between the US Department of Energy and UK Nuclear Decommissioning Authority

    Broader source: Energy.gov [DOE]

    Statement of Intent between the US Department of Energy and UK Nuclear Decommissioning Authority for exchange of information concerning management of radioactive waste.

  2. EIS-0329: Proposed Construction, Operation, Decontamination/Decommissioning of Depleted Uranium Hexafluoride Conversion Facilities

    Broader source: Energy.gov [DOE]

    This EIS analyzes DOE's proposal to construct, operate, maintain, and decontaminate and decommission two depleted uranium hexafluoride (DUF 6) conversion facilities, at Portsmouth, Ohio, and Paducah, Kentucky.

  3. EIS-0119: Decommissioning of Eight Surplus Production Reactors at the Harford Site, Richland, WA

    Broader source: Energy.gov [DOE]

    This EIS presents analyses of potential environmental impacts of decommissioning the eight surplus production reactors at the Hanford Site near Richland, Washington.

  4. EIS-0119: Decommissioning of Eight Surplus Production Reactors at the Hanford Site, Richland, Washington

    Broader source: Energy.gov [DOE]

    This EIS presents analyses of potential environmental impacts of decommissioning the eight surplus production reactors at the Hanford Site near Richland, Washington.

  5. Role of decommissioning plan and its progress for the PUSPATI TRIGA Reactor

    SciTech Connect (OSTI)

    Zakaria, Norasalwa Mustafa, Muhammad Khairul Ariff Anuar, Abul Adli Idris, Hairul Nizam Ba'an, Rohyiza

    2014-02-12

    Malaysian nuclear research reactor, the PUSPATI TRIGA Reactor, reached its first criticality in 1982, and since then, it has been serving for more than 30 years for training, radioisotope production and research purposes. Realizing the age and the need for its decommissioning sometime in the future, a ground basis of assessment and an elaborative project management need to be established, covering the entire process from termination of reactor operation to the establishment of final status, documented as the Decommissioning Plan. At international level, IAEA recognizes the absence of Decommissioning Plan as one of the factors hampering progress in decommissioning of nuclear facilities in the world. Throughout the years, IAEA has taken initiatives and drawn out projects in promoting progress in decommissioning programmes, like CIDER, DACCORD and R2D2P, for which Malaysia is participating in these projects. This paper highlights the concept of Decommissioning plan and its significances to the Agency. It will also address the progress, way forward and challenges faced in developing the Decommissioning Plan for the PUSPATI TRIGA Reactor. The efforts in the establishment of this plan helps to provide continual national contribution at the international level, as well as meeting the regulatory requirement, if need be. The existing license for the operation of PUSPATI TRIGA Reactor does not impose a requirement for a decommissioning plan; however, the renewal of license may call for a decommissioning plan to be submitted for approval in future.

  6. A Plutonium Finishing Plant Model for the Cercla Removal Action and Decommissioning Construction Final Report

    SciTech Connect (OSTI)

    Hopkins, A. [Fluor Hanford, Inc, Richland, WA (United States)

    2008-07-01

    The joint policy between the U.S. Environmental Protection Agency (EPA) and the U.S. Department of Energy (DOE) for decommissioning buildings at DOE facilities documents an agreement between the agencies to perform decommissioning activities including demolition under the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). The use of removal actions for decommissioning integrates EPA oversight authority, DOE lead agency responsibility, and state authority for decommissioning activities. Once removal actions have been performed under CERCLA, a construction completion report is required to document the completion of the required action. Additionally, a decommissioning report is required under DOE guidance. No direct guidance was found for documenting completion of decommissioning activities and preparing a final report that satisfies the CERCLA requirements and the DOE requirements for decommissioning. Additional guidance was needed for the documentation of construction completion under CERCLA for D and D projects undertaken under the joint policy that addresses the requirements of both agencies. A model for the construction completion report was developed to document construction completion for CERCLA D and D activities performed under the joint EPA/DOE policy at the Plutonium Finishing Plant (PFP). The model documentation report developed at PFP integrates the DOE requirements for establishing decommissioning end-points, documenting end-point completion and preparing a final decommissioning report with the CERCLA requirements to document completion of the action identified in the Action Memorandum (AM). The model includes the required information on health and safety, data management, cost and schedule and end-points completion. (authors)

  7. Final Site-Specific Decommissioning Inspection Report for the University of Washington Research and Test Reactor

    SciTech Connect (OSTI)

    Sarah Roberts

    2006-10-18

    Report of site-specific decommissioning in-process inspection activities at the University of Washington Research and Test Reactor Facility.

  8. Non-Destructive Analysis Calibration Standards for Gaseous Diffusion Plant (GDP) Decommissioning

    Broader source: Energy.gov [DOE]

    The decommissioning of Gaseous Diffusion Plant facilities requires accurate, non-destructive assay (NDA) of residual enriched uranium in facility components for safeguards and nuclear criticality...

  9. In Situ Decommissioning Sensor Network, Meso-Scale Test Bed - Phase 3 Fluid Injection Test Summary Report

    SciTech Connect (OSTI)

    Serrato, M. G.

    2013-09-27

    The DOE Office of Environmental management (DOE EM) faces the challenge of decommissioning thousands of excess nuclear facilities, many of which are highly contaminated. A number of these excess facilities are massive and robust concrete structures that are suitable for isolating the contained contamination for hundreds of years, and a permanent decommissioning end state option for these facilities is in situ decommissioning (ISD). The ISD option is feasible for a limited, but meaningfull number of DOE contaminated facilities for which there is substantial incremental environmental, safety, and cost benefits versus alternate actions to demolish and excavate the entire facility and transport the rubble to a radioactive waste landfill. A general description of an ISD project encompasses an entombed facility; in some cases limited to the blow-grade portion of a facility. However, monitoring of the ISD structures is needed to demonstrate that the building retains its structural integrity and the contaminants remain entombed within the grout stabilization matrix. The DOE EM Office of Deactivation and Decommissioning and Facility Engineering (EM-13) Program Goal is to develop a monitoring system to demonstrate long-term performance of closed nuclear facilities using the ISD approach. The Savannah River National Laboratory (SRNL) has designed and implemented the In Situ Decommissioning Sensor Network, Meso-Scale Test Bed (ISDSN-MSTB) to address the feasibility of deploying a long-term monitoring system into an ISD closed nuclear facility. The ISDSN-MSTB goal is to demonstrate the feasibility of installing and operating a remote sensor network to assess cementitious material durability, moisture-fluid flow through the cementitious material, and resulting transport potential for contaminate mobility in a decommissioned closed nuclear facility. The original ISDSN-MSTB installation and remote sensor network operation was demonstrated in FY 2011-12 at the ISDSN-MSTB test cube located at the Florida International University Applied Research Center, Miami, FL (FIU-ARC). A follow-on fluid injection test was developed to detect fluid and ion migration in a cementitious material/grouted test cube using a limited number of existing embedded sensor systems. This In Situ Decommissioning Sensor Network, Meso-Scale Test Bed (ISDSN-MSTB) - Phase 3 Fluid Injection Test Summary Report summarizes the test implementation, acquired and processed data, and results from the activated embedded sensor systems used during the fluid injection test. The ISDSN-MSTB Phase 3 Fluid Injection Test was conducted from August 27 through September 6, 2013 at the FIU-ARC ISDSN-MSTB test cube. The fluid injection test activated a portion of the existing embedded sensor systems in the ISDSN-MSTB test cube: Electrical Resistivity Tomography-Thermocouple Sensor Arrays, Advance Tensiometer Sensors, and Fiber Loop Ringdown Optical Sensors. These embedded sensor systems were activated 15 months after initial placement. All sensor systems were remotely operated and data acquisition was completed through the established Sensor Remote Access System (SRAS) hosted on the DOE D&D Knowledge Management Information Tool (D&D DKM-IT) server. The ISDN Phase 3 Fluid Injection Test successfully demonstrated the feasibility of embedding sensor systems to assess moisture-fluid flow and resulting transport potential for contaminate mobility through a cementitious material/grout monolith. The ISDSN embedded sensor systems activated for the fluid injection test highlighted the robustness of the sensor systems and the importance of configuring systems in-depth (i.e., complementary sensors and measurements) to alleviate data acquisition gaps.

  10. Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 4

    SciTech Connect (OSTI)

    Owen, P.T.; Knox, N.P.; Fielden, J.M.; Faust, R.A.

    1983-09-01

    This bibliography of 657 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fourth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic documents of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - have been references in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; and (6) Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author, or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. Appendix A lists 264 bibliographic references to literature identified during this reporting period but not abstracted due to time constraints. Title and publication description indexes are given for this appendix. Appendix B defines frequently used acronyms, and Appendix C lists the recipients of this report according to their corporate affiliation.

  11. Heavy Water Components Test Reactor Decommissioning - Major Component Removal

    SciTech Connect (OSTI)

    Austin, W.; Brinkley, D.

    2010-05-05

    The Heavy Water Components Test Reactor (HWCTR) facility (Figure 1) was built in 1961, operated from 1962 to 1964, and is located in the northwest quadrant of the Savannah River Site (SRS) approximately three miles from the site boundary. The HWCTR facility is on high, well-drained ground, about 30 meters above the water table. The HWCTR was a pressurized heavy water test reactor used to develop candidate fuel designs for heavy water power reactors. It was not a defense-related facility like the materials production reactors at SRS. The reactor was moderated with heavy water and was rated at 50 megawatts thermal power. In December of 1964, operations were terminated and the facility was placed in a standby condition as a result of the decision by the U.S. Atomic Energy Commission to redirect research and development work on heavy water power reactors to reactors cooled with organic materials. For about one year, site personnel maintained the facility in a standby status, and then retired the reactor in place. In 1965, fuel assemblies were removed, systems that contained heavy water were drained, fluid piping systems were drained, deenergized and disconnected and the spent fuel basin was drained and dried. The doors of the reactor facility were shut and it wasn't until 10 years later that decommissioning plans were considered and ultimately postponed due to budget constraints. In the early 1990s, DOE began planning to decommission HWCTR again. Yet, in the face of new budget constraints, DOE deferred dismantlement and placed HWCTR in an extended surveillance and maintenance mode. The doors of the reactor facility were welded shut to protect workers and discourage intruders. The $1.6 billion allocation from the American Recovery and Reinvestment Act to SRS for site clean up at SRS has opened the doors to the HWCTR again - this time for final decommissioning. During the lifetime of HWCTR, 36 different fuel assemblies were tested in the facility. Ten of these experienced cladding failures as operational capabilities of the different designs were being established. In addition, numerous spills of heavy water occurred within the facility. Currently, radiation and radioactive contamination levels are low within HWCTR with most of the radioactivity contained within the reactor vessel. There are no known insults to the environment, however with the increasing deterioration of the facility, the possibility exists that contamination could spread outside the facility if it is not decommissioned. An interior panoramic view of the ground floor elevation taken in August 2009 is shown in Figure 2. The foreground shows the transfer coffin followed by the reactor vessel and control rod drive platform in the center. Behind the reactor vessel is the fuel pool. Above the ground level are the polar crane and the emergency deluge tank at the top of the dome. Note the considerable rust and degradation of the components and the interior of the containment building. Alternative studies have concluded that the most environmentally safe, cost effective option for final decommissioning is to remove the reactor vessel, steam generators, and all equipment above grade including the dome. Characterization studies along with transport models have concluded that the remaining below grade equipment that is left in place including the transfer coffin will not contribute any significant contamination to the environment in the future. The below grade space will be grouted in place. A concrete cover will be placed over the remaining footprint and the groundwater will be monitored for an indefinite period to ensure compliance with environmental regulations. The schedule for completion of decommissioning is late FY2011. This paper describes the concepts planned in order to remove the major components including the dome, the reactor vessel (RV), the two steam generators (SG), and relocating the transfer coffin (TC).

  12. EIS-0080: Decommissioning of the Shippingport Atomic Power Station, Hanford Site, Richland, Washington

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy's Remedial Actions Program Office developed this statement to assess the impacts of decommissioning the Shippingport Atomic Power Station as well as analyze possible decommissioning alternatives, evaluate potential environmental impacts associated with each alternative, and present cost estimates for each alternative.

  13. The Status of NRC Decommissioning Guidance on Intentional Soil Mixing

    SciTech Connect (OSTI)

    Watson, B.A.

    2007-07-01

    In 1997, the U.S. Nuclear Regulatory Commission (NRC) published the License Termination Rule (LTR) as Subpart E of 10 CFR Part 20, which established the license termination criteria for unrestricted use and the controls for restricted use. By 2003, the NRC staff's experience with the LTR revealed some important implementation issues impacting the decommissioning of sites, and these were addressed to the Commission (SECY-03-0069). In 2004, the staff provided the Commission with its analysis of a ninth issue, intentional soil mixing (SECY-04-0035). The Commission approved the staff's recommendations, with comments. In the draft revision of Supplement 1 to NUREG-1757, 'Consolidated Decommissioning Guidance', the staff endorsed the current practice of allowing intentional soil mixing to meet the waste acceptance criteria of offsite disposal facilities and the limited use of this practice to demonstrate compliance with the LTR criteria. The staff recommended including a provision that the staff would consider intentional mixing on a case-by-case basis, provided that the resulting contaminated area footprint is not increased and clean soil from outside the footprint is not mixed with contaminated soil to lower the concentrations. In addition, the staff would consider only those rare cases in which the mixing of clean soil is the only viable option for achieving the dose levels of the LTR. In 2005, the staff issued draft Supplement 1 to NUREG-1757 for public comment. The staff evaluated the public comments, including those from a number of States, and revised the guidance. The staff subsequently summarized the public comments on the draft guidance for the Commission (SECY-06-0143) in early 2006. This paper will discuss the public comments related to intentional mixing, the Commission's comments in its staff requirements memorandum, and the revision to the guidance in NUREG-1757 incorporating the current NRC decommissioning policy for intentional soil mixing. (authors)

  14. Decommissioning Cost Estimating Factors And Earned Value Integration

    SciTech Connect (OSTI)

    Sanford, P.C.; Cimmarron, E.

    2008-07-01

    The Rocky Flats 771 Project progressed from the planning stage of decommissioning a plutonium facility, through the strip-out of highly-contaminated equipment, removal of utilities and structural decontamination, and building demolition. Actual cost data was collected from the strip-out activities and compared to original estimates, allowing the development of cost by equipment groupings and types and over time. Separate data was developed from the project control earned value reporting and compared with the equipment data. The paper discusses the analysis to develop the detailed factors for the different equipment types, and the items that need to be considered during characterization of a similar facility when preparing an estimate. The factors are presented based on direct labor requirements by equipment type. The paper also includes actual support costs, and examples of fixed or one-time start-up costs. The integration of the estimate and the earned value system used for the 771 Project is also discussed. The paper covers the development of the earned value system as well as its application to a facility to be decommissioned and an existing work breakdown structure. Lessons learned are provided, including integration with scheduling and craft supervision, measurement approaches, and verification of scope completion. In summary: The work of decommissioning the Rocky Flats 771 Project process equipment was completed in 2003. Early in the planning process, we had difficulty in identifying credible data and implementing processes for estimating and controlling this work. As the project progressed, we were able to collect actual data on the costs of removing plutonium contaminated equipment from various areas over the life of this work and associate those costs with individual pieces of equipment. We also were able to develop and test out a system for measuring the earned value of a decommissioning project based on an evolving estimate. These were elements that would have been useful to us in our early planning process, and we would expect that they would find application elsewhere as the DOE weapons complex and some commercial nuclear facilities move towards closure. (authors)

  15. SAVANNAH RIVER SITE R REACTOR DISASSEMBLY BASIN IN SITU DECOMMISSIONING

    SciTech Connect (OSTI)

    Langton, C.; Blankenship, J.; Griffin, W.; Serrato, M.

    2009-12-03

    The US DOE concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate in tact, structurally sound facilities that are no longer needed for their original purpose of, i.e., generating (reactor facilities), processing(isotope separation facilities) or storing radioactive materials. The 105-R Disassembly Basin is the first SRS reactor facility to undergo the in-situ decommissioning (ISD) process. This ISD process complies with the105-R Disassembly Basin project strategy as outlined in the Engineering Evaluation/Cost Analysis for the Grouting of the R-Reactor Disassembly Basin at the Savannah River Site and includes: (1) Managing residual water by solidification in-place or evaporation at another facility; (2) Filling the below grade portion of the basin with cementitious materials to physically stabilize the basin and prevent collapse of the final cap - Sludge and debris in the bottom few feet of the basin will be encapsulated between the basin floor and overlying fill material to isolate if from the environment; (3) Demolishing the above grade portion of the structure and relocating the resulting debris to another location or disposing of the debris in-place; and (4) Capping the basin area with a concrete slab which is part of an engineered cap to prevent inadvertent intrusion. The estimated total grout volume to fill the 105-R Reactor Disassembly Basin is 24,424 cubic meters or 31,945 cubic yards. Portland cement-based structural fill materials were design and tested for the reactor ISD project and a placement strategy for stabilizing the basin was developed. Based on structural engineering analyses and work flow considerations, the recommended maximum lift height is 5 feet with 24 hours between lifts. Pertinent data and information related to the SRS 105-R-Reactor Disassembly Basin in-situ decommissioning include: regulatory documentation, residual water management, area preparation activities, technology needs, fill material designs and testing, and fill placement strategy. This information is applicable to decommissioning both the 105-P and 105-R facilities. The ISD process for the entire 105-P and 105-R reactor facilities will require approximately 250,000 cubic yards (191,140 cubic meters) of grout and 2,400 cubic yards (1,840 cubic meters) of structural concrete which will be placed over a twelve month period to meet the accelerated schedule ISD schedule. The status and lessons learned in the SRS Reactor Facility ISD process will be described.

  16. 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)

  17. Y-12 Plant decontamination and decommissioning technology logic diagram for Building 9201-4. Volume 2: Technology logic diagram

    SciTech Connect (OSTI)

    1994-09-01

    The Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4 (TLD) was developed to provide a decision-support tool that relates decontamination and decommissioning (D and D) problems at Bldg. 9201-4 to potential technologies that can remediate these problems. This TLD identifies the research, development, demonstration, testing, and evaluation needed for sufficient development of these technologies to allow for technology transfer and application to D and D and waste management (WM) activities. It is essential that follow-on engineering studies be conducted to build on the output of this project. These studies will begin by selecting the most promising technologies identified in the TLD and by finding an optimum mix of technologies that will provide a socially acceptable balance between cost and risk. The TLD consists of three fundamentally separate volumes: Vol. 1 (Technology Evaluation), Vol. 2 (Technology Logic Diagram), and Vol. 3 (Technology Evaluation Data Sheets). Volume 2 contains the logic linkages among environmental management goals, environmental problems, and the various technologies that have the potential to solve these problems. Volume 2 has been divided into five sections: Characterization, Decontamination, Dismantlement, Robotics/Automation, and Waste Management. Each section contains logical breakdowns of the Y-12 D and D problems by subject area and identifies technologies that can be reasonably applied to each D and D challenge.

  18. Deactivation & Decommissioning Knowledge Management Information Tool (D&D

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

    KM-IT) | Department of Energy Knowledge Management Information Tool (D&D KM-IT) Deactivation & Decommissioning Knowledge Management Information Tool (D&D KM-IT) Deactivation & Decommissioning Knowledge Management Information Tool (D&D KM-IT) The Deactivation and Decommissioning Knowledge Management Information Tool (D&D KM-IT) serves as a centralized repository providing a common interface for all D&D related activities. It assists users in gathering, analyzing,

  19. mhtml:file://H:\CATX\APPROVED-CXS\EERE FOA 1201 - Rankine Cycle

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

    . ., . . BNL-68599 PRODUCTION OF RADIOACTIVE IODINE David J. Schlyer Iodine-123 Probably the most 'widely used cyclotron produced radiohalogen is 1-123. It has gradually replaced I-13 1 as the isotope of choice for diagnostic radiopharmaceuticals containing radioiodine. It gives a much lower radiation dose to the patient and the gamma ray energy of 159 keV is ideally suited for use in a gamma camera. The gamma ray will penetrate tissue very effectively without excessive radiation dose. For this

  20. Applied combustion

    SciTech Connect (OSTI)

    1993-12-31

    From the title, the reader is led to expect a broad practical treatise on combustion and combustion devices. Remarkably, for a book of modest dimension, the author is able to deliver. The text is organized into 12 Chapters, broadly treating three major areas: combustion fundamentals -- introduction (Ch. 1), thermodynamics (Ch. 2), fluid mechanics (Ch. 7), and kinetics (Ch. 8); fuels -- coal, municipal solid waste, and other solid fuels (Ch. 4), liquid (Ch. 5) and gaseous (Ch. 6) fuels; and combustion devices -- fuel cells (Ch. 3), boilers (Ch. 4), Otto (Ch. 10), diesel (Ch. 11), and Wankel (Ch. 10) engines and gas turbines (Ch. 12). Although each topic could warrant a complete text on its own, the author addresses each of these major themes with reasonable thoroughness. Also, the book is well documented with a bibliography, references, a good index, and many helpful tables and appendices. In short, Applied Combustion does admirably fulfill the author`s goal for a wide engineering science introduction to the general subject of combustion.

  1. CPP-603 Chloride Removal System Decontamination and Decommissioning. Final report

    SciTech Connect (OSTI)

    Moser, C.L.

    1993-02-01

    The CPP-603 (annex) Chloride Removal System (CRS) Decontamination and Decommissioning (D&D) Project is described in this report. The CRS was used for removing Chloride ions and other contaminants that were suspended in the waters of the underwater fuel storage basins in the CPP-603 Fuel Receiving and Storage Facility (FRSF) from 1975 to 1981. The Environmental Checklist and related documents, facility characterization, decision analysis`, and D&D plans` were prepared in 1991. Physical D&D activities were begun in mid summer of 1992 and were completed by the end of November 1992. All process equipment and electrical equipment were removed from the annex following accepted asbestos and radiological contamination removal practices. The D&D activities were performed in a manner such that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory (INEL) occurred.

  2. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes

    SciTech Connect (OSTI)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

  3. DOE Environmental Management Strategy and Experience for In-Situ Decommissioning

    Broader source: Energy.gov [DOE]

    In situ decommissioning (ISD) is the permanent entombment of a contaminated facility. At present, ISD is not recognized or addressed in the Department of Energy (DOE) and Office of Environmental...

  4. Five-Year Technology Development Strategic Plan Targets EM’s Decommissioning Challenges

    Broader source: Energy.gov [DOE]

    WASHINGTON, D.C. – Leaders from EM headquarters and field offices and the UK’s Sellafield nuclear site gathered recently to discuss developing technologies needed to address decommissioning challenges across the Cold War cleanup program.

  5. EA-1053: Decontaminating and Decommissioning the General Atomics Hot Cell Facility, San Diego, California

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of the proposal for low-level radioactive and mixed wastes generated by decontaminating and decommissioning activities at the U.S. Department of Energy's...

  6. Idaho Site Closes Out Decontamination and Decommissioning Project about $440 Million under Cost

    Broader source: Energy.gov [DOE]

    IDAHO FALLS, Idaho – The Idaho Cleanup Project (ICP) successfully closed out a $796 million nuclear facility decontamination and decommissioning project. The work was completed about $440 million under cost.

  7. DOE EM Project Experience & Lessons Learned for In Situ Decommissioning (Feb. 2013)

    Broader source: Energy.gov [DOE]

    The purpose of the "DOE EM Project Experience & Lessons Learned for In Situ Decommissioning" report is to capture the considerable technical experience gained to date for implementation of In...

  8. Uranium Enrichment Decontamination and Decommissioning Fund's Fiscal Year 2011 Financial Statement Audit

    Energy Savers [EERE]

    Uranium Enrichment Decontamination and Decommissioning Fund's Fiscal Year 2011 Financial Statement Audit OAS-FS-13-02 October 2012 September 7, 2012 Mr. Gregory Friedman Inspector General U.S. Department of Energy 1000 Independence Avenue, S.W. Room 5D-039 Washington, DC 20585 Dear Mr. Friedman: We have audited the financial statements of the Department of Energy's (the Department) Uranium Enrichment Decontamination and Decommissioning Fund (D&D Fund) as of and for the year ended September

  9. Role of decommissioning plan and its progress for the PUSPATI TRIGA Reactor

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect Role of decommissioning plan and its progress for the PUSPATI TRIGA Reactor Citation Details In-Document Search Title: Role of decommissioning plan and its progress for the PUSPATI TRIGA Reactor Malaysian nuclear research reactor, the PUSPATI TRIGA Reactor, reached its first criticality in 1982, and since then, it has been serving for more than 30 years for training, radioisotope production and research purposes. Realizing the age and the need for its

  10. Engineering Evaluation/Cost Analysis for Decommissioning of the Engineering Test Reactor Complex

    SciTech Connect (OSTI)

    A. B. Culp

    2006-10-01

    Preparation of this Engineering Evaluation/Cost Analysis is consistent with the joint U.S. Department of Energy and U.S. Environmental Protection Agency Policy on Decommissioning of Department of Energy Facilities Under the Comprehensive Environmental Response, Compensation, and Liability Act, which establishes the Comprehensive Environmental Response, Compensation, and Liability Act non-time-critical removal action (NTCRA) process as an approach for decommissioning.

  11. Application of the New Decommissioning Regulation to the Nuclear Licensed Facilities (NLF) at Fontenay-aux-Roses's Nuclear Center (CEA)

    SciTech Connect (OSTI)

    Sauret, Josiane; Piketty, Laurence; Jeanjacques, Michel

    2008-01-15

    This abstract describes the application of the new decommissioning regulation on all Nuclear Licensed Facilities (NLF is to say INB in French) at Fontenay-aux-Roses's Center (CEA/FAR). The decommissioning process has been applied in six buildings which are out of the new nuclear perimeter proposed (buildings no 7, no 40, no 94, no 39, no 52/1 and no 32) and three buildings have been reorganized (no 54, no 91 and no 53 instead of no 40 and no 94) in order to increase the space for temporary nuclear waste disposal and to reduce the internal transports of nuclear waste on the site. The advantages are the safety and radioprotection improvements and a lower operating cost. A global safety file was written in 2002 and 2003 and was sent to the French Nuclear Authority on November 2003. The list of documents required is given in the paragraph I of this paper. The main goals were two ministerial decrees (one decree for each NLF) getting the authorization to modify the NLF perimeter and to carry out cleaning and dismantling activities leading to the whole decommissioning of all NLF. Some specific authorizations were necessary to carry out the dismantling program during the decommissioning procedure. They were delivered by the French Nuclear Safety Authority (FNSA) or with limited delegation by the General Executive Director (GED) on the CEA Fontenay-aux-Roses's Center, called internal authorization. Some partial dismantling or decontamination examples are given below: - evaporator for the radioactive liquid waste treatment station (building no 53): FNSA authorization: phase realised in 2002/2003. - disposal tanks for the radioactive liquid waste treatment station (building no 53) FNSA authorization: phase realised in 2004, - incinerator for the radioactive solid waste treatment station (building no 07): FNSA authorization: operation realised in 2004, - research equipments in the building no. 54 and building no. 91: internal authorization ; realised in 2005, - sample-taking to characterize solvent contained in one tank of Petrus installation (NLF 57, building 18) for radiological and chemical analysis needed to prepare the treatment and the evacuation of these wastes : internal authorization ; realised in june 2005. It was possible to plan the whole decommissioning process on the Nuclear Licensed Facilities of Fontenay-aux-Roses's Center (CEA/FAR) taking into account the French new regulation and to plan a coherent and continue program activity for the dismantling process. For the program not to be interrupted during the administrative process (2003-2006), specific authorisations have been delivered by the French Nuclear Safety Authority or by the General Executive Director (GED) on the CEA Fontenay-aux- Roses's Center (internal authorization). The time schedule to complete the entire program is until 2017 for NLF 'Procede' (NLF no 165) and until 2018 for NLF 'Support' (NLF no 166). Since 1999, an annual press meeting has been organised by the Fontenay-aux-Roses's Center Head Executive Manager.

  12. Deactivation and Decommissioning Planning and Analysis with Geographic Information Systems

    SciTech Connect (OSTI)

    Bollinger, James S.; Koffman, Larry D.; Austin, William E.

    2008-01-15

    From the mid-1950's through the 1980's, the U.S. Department of Energy's Savannah River Site produced nuclear materials for the weapons stockpile, for medical and industrial applications, and for space exploration. Although SRS has a continuing defense-related mission, the overall site mission is now oriented toward environmental restoration and management of legacy chemical and nuclear waste. With the change in mission, SRS no longer has a need for much of the infrastructure developed to support the weapons program. This excess infrastructure, which includes over 1000 facilities, will be decommissioned and demolished over the forthcoming years. Dis-positioning facilities for decommissioning and deactivation requires significant resources to determine hazards, structure type, and a rough-order-of-magnitude estimate for the decommissioning and demolition cost. Geographic information systems (GIS) technology was used to help manage the process of dis-positioning infrastructure and for reporting the future status of impacted facilities. Several thousand facilities of various ages and conditions are present at SRS. Many of these facilities, built to support previous defense-related missions, now represent a potential hazard and cost for maintenance and surveillance. To reduce costs and the hazards associated with this excess infrastructure, SRS has developed an ambitious plan to decommission and demolish unneeded facilities in a systematic fashion. GIS technology was used to assist development of this plan by: providing locational information for remote facilities, identifying the location of known waste units adjacent to buildings slated for demolition, and for providing a powerful visual representation of the impact of the overall plan. Several steps were required for the development of the infrastructure GIS model. The first step involved creating an accurate and current GIS representation of the infrastructure data. This data is maintained in a Computer Aided Design (CAD) system and had to be imported into a GIS framework. Since the data is maintained in a different format in CAD, import into GIS involved several spatial processing steps to convert various geometric shapes present in the CAD data to self-closing polygons. The polygons represent facility footprints in plan or map view. Once these were successfully imported and converted, building identifier attributes from the CAD had to be associated with the appropriate polygons in GIS. Attributes are stored as graphical information in a CAD system and are not 'attached' to a building in a relational sense. In GIS, attributes such as building names, building area, hazards, or other descriptive information, must be associated or related to the spatial polygon representing a particular building. This spatial relationship between building polygons and the descriptive attribute information is very similar to relating tables of information in a relational database in which each table record has a unique identifier that can be used to join or relate that table to other tables of information present in the database. The CAD building identifiers were imported into the GIS and several spatial processing steps were used to associate building polygons with the correct identifiers. These spatial steps involved determining the intersection of and nearest identifiers with each building polygon in the GIS. Automating this process in GIS saved a significant amount of time. Once a current and geographically correct representation of the infrastructure data had been created in GIS, field-engineering teams collected information for each facility. This information included the building area, radiological hazards and the associated area, industrial hazards such as asbestos or mercury, structure type (e.g. hardened, industrial, nuclear), annual surveillance and monitoring cost, and other engineering data. The facility engineering data was used in a simple model to determine the rough-order-of-magnitude cost for decontaminating and demolishing each facility. Finally, the engineering and cost data was linked to the GIS model so that this data could be rapidly displayed and analyzed in its geographic context. Once the GIS representing SRS infrastructure and associated descriptive attribute information was developed, detailed maps depicting the future status of all site facilities were created. These maps display the relationship between known waste units and buildings that will be decommissioned and demolished. Cost and hazard information was also depicted illustrating areas and facilities that could present a particular demolition challenge. Although the GIS was quite helpful as an engineering and planning tool, its real power was evident in communicating the impact of the facilities disposition plan to senior management and other stakeholders.

  13. Technology, safety and costs of decommissioning a Reference Boiling Water Reactor Power Station. Main report. Volume 1

    SciTech Connect (OSTI)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWe.

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

    SciTech Connect (OSTI)

    P.C. Weaver

    2010-12-15

    5098-SR-03-0 FINAL REPORT- INDEPENDENT VERIFICATION SURVEY OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT OUTSIDE AREAS, BROOKHAVEN NATIONAL LABORATORY

  15. LETTER REPORT INDEPENDENT VERIFICATION OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT FAN HOUSE, BUILDING 704 BNL

    SciTech Connect (OSTI)

    P.C. Weaver

    2010-10-22

    5098-LR-01-0 -LETTER REPORT INDEPENDENT VERIFICATION OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT FAN HOUSE, BUILDING 704 BROOKHAVEN NATIONAL LABORATORY

  16. DECOMMISSIONING OF NUCLEAR FACILITIES IN GERMANY - STATUS AT BMBF SITES

    SciTech Connect (OSTI)

    Papp, R.; Komorowski, K.

    2002-02-25

    In a period of approximately 40 years prior to 1994, the German Federal Government had spent about {approx} 15 billion to promote nuclear technology. These funds were earmarked for R&D projects as well as demonstration facilities which took up operation between 1960 and 1980. These BMBF (Federal Ministry for Research) facilities were mainly located at the sites of the federal research centers at Juelich and Karlsruhe (the research reactors AVR, FR2, FRJ-1, KNK, and MZFR, the pilot reprocessing plant WAK) but included also the pilot plants SNR-300 and THTR-300 for fast breeder and high-temperature gas-cooled reactor development, respectively, and finally the salt mine Asse which had been used for waste emplacement prior to conversion into an underground research laboratory. In the meantime, almost all of these facilities were shut down and are now in a state of decommissioning and dismantling. This is mainly due to the facts that R&D needs are satisfied or do not exist any more and that, secondly, the lack of political consensus led to the cancellation of advanced nuclear technology.

  17. Decommissioning of the Molten Salt Reactor Experiment: A technical evaluation

    SciTech Connect (OSTI)

    Notz, K.J.

    1988-01-01

    This report completes a technical evaluation of decommissioning planning for the former Molten Salt Reactor Experiment, which was shut down in December, 1969. The key issues revolve around the treatment and disposal of some five tons of solid fuel salt which contains over 30 kg of fissionable uranium-233 plus fission products and higher actinides. The chemistry of this material is complicated by the formation of elemental fluorine via a radiolysis reaction under certain conditions. Supporting studies carried out as part of this evaluation include (a) a broad scope analysis of possible options for storage/disposal of the salts, (b) calculation of nuclide decay in future years, (c) technical evaluation of the containment facility and hot cell penetrations, (d) review and update of surveillance and maintenance procedures, (e) measurements of facility groundwater radioactivity and sump pump operation, (f) laboratory studies of the radiolysis reaction, and (g) laboratory studies which resulted in finding a suitable getter for elemental fluorine. In addition, geologic and hydrologic factors of the surrounding area were considered, and also the implications of entombment of the fuel in-place with concrete. The results of this evaluation show that the fuel salt cannot be left in its present form and location permanently. On the other hand, extended storage in its present form is quite acceptable for 20 to 30 years, or even longer. For continued storage in-place, some facility modifications are recommended. 30 refs., 5 figs., 9 tabs.

  18. Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216

    SciTech Connect (OSTI)

    Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi; Cochran, John R.

    2013-07-01

    Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these include the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the Iraqi Decommissioning Directorate (IDD) is responsible for decommissioning activities. The IDD and the RWTMD work together on decommissioning projects. The IDD has developed plans and has completed decommissioning of the GeoPilot Facility in Baghdad and the Active Metallurgical Testing Laboratory (LAMA) in Al-Tuwaitha. Given this experience, the IDD has initiated work on more dangerous facilities. Plans are being developed to characterize, decontaminate and decommission the Tamuz II Research Reactor. The Tammuz Reactor was destroyed by an Israeli air-strike in 1981 and the Tammuz II Reactor was destroyed during the First Gulf War in 1991. In addition to being responsible for managing the decommissioning wastes, the RWTMD is responsible for more than 950 disused sealed radioactive sources, contaminated debris from the first Gulf War and (approximately 900 tons) of naturally-occurring radioactive materials wastes from oil production in Iraq. The RWTMD has trained staff, rehabilitated the Building 39 Radioactive Waste Storage building, rehabilitated portions of the French-built Radioactive Waste Treatment Station, organized and secured thousands of drums of radioactive waste organized and secured the stores of disused sealed radioactive sources. Currently, the IDD and the RWTMD are finalizing plans for the decommissioning of the Tammuz II Research Reactor. (authors)

  19. DECOMMISSIONING OF THE NUCLEAR FACILITIES OF VKTA AT THE ROSSENDORF RESEARCH SITE

    SciTech Connect (OSTI)

    U. Helwig, W. Boessert

    2003-02-27

    VKTA decommissioned the old nuclear facilities of former GDR's (German Democratic Republic) Central Institute of Nuclear Research which was closed end of 1991. VKTA is responsible for fissile material and waste management, environmental and radiation protection and runs an accredited laboratory for environmental and radionuclide analytics. The Rossendorf research site is located east of the city of Dresden. The period from 1982 to about 1997 was mainly characterized by obtaining the necessary licenses for decommissioning and developing a new infrastructure (i.e. waste treatment facility, interim storages for fissile material and waste, clearance monitoring facility). The decommissioning work has been in progress since that time. The decommissioning projects are concentrated on three complexes: (1) the reactors and a fuel development and testing facility, (2) the radioisotope production facilities, and (3) the former liquid and solid waste storage facilities. The status of decommissioning progress and treatment of the residues will be demonstrated. Finally an outlook will be given on the future tasks of VKTA based on the ''Conception VKTA 2000 plus'', which was confirmed by the Saxonian government last year.

  20. Decommissioning and PIE of the MEGAPIE spallation target

    SciTech Connect (OSTI)

    Latge, C.; Henry, J.; Wohlmuther, M.; Dai, Y.; Gavillet, D.; Hammer, B.; Heinitz, S.; Neuhausen, J.; Schumann, D.; Thomsen, K.; Tuerler, A.; Wagner, W.; Gessi, A.; Guertin, A.; Konstantinovic, M.; Lindau, R.; Maloy, S.; Saito, S.

    2013-07-01

    A key experiment in the Accelerated Driven Systems roadmap, the MEGAwatt PIlot Experiment (MEGAPIE) (1 MW) was initiated in 1999 in order to design and build a liquid lead-bismuth spallation target, then to operate it into the Swiss spallation neutron facility SINQ at Paul Scherrer Institute. The target has been designed, manufactured, and tested during integral tests, before irradiation carried out end of 2006. During irradiation, neutron and thermo hydraulic measurements were performed allowing deep interpretation of the experiment and validation of the models used during design phase. The decommissioning, Post Irradiation Examinations and waste management phases were defined properly. The phases dedicated to cutting, sampling, cleaning, waste management, samples preparation and shipping to various laboratories were performed by PSI teams: all these phases constitute a huge work, which allows now to perform post-irradiation examination (PIE) of structural material, irradiated in relevant conditions. Preliminary results are presented in the paper, they concern chemical characterization. The following radio-nuclides have been identified by ?-spectrometry: {sup 60}Co, {sup 101}Rh, {sup 102}Rh, {sup 108m}Ag, {sup 110m}Ag, {sup 133}Ba, {sup 172}Hf/Lu, {sup 173}Lu, {sup 194}Hg/Au, {sup 195}Au, {sup 207}Bi. For some of these nuclides the activities can be easily evaluated from ?-spectrometry results ({sup 207}Bi, {sup 194}Hg/Au), while other nuclides can only be determined after chemical separations ({sup 108m}Ag, {sup 110m}Ag, {sup 195}Au, {sup 129}I, {sup 36}Cl and ?-emitting {sup 208-210}Po). The concentration of {sup 129}I is lower than expected. The chemical analysis already performed on spallation and corrosion products in the lead-bismuth eutectic (LBE) are very relevant for further applications of LBE as a spallation media and more generally as a coolant.

  1. Mobile worksystems for decontamination and decommissioning operations. Final report

    SciTech Connect (OSTI)

    1997-02-01

    This project is an interdisciplinary effort to develop effective mobile worksystems for decontamination and decommissioning (D&D) of facilities within the DOE Nuclear Weapons Complex. These mobile worksystems will be configured to operate within the environmental and logistical constraints of such facilities and to perform a number of work tasks. Our program is designed to produce a mobile worksystem with capabilities and features that are matched to the particular needs of D&D work by evolving the design through a series of technological developments, performance tests and evaluations. The Phase I effort was based on a robot called the Remote Work Vehicle (RWV) that was previously developed by CMU for use in D&D operations at the Three Mile Island Unit 2 Reactor Building basement. During Phase I of this program, the RWV was rehabilitated and upgraded with contemporary control and user interface technologies and used as a testbed for remote D&D operations. We established a close working relationship with the DOE Robotics Technology Development Program (RTDP). In the second phase, we designed and developed a next generation mobile worksystem, called Rosie, and a semi-automatic task space scene analysis system, called Artisan, using guidance from RTDP. Both systems are designed to work with and complement other RTDP D&D technologies to execute selective equipment removal scenarios in which some part of an apparatus is extricated while minimally disturbing the surrounding objects. RTDP has identified selective equipment removal as a timely D&D mission, one that is particularly relevant during the de-activation and de-inventory stages of facility transitioning as a means to reduce the costs and risks associated with subsequent surveillance and monitoring. In the third phase, we tested and demonstrated core capabilities of Rosie and Artisan; we also implemented modifications and enhancements that improve their relevance to DOE`s facility transitioning mission.

  2. Technology, Safety and Costs of Decommissioning a Reference Uranium Hexafluoride Conversion Plant

    SciTech Connect (OSTI)

    Elder, H. K.

    1981-10-01

    Safety and cost information is developed for the conceptual decommissioning of a commercial uranium hexafluoride conversion (UF{sub 6}) plant. Two basic decommissioning alternatives are studied to obtain comparisons between cost and safety impacts: DECON, and passive SAFSTOR. A third alternative, DECON of the plant and equipment with stabilization and long-term care of lagoon wastes. is also examined. DECON includes the immediate removal (following plant shutdown) of all radioactivity in excess of unrestricted release levels, with subsequent release of the site for public use. Passive SAFSTOR requires decontamination, preparation, maintenance, and surveillance for a period of time after shutdown, followed by deferred decontamination and unrestricted release. DECON with stabilization and long-term care of lagoon wastes (process wastes generated at the reference plant and stored onsite during plant operation} is also considered as a decommissioning method, although its acceptability has not yet been determined by the NRC. The decommissioning methods assumed for use in each decommissioning alternative are based on state-of-the-art technology. The elapsed time following plant shutdown required to perform the decommissioning work in each alternative is estimated to be: for DECON, 8 months; for passive SAFSTOR, 3 months to prepare the plant for safe storage and 8 months to accomplish deferred decontamination. Planning and preparation for decommissioning prior to plant shutdown is estimated to require about 6 months for either DECON or passive SAFSTOR. Planning and preparation prior to starting deferred decontamination is estimated to require an additional 6 months. OECON with lagoon waste stabilization is estimated to take 6 months for planning and about 8 months to perform the decommissioning work. Decommissioning cost, in 1981 dollars, is estimated to be $5.91 million for OECON. For passive SAFSTOR, preparing the facility for safe storage is estimated to cost $0.88 million, the annual maintenance and surveillance cost is estimated to be about $0.095 million, and deferred decontamination is estimated to cost about $6.50 million. Therefore, passive SAFSTOR for 10 years is estimated to cost $8.33 million in nondiscounted 1981 dollars. DECON with lagoon waste stabilization is estimated to cost about $4.59 million, with an annual cost of $0.011 million for long-term care. All of these estimates include a 25% contingency. Waste management costs for DECON, including the net cost of disposal of the solvent extraction lagoon wastes by shipping those wastes to a uranium mill for recovery of residual uranium, comprise about 38% of the total decommissioning cost. Disposal of lagoon waste at a commercial low-level waste burial ground is estimated to add $10.01 million to decommissioning costs. Safety analyses indicate that radiological and nonradiological safety impacts from decommissioning activities should be small. The 50-year committed dose equivalent to members of the public from airborne releases during normal decommissioning activities is estimated to 'Je about 4.0 man-rem. Radiation doses to the public from accidents are found to be very low for all phases of decommissioning. Occupational radiation doses from normal decommissioning operations (excluding transport operations) are estimated to be about 79 man-rem for DECON and about 80 man-rem for passive SAFSTOR with 10 years of safe storage. Doses from DECON with lagoon waste stabilization are about the same as for DECON except there is less dose resulting from transportation of radioactive waste. The number of fatalities and serious lost-time injuries not related to radiation is found to be very small for all decommissioning alternatives. Comparison of the cost estimates shows that DECON with lagoon waste stabilization is the least expensive method. However, this alternative does not allow unrestricted release of the site. The cumulative cost of maintenance and surveillance and the higher cost of deferred decontamination makes passive SAFSTOR more expensive than DECON. Several methods to assure that the licensee has adequate funds for decommissioning are considered. The methods investigated (all based on expected decommissioning costs) range from a single payment when plant operations begin, to payments into a sinking fund during the normal plant operating period, to a single payment when normal plant operations cease and decommissioning begins.

  3. Technical Aspects Regarding the Management of Radioactive Waste from Decommissioning of Nuclear Facilities

    SciTech Connect (OSTI)

    Dragolici, F.; Turcanu, C. N.; Rotarescu, G.; Paunica, I.

    2003-02-25

    The proper application of the nuclear techniques and technologies in Romania started in 1957, once with the commissioning of the Research Reactor VVR-S from IFIN-HH-Magurele. During the last 45 years, appear thousands of nuclear application units with extremely diverse profiles (research, biology, medicine, education, agriculture, transport, all types of industry) which used different nuclear facilities containing radioactive sources and generating a great variety of radioactive waste during the decommissioning after the operation lifetime is accomplished. A new aspect appears by the planning of VVR-S Research Reactor decommissioning which will be a new source of radioactive waste generated by decontamination, disassembling and demolition activities. By construction and exploitation of the Radioactive Waste Treatment Plant (STDR)--Magurele and the National Repository for Low and Intermediate Radioactive Waste (DNDR)--Baita, Bihor county, in Romania was solved the management of radioactive wastes arising from operation and decommissioning of small nuclear facilities, being assured the protection of the people and environment. The present paper makes a review of the present technical status of the Romanian waste management facilities, especially raising on treatment capabilities of ''problem'' wastes such as Ra-266, Pu-238, Am-241 Co-60, Co-57, Sr-90, Cs-137 sealed sources from industrial, research and medical applications. Also, contain a preliminary estimation of quantities and types of wastes, which would result during the decommissioning project of the VVR-S Research Reactor from IFIN-HH giving attention to some special category of wastes like aluminum, graphite and equipment, components and structures that became radioactive through neutron activation. After analyzing the technical and scientific potential of STDR and DNDR to handle big amounts of wastes resulting from the decommissioning of VVR-S Research Reactor and small nuclear facilities, the necessity of up-gradation of these nuclear objectives before starting the decommissioning plan is revealed. A short presentation of the up-grading needs is also presented.

  4. Development And Implementation Of A Strategic Technical Baseline Approach For Nuclear Decommissioning And Clean Up Programmes In The UK

    SciTech Connect (OSTI)

    Brownridge, M.; Ensor, B.

    2008-07-01

    The NDA mission as set out within the Energy Act 2004 and stated in the NDA strategy is clear: - 'to deliver a world class programme of safe, cost-effective, accelerated and environmentally responsible decommissioning of the UK's civil nuclear legacy in an open and transparent manner and with due regard to the socio-economic impacts on our communities. Critical to achieving the NDA main objective and overall mission is to accelerate and deliver clean-up programmes through the application of appropriate and innovative technology. The NDA remit also requires us to secure good practice by contractors and carry out and promote research into matters relating to the decommissioning and clean up of nuclear installations and sites. NDA have defined a strategic approach for the underpinning of operational and decommissioning activities where each nuclear site is required to write within the Life Time Plans (LTP) the proposed technical baseline for those activities. This enables the robustness of the activities to be assessed, the gaps and opportunities and accompanying Research and Developments (R and D) requirements to be highlighted and investment to be targeted at key technical issues. NDA also supports the development of a commercial framework where innovation is encouraged and improvements can be demonstrated against the technical baseline. In this paper we will present NDA's overall strategic approach, the benefits already realised and highlight the areas for continued development. In conclusion: The development and implementation of a strategic approach to robustly underpin the technical components of the lifetime plans for operational and decommissioning activities on NDA sites has been extremely successful. As well as showing how mature technology assumptions are and where the key gaps and risks are it has also provided a method for highlighting opportunities to improve on that baseline. The use of a common template across all NDA LTPs has enabled direct comparison of issues, identification of inter-site dependencies and scheduling hold points and a platform for sharing success and good practice. This deployment of TRLs and TBURDs across all 20 UK NDA sites is unique. The strategic approach is linked into wider areas in NDA's mission including NDA skills strategy and NDA's Direct Research Portfolio. NDA plan to ensure the strategic approach continues to evolve by the following activities: - Benchmarking the success of the TBURD and consistency of TRL evaluation to develop to a world class model; - Development of quantitative as well as qualitative methods of measuring the benefits realised; - Further support the development of technical interest groups where good practice is rewarded, shared, deployed and the benefit realised is measured; - Seek to reward innovation through the technical baselines and continue to develop the commercial framework. The progress described to date has summarised the work to develop the approach and indicated how it has been embedded and applied within three LTP cycles. NDA will further develop the TBURD through international benchmarking to create a process that is world class and clearly linked to delivery and innovation in order to reduce cost and schedule. (authors)

  5. Decontamination and decommissioning of building 889 at Rocky Flats Environmental Technology Site

    SciTech Connect (OSTI)

    Dorr, K.A.; Hickman, M.E.; Henderson, B.J.; Sexton, R.J.

    1997-09-01

    At the Rocky Flats site, the building 889 decommissioning project was the first large-scale decommissioning project of a radiologically contaminated facility at Rocky Flats. The scope consisted of removal of all equipment and utility systems from the interior of the building, decontamination of interior building surfaces, and the demolition of the facility to ground level. Details of the project management plan, including schedule, engineering, cost, characterization methodologies, decontamination techniques, radiological control requirements, and demolition methods, are provided in this article. 1 fig., 3 tabs.

  6. Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Appendices

    SciTech Connect (OSTI)

    Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

    1982-03-01

    Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and EMTOMB (entombment). The study results are presented in two volumes. Volume 2 (Appendices) contains the detailed data that support the results given in Volume 1, including unit-component data.

  7. Environmental assessment of decommissioning radioisotope thermoelectric generators (RTG) in northwest Russia

    SciTech Connect (OSTI)

    Hosseini, A.; Standring, W.J.F.; Brown, J.E.; Dowdall, M.; Amundsen, I.B.

    2007-07-01

    This article presents some results from assessment work conducted as part of a joint Norwegian-Russian project to decommission radioisotope thermoelectric generators (RTG) in Northwest Russia. Potential worst case accident scenarios, based on the decommissioning procedures for RTGs, were assessed to study possible radiation effects to the environment. Close contact with exposed RTG sources will result in detrimental health effects. However, doses to marine biota from ingestion of radioactivity under the worst-case marine scenario studied were lower than threshold limits given in IAEA literature. (authors)

  8. Decommissioning strategy options for MR reactor at the Kurchatov Institute, Moscow

    SciTech Connect (OSTI)

    Cross, M.T.; Harman, N.F.; Charles, D.; Harper, A.; Bylkin, B.K.; Gorlinsky, Yu.E.; Kolyadin, V.I.; Kutkov, V.A.; Pavlenko, V.I.; Sivintsev, Yu.V.; Lobach, Yu.N.

    2007-07-01

    The principal decommissioning goal for the nuclear installations of the Kurchatov Institute is the removal of spent fuel, reactor facilities and radioactive waste from the Institute's site. As the result of decommissioning, the buildings, constructions and areas should be cleaned to residual contamination levels acceptable to the stakeholders. These levels are determined in view of possible options for the rehabilitation of the Institute's areas under conditions of compliance with acting legislation for safety provisions for staff, population noting the proximity of the site to the local urban environment. Research reactor MR was commissioned in 1963 for reactor materials testing and finally shutdown in 1993. The reactor power with the experimental loops was 50 MW,. Several features were identified for the development of a decommissioning strategy for this reactor, namely: the strategy should consider many factors in a broad approach with international, inter-industry and long-term perspectives; the current situation for decommissioning is uncertain and must account for the views of a variety of stakeholders on possible final conditions and further use of the site and the route to achieve these; and a lack of sufficiency in the national legislation base for execution of the work and the possible options for its completion. On the basis of worldwide experience, the strategy for decommissioning of reactor MR was determined as follows: - determination of the options for the final rehabilitation of the Institute's areas; - determination of the stakeholders and their priority concerns; - determination of the strategy options for achievement of the final status; - determination of the main factors influencing the selection of the decommissioning strategy; - selection of the most acceptable strategies on the basis of a multi-attribute analysis; - determination of the main stages and principles of implementation of the selected strategy; and - development of the decommissioning activities considering the work that will be required. As the result of the multi-attribute analysis, the following conclusion has been made: the preferred final status of the facility is for a nuclear re-use application the preferred decommissioning option is immediate dismantling. (authors)

  9. Selecting the optimum decommissioning strategy for UKAEA`s redundant reactors

    SciTech Connect (OSTI)

    Wratten, T.J.; Nelson, R.L.

    1995-12-31

    The United Kingdom Atomic Energy Authority has built and operated a wide range of radioactive facilities since the late 1940s for the development of weapons, reactor systems, radioisotopes, fuel and reprocessing technology. Most of these plants are now closed and a major task for UKAEA Government Division (UKAEA-GD) is to manage their decommissioning safely and at minimum cost to the UK taxpayer. Safety and economic considerations generally require that some decommissioning work is undertaken immediately after closure, and for this work to be completed as quickly as possible. For a reactor, this normally involves the removal of irradiated fuel and coolant and the reduction of the radioactive inventory by removal of non-fixed items of plant and equipment. Beyond this, there are a large number of possible options for the timing and scope of decommissioning work. This paper describes how a methodology has been developed which uses option studies to establish the minimum discounted cost strategy for the decommissioning of major facilities, using as examples the wide range of reactors which form part of UKAEA-GD`s list of nuclear liabilities.

  10. EIS-0364: Decommissioning of the Fast Flux Test Facility, Hanford Site, Richland, WA

    Office of Energy Efficiency and Renewable Energy (EERE)

    The U.S. Department of Energy (DOE) announces its intent to prepare an Environmental Impact Statement (EIS), pursuant to the National Environmental Policy Act of 1969 (NEPA), on proposed decommissioning of the Fast Flux Test Facility (FFTF) at the Hanford Site, Richland, Washington.

  11. Impact of Lack of Consistent Free Release Standards on Decommissioning Projects and Costs

    SciTech Connect (OSTI)

    Devgun, J. S.

    2002-02-26

    While the Nuclear Regulatory Commission has had specific and dose-based standards for the release of liquids and gases for a long time, there are no regulatory mechanisms in place for the release of solid bulk materials from a nuclear power plant. Even though free releases of small quantities of solid materials continue under existing guidelines from the operating plants, the regulatory void creates major difficulties for the bulk materials that result from the decommissioning of a nuclear site. Decommissioning of a commercial nuclear power plant generates large quantities of solid bulk materials such as concrete, metal, and demolition debris. Disposition of such materials has a large impact on the overall decommissioning cost. Yet, there are no clear and cost-effective alternatives for the disposal of these materials from a regulatory perspective. This paper discusses the methodologies for clearance of solid materials1, their applicability to the disposition of bulk materials, and the impact of lack of consistent free release standards on the decommissioning projects and costs.

  12. Role of the statistician in the decommissioning of the New Brunswick Laboratory and other nuclear facilities

    SciTech Connect (OSTI)

    Gilbert, R.O.

    1980-12-01

    This report examines what the statistician can contribute to decommissioning operations, with particular emphasis on the New Brunswick Laboratory (NBL) currently scheduled for decommissioning beginning in FY81. In the opinion of the author, a professional statistician should be a full member of the planning team directing decommissioning operations at the New Brunswick Laboratory. This opinion is based in part on the familiarity with the valuable contributions made by statisticians toward the cleanup of transuranics in soil on the Enewetak Atoll. More generally, however, the professional statistician can help plan the decommissioning effort to help ensure that representative data are obtained, analyzed and, interpreted in appropriate ways so that RA decisions can be made with the required confidence. The statistician's contributions at the NBL could include providing guidance on the number and location of samples and in-situ measurements, analyzing and interpreting these data, designing a data management and documentation system, interfacing with the certification contractor's statistician, and assisting in writing documentation and final reports. In all cases, the statistician should work closely with the professional health physicist and others on the planning team in a closely coordinated effort of planning and data analysis.

  13. Reactor Design and Decommissioning - An Overview of International Activities in Post Fukushima Era1 - 12396

    SciTech Connect (OSTI)

    Devgun, Jas S.; Laraia, Michele; Dinner, Paul

    2012-07-01

    Accidents at the Fukushima Dai-ichi reactors as a result of the devastating earthquake and tsunami of March 11, 2011 have not only dampened the nuclear renaissance but have also initiated a re-examination of the design and safety features for the existing and planned nuclear reactors. Even though failures of some of the key site features at Fukushima can be attributed to events that in the past would have been considered as beyond the design basis, the industry as well as the regulatory authorities are analyzing what features, especially passive features, should be designed into the new reactor designs to minimize the potential for catastrophic failures. It is also recognized that since the design of the Fukushima BWR reactors which were commissioned in 1971, many advanced safety features are now a part of the newer reactor designs. As the recovery efforts at the Fukushima site are still underway, decisions with respect to the dismantlement and decommissioning of the damaged reactors and structures have not yet been finalized. As it was with Three Mile Island, it could take several decades for dismantlement, decommissioning and clean up, and the project poses especially tough challenges. Near-term assessments have been issued by several organizations, including the IAEA, the USNRC and others. Results of such investigations will lead to additional improvements in system and site design measures including strengthening of the anti-tsunami defenses, more defense-in-depth features in reactor design, and better response planning and preparation involving reactor sites. The question also arises what would the effect be on the decommissioning scene worldwide, and what would the effect be on the new reactors when they are eventually retired and dismantled. This paper provides an overview of the US and international activities related to recovery and decommissioning including the decommissioning features in the reactor design process and examines these from a new perspective in the post Fukushima -accident era. Accidents at the Fukushima Daiichi reactors in the aftermath of the devastating earthquake and tsunami of March 11, 2011 have slowed down the nuclear renaissance world-wide and may have accelerated decommissioning either because some countries have decided to halt or reduce nuclear, or because the new safety requirements may reduce life-time extensions. Even in countries such as the UK and France that favor nuclear energy production existing nuclear sites are more likely to be chosen as sites for future NPPs. Even as the site recovery efforts continue at Fukushima and any decommissioning decisions are farther into the future, the accidents have focused attention on the reactor designs in general and specifically on the Fukushima type BWRs. The regulatory authorities in many countries have initiated a re-examination of the design of the systems, structures and components and considerations of the capability of the station to cope with beyond-design basis events. Enhancements to SSCs and site features for the existing reactors and the reactors that will be built will also impact the decommissioning phase activities. The newer reactor designs of today not only have enhanced safety features but also take into consideration the features that will facilitate future decommissioning. Lessons learned from past management and operation of reactors as well as the lessons from decommissioning are incorporated into the new designs. However, in the post-Fukushima era, the emphasis on beyond-design-basis capability may lead to significant changes in SSCs, which eventually will also have impact on the decommissioning phase. Additionally, where some countries decide to phase out the nuclear power, many reactors may enter the decommissioning phase in the coming decade. While the formal updating and expanding of existing guidance documents for accident cleanup and decommissioning would benefit by waiting until the Fukushima project has progressed sufficiently for that experience to be reliably interpreted, the development of structured on-line sharing of information and especially the creation of an on-line compendium of methods, tools, and techniques by which damaged fuel and other unique situations have been addressed can be addressed sooner and maintained as new problems and solutions arise and are resolved. The IAEA's new 'WEB 2.0 tool' CONNECT is expected to play a significant role in this and related information-sharing activities. The trend in some countries such as the United States has been to re-license the existing reactors for additional twenty years, beyond the original design life. Given the advances in technology over the past four decades, and considering that the newer designs incorporate significant improvements in safety systems, it may not be economical or technically feasible to retrofit enhancements into some of the older reactors. In such cases, the reactors may be retired from service and decommissioned. Overall, the energy demand in the world continues to rise, with sharp increases in the Asian countries, and nuclear power's role in the world's energy supply is expected to continue. Events at Fukushima have led to a re-examination on many fronts, including reactor design and regulatory requirements. Further changes may occur in these areas in the post-Fukushima era. These changes in turn will also impact the world-wide decommissioning scene and the decommissioning phase of the future reactors. (authors)

  14. Sixteen Years of International Co-operation. The OECD/NEA Co-operative Programme on Decommissioning

    SciTech Connect (OSTI)

    Menon, S.; Valencia, L.

    2002-02-25

    The Co-operative Programme on Decommissioning under the administration of the Radioactive Waste Management Committee of the OECD Nuclear Energy Agency (NEA) has recently completed sixteen years of operation. The Programme, which is essentially an information exchange programme between decommissioning projects, came into being in 1985. It has grown from an initial 10 decommissioning projects from 7 countries to 39 projects from 14 countries today. From purely information exchange to start with, the Programme has, in later years, been functioning as a voice for the collective expression of views of the implementers of nuclear decommissioning. During the first sixteen years of the operation of the Co-operative Programme, nuclear decommissioning has grown from local specialist activities within projects to a competitive commercial industry. By the dismantling and release from regulatory control of over a dozen diverse nuclear facilities, the Programme has been able to demonstrate in practice, that nuclear decommissioning can be performed safely both for the workers and the public, and that this can be done at reasonable costs in an environmentally friendly fashion. During the recent years, discussions and work within the Co-operative Programme, specially within some of the Task Groups, have had/are having effects and repercussions not just in the field of nuclear decommissioning, but can possibly affect activities and regulations in other industries. This paper describes how the Programme and its activities and procedures have evolved over the years and indicate the directions of developments in the organization and execution of decommissioning projects. Finally, it gives a brief overview of the achievements of the Cooperative Programme and visualizes future developments in the field of nuclear decommissioning.

  15. Decommissioning of the secondary containment of the steam generating heavy water reactor at UKAEA-Winfrith

    SciTech Connect (OSTI)

    Miller, Keith; Cornell, Rowland; Parkinson, Steve; McIntyre, Kevin; Staples, Andy

    2007-07-01

    Available in abstract form only. Full text of publication follows: The Winfrith SGHWR was a prototype nuclear power plant operated for 23 years by the United Kingdom Atomic Energy Authority (UKAEA) until 1990 when it was shut down permanently. The current Stage 1 decommissioning contract is part of a multi-stage strategy. It involves the removal of all the ancillary plant and equipment in the secondary containment and non-containment areas ahead of a series of contracts for the decommissioning of the primary containment, the reactor core and demolition of the building and all remaining facilities. As an outcome of a competitive tending process, the Stage 1 decommissioning contract was awarded to NUKEM with operations commencing in April 2005. The decommissioning processes involved with these plant items will be described with some emphasis of the establishment of multiple work-fronts for the production, recovery, treatment and disposal of mainly tritium-contaminated waste arising from its contact with the direct cycle reactor coolant. The means of size reduction of a variety of large, heavy and complex items of plant made from a range of materials will also be described with some emphasis on the control of fumes during hot cutting operations and establishing effective containments within a larger secondary containment structure. Disposal of these wastes in a timely and cost-effective manner is a major challenge facing the decommissioning team and has required the development of a highly efficient means of packing the resultant materials into mainly one-third height ISO containers for disposal as LLW. Details of the quantities of LLW and exempt wastes handled during this process will be given with a commentary about the difficulty in segregating these two waste streams efficiently. (authors)

  16. Recommended values for the distribution coefficient (Kd) to be used in dose assessments for decommissioning the Zion Nuclear Power Plant

    SciTech Connect (OSTI)

    Sullivan, T.

    2014-09-24

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled. The remaining underground structures will contain low amounts of residual licensed radioactive material. An important component of the decommissioning process is the demonstration that any remaining activity will not cause a hypothetical individual to receive a dose in excess of 25 mrem/y as specified in 10CFR20 SubpartE.

  17. Recommended values for the distribution coefficient (Kd) to be used in dose assessments for decommissioning the Zion Nuclear Power Plant

    SciTech Connect (OSTI)

    Sullivan T.

    2014-06-09

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled. The remaining underground structures will contain low amounts of residual licensed radioactive material. An important component of the decommissioning process is the demonstration that any remaining activity will not cause a hypothetical individual to receive a dose in excess of 25 mrem/y as specified in 10CFR20 SubpartE.

  18. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes. Environmental Restoration Program

    SciTech Connect (OSTI)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

  19. Trip report: European Communities 1989 International Conference on Decommissioning of Nuclear Installations, Brussels, Belgium, October 24-27, 1989

    SciTech Connect (OSTI)

    Rankin, W.N.

    1989-01-01

    The European community is conducting research on the decommissioning of nuclear installations. The prime objective is to develop effective techniques to ensure the protection of man and his environment against the potential hazards of nuclear installations that have been shut down. The results of the 1979--1983 research program were presented in a conference held in Luxembourg. This program was primarily concerned with decommissioning nuclear power plants. The 1984--1988 program was extended to all types of nuclear installations. Fuel fabrication, enrichment and reprocessing plants, and research and development facilities having fulfilled their useful purposes are also awaiting decommissioning. This Program has produced numerous scientific and technical achievements. Great progress has in particular been achieved in the reduction of metal waste arising from decommissioning, due to advances in areas such as the development of aggressive decontamination procedures and of techniques for melting and recycling low-level radioactive waste metal.

  20. Decommissioning of the secondary containment of the steam generating heavy water reactor at UKAEA Winfrith

    SciTech Connect (OSTI)

    Miller, K.D.; Cornell, R.M.; Parkinson, S.J.; McIntyre, K.; Staples, A.

    2007-07-01

    The Winfrith SGHWR was a prototype nuclear power plant operated for 23 years by the United Kingdom Atomic Energy Authority (UKAEA) until 1990 when it was shut down permanently. The current Stage 1 decommissioning contract is part of a multi-stage strategy. It involves the removal of all the ancillary plant and equipment in the secondary containment and non-containment areas ahead of a series of contracts for the decommissioning of the primary containment, the reactor core and demolition of the building and ail remaining facilities. As an outcome of a competitive tending process, the Stage 1 decommissioning contract was awarded to NUKEM with operations commencing in April 2005. The decommissioning processes involved with these plant items will be described with some emphasis of the establishment of multiple work-fronts for the production, recovery, treatment and disposal of mainly tritium-contaminated waste arising from its contact with the direct cycle reactor coolant. The means of size reduction of a variety of large, heavy and complex items of plant made from a range of materials will also be described with some emphasis on the control of fumes during hot cutting operations and establishing effective containments within a larger secondary containment structure. Disposal of these wastes in a timely and cost-effective manner is a major challenge facing the decommissioning team and has required the development of a highly efficient means of packing the resultant materials into mainly one-third height IS0 containers for disposal as LLW. Details of the quantities of LLW and exempt wastes handled during this process will be given with a commentary about the difficulty in segregating these two waste streams efficiently. The paper sets out to demonstrate the considerable progress that has been made with these challenging decommissioning operations at the SGHWR plant and to highlight some of the techniques and processes that have contributed to the overall success of the process. The overall management and control of safety during ail aspects of this challenging contract are major features of the paper, greatly assisted by the adoption from the outset of a non-adversarial team working approach between client and contractor. This has greatly assisted in developing safe and cost-effective solutions to a number of problems that have arisen during the programme, demonstrating the worth of adopting this co-operative approach for mutual benefit. (authors)

  1. How To Apply

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

    CSCNSI How To Apply How to Apply for Computer System, Cluster, and Networking Summer Institute Emphasizes practical skills development Contact Leader Stephan Eidenbenz (505)...

  2. Two Approaches to Reactor Decommissioning: 10 CFR Part 50 License Termination and License Amendment, Lessons Learned from the Regulatory Perspective

    SciTech Connect (OSTI)

    Watson, B.A.; Buckley, J.T.; Craig, C.M.

    2006-07-01

    Trojan Nuclear Plant (Trojan) and Maine Yankee Nuclear Plant (Maine Yankee) were the first two power reactors to complete decommissioning under the U. S. Nuclear Regulatory Commission's (NRC's) License Termination Rule (LTR), 10 CFR Part 20, Subpart E. The respective owners' decisions to decommission the sites resulted in different approaches to both the physical aspects of the decommissioning, and the approach for obtaining approval for completing the decommissioning in accordance with regulations. Being in different States, the two single-unit pressurized water reactor sites had different State requirements and levels of public interest that impacted the decommissioning approaches. This resulted in significant differences in decommissioning planning, conduct of decommissioning operations, volumes of low- level radioactive waste disposed, and the final status survey (FSS) program. While both licensees have Independent Spent Fuel Storage Installations (ISFSIs), Trojan obtained a separate license for the ISFSI in accordance with the requirements of 10 CFR Part 72 and terminated their 10 CFR Part 50 license. Maine Yankee elected to obtain a general license under 10 CFR Part 50 for the ISFSI and reduce the physical site footprint to the ISFSI through a series of license amendments. While the NRC regulations are flexible and allow different approaches to ISFSI licensing there are separate licensing requirements that must be addressed. In 10 CFR 50.82, the NRC mandates public participation in the decommissioning process. For Maine Yankee, public input resulted in the licensee entering into an agreement with a concerned citizen group and resulted in State legislation that significantly lowered the dose limit below the NRC radiological criteria of 25 mrem (0.25 mSv) per year (yr) in 10 CFR 20.1402 for unrestricted use. The lowering of the radiological criteria resulted in a significant dose modeling effort using site-specific Derived Concentrations Guideline Levels (DCGLs) that were well below the NRC DCGL screening values. This contributed to a longer than anticipated period to obtain NRC approval of the Maine Yankee License Termination Plan (LTP). By employing the lessons learned from its first LTP submittal, which was not accepted by the NRC staff, Trojan was able to obtain approval of its revised LTP promptly. While both licensees provided final status survey reports (FSSRs) for NRC approval, the Trojan approach to decommissioning and data management allowed NRC to efficiently review FSS records and supporting documentation. Therefore, NRC was able to review Trojan's FSSR more efficiently than Maine Yankee's FSSR. This paper describes the regulatory impacts of the two different approaches to the decommissioning, the development of licensee required plans, decommissioning operations and records, the differences in licensing processes, and the lessons learned for improving the processes. (authors)

  3. Criticality Safety Lessons Learned in a Deactivation and Decommissioning Environment [A Guide for Facility and Project Managers

    SciTech Connect (OSTI)

    NIRIDER, L.T.

    2003-08-06

    This document was designed as a reference and a primer for facility and project managers responsible for Deactivation and Decommissioning (D&D) processes in facilities containing significant inventories of fissionable materials. The document contains lessons learned and guidance for the development and management of criticality safety programs. It also contains information gleaned from occurrence reports, assessment reports, facility operations and management, NDA program reviews, criticality safety experts, and criticality safety evaluations. This information is designed to assist in the planning process and operational activities. Sufficient details are provided to allow the reader to understand the events, the lessons learned, and how to apply the information to present or planned D&D processes. Information is also provided on general lessons learned including criticality safety evaluations and criticality safety program requirements during D&D activities. The document also explores recent and past criticality accidents in operating facilities, and it extracts lessons learned pertinent to D&D activities. A reference section is included to provide additional information. This document does not address D&D lessons learned that are not pertinent to criticality safety.

  4. Screening evaluation of radionuclide groundwater concentrations for the end state basement fill model Zion Nuclear Power Station decommissioning project

    SciTech Connect (OSTI)

    Sullivan T.

    2014-06-09

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled with clean material. The final selection of fill material has not been made.

  5. Web-based training related to NRC staff review of dose modeling aspects of license termination and decommissioning plans

    SciTech Connect (OSTI)

    LePoire, D.; Arnish, J.; Cheng, J.J.; Kamboj, S.; Richmond, P.; Chen, S.Y.; Barr, C.; McKenney, C.

    2007-07-01

    NRC licensees at decommissioning nuclear facilities submit License Termination Plans (LTP) or Decommissioning Plans (DP) to NRC for review and approval. To facilitate a uniform and consistent review of these plans, the NRC developed training for its staff. A live classroom course was first developed in 2005, which targeted specific aspects of the LTP and DP review process related to dose-based compliance demonstrations or modeling. A web-based training (WBT) course is being developed in 2006 to replace the classroom-based course. The advantage of the WBT is that it will allow for staff training or refreshers at any time, while the advantage of a classroom-based course is that it provides a forum for lively discussion and the sharing of experience of classroom participants. The training course consists of the core and advanced modules tailored to specific NRC job functions. Topics for individual modules include identifying the characteristics of simple and complex sites, identifying when outside expertise or consultation is needed, demonstrating how to conduct acceptance and technical reviews of dose modeling, and providing details regarding the level of justification needed for realistic scenarios for both dose modeling and derivation of DCGLs. Various methods of applying probabilistic uncertainty analysis to demonstrate compliance with dose-based requirements are presented. These approaches include 1) modeling the pathways of radiological exposure and estimating doses to receptors from a combination of contaminated media and radionuclides, and 2) using probabilistic analysis to determine an appropriate set of input parameters to develop derived concentration guideline limits or DCGLs (DCGLs are media- and nuclide-specific concentration limits that will meet dose-based, license termination rule criteria found in 10 CFR Part 20, Subpart E). Calculation of operational (field) DCGL's from media- and nuclide-specific DCGLs and use of operational DCGLs in conducting final status surveys are addressed in the WBT. Realistic case examples are presented and analyzed including the abstraction of a realistic site into a conceptual model and computer model. A case history is also used to demonstrate development of NRC review documents such as requests for additional information (RAIs). To enhance the web-based training experience, audio, animations, linked documents, quizzes, and scripts are being integrated with a commercial web-based training package that supports simple navigation. The course is also being integrated into both existing and state-of-the-art learning management systems. A testing group is being utilized to identify and help resolve training issues prior to deployment of the course. When completed, the course can be accessed for credited training with required modules dependent on the job category of the training participant. The modules will also be accessible to NRC staff for review or refresher following initial course completion. WBT promotes consistency in reviews and has the advantage of being able to be used as a resource to staff at any time. The WBT will provide reviewers with knowledge needed to perform risk-informed analyses (e.g., information related to development of realistic scenarios and use of probabilistic analysis). WBT on review of LTP or DP dose modeling will promote staff development, efficiency, and effectiveness in performing risk-informed, performance-based reviews of decommissioning activities at NRC-licensed facilities. (authors)

  6. Web-based training related to NRC staff review of dose modeling aspects of license termination and decommissioning plans.

    SciTech Connect (OSTI)

    LePoire, D.; Arnish, J.; Cheng, J. J.; Kamboj, S.; Richmond, P.; Chen, S. Y.; Barr, C.; McKenney, C.; Environmental Science Division; NRC

    2007-01-01

    NRC licensees at decommissioning nuclear facilities submit License Termination Plans (LTP) or Decommissioning Plans (DP) to NRC for review and approval. To facilitate a uniform and consistent review of these plans, the NRC developed training for its staff. A live classroom course was first developed in 2005, which targeted specific aspects of the LTP and DP review process related to dose-based compliance demonstrations or modeling. A web-based training (WBT) course is being developed in 2006 to replace the classroom-based course. The advantage of the WBT is that it will allow for staff training or refreshers at any time, while the advantage of a classroom-based course is that it provides a forum for lively discussion and the sharing of experience of classroom participants. The training course consists of the core and advanced modules tailored to specific NRC job functions. Topics for individual modules include identifying the characteristics of simple and complex sites, identifying when outside expertise or consultation is needed, demonstrating how to conduct acceptance and technical reviews of dose modeling, and providing details regarding the level of justification needed for realistic scenarios for both dose modeling and derivation of DCGLs. Various methods of applying probabilistic uncertainty analysis to demonstrate compliance with dose-based requirements are presented. These approaches include: (1) modeling the pathways of radiological exposure and estimating doses to receptors from a combination of contaminated media and radionuclides, and (2) using probabilistic analysis to determine an appropriate set of input parameters to develop derived concentration guideline limits or DCGLs (DCGLs are media- and nuclide-specific concentration limits that will meet dose-based, license termination rule criteria found in 10 CFR Part 20, Subpart E). Calculation of operational (field) DCGL's from media- and nuclide-specific DCGLs and use of operational DCGLs in conducting final status surveys are addressed in the WBT. Realistic case examples are presented and analyzed including the abstraction of a realistic site into a conceptual model and computer model. A case history is also used to demonstrate development of NRC review documents such as requests for additional information (RAIs). To enhance the web-based training experience, audio, animations, linked documents, quizzes, and scripts are being integrated with a commercial web-based training package that supports simple navigation. The course is also being integrated into both existing and state-of-the-art learning management systems. A testing group is being utilized to identify and help resolve training issues prior to deployment of the course. When completed, the course can be accessed for credited training with required modules dependent on the job category of the training participant. The modules will also be accessible to NRC staff for review or refresher following initial course completion. WBT promotes consistency in reviews and has the advantage of being able to be used as a resource to staff at any time. The WBT provides reviewers with knowledge needed to perform risk-informed analyses (e.g., information related to development of realistic scenarios and use of probabilistic analysis). WBT on review of LTP or DP dose modeling promotes staff development, efficiency, and effectiveness in performing risk-informed, performance-based reviews of decommissioning activities at NRC-licensed facilities.

  7. Environmental Assessment for decommissioning the Strategic Petroleum Reserve Weeks Island Facility, Iberia Parish, Louisiana

    SciTech Connect (OSTI)

    1995-12-01

    The Strategic Petroleum Reserve (SPR) Weeks Island site is one of five underground salt dome crude oils storage facilities operated by the Department of Energy (DOE). It is located in Iberia Parish, Louisiana. The purpose of the proposed action is to decommission the Weeks Island crude oil storage after the oil inventory has been transferred to other SPR facilities. Water intrusion into the salt dome storage chambers and the development of two sinkholes located near the aboveground facilities has created uncertain geophysical conditions. This Environmental Assessment describes the proposed decommissioning operation, its alternatives, and potential environmental impacts. Based on this analyses, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) and has issued the Finding of No Significant Impact (FONSI).

  8. Challenges with Final Status Surveys at a Large Decommissioning Site - 13417

    SciTech Connect (OSTI)

    Downey, Heath; Collopy, Peter; Shephard, Eugene; Walter, Nelson; Conant, John

    2013-07-01

    As part of decommissioning a former nuclear fuel manufacturing site, one of the crucial final steps is to conduct Final Status Surveys (FSS) in order to demonstrate compliance with the release criteria. At this decommissioning site, the area for FSS was about 100 hectares (248 acres) and included varying terrain, wooded areas, ponds, excavations, buildings and a brook. The challenges in performing the FSS included determining location, identifying FSS units, logging gamma walkover survey data, determining sample locations, managing water in excavations, and diverting water in the brook. The approaches taken to overcome these challenges will be presented in the paper. The paper will present and discuss lessons learned that will aid others in the FSS process. (authors)

  9. Interim Status of the Accelerated Site Technology Deployment Integrated Decontamination and Decommissioning Project

    SciTech Connect (OSTI)

    A. M Smith; G. E. Matthern; R. H. Meservey

    1998-11-01

    The Idaho National Engineering and Environmental Laboratory (INEEL), Fernald Environmental Management Project (FEMP), and Argonne National Laboratory - East (ANL-E) teamed to establish the Accelerated Site Technology Deployment (ASTD) Integrated Decontamination and Decommissioning (ID&D) project to increase the use of improved technologies in D&D operations. The project is making the technologies more readily available, providing training, putting the technologies to use, and spreading information about improved performance. The improved technologies are expected to reduce cost, schedule, radiation exposure, or waste volume over currently used baseline methods. They include some of the most successful technologies proven in the large-scale demonstrations and in private industry. The selected technologies are the Pipe Explorer, the GammaCam, the Decontamination Decommissioning and Remediation Optimal Planning System (DDROPS), the BROKK Demolition Robot, the Personal Ice Cooling System (PICS), the Oxy-Gasoline Torch, the Track-Mounted Shear, and the Hand-Held Shear.

  10. Applied Research Center

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

    ARC Privacy and Security Notice Skip over navigation Search the JLab Site Applied Research Center Please upgrade your browser. This site's design is only visible in a graphical browser that supports web standards, but its content is accessible to any browser. Concerns? Applied Research Center ARC Home Consortium News EH&S Reports print version ARC Resources Commercial Tenants ARC Brochure Library Conference Room Applied Research Center Applied Research Center front view Applied Research

  11. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text

    SciTech Connect (OSTI)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

  12. Nuclear facility decommissioning and site remedial actions. Volume 1. A selected bibliography

    SciTech Connect (OSTI)

    Faust, R.A.; Fore, C.S.; Knox, N.P.

    1980-09-01

    This bibliography of 633 references represents the first in a series to be produced by the Remedial Actions Program Information Center (RAPIC) containing scientific, technical, economic, and regulatory information concerning the decommissioning of nuclear facilities. Major chapters selected for this bibliography are Facility Decommissioning, Uranium Mill Tailings Cleanup, Contaminated Site Restoration, and Criteria and Standards. The references within each chapter are arranged alphabetically by leading author, corporate affiliation, or title of the document. When the author is not given, the corporate affiliation appears first. If these two levels of authorship are not given, the title of the document is used as the identifying level. Indexes are provided for (1) author(s), (2) keywords, (3) title, (4) technology development, and (5) publication description. An appendix of 123 entries lists recently acquired references relevant to decommissioning of nuclear facilities. These references are also arranged according to one of the four subject categories and followed by author, title, and publication description indexes. The bibliography was compiled from a specialized data base established and maintained by RAPIC to provide information support for the Department of Energy's Remedial Actions Program, under the cosponsorship of its three major components: Surplus Facilities Management Program, Uranium Mill Tailings Remedial Actions Program, and Formerly Utilized Sites Remedial Actions Program. RAPIC is part of the Ecological Sciences Information Center within the Information Center Complex at Oak Ridge National Laboratory.

  13. Lessons Learned Following the Successful Decommissioning of a Reaction Vessel Containing Lime Sludge and Technetium-99

    SciTech Connect (OSTI)

    Dawson, P. M.; Watson, D. D.; Hylko, J. M.

    2002-02-25

    This paper documents how WESKEM, LLC utilized available source term information, integrated safety management, and associated project controls to safely decommission a reaction vessel and repackage sludge containing various Resource Conservation and Recovery Act constituents and technetium-99 (Tc-99). The decommissioning activities were segmented into five separate stages, allowing the project team to control work related decisions based on their knowledge, experience, expertise, and field observations. The information and experience gained from each previous stage and rehearsals contributed to modifying subsequent entries, further emphasizing the importance of developing hold points and incorporating lessons learned. The hold points and lessons learned, such as performing detailed personal protective equipment (PPE) inspections during sizing and repackaging operations, and using foam-type piping insulation to prevent workers from cutting or puncturing their PPE on sharp edge s or small shards generated during sizing operations, minimized direct contact with the Tc-99. To prevent the spread of contamination, the decommissioning activities were performed inside a containment enclosure connected to negative air machines. After performing over 235 individual entries totaling over 285 project hours, only one first aid was recorded during this five-stage project.

  14. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12. Environmental Restoration Program

    SciTech Connect (OSTI)

    Not Available

    1991-09-01

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

  15. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12

    SciTech Connect (OSTI)

    Owen, P. T.; Webb, J. R.; Knox, N. P.; Goins, L. F.; Harrell, R. E.; Mallory, P. K.; Cravens, C. D.

    1991-09-01

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

  16. ENVIRONMENTAL PROBLEMS ASSOCIATED WITH DECOMMISSIONING THE CHERNOBYL NUCLEAR POWER PLANT COOLING POND

    SciTech Connect (OSTI)

    Farfan, E.

    2009-09-30

    Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.

  17. Environmental Problems Associated With Decommissioning The Chernobyl Nuclear Power Plant Cooling Pond

    SciTech Connect (OSTI)

    Farfan, E. B.; Jannik, G. T.; Marra, J. C.; Oskolkov, B. Ya.; Bondarkov, M. D.; Gaschak, S. P.; Maksymenko, A. M.; Maksymenko, V. M.; Martynenko, V. I.

    2009-11-09

    Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.

  18. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 1. Main report. Technical report, September 1977-October 1979

    SciTech Connect (OSTI)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE.

  19. Joint US/Russian study on the development of a decommissioning strategy plan for RBMK-1000 unit No. 1 at the Leningrad Nuclear Power Plant

    SciTech Connect (OSTI)

    1997-12-01

    The objective of this joint U.S./Russian study was to develop a safe, technically feasible, economically acceptable strategy for decommissioning Leningrad Nuclear Power Plant (LNPP) Unit No. 1 as a representative first-generation RBMK-1000 reactor. The ultimate goal in developing the decommissioning strategy was to select the most suitable decommissioning alternative and end state, taking into account the socioeconomic conditions, the regulatory environment, and decommissioning experience in Russia. This study was performed by a group of Russian and American experts led by Kurchatov Institute for the Russian efforts and by the Pacific Northwest National Laboratory for the U.S. efforts and for the overall project.

  20. Groundwater Monitoring and Control Before Decommissioning of the Research Reactor VVR-S from Magurele-Bucharest

    SciTech Connect (OSTI)

    Dragusin, Mitica

    2008-01-15

    The research reactor type VVR-S (tank type, water is cooler, moderator and reflector, thermal power- 2 MW, thermal energy- 9. 52 GW d) was put into service in July 1957 and, in December 1997 was shout down. In 2002, Romanian Government decided to put the research reactor in the permanent shut-down in order to start the decommissioning. This nuclear facility was used in nuclear research and radioisotope production for 40 years, without events, incidents or accidents. Within the same site, in the immediate vicinity of the research reactor, there are many other nuclear facilities: Radioactive Waste Treatment Plant, Tandem Van der Graaf heavy ions accelerator, Cyclotron, Industrial Irradiator, Radioisotope Production Center. The objectives of this work were dedicated on the water underground analyses described in the following context: - presentation of the approaches in planning the number of drillings, vertical soil profiles (characteristics, analyses, direction of the flow of underground water, uncertainties in measurements); - presentation of the instrumentation used in analyses of water, soil and vegetation samples - analyses and final conclusions on results of the measurements; - comparison of the results of measurements on underground water from drillings with the measurements results on samples from the town and the system of drinking water - supplied from the second level of underground water. According to the analysis, in general, no values higher than the Minimum Detectable Activity were detected in water samples (MDA) for Pb{sup 212}, Bi{sup 214}, Pb{sup 214}, Ac{sup 228}, but situated under values foreseen in drinking water. Distribution of Uranium As results of the Uranium determination, values higher than 0,004 mg/l (4 ppb) were detected, values that represent the average contents in the underground water. The higher values, 2-3 times higher than background, were detected in the water from the drillings F15, F12, F5, F13, drillings located between RWTP (Radioactive Waste Treatment Plant) - the 300 m{sup 3} tanks and the Spent Filters Storage (SFS). At south of this area, on the leaking direction of the underground water layer, in the drillings F1, F2, F3, F18 and at east, in F6, F7, the natural Uranium values are within the background for the underground-water. Distribution of Radon For the Radon determination with RAD 7 equipment, water samples were taken from the same piezo-metrical drilling, 2 or 4 times during of six months period, and then, the average contents were calculated, which varied between 0,35 - 2,1 Bq/l. The values higher than 1,1 -1,2 Bq/l were detected in the water taken from the drillings located in the northern part (F10, F11) and in the eastern part (F6, F8) of the Institute fences (around of the radioactive waste storage facilities). The concentrations of 0,3 - 0,5 Bq/l are in the underground-water layer 'intercepted' by the piezo-metrical drillings (F1, F2, F3) located near the Nuclear Reactor. Concentration of heavy metals: 0.04-0.08 mg/l Pb in F5, F14, F7, F8 exceeding MCA-Maximum Admissible Concentration (0.01 mg/l) for Pb, and for Zn in F5, F7, F8, F14 are 0.2-0.5 mg/l situated under MCA , and 0.18 mg/l in F18, in accordance with tendency of decreasing of concentration of contaminants. After 50 years of deploying nuclear activities on the site the underground water quality is in very good condition. Taking into consideration the direction of the underground water flow, it results that, only in the area of underground pipe, around of the research reactor and radioactive waste treatment plant, the quality of water is influenced, and remediation actions are not necessary. Based on measurements executed in F18, the water quality is the same with any other part of the region. During the decommissioning of the Research Reactor, the samples from 18 drillings will be analysed monthly, and the contents of the heavy metals, Pb and Zn, will be monitored carefully, together with all the factors: air, soil, vegetation, subsoil, water surface and underground water. A great attention will be paid to the dismantlement of the underground structures, the 30 m{sup 3} tank, that collects all the liquid radioactive waste from the reactor, the pipes that connects this tank to the other two 300 m{sup 3} tanks, from RWTP, the ventilation ducts between the Spent Filters Storage and reactor's stack, in order to prevent contamination of surface and underground water. Engineering Absorbent Barriers will be used both for hydrophilic substances and for hydrophobic substances, tents will be used for preventing the spread of possible contaminants from the pipes and tanks, owing to the precipitation or wind, and the tanks and pipes will be drained to eliminate the spills. Since we are dealing with a multinuclear facility site, the on site and off site Monitoring Program of Institute will be properly upgraded, taking into account the values of the derived emission limit approved by Regulatory Body, before, during and after the completion of the works with impact on underground water. In another work will be presented radiological map of land associated of decommissioning project (on surface, at 0.15 m and 0.30 m in depth of soil) and estimation of migration rate in soil up to ground water level. Applying these measures, taking account of the radiological status at the beginning of the project, will mean savings and a good protection of the environment in completing the decommissioning project.

  1. Innovative Decontamination Technology for Use in Gaseous Diffusion Plant Decommissioning

    SciTech Connect (OSTI)

    Peters, M.J.; Norton, C.J.; Fraikor, G.B.; Potter, G.L.; Chang, K.C.

    2006-07-01

    The results of bench scale tests demonstrated that TechXtract{sup R} RadPro{sup TM} technology (hereinafter referred to as RadPro{sup R}) can provide 100% coverage of complex mockup gaseous diffusion plant (GDP) equipment and can decontaminate uranium (U) deposits with 98% to 99.99% efficiency. Deployment tests demonstrated RadPro{sup R} can be applied as foam, mist/fog, or steam, and fully cover the internal surfaces of complex mockup equipment, including large piping. Decontamination tests demonstrated that two formulations of RadPro{sup R}, one with neutron attenuators and one without neutron attenuators, could remove up to 99.99% of uranyl fluoride deposits, one of the most difficult to remove deposits in GDP equipment. These results were supplemented by results from previous tests conducted in 1994 that showed RadPro{sup R} could remove >97% of U and Tc-99 contamination from actual GDP components. Operational use of RadPro{sup R} at other DOE and commercial facilities also support these data. (authors)

  2. Applied & Computational Math

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

    & Computational Math - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us ... Twitter Google + Vimeo GovDelivery SlideShare Applied & Computational Math HomeEnergy ...

  3. Applied Math & Software

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

    Math & Software - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us ... Twitter Google + Vimeo GovDelivery SlideShare Applied Math & Software HomeTransportation ...

  4. Applied Energy Programs

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

    (DoD) programs at Los Alamos, and to industry through the Laboratory's Technology Transfer Division. The Applied Energy programs encompass the broad set of energy focus areas:...

  5. Revised analyses of decommissioning for the reference pressurized Water Reactor Power Station. Volume 2, Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure: Appendices, Final report

    SciTech Connect (OSTI)

    Konzek, G.J.; Smith, R.I.; Bierschbach, M.C.; McDuffie, P.N.

    1995-11-01

    With the issuance of the final Decommissioning Rule (July 27, 1998), owners and operators of licensed nuclear power plants are required to prepare, and submit to the US Nuclear Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. The NRC staff is in need of bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to provide some of the needed bases documentation. This report contains the results of a review and reevaluation of the 1978 PNL decommissioning study of the Trojan nuclear power plant (NUREG/CR-0130), including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the nuclear power plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5--7 year period during which time the spent fuel is stored in the spent fuel pool, prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clean structures on the site and to restore the site to a ``green field`` condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities.

  6. Characterization of the Hanford 300 area burial grounds. Final report: decontamination and decommissioning

    SciTech Connect (OSTI)

    Phillips, S.J.; Ames, L.L.; Fitzner, R.E.; Gee, G.W.; Sandness, G.A.; Simmons, C.S.

    1980-01-01

    Pacific Northwest Laboratory conducted a series of investigations at the Hanford Site to develop technologies for characterizing and monitoring radioactive waste burial facilities that could be used in determining appropriate decommissioning alternatives. Specific objectives were to develop unique functional geophysics, geochemical, soil physics, numerical modeling, and biological methodologies needed to better characterize and monitor buried radioactive waste disposal sites. To meet these objectives the project was divided into four tasks: Task I, Geophysical Evaluation - Geophysical surveys were taken to locate and define the gross composition of waste materials. Task II, Geochemical Analysis - The interaction of disposed radionuclides with geologic media was analyzed through an integrated radiochemical procedure. Task III, Fluid Transport and Modeling - Computer modeling of water migration in partially saturated groundwater systems was verified with actual data collected at a field test facility used to monitor micrometeorological and geohydrological energy and mass transfer factors. Task IV, Biological Transport - Several biological organisms were evaluated for potential radionuclide uptake and transport. Along with the four tasks, the project included a review of pertinent literature and regulatory issues that might affect the alternatives selected. Surveys were taken of the surrounding area and specific sites and operations. The overall results indicated that the 300 Area Burial Grounds have been adequate in containing radioactive waste. Based on the results of the project, the alternatives identified for decommissioning these sites are exhumation and translocation, entombment, perpetual care, and abandonment. Perpetual care (currently used) appears to be the best decommissioning alternative for these burial grounds at this time. However, another alternative may be selected depending on future waste management policies, plans, or activities.

  7. Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron Activated Shield Wall

    SciTech Connect (OSTI)

    Michael R. Kruzic

    2007-09-16

    Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility was used in the early to mid-1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles in the immediate area. Identified as Corrective Action Unit 115, the TCA facility was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the ''Federal Facility Agreement and Consent Order''. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously provided technical decisions are made by an experienced decision maker within the site conceptual site model, identified in the Data Quality Objective process. Facility closure involved a seven-step decommissioning strategy. Key lessons learned from the project included: (1) Targeted preliminary investigation activities provided a more solid technical approach, reduced surprises and scope creep, and made the working environment safer for the D&D worker. (2) Early identification of risks and uncertainties provided opportunities for risk management and mitigation planning to address challenges and unanticipated conditions. (3) Team reviews provided an excellent mechanism to consider all aspects of the task, integrated safety into activity performance, increase team unity and ''buy-in'' and promoted innovative and time saving ideas. (4) Development of CED protocols ensured safety and control. (5) The same proven D&D strategy is now being employed on the larger ''sister'' facility, Test Cell C.

  8. Office of Environmental Management Uranium Enrichment Decontamination and Decommissioning Fund financial statements, September 30, 1995 and 1994

    SciTech Connect (OSTI)

    1996-02-21

    The Energy Policy Act of 1992 (Act) requires the Department of Energy to retain ownership and responsibility for the costs of environmental cleanup resulting from the Government`s operation of the three gaseous diffusion facilities located at the K-25 site in Oak Ridge, Tennessee; Paducah, Kentucky; and Portsmouth, Ohio. The Act transferred the uranium enrichment enterprise to the United States Enrichment Corporation (USEC) as of July 1, 1993, and established the Uranium Enrichment Decontamination and Decommissioning Fund (D&D Fund) to: Pay for the costs of decontamination and decommissioning at the diffusion facilities; pay the annual costs for remedial action at the diffusion facilities to the extent that the amount in the Fund is sufficient; and reimburse uranium/thorium licensees for the costs of decontamination, decommissioning, reclamation, and other remedial actions which are incident to sales to the Government.

  9. Office of Environmental Management uranium enrichment decontamination and decommissioning fund financial statements. September 30, 1994 and 1993

    SciTech Connect (OSTI)

    Marwick, P.

    1994-12-15

    The Energy Policy Act of 1992 (Act) transferred the uranium enrichment enterprise to the United States Enrichment Corporation as of July 1, 1993. However, the Act requires the Department of Energy to retain ownership and responsibility for the costs of environmental cleanup resulting from the Government`s operation of the three gaseous diffusion facilities located in Oak Ridge, Tennessee; Paducah, Kentucky; and Portsmouth, Ohio (diffusion facilities). The Act established the Uranium Enrichment Decontamination and Decommissioning Fund (D&D Fund) to: Pay for the costs of decontamination and decommissioning at the diffusion facilities; Pay the annual costs for remedial action at the diffusion facilities to the extent that the amount in the Fund is sufficient; and Reimburse uranium/thorium licensees for the costs of decontamination, decommissioning, reclamation, and other remedial actions which are incident to sales to the Government.

  10. Technology, Safety and Costs of Decommissioning a Reference Low-Level Waste Burial Ground. Appendices

    SciTech Connect (OSTI)

    1980-06-01

    Safety and cost information are developed for the conceptual decommissioning of commercial low-level waste (LLW) burial grounds. Two generic burial grounds, one located on an arid western site and the other located on a humid eastern site, are used as reference facilities for the study. The two burial grounds are assumed to have the same site capacity for waste, the same radioactive waste inventory, and similar trench characteristics and operating procedures. The climate, geology. and hydrology of the two sites are chosen to be typical of real western and eastern sites. Volume 2 (Appendices) contains the detailed analyses and data needed to support the results given in Volume 1.

  11. Technology, Safety and Costs of Decommissioning a Reference Low-Level Waste Burial Ground. Main Report

    SciTech Connect (OSTI)

    Murphy, E. S.; Holter, G. M.

    1980-06-01

    Safety and cost information are developed for the conceptual decommissioning of commercial low-level waste (LLW) burial grounds. Two generic burial grounds, one located on an arid western site and the other located on a humid eastern site, are used as reference facilities for the study. The two burial grounds are assumed to have the same site capacity for waste, the same radioactive waste inventory, and similar trench characteristics and operating procedures. The climate, geology. and hydrology of the two sites are chosen to be typical of real western and eastern sites. Volume 1 (Main Report) contains background information and study results in summary form.

  12. Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron-Activated Shield Wall

    SciTech Connect (OSTI)

    Michael R. Kruzic

    2008-06-01

    Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility (Figure 1) was used in the early to mid-1960s for testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles. The TCA facility, known as Corrective Action Unit 115, was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the Federal Facility Agreement and Consent Order. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously, provided technical decisions are made by an experienced decision maker within the site conceptual site model. Facility closure involved a seven-step decommissioning strategy. First, preliminary investigation activities were performed, including review of process knowledge documentation, targeted facility radiological and hazardous material surveys, concrete core drilling and analysis, shield wall radiological characterization, and discrete sampling, which proved to be very useful and cost-effective in subsequent decommissioning planning and execution and worker safety. Second, site setup and mobilization of equipment and personnel were completed. Third, early removal of hazardous materials, including asbestos, lead, cadmium, and oil, was performed ensuring worker safety during more invasive demolition activities. Process piping was to be verified void of contents. Electrical systems were de-energized and other systems were rendered free of residual energy. Fourth, areas of high radiological contamination were decontaminated using multiple methods. Contamination levels varied across the facility. Fixed beta/gamma contamination levels ranged up to 2 million disintegrations per minute (dpm)/100 centimeters squared (cm2) beta/gamma. Removable beta/gamma contamination levels seldom exceeded 1,000 dpm/100 cm2, but, in railroad trenches on the reactor pad containing soil on the concrete pad in front of the shield wall, the beta dose rates ranged up to 120 milli-roentgens per hour from radioactivity entrained in the soil. General area dose rates were less than 100 micro-roentgens per hour. Prior to demolition of the reactor shield wall, removable and fixed contaminated surfaces were decontaminated to the best extent possible, using traditional decontamination methods. Fifth, large sections of the remaining structures were demolished by mechanical and open-air controlled explosive demolition (CED). Mechanical demolition methods included the use of conventional demolition equipment for removal of three main buildings, an exhaust stack, and a mobile shed. The 5-foot (ft), 5-inch (in.) thick, neutron-activated reinforced concrete shield was demolished by CED, which had never been performed at the NTS.

  13. SAVANNAH RIVER SITE R-REACTOR DISASSEMBLY BASIN IN-SITU DECOMMISSIONING -10499

    SciTech Connect (OSTI)

    Langton, C.; Serrato, M.; Blankenship, J.; Griffin, W.

    2010-01-04

    The US DOE concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate intact, structurally sound facilities that are no longer needed for their original purpose, i.e., generating (reactor facilities), processing(isotope separation facilities) or storing radioactive materials. The 105-R Disassembly Basin is the first SRS reactor facility to undergo the in-situ decommissioning (ISD) process. This ISD process complies with the 105-R Disassembly Basin project strategy as outlined in the Engineering Evaluation/Cost Analysis for the Grouting of the R-Reactor Disassembly Basin at the Savannah River Site and includes: (1) Managing residual water by solidification in-place or evaporation at another facility; (2) Filling the below grade portion of the basin with cementitious materials to physically stabilize the basin and prevent collapse of the final cap - Sludge and debris in the bottom few feet of the basin will be encapsulated between the basin floor and overlying fill material to isolate it from the environment; (3) Demolishing the above grade portion of the structure and relocating the resulting debris to another location or disposing of the debris in-place; and (4) Capping the basin area with a concrete slab which is part of an engineered cap to prevent inadvertent intrusion. The estimated total grout volume to fill the 105-R Reactor Disassembly Basin is 24,384 cubic meters or 31,894 cubic yards. Portland cement-based structural fill materials were designed and tested for the reactor ISD project, and a placement strategy for stabilizing the basin was developed. Based on structural engineering analyses and material flow considerations, maximum lift heights and differential height requirements were determined. Pertinent data and information related to the SRS 105-R Reactor Disassembly Basin in-situ decommissioning include: regulatory documentation, residual water management, area preparation activities, technology needs, fill material designs and testing, and fill placement strategy. This information is applicable to decommissioning both the 105-P and 105-R facilities. The ISD process for the entire 105-P and 105-R reactor facilities will require approximately 250,000 cubic yards (191,140 cubic meters) of grout and approximately 3,900 cubic yards (2,989 cubic meters) of structural concrete which will be placed over about an eighteen month period to meet the accelerated schedule ISD schedule. The status and lessons learned in the SRS Reactor Facility ISD process will be described.

  14. Industrial Hygiene Concerns during the Decontamination and Decommissioning of the Tokamak Fusion Test Reactor

    SciTech Connect (OSTI)

    M.E. Lumia; C.A. Gentile

    2002-01-18

    A significant industrial hygiene concern during the Decontamination and Decommissioning (D and D) of the Tokamak Fusion Test Reactor (TFTR) was the oxidation of the lead bricks' surface, which were utilized for radiation shielding. This presented both airborne exposure and surface contamination issues for the workers in the field removing this material. This paper will detail the various protection and control methods tested and implemented to protect the workers, including those technologies deployed to decontaminate the work surfaces. In addition, those techniques employed to recycle the lead for additional use at the site will be discussed.

  15. REVIEW OF INDUSTRIES AND GOVERNMENT AGENCIES FOR TECHNOLOGIES APPLICABLE TO DEACTIVATION AND DECOMMISSIONING OF NUCLEAR WEAPONS FACILITIES

    SciTech Connect (OSTI)

    Reilkoff, T. E.; Hetland, M. D.; O'Leary, E. M.

    2002-02-25

    The Deactivation and Decommissioning Focus Area's (DDFA's) mission is to develop, demonstrate, and deploy improved deactivation and decommissioning (D&D) technologies. This mission requires that emphasis be continually placed on identifying technologies currently employed or under development in other nuclear as well as nonnuclear industries and government agencies. In support of DDFA efforts to clean up the U.S. Department of Energy's (DOE's) radiologically contaminated surplus facilities using technologies that improve worker safety, reduce costs, and accelerate cleanup schedules, a study was conducted to identify innovative technologies developed for use in nonnuclear arenas that are appropriate for D&D applications.

  16. Applied Science/Techniques

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

    Applied ScienceTechniques Print The ALS is an excellent incubator of new scientific techniques and instrumentation. Many of the technical advances that make the ALS a world-class...

  17. Nuclear facility decommissioning and site remedial actions: A selected bibliography: Volume 8

    SciTech Connect (OSTI)

    Owen, P.T.; Michelson, D.C.; Knox, N.P.

    1987-09-01

    The 553 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eighth in a series of reports. Foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of energy's remedial action program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Facilities Contaminated with Naturally Occurring Radionuclides, Uranium Mill Tailings Remedial Action Program, Uranium Mill Tailings Management, Technical Measurements Center, and General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. The appendix contains a list of frequently used acronyms and abbreviations.

  18. Comments received on proposed rule on radiological criteria for decommissioning and related documents

    SciTech Connect (OSTI)

    Page, G.; Caplin, J.; Smith, D.

    1996-03-01

    The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for the decommissioning of NRC-licensed facilities. As a part of this action, the Commission published in the Federal Register (59 FR 43200), on August 22, 1994, a proposed rule on radiological criteria for decommissioning, soliciting comments both on the rule as proposed and on certain specific items as identified in its supplementary statement of considerations. A draft Generic Environmental Impact Statement (GEIS) in support of the rule, also published in August 1994 as NUREG-1496, along with its Appendix A (NUREG-1501), were also made available for comment. A staff working draft on regulatory guidance (NUREG-1500)was also made available. This report summarizes the 1,309 comments on the proposed rule and supplementary items and the 311 comments on the GEIS as excerpted from 101 docketed letters received associated in the Federal/Register notice. Comments from two NRC/Agreement-States meetings are also summarized.

  19. Decontamination and decommissioning of the Kerr-McGee Cimarron Plutonium Fuel Plant

    SciTech Connect (OSTI)

    Not Available

    1994-05-01

    This final report is a summary of the events that completes the decontamination and decommissioning of the Cimarron Corporation`s Mixed Oxides Fuel Plant (formally Sequoyah Fuels Corporation and formerly Kerr-McGee Nuclear Corporation - all three wholly owned subsidiaries of the Kerr-McGee Corporation). Included are details dealing with tooling and procedures for performing the unique tasks of disassembly decontamination and/or disposal. That material which could not be economically decontaminated was volume reduced by disassembly and/or compacted for disposal. The contaminated waste cleaning solutions were processed through filtration and ion exchange for release or solidified with cement for L.S.A. waste disposal. The L.S.A. waste was compacted, and stabilized as required in drums for burial in an approved burial facility. T.R.U. waste packaging and shipping was completed by the end of July 1987. This material was shipped to the Hanford, Washington site for disposal. The personnel protection and monitoring measures and procedures are discussed along with the results of exposure data of operating personnel. The shipping containers for both T.R.U. and L.S.A. waste are described. The results of the decommissioning operations are reported in six reports. The personnel protection and monitoring measures and procedures are contained and discussed along with the results of exposure data of operating personnel in this final report.

  20. Characterization of decontamination and decommissioning wastes expected from the major processing facilities in the 200 Areas

    SciTech Connect (OSTI)

    Amato, L.C.; Franklin, J.D.; Hyre, R.A.; Lowy, R.M.; Millar, J.S.; Pottmeyer, J.A.; Duncan, D.R.

    1994-08-01

    This study was intended to characterize and estimate the amounts of equipment and other materials that are candidates for removal and subsequent processing in a solid waste facility when the major processing and handling facilities in the 200 Areas of the Hanford Site are decontaminated and decommissioned. The facilities in this study were selected based on processing history and on the magnitude of the estimated decommissioning cost cited in the Surplus Facilities Program Plan; Fiscal Year 1993 (Winship and Hughes 1992). The facilities chosen for this study include B Plant (221-B), T Plant (221-T), U Plant (221-U), the Uranium Trioxide (UO{sub 3}) Plant (224-U and 224-UA), the Reduction Oxidation (REDOX) or S Plant (202-S), the Plutonium Concentration Facility for B Plant (224-B), and the Concentration Facility for the Plutonium Finishing Plant (PFP) and REDOX (233-S). This information is required to support planning activities for current and future solid waste treatment, storage, and disposal operations and facilities.

  1. Summary of comments received from workshops on radiological criteria for decommissioning

    SciTech Connect (OSTI)

    Caplin, J.; Page, G.; Smith, D.; Wiblin, C.

    1994-01-01

    The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for site cleanup and decommissioning of NRC-licensed facilities. Open public meetings were held during 1993 in Chicago, IL, San Francisco, CA, Boston, MA, Dallas, TX, Philadelphia, PA, Atlanta, GA, and Washington, DC. Interested parties were invited to provide input on the rulemaking issues before the NRC staff develops a draft proposed rule. This report summarizes 3,635 comments categorized from transcripts of the seven workshops and 1,677 comments from 100 NRC docketed letters from individuals and organizations. No analysis or response to the comments is included. The comments reflect a broad spectrum of viewpoints on the issues related to radiological criteria for site cleanup and decommissioning. The NRC also held public meetings on the scope of the Generic Environmental Impact Statement (GEIS) during July 1993. The GEIS meetings were held in Washington, DC., San Francisco, CA, Oklahoma City, OK, and Cleveland, OH. Related comments from these meetings were reviewed and comments which differed substantially from those from the workshops are also summarized in the body of the report. A summary of the comments from the GEIS scoping meetings is included as an Appendix.

  2. How To Apply

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

    How To Apply How to Apply for Computer System, Cluster, and Networking Summer Institute Emphasizes practical skills development Contacts Program Lead Carolyn Connor (505) 665-9891 Email Professional Staff Assistant Nickole Aguilar Garcia (505) 665-3048 Email The 2016 application process will commence January 5 through February 13, 2016. Applicants must be U.S. citizens. Required Materials Current resume Official university transcript (with Spring courses posted and/or a copy of Spring 2016

  3. Study on Evaluation of Project Management Data for Decommissioning of Uranium Refining and Conversion Plant - 12234

    SciTech Connect (OSTI)

    Usui, Hideo; Izumo, Sari; Tachibana, Mitsuo; Shibahara, Yuji; Morimoto, Yasuyuki; Tokuyasu, Takashi; Takahashi, Nobuo; Tanaka, Yoshio; Sugitsue, Noritake

    2012-07-01

    Some of nuclear facilities that would no longer be required have been decommissioned in JAEA (Japan Atomic Energy Agency). A lot of nuclear facilities have to be decommissioned in JAEA in near future. To implement decommissioning of nuclear facilities, it was important to make a rational decommissioning plan. Therefore, project management data evaluation system for dismantling activities (PRODIA code) has been developed, and will be useful for making a detailed decommissioning plan for an object facility. Dismantling of dry conversion facility in the uranium refining and conversion plant (URCP) at Ningyo-toge began in 2008. During dismantling activities, project management data such as manpower and amount of waste generation have been collected. Such collected project management data has been evaluated and used to establish a calculation formula to calculate manpower for dismantling equipment of chemical process and calculate manpower for using a green house (GH) which was a temporary structure for preventing the spread of contaminants during dismantling. In the calculation formula to calculate project management data related to dismantling of equipment, the relation of dismantling manpower to each piece of equipment was evaluated. Furthermore, the relation of dismantling manpower to each chemical process was evaluated. The results showed promise for evaluating dismantling manpower with respect to each chemical process. In the calculation formula to calculate project management data related to use of the GH, relations of GH installation manpower and removal manpower to GH footprint were evaluated. Furthermore, the calculation formula for secondary waste generation was established. In this study, project management data related to dismantling of equipment and use of the GH were evaluated and analyzed. The project management data, manpower for dismantling of equipment, manpower for installation and removal of GH, and secondary waste generation from GH were considered. Establishment of the calculation formula for dismantling of each kind of equipment makes it possible to evaluate manpower for dismantling the whole facility. However, it is not easy to prepare calculation formula for all kinds of equipment that exist in the facility. Therefore, a simpler evaluation method was considered to calculate manpower based on facility characteristics. The results showed promise for evaluating dismantling manpower with respect to each chemical process. For dismantling of contaminated equipment, a GH has been used for protection of the spread of contamination. The use of a GH increases manpower for installation and removal of GH etc. Moreover, structural materials of the GH such as plastic sheets, adhesive tape become a burnable secondary waste. To create an effective dismantling plan, it is necessary to carefully consider use of a GH preliminarily. Thus, an evaluation method of project management data such as manpower and secondary waste generation was considered. The results showed promise for evaluating project management data of GH by using established calculation formula. (authors)

  4. Web-Based Training on Reviewing Dose Modeling Aspects of NRC Decommissioning and License Termination Plans

    SciTech Connect (OSTI)

    LePoire, D.; Cheng, J.J.; Kamboj, S.; Arnish, J.; Richmond, P.; Chen, S.Y.; Barr, C.; McKenney, C.

    2008-01-15

    NRC licensees at decommissioning nuclear facilities submit License Termination Plans (LTP) or Decommissioning Plans (DP) to NRC for review and approval. To facilitate a uniform and consistent review of these plans, the NRC developed training for its staff. A live classroom course was first developed in 2005, which targeted specific aspects of the LTP and DP review process related to dose-based compliance demonstrations or modeling. A web-based training (WBT) course was developed in 2006 and 2007 to replace the classroom-based course. The advantage of the WBT is that it will allow for staff training or refreshers at any time, while the advantage of a classroom-based course is that it provides a forum for lively discussion and the sharing of experience of classroom participants. The objective of this course is to train NRC headquarters and regional office staff on how to review sections of a licensee's DP or LTP that pertain to dose modeling. The DP generally refers to the decommissioning of non-reactor facilities, while the LTP refers specifically to the decommissioning of reactors. This review is part of the NRC's licensing process, in which the NRC determines if a licensee has provided a suitable technical basis to support derived concentration guideline levels (DCGLs)1 or dose modeling analyses performed to demonstrate compliance with dose-based license termination rule criteria. This type of training is one component of an organizational management system. These systems 'use a range of practices to identify, create, represent, and distribute knowledge for reuse, awareness and learning'. This is especially important in an organization undergoing rapid change or staff turnover to retain organizational information and processes. NRC is committed to maintaining a dynamic program of training, development, and knowledge transfer to ensure that the NRC acquires and maintains the competencies needed to accomplish its mission. This paper discusses one specific project related to training, developing, and transferring knowledge to NRC staff on how to review dose-modeling portions of licensee-submitted DPs and LTPs. This project identified specific cases and examples, created easily updateable educational modules, represented material in an engaging format through animations, video, and graphics, and distributed information on how to perform these reviews in an accessible, web-based format. WBT promotes consistency in reviews and has the advantage of being able to be used as a resource to staff at any time. The WBT will provide reviewers with knowledge needed to perform risk-informed analyses (e.g., information related to development of realistic scenarios and use of probabilistic analysis). WBT on review of LTP or DP dose modeling will promote staff development, efficiency, and effectiveness in performing risk-informed, performance-based reviews of decommissioning activities at NRC-licensed facilities. One of the key advantages of this type of web-based training is that it can be loaded on-demand and can be reused indefinitely. In addition to the benefits of on-demand training, the modules can also be used for reference. The presentations are hosted on a web server that can be accessed by registered users at any time. Staff can return to a particular module to review the material long after they have completed the course.

  5. Revised analyses of decommissioning for the reference boiling water reactor power station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure - appendices. Final report

    SciTech Connect (OSTI)

    Smith, R.I.; Bierschbach, M.C.; Konzek, G.J.; McDuffie, P.N.

    1996-07-01

    The NRC staff is in need of decommissioning bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to update the needed bases documentation. This report presents the results of a review and reevaluation of the PNL 1980 decommissioning study of the Washington Public Power Supply System`s Washington Nuclear Plant Two (WNP-2) located at Richland, Washington, including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5-7 year period during which time the spent fuel is stored in the spent fuel pool prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clear structures on the site and to restore the site to a {open_quotes}green field{close_quotes} condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities. Sensitivity of the total license termination cost to the disposal costs at different low-level radioactive waste disposal sites, to different depths of contaminated concrete surface removal within the facilities, and to different transport distances is also examined.

  6. EA-1889: Disposal of Decommissioned, Defueled Naval Reactor Plants from USS Enterprise (CVN 65) at the Hanford Site, Richland, Washington

    Broader source: Energy.gov [DOE]

    This EA, prepared by the Department of the Navy, evaluates the environmental impacts of the disposal of decommissioned, defueled, naval reactor plants from the USS Enterprise at DOE’s Hanford Site, Richland, Washington. DOE participated as a cooperating agency in the preparation of this EA. The Department of the Navy issued its FONSI on August 23, 2012.

  7. Apply for Beamtime

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

    Apply for Beamtime Apply for Beamtime Print Friday, 28 August 2009 13:23 Available Beamlines Determine which ALS beamlines are suitable for your experiment. To do this, you can review the ALS Beamlines Directory, contact the appropriate beamline scientist listed on the Directory, and/or contact the This e-mail address is being protected from spambots. You need JavaScript enabled to view it . Log In to the ALSHub user portal ALSHub Login For More Information About the Types of Proposals To learn

  8. Decontamination and decommissioning plan for processing contaminated NaK at the INEL

    SciTech Connect (OSTI)

    LaRue, D.M.; Dolenc, M.R.

    1986-09-01

    This decontamination and decommissioning (D D) plan describes the work elements and project management plan for processing four containers of contaminated sodium/potassium (NaK) and returning the Army Reentry Vehicle Facility Site (ARVFS) to a reusable condition. The document reflects the management plan for this project before finalizing the conceptual design and preliminary prototype tests of the reaction kinetics. As a result, the safety, environmental, and accident analyses are addressed as preliminary assessments before completion at a later date. ARVFS contains an earth-covered bunker, a cylindrical test pit and metal shed, and a cable trench connecting the two items. The bunker currently stores the four containers of NaK from the meltdown of the EBR-1 Mark II core. The D D project addressed in this plan involves processing the contaminated NaK and returning the ARVFS to potential reuse after cleanup.

  9. Decontamination and decommissioning plan for processing contaminated NaK at the INEL

    SciTech Connect (OSTI)

    LaRue, D.M.; Dolenc, M.R.

    1986-09-01

    This decontamination and decommissioning (D&D) plan describes the work elements and project management plan for processing four containers of contaminated sodium/potassium (NaK) and returning the Army Reentry Vehicle Facility Site (ARVFS) to a reusable condition. The document reflects the management plan for this project before finalizing the conceptual design and preliminary prototype tests of the reaction kinetics. As a result, the safety, environmental, and accident analyses are addressed as preliminary assessments before completion at a later date. ARVFS contains an earth-covered bunker, a cylindrical test pit and metal shed, and a cable trench connecting the two items. The bunker currently stores the four containers of NaK from the meltdown of the EBR-1 Mark II core. The D&D project addressed in this plan involves processing the contaminated NaK and returning the ARVFS to potential reuse after cleanup.

  10. Final report of the decontamination and decommissioning of the BORAX-V facility turbine building

    SciTech Connect (OSTI)

    Arave, A.E.; Rodman, G.R.

    1992-12-01

    The Boiling Water Reactor Experiment (BORAX)-V Facility Turbine Building Decontamination and Decommissioning (D&D) Project is described in this report. The BORAX series of five National Reactor Testing Station (NRTS) reactors pioneered intensive work on boiling water reactor (BWR) experiments conducted between 1953 and 1964. Facility characterization, decision analyses, and D&D plans for the turbine building were prepared from 1979 through 1990. D&D activities of the turbine building systems were initiated in November of 1988 and completed with the demolition and backfill of the concrete foundation in March 1992. Due to the low levels of radioactivity and the absence of loose contamination, the D&D activities were completed with no radiation exposure to the workers. The D&D activities were performed in a manner that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory (INEL) remain.

  11. Final report of the decontamination and decommissioning of the BORAX-V facility turbine building

    SciTech Connect (OSTI)

    Arave, A.E.; Rodman, G.R.

    1992-12-01

    The Boiling Water Reactor Experiment (BORAX)-V Facility Turbine Building Decontamination and Decommissioning (D D) Project is described in this report. The BORAX series of five National Reactor Testing Station (NRTS) reactors pioneered intensive work on boiling water reactor (BWR) experiments conducted between 1953 and 1964. Facility characterization, decision analyses, and D D plans for the turbine building were prepared from 1979 through 1990. D D activities of the turbine building systems were initiated in November of 1988 and completed with the demolition and backfill of the concrete foundation in March 1992. Due to the low levels of radioactivity and the absence of loose contamination, the D D activities were completed with no radiation exposure to the workers. The D D activities were performed in a manner that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory (INEL) remain.

  12. Low Level Radioactive Wastes Conditioning during Decommissioning of Salaspils Research Reactor

    SciTech Connect (OSTI)

    Abramenkova, G.; Klavins, M.; Abramenkovs, A.

    2008-01-15

    The decommissioning of Salaspils research reactor is connected with the treatment of 2200 tons different materials. The largest part of all materials ({approx}60 % of all dismantled materials) is connected with low level radioactive wastes conditioning activities. Dismantled radioactive materials were cemented in concrete containers using water-cement mortar. According to elaborated technology, the tritiated water (150 tons of liquid wastes from special canalization tanks) was used for preparation of water-cement mortar. Such approach excludes the emissions of tritiated water into environment and increases the efficiency of radioactive wastes management system for decommissioning of Salaspils research reactor. The Environmental Impact Assessment studies for Salaspils research reactor decommissioning (2004) and for upgrade of repository 'Radons' for decommissioning purposes (2005) induced the investigations of radionuclides release parameters from cemented radioactive waste packages. These data were necessary for implementation of quality assurance demands during conditioning of radioactive wastes and for safety assessment modeling for institutional control period during 300 years. Experimental studies indicated, that during solidification of water- cement samples proceeds the increase of temperature up to 81 deg. C. It is unpleasant phenomena since it can result in damage of concrete container due to expansion differences for mortar and concrete walls. Another unpleasant factor is connected with the formation of bubbles and cavities in the mortar structure which can reduce the mechanical stability of samples and increase the release of radionuclides from solidified cement matrix. The several additives, fly ash and PENETRON were used for decrease of solidification temperature. It was found, that addition of fly ash to the cement-water mortar can reduce the solidification temperature up to 62 deg. C. Addition of PENETRON results in increasing of solidification temperature up to 83 deg. C. Experimental data shows, that water/cement ratio significantly influences on water-cement mortar's viscosity and solidified samples mechanical stability. Increasing of water ratio from 0.45 up to 0.65 decreases water-cement mortar's viscosity from 1100 mPas up to 90 mPas. Significant reduction of viscosity is an important factor, which facilitates the fulfillment all gaps and cavities with the mortar during conditioning of solid radioactive wastes in containers. On the other hand, increase water ratio from 0.45 up to 0.65 decreases mechanical stability of water-cement samples from 23 N/mm{sup 2} to the 12 N/mm{sup 2}. It means that water-cement bulk stability significantly decreases with increasing of water content. Technologically is important to increase the tritiated water content in container with cemented radioactive wastes. It gives a possibility to increase the fulfillment of container with radioactive materials. On the other hand, additional water significantly reduces bulk stability of containers with cemented radioactive wastes, which can result in disintegration of radioactive wastes packages in repository during 300 years. Taking into account the experimental results, it is not recommended to exceed the water/cement ratio more than 0.60. Tritium and Cs{sup 137} leakage tests show, that radionuclides release curves has a complicate structure. Experimental results indicated that addition of fly ash result in facilitation of tritium and cesium release in water phase. This is unpleasant factor, which significantly decreases the safety of disposed radioactive wastes. Despite the positive impact on solidification temperature drop, the addition of fly ash to the cement-water mortar is not recommended in case of cementation of radionuclides in concrete containers. In conclusion: The cementation processes of solid radioactive wastes in concrete containers were investigated. The influence of additives on cementation processes was studied. It was shown, that the increasing of water ratio from 0.45 up to 0.65 decreases water-cement mortar

  13. Nuclear Rocket Test Facility Decommissioning Including Controlled Explosive Demolition of a Neutron-Activated Shield Wall

    SciTech Connect (OSTI)

    Michael Kruzic

    2007-09-01

    Located in Area 25 of the Nevada Test Site, the Test Cell A Facility was used in the 1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program. The facility was decontaminated and decommissioned (D&D) in 2005 using the Streamlined Approach For Environmental Restoration (SAFER) process, under the Federal Facilities Agreement and Consent Order (FFACO). Utilities and process piping were verified void of contents, hazardous materials were removed, concrete with removable contamination decontaminated, large sections mechanically demolished, and the remaining five-foot, five-inch thick radiologically-activated reinforced concrete shield wall demolished using open-air controlled explosive demolition (CED). CED of the shield wall was closely monitored and resulted in no radiological exposure or atmospheric release.

  14. Available decontamination and decommissioning capabilities at the Savannah River Technology Center

    SciTech Connect (OSTI)

    Polizzi, L.M.; Norkus, J.K.; Paik, I.K.; Wooten, L.A.

    1992-08-19

    The Safety Analysis and Engineering Services Group has performed a survey of the Savannah River Technology Center (SRTC) technical capabilities, skills, and experience in Decontamination and Decommissioning (D&D) activities. The goal of this survey is to enhance the integration of the SRTC capabilities with the technical needs of the Environmental Restoration Department D&D program and the DOE Office of Technology Development through the Integrated Demonstration Program. This survey has identified technical capabilities, skills, and experience in the following D&D areas: Characterization, Decontamination, Dismantlement, Material Disposal, Remote Systems, and support on Safety Technology for D&D. This review demonstrates the depth and wealth of technical capability resident in the SRTC in relation to these activities, and the unique qualifications of the SRTC to supply technical support in the area of DOE facility D&D. Additional details on specific technologies and applications to D&D will be made available on request.

  15. Available decontamination and decommissioning capabilities at the Savannah River Technology Center

    SciTech Connect (OSTI)

    Polizzi, L.M.; Norkus, J.K.; Paik, I.K.; Wooten, L.A.

    1992-08-19

    The Safety Analysis and Engineering Services Group has performed a survey of the Savannah River Technology Center (SRTC) technical capabilities, skills, and experience in Decontamination and Decommissioning (D D) activities. The goal of this survey is to enhance the integration of the SRTC capabilities with the technical needs of the Environmental Restoration Department D D program and the DOE Office of Technology Development through the Integrated Demonstration Program. This survey has identified technical capabilities, skills, and experience in the following D D areas: Characterization, Decontamination, Dismantlement, Material Disposal, Remote Systems, and support on Safety Technology for D D. This review demonstrates the depth and wealth of technical capability resident in the SRTC in relation to these activities, and the unique qualifications of the SRTC to supply technical support in the area of DOE facility D D. Additional details on specific technologies and applications to D D will be made available on request.

  16. Information Science, Computing, Applied Math

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

    Information Science, Computing, Applied Math science-innovationassetsimagesicon-science.jpg Information Science, Computing, Applied Math National security depends on science ...

  17. Applied Cathode Enhancement and

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

    Applied Cathode Enhancement and Robustness Technologies (ACERT) Team Our project team, a part of Los Alamos National Laboratory (LANL) comprised of world leading experts from fields of accelerator design & testing, chemical synthesis of nanomaterials (quantum dots), and shielding application of nanomaterials (graphene and other atomically-thin sheets). Our goal is to develop and demonstrate 'designer' cold cathode electron sources with tunable parameters (bandgap, efficiency, optical

  18. Applied Computer Science

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

    7 Applied Computer Science Innovative co-design of applications, algorithms, and architectures in order to enable scientific simulations at extreme scale Leadership Group Leader Linn Collins Email Deputy Group Leader (Acting) Bryan Lally Email Climate modeling visualization Results from a climate simulation computed using the Model for Prediction Across Scales (MPAS) code. This visualization shows the temperature of ocean currents using a green and blue color scale. These colors were

  19. Nuclear facility decommissioning and site remedial actions: A selected bibliography, volume 9

    SciTech Connect (OSTI)

    Owen, P.T.; Knox, N.P.; Michelson, D.C.; Turmer, G.S.

    1988-09-01

    The 604 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the ninth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's remedial action programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Subsections for sections 1, 2, 5, and 6 include: Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at (615) 576-0568 or FTS 626-0568.

  20. Issues in UK cleanup and decommissioning; a strategic R and D programme

    SciTech Connect (OSTI)

    Tinsley, T.P.; Ashley, V.B.; Morgan, H.G.; Fairhall, G.A.

    2008-07-01

    Nexia Solutions is contracted to manage and carry out research on behalf of the Nuclear Decommissioning Authority (NDA). This paper will describe the nuclear research ongoing and how it fits in with the UK cleanup and decommissioning strategy. The aim of the strategic R and D programme is to assist the NDA in maintaining a technical portfolio which will:- - identify and address challenges and clean-up problems that do not have an existing solution; - resolve potential inconsistencies between sites in the technical bases for certain strategic decisions and their implementation; - maintain options while developing strategy (emerging risks); - save costs by developing multi-site solutions; - provide technology, skills and facilities on the timescale required. The strategy for the R and D programme has been developed from a top-level approach by understanding the challenges which need to be addressed and prioritising these according to the objectives of the programme. The programme has demonstrated that a technical portfolio comprising six areas, each containing a number of key themes, is appropriate to address the technical challenges which the NDA faces and aligns with the NDA's technical issues register. An important aspect of the R and D programme is that it should create opportunities for undertaking the NDA mission more effectively. This arises from the emphasis given in those technical programmes which define the challenge more precisely and thus provide a platform from which to produce innovative solutions. The paper will present an overview of the strategic R and D programme along with the key technical programme areas. Examples will be provided of the technical work ongoing, and the results obtained so far. (author)

  1. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Vol. 18. Part 2. Indexes

    SciTech Connect (OSTI)

    1997-09-01

    This bibliography contains 3638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D&D), uranium mill tailings management, and site remedial actions. This report is the eighteenth in a series of bibliographies prepared annually for the U.S. Department of Energy (DOE) Office of Environmental Restoration. Citations to foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - have been included in Part 1 of the report. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration Program; (2) DOE D&D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized Sites Remedial Action Programs; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluations; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues. Within the 16 sections, the citations are sorted by geographic location. If a geographic location is not specified, the citations are sorted according to the document title. In Part 2 of the report, indexes are provided for author, author affiliation, selected title phrase, selected title word, publication description, geographic location, and keyword.

  2. EIS-0259: Disposal of Decommissioned, Defueled Cruiser, Ohio Class and Los Angeles Class Naval Reactor Plants, Hanford Site, Richland (adopted from Navy)

    Broader source: Energy.gov [DOE]

    This EIS analyzes the alternate ways for disposing of decommissioned, defieled reactor compliments from U.S. Navy nuclear-powered cruisers, (Bainbridge, Truxtun, Long Beach, California Class and Virginia Class) and Los Angeles Class, and Ohio Class submarines.

  3. EIS-0226: Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center

    Broader source: Energy.gov [DOE]

    This EIS evaluates the potential environmental impacts of the range of reasonable alternatives to decommission and/or maintain long-term stewardship at WNYNSC. The alternatives analyzed in the EIS...

  4. Apply for Beamtime

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

    Apply for Beamtime Print Available Beamlines Determine which ALS beamlines are suitable for your experiment. To do this, you can review the ALS Beamlines Directory, contact the appropriate beamline scientist listed on the Directory, and/or contact the This e-mail address is being protected from spambots. You need JavaScript enabled to view it . Log In to the ALSHub user portal ALSHub Login For More Information About the Types of Proposals To learn more about the three different types of

  5. Apply for Beamtime

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

    Apply for Beamtime Print Available Beamlines Determine which ALS beamlines are suitable for your experiment. To do this, you can review the ALS Beamlines Directory, contact the appropriate beamline scientist listed on the Directory, and/or contact the This e-mail address is being protected from spambots. You need JavaScript enabled to view it . Log In to the ALSHub user portal ALSHub Login For More Information About the Types of Proposals To learn more about the three different types of

  6. Suggestion of typical phases of in-vessel fuel-debris by thermodynamic calculation for decommissioning technology of Fukushima-Daiichi nuclear power station

    SciTech Connect (OSTI)

    Ikeuchi, Hirotomo; Yano, Kimihiko; Kaji, Naoya; Washiya, Tadahiro; Kondo, Yoshikazu; Noguchi, Yoshikazu

    2013-07-01

    For the decommissioning of the Fukushima-Daiichi Nuclear Power Station (1F), the characterization of fuel-debris in cores of Units 1-3 is necessary. In this study, typical phases of the in-vessel fuel-debris were estimated using a thermodynamic equilibrium (TDE) calculation. The FactSage program and NUCLEA database were applied to estimate the phase equilibria of debris. It was confirmed that the TDE calculation using the database can reproduce the phase separation behavior of debris observed in the Three Mile Island accident. In the TDE calculation of 1F, the oxygen potential [G(O{sub 2})] was assumed to be a variable. At low G(O{sub 2}) where metallic zirconium remains, (U,Zr)O{sub 2}, UO{sub 2}, and ZrO{sub 2} were found as oxides, and oxygen-dispersed Zr, Fe{sub 2}(Zr,U), and Fe{sub 3}UZr{sub 2} were found as metals. With an increase in zirconium oxidation, the mass of those metals, especially Fe{sub 3}UZr{sub 2}, decreased, but the other phases of metals hardly changed qualitatively. Consequently, (U,Zr)O{sub 2} is suggested as a typical phase of oxide, and Fe{sub 2}(Zr,U) is suggested as that of metal. However, a more detailed estimation is necessary to consider the distribution of Fe in the reactor pressure vessel through core-melt progression. (authors)

  7. Decommissioning of eight surplus production reactors at the Hanford Site, Richland, Washington. Addendum (Final Environmental Impact Statement)

    SciTech Connect (OSTI)

    Not Available

    1992-12-01

    The first section of this volume summarizes the content of the draft environmental impact statement (DEIS) and this Addendum, which together constitute the final environmental impact statement (FEIS) prepared on the decommissioning of eight surplus plutonium production reactors at Hanford. The FEIS consists of two volumes. The first volume is the DEIS as written. The second volume (this Addendum) consists of a summary; Chapter 9, which contains comments on the DEIS and provides DOE`s responses to the comments; Appendix F, which provides additional health effects information; Appendix K, which contains costs of decommissioning in 1990 dollars; Appendix L, which contains additional graphite leaching data; Appendix M, which contains a discussion of accident scenarios; Appendix N, which contains errata; and Appendix 0, which contains reproductions of the letters, transcripts, and exhibits that constitute the record for the public comment period.

  8. Session 31B - Panel: Opportunities in the UK with the Nuclear Decommissioning Authority (NDA)

    SciTech Connect (OSTI)

    Benda, Gary; Hayes, David; Gorham, Ron; Wareing, Mark; Simper, Adrian; Selby, Terry

    2006-07-01

    The NDA participated in a panel session 31B on Wednesday afternoon starting at 3:15. The NDA is a non-departmental public body, set up in April 2005 under the Energy Act 2004 to take strategic responsibility for the UK's nuclear legacy. Details of their organization and history are located on their web site at www.nda.gov.uk. Also copies of their Power Point presentations made at WM'06 are available on their web site. Their core objective is to ensure that the 20 civil public sector nuclear sites under our ownership are decommissioned and cleaned up safely, securely, cost effectively and in ways that protect the environment for this and future generations. They lead the development of a unified and coherent decommissioning strategy, working in partnership with regulators and site licensees to achieve best value, optimum impact on local communities, and the highest environmental standards. The NDA's main task is the decommissioning and clean up of civil nuclear sites. If the Government decides it is necessary, however, the Energy Act 2004 allows the NDA to take responsibility for sites currently operated by, or on behalf of, the Ministry of Defence (MoD). Resources will then be transferred from the MoD to meet the costs of clean up. The NDA made a number of presentations to allow conference delegates the opportunity to understand some of the major aspects of their work and to interact with NDA staff. These included the following topics and gave opportunity for audience discussion: - A brief presentation to update on progress by the NDA; - Outline of low level waste management and the prioritisation process; - Discussion of the competition schedule related to low level waste management and the Drigg site. The following presentations and handout were delivered in various sessions of the conference as noted below and are available on their web page including the WM'06 Plenary Session presentation by Sir Anthony Cleaver, Chairman of the NDA. During Session 31B, the following Power Point presentations were made. NDA Overview by David Hayes, Director of Special Projects National M and O Contractor Work Prioritisation Process by Mark Wareing, including topics on: - Need for prioritisation; - Development of the process; - Using the process as a measure of progress. Competition by Ron Gorham, Head of Procurement, including topics on: - The current model; - What NDA are actually competing; - The acquisition process; - NDA aspirations for competition; - NDA aspirations from the market. Low Level Waste Contracting in the UK by Adrian Simper, Expenditure and Programme Strategy Manager, including topics on: - Low Level Waste: NDA responsibilities, Definitions, Arisings; - Proposed NDA Procurement for LLW Management: Scope, Contracting approach, Timetable. The NDA responded to questions from the audience and also announced that the NDA will be holding a special Industry Day for potential contractors interested in the first NDA competition - the Low Level Waste Repository near Drigg in Cumbria. The event is scheduled on the 25-26 April 2006 with more details on their web site at www.nda.gov.uk. (authors)

  9. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text. Environmental Restoration Program

    SciTech Connect (OSTI)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

  10. Cost Estimating for Decommissioning of a Plutonium Facility--Lessons Learned From The Rocky Flats Building 771 Project

    SciTech Connect (OSTI)

    Stevens, J. L.; Titus, R.; Sanford, P. C.

    2002-02-26

    The Rocky Flats Closure Site is implementing an aggressive approach in an attempt to complete Site closure by 2006. The replanning effort to meet this goal required that the life-cycle decommissioning effort for the Site and for the major individual facilities be reexamined in detail. As part of the overall effort, the cost estimate for the Building 771 decommissioning project was revised to incorporate both actual cost data from a recently-completed similar project and detailed planning for all activities. This paper provides a brief overview of the replanning process and the original estimate, and then discusses the modifications to that estimate to reflect new data, methods, and planning rigor. It provides the new work breakdown structure and discusses the reasons for the final arrangement chosen. It follows with the process used to assign scope, cost, and schedule elements within the new structure, and development of the new code of accounts. Finally, it describes the project control methodology used to track the project, and provides lessons learned on cost tracking in the decommissioning environment.

  11. Finding of no significant impact, decontamination and decommissioning of Battelle Columbus Laboratories in Columbus and West Jefferson, Ohio

    SciTech Connect (OSTI)

    Not Available

    1990-01-01

    This Environmental Assessment has been developed by the Department of Energy in accordance with the requirements of the National Environmental Policy Act of 1969 for the proposed decommissioning of contaminated areas at the Battelle Memorial Institute, Columbus, Ohio. The discussions in Section 1.0 provide general background information on the proposed action. Section 2.0 describes the existing radiological and non-radiological condition of the Battelle Columbus Laboratories. Section 3.0 identifies the alternatives considered for the proposed action and describes in detail the proposed decommissioning project. Section 4.0 evaluates the potential risks the project poses to human health and the environment. Section 5.0 presents the Department of Energy's proposed action. As a result of nuclear research and development activities conducted over a period of approximately 43 years performed for the Department of Energy, its predecessor agencies, and under commercial contracts, the 15 buildings became contaminated with varying amounts of radioactive material. The Department of Energy no longer has a need to utilize the facilities and is contractually obligate to remove that contamination such that they can be used by their owners without radiological restrictions. This Environmental Assessment for the Battelle Columbus Laboratories Decommissioning Project is consistent with the direction from the Secretary of Energy that public awareness and participation be considered in sensitive projects and is an appropriate document to determine action necessary to satisfy the requirements of the National Environmental Policy Act. 30 refs., 6 figs., 9 tabs.

  12. ORISE: Applied health physics projects

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

    Applied health physics projects The Oak Ridge Institute for Science and Education (ORISE) provides applied health physics services to government agencies needing technical support ...

  13. Facility Decontamination and Decommissioning Program Surveillance and Maintenance Plan, Revision 2

    SciTech Connect (OSTI)

    Poderis, Reed J.; King, Rebecca A.

    2013-09-30

    This Surveillance and Maintenance (S&M) Plan describes the activities performed between deactivation and final decommissioning of the following facilities located on the Nevada National Security Site, as documented in the Federal Facility Agreement and Consent Order under the Industrial Sites program as decontamination and decommissioning sites: ? Engine Maintenance, Assembly, and Disassembly (EMAD) Facility: o EMAD Building (Building 25-3900) o Locomotive Storage Shed (Building 25-3901) ? Test Cell C (TCC) Facility: o Equipment Building (Building 25-3220) o Motor Drive Building (Building 25-3230) o Pump Shop (Building 25-3231) o Cryogenic Lab (Building 25-3232) o Ancillary Structures (e.g., dewars, water tower, piping, tanks) These facilities have been declared excess and are in various stages of deactivation (low-risk, long-term stewardship disposition state). This S&M Plan establishes and implements a solid, cost-effective, and balanced S&M program consistent with federal, state, and regulatory requirements. A graded approach is used to plan and conduct S&M activities. The goal is to maintain the facilities in a safe condition in a cost-effective manner until their final end state is achieved. This plan accomplishes the following: ? Establishes S&M objectives and framework ? Identifies programmatic guidance for S&M activities to be conducted by National Security Technologies, LLC, for the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) ? Provides present facility condition information and identifies hazards ? Identifies facility-specific S&M activities to be performed and their frequency ? Identifies regulatory drivers, NNSA/NFO policies and procedures, and best management practices that necessitate implementation of S&M activities ? Provides criteria and frequencies for revisions and updates ? Establishes the process for identifying and dispositioning a condition that has not been previously identified or documented ? Provides instructions for implementing annual S&M inspections and activities The following facilities that were included in Revision 1 of this plan have reached final disposition and are no longer in the S&M program: ? Reactor Maintenance, Assembly, and Disassembly Facility, Building 25-3110 ? Test Cell A Facility, Building 25-3113 ? TCC Facility, Building 25-3210 ? Pluto Disassembly Facility, Building 26-2201 ? Super Kukla Facility, Building 27-5400

  14. Soil Segregation technology: reducing uncertainty and increasing efficiency during radiological decommissioning - a case study

    SciTech Connect (OSTI)

    Lombardo, A.J.; Orthen, R.F.; Shonka, J.J.; Scott, L.M.

    2007-07-01

    The regulatory release of sites and facilities (property) for restricted or unrestricted use has evolved beyond prescribed levels to model-derived dose and risk based limits. Dose models for deriving corresponding soil radionuclide concentration guidelines are necessarily simplified representations of complex processes. It is not practical to obtain data to fully or accurately characterize transport and exposure pathway processes. Similarly, it is not possible to predict future conditions with certainty absent durable land use restrictions. To compensate for the shortage of comprehensive characterization data and site specific inputs to describe the projected 'as-left' contaminated zone, conservative default values are used to derive acceptance criteria. The result is overly conservative criteria. Furthermore, implementation of a remediation plan and subsequent final surveys to show compliance with the conservative criteria often result in excessive remediation due to the large uncertainty. During a recent decommissioning project of a site contaminated with thorium, a unique approach to dose modeling and remedial action design was implemented to effectively manage end-point uncertainty. The approach used a dynamic feedback dose model and soil segregation technology to characterize impacted material with precision and accuracy not possible with static control approaches. Utilizing the remedial action goal 'over excavation' and subsequent auto-segregation of excavated material for refill, the end-state (as-left conditions of the refilled excavation) RESRAD input parameters were re-entered to assess the final dose. The segregation process produced separate below and above criteria material stockpiles whose volumes were optimized for maximum refill and minimum waste. The below criteria material was returned to the excavation without further analysis, while the above criteria material was packaged for offsite disposal. Using the activity concentration data recorded by the segregation system and the as-left configuration of the refilled excavation, the end state model of the site was prepared with substantially reduced uncertainty. The major projected benefits of this approach are reviewed as well as the performance of the segregation system and lessons learned including: 1) Total, first-attempt data discovery brought about by simultaneously conducted characterization and final status surveys, 2) Lowered project costs stemming from efficient analysis and abstraction of impacted material and reduced offsite waste disposal volume, 3) Lowered project costs due to increased remediation/construction efficiency and decreased survey and radio-analytical expenses, and 4) Improving the decommissioning experience with new regulatory guidance. (authors)

  15. Implementation of 10 CFR 20.1406 Through Life Cycle Planning for Decommissioning

    SciTech Connect (OSTI)

    O'Donnell, E.; Ott, W.R.

    2008-07-01

    This paper summarizes a regulatory guide that the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, is currently developing for use in implementing Title 10, Section 20.1406, of the Code of Federal Regulations (10 CFR 20.1406), 'Minimization of Contamination'. The intent of the regulation is to diminish the occurrence and severity of 'legacy sites' by taking measures to reduce and control contamination and facilitate eventual decommissioning. The thrust of the regulatory guide is to encourage applicants to use technically sound engineering judgment and a practical risk-informed approach to achieve the objectives of 10 CFR 20.1406. In particular, such an approach should consider the materials and processes involved (e.g., solids, liquids, gases), and focus on (1) the relative significance of potential contamination, (2) areas that are most susceptible to leaks, and (3) the appropriate level of consideration that should be incorporated in facility design and operational procedures to prevent and control contamination. (authors)

  16. Technical program plan for the transitioning, decommissioning, and final disposition focus area

    SciTech Connect (OSTI)

    Not Available

    1994-01-01

    Hundreds of aging nuclear materials processing facilities within the Department of Energy`s (DOE) Weapons Complex are now being shut down and deactivated. These facilities, situated throughout the United States, will require a monumental effort to clean up safely and with minimal environmental insult. Current cleanup technologies tend to be labor intensive and expensive, they produce an unacceptably large volume of waste, and they expose workers to radioactive and other hazardous substances. This document describes an emerging program designed to develop and demonstrate new technical approaches to the decontamination and decommissioning (D&D) program for DOE`s nuclear materials processing facilities. Sponsored by the DOE Office of Technology Development within the Office of Environmental Restoration and Waste Management (EM), the program seeks to integrate the strengths of DOE`s technical, managerial, and systems engineering capabilities with those of industry, universities, and other government agencies. Once developed, these technologies will help to provide US industry with a competitive edge in the worldwide market that exists for improved environmental restoration and D&D services.

  17. A survey of commercially available manipulators, end-effectors, and delivery systems for reactor decommissioning activities

    SciTech Connect (OSTI)

    Henley, D.R.; Litka, T.J.

    1996-05-01

    Numerous nuclear facilities owned by the U.S. Department of Energy (DOE) are under consideration for decommissioning. Currently, there are no standardized, automated, remote systems designed to dismantle and thereby reduce the size of activated reactor components and vessels so that they can be packaged and shipped to disposal sites. Existing dismantling systems usually consist of customized, facility-specific tooling that has been developed to dismantle a specific reactor system. Such systems have a number of drawbacks. Generally, current systems cannot be disassembled, moved, and reused. Developing and deploying the tooling for current systems is expensive and time-consuming. In addition, the amount of manual work is significant because long-handled tools must be used; as a result, personnel are exposed to excessive radiation. A standardized, automated, remote system is therefore needed to deliver the tooling necessary to dismantle nuclear facilities at different locations. Because this system would be reusable, it would produce less waste. The system would also save money because of its universal design, and it would be more reliable than current systems.

  18. Applied Optoelectronics | Open Energy Information

    Open Energy Info (EERE)

    optical semiconductor devices, packaged optical components, optical subsystems, laser transmitters, and fiber optic transceivers. References: Applied Optoelectronics1...

  19. Decommissioning of the remediation systems at Waverly, Nebraska, in 2011-2012.

    SciTech Connect (OSTI)

    LaFreniere, L. M.

    2012-06-29

    The Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA) operated a grain storage facility in Waverly, Nebraska, from 1952 to 1974. During this time, the grain fumigant '80/20' (carbon tetrachloride/carbon disulfide) was used to preserve stored grain. In 1982, sampling by the U.S. Environmental Protection Agency (EPA) found carbon tetrachloride contamination in the town's groundwater. After an investigation of the contaminant distribution, the site was placed on the National Priority List (NPL) in 1986, and the CCC/USDA accepted responsibility for the contamination. An Interagency Compliance Agreement between the EPA and the CCC/USDA was finalized in May 1988 (EPA 1990). The EPA (Woodward-Clyde Consultants, contractor) started immediate cleanup efforts in 1987 with the installation of an air stripper, a soil vapor extraction system, a groundwater extraction well, and groundwater and soil gas monitoring wells (Woodward-Clyde 1986, 1988a,b). After the EPA issued its Record of Decision (ROD; EPA 1990), the CCC/USDA (Argonne National Laboratory, contractor) took over operation of the treatment systems. The CCC/USDA conducted a site investigation (Argonne 1991, 1992a,b), during which a carbon tetrachloride plume in groundwater was discovered northeast of the former facility. This plume was not being captured by the existing groundwater extraction system. The remediation system was modified in 1994 (Argonne 1993) with the installation of a second groundwater extraction well to contain the contamination further. Subsequently, a detailed evaluation of the system resulted in a recommendation to pump only the second well to conserve water in the aquifer (Argonne 1995). Sampling and analysis after implementation of this recommendation showed continued decreases in the extent and concentrations of the contamination with only one well pumping (Argonne 1999). The CCC/USDA issued quarterly monitoring reports from 1988 to 2009. Complete documentation of the CCC/USDA characterization and remediation efforts, including the quarterly monitoring reports, is on the compact disc inside the back cover of this report. The EPA reported on the progress of the remediation systems in a series of five-year reviews (EPA 1993, 1999, 2004, 2009). These reports and other EPA documentation are also on the compact disc inside the back cover of this report, along with the Woodward-Clyde (1986, 1988a,b) documentation cited. Starting in 2006, the analytical results for groundwater (the only medium still being monitored) showed no carbon tetrachloride concentrations above the maximum contaminant level (MCL) of 5.0 g/L. Because the cleanup goals specified in the ROD (EPA 1990) had been met, the EPA removed the site from the NPL in November 2006 (Appendix A). In 2008 the National Pollutant Discharge Elimination System (NPDES) permit for the remediation system was deactivated, and a year later the EPA released its fourth and final five-year report (EPA 2009), indicating that no further action was required for the site and that the site was ready for unlimited use. In 2011-2012, the CCC/USDA decommissioned the remediation systems at Waverly. This report documents the decommission process and closure of the site.

  20. Sorption (Kd) measurements in support of dose assessments for Zion Nuclear Station Decommissioning

    SciTech Connect (OSTI)

    Yim S. P.; Sullivan T.; Milian, L.

    2012-12-12

    The Zion Nuclear Power Station is being decommissioned. ZionSolutions proposes to leave much of the below grade structures in place and to fill them with clean concrete demolition debris from the above grade parts of the facility. This study, commissioned by ZionSolutions and conducted by the Brookhaven National Laboratory (BNL) was performed to provide site-specific data for performance assessment calculations to support the request to terminate the NRC license and allow unrestricted use of the facility. Specifically, this study measured the distribution coefficient for five radionuclides of concern using site-specific soils and groundwater. The distributions coefficient is a measure of the amount of the radionuclide that will remain sorbed to the soil or concrete that is present relative to the amount that will remain in solution. A high distribution coefficient indicates most of the radionuclide will remain on the solid material and will not be available for transport by the groundwater. The radionuclides of concern are Fe-55, Co-60, Ni-63, Sr-90, and Cs-137. Tests were performed following ASTM C1733-10, Standard Test Methods for Distribution Coefficients of Inorganic Species by the Batch Method. Sr-85 was used in the testing as an analogue for Sr-90 because it behaves similarly with respect to sorption and has a gamma emission that is easier to detect than the beta emission from Sr-90. Site-specific soils included disturbed sand (sand removed during construction and used as backfill), native sand, silt/clay and silt. In addition, concrete cores from the Unit-1 Containment Building and the Crib House were broken into particles less than 2 mm in size and tested to obtain distribution coefficients for the five nuclides.

  1. Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4. Volume 1: Technology evaluation

    SciTech Connect (OSTI)

    1994-09-01

    During World War 11, the Oak Ridge Y-12 Plant was built as part of the Manhattan Project to supply enriched uranium for weapons production. In 1945, Building 9201-4 (Alpha-4) was originally used to house a uranium isotope separation process based on electromagnetic separation technology. With the startup of the Oak Ridge K-25 Site gaseous diffusion plant In 1947, Alpha-4 was placed on standby. In 1953, the uranium enrichment process was removed, and installation of equipment for the Colex process began. The Colex process--which uses a mercury solvent and lithium hydroxide as the lithium feed material-was shut down in 1962 and drained of process materials. Residual Quantities of mercury and lithium hydroxide have remained in the process equipment. Alpha-4 contains more than one-half million ft{sup 2} of floor area; 15,000 tons of process and electrical equipment; and 23,000 tons of insulation, mortar, brick, flooring, handrails, ducts, utilities, burnables, and sludge. Because much of this equipment and construction material is contaminated with elemental mercury, cleanup is necessary. The goal of the Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4 is to provide a planning document that relates decontamination and decommissioning and waste management problems at the Alpha-4 building to the technologies that can be used to remediate these problems. The Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4 builds on the methodology transferred by the U.S. Air Force to the Environmental Management organization with DOE and draws from previous technology logic diagram-efforts: logic diagrams for Hanford, the K-25 Site, and ORNL.

  2. Characterization of radioactive aerosols generated during the demolition of the concrete bioshield of a reactor undergoing decommissioning

    SciTech Connect (OSTI)

    Landolt, R.R.

    1996-12-31

    Particle size distribution studies were performed on aerosols generated during the cutting of the core support floor of the Ft. St. Vrain reactor which is undergoing decommissioning. The activity median aerodynamic diameter (AMAD) for Co-60 in the aerosol was found to be considerably larger than the currently used 1-micron default value and in one case larger than the newly recommended 5-micron reference value for occupational exposure. The reverse was true for Cs-137 where the AMAD was found to be in the sub-micron range possibly caused by high solubility of the radiocesium into the water spray used in the cutting operation.

  3. DECOMMISSIONING OF SHIELDED FACILITIES AT WINFRITH USED FOR POST IRRADIATION EXAMINATION OF NUCLEAR FUELS & OTHER ACTIVE ITEMS

    SciTech Connect (OSTI)

    Miller, K.D.; Parkinson, S.J.; Cornell, R.M.; Staples, A.T.

    2003-02-27

    This paper describes the approaches used in the clearing, cleaning, decontamination and decommissioning of a very large suite of seven concrete shielded caves and other facilities used by UKAEA at Winfrith Technology Centre, England over a period of about 30 years for the postirradiation examination (PIE) of a wide range of nuclear fuels and other very active components. The basic construction of the facilities will first be described, setting the scene for the major challenges that 1970s' thinking posed for decommissioning engineers. The tendency then to use large and heavy items of equipment supported upon massive steel bench structures produced a series of major problems that had to be overcome. The means of solving these problems by utilization of relatively simple and inexpensive equipment will be described. Later, a further set of challenges was experienced to decontaminate the interior surfaces to allow man entries to be undertaken at acceptable dose rates. The paper will describe the types of tooling used and the range of complementary techniques that were employed to steadily reduce the dose rates down to acceptable levels. Some explanations will also be given for the creation of realistic dose budgets and the methods of recording and continuously assessing the progress against these budgets throughout the project. Some final considerations are given to the commercial approaches to be adopted throughout this major project by the decommissioning engineers. Particular emphasis will be given to the selection of equipment and techniques that are effective so that the whole process can be carried out in a cost-effective and timely manner. The paper also provides brief complementary information obtained during the decommissioning of a plutonium-contaminated facility used for a range of semi-experimental purposes in the late 1970s. The main objective here was to remove the alpha contamination in such a manner that the volume of Plutonium Contaminated Materials (P CM) was minimized and to clean the whole facility to a free-breathing state such that it would be available for other work or subsequent demolition.

  4. A Strategy for Skills to meet the demands of Nuclear Decommissioning and Clean-up in the UK

    SciTech Connect (OSTI)

    Brownridge, M.; Ensor, B.

    2008-07-01

    The NDA remit as set out within the Energy Act includes - 'to ensure the availability of skills required to deliver the overall decommissioning and nuclear clean-up mission'. The NDA approach to meeting their statutory obligation is by: - finding the best ways of re-training, re-skilling or re-deploying people in a way that encourages a more flexible workforce; - identifying and communicating the skills and workforce requirements to deliver the mission; and - developing the infrastructure and capability initiatives in line with long term needs, for example, a National Skills Academy for Nuclear, Nuclear Institute, National Graduate Scheme, and - developing locally specific provision. Firstly, NDA has set the requirement for nuclear sites to write down within the Life Time Plans (LTP), at a high level, their Site Skills Strategies; furthermore, a National Skills Working Group has been established to develop tactical cross sector solutions to support the NDA's Skills Strategy. In support of the short, medium and long term needs to meet demands of the NDA sites and the nuclear decommissioning sector, as well as being aware of the broader nuclear sector, investments have been made in infrastructure and skills programmes such as: - A National Skills Academy for Nuclear - including UK wide representation of the whole nuclear sector; - A Nuclear Institute in partnership with the University of Manchester focussing on world class research and skills in Radiation Sciences and Decommissioning Engineering; - Post Graduate sponsorship for decommissioning related projects; - A National Graduate Scheme partnership with nuclear related employers; - Vocational qualifications and Apprenticeship Schemes - Engaging 14-19 year old students to encourage the take up of Science related subjects; and - A sector wide 'Skills Passport'. In conclusion: The skills challenge has many dimensions but requires addressing due to the clear link to improved business performance and the availability of key resources in a diminishing and competitive environment. The diminishing skill base is due to reasons such as demographics and competition from other industries such as the oil industry. Getting the balance between meeting regional and national requirements will prove critical to success. The lack of clarity on the long term needs will also drive the strategy. NDA recognises that the work to date is the beginning of a long term approach and programme. We have developed a skills strategy that is consistent across all 20 sites and examples of key developments in infrastructure are in progress. Looking forward NDA will seek benchmarking opportunities and ways to make tangible links between skills and performance. (authors)

  5. Apply

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

    Unofficial transcripts are acceptable. If transcripts are not in English, provide a translation. If grades are not in the U.S.-traditional lettered (A,B,C), or GPA (out of 4.0)...

  6. Final EIS for Decommissioning and/or Long-Term Stewardship at the WVDP and Western New York Nuclear Service Center

    Energy Savers [EERE]

    DOE/EIS-0226 January 2010 Final Environmental Impact Statement for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center A Summary and Guide for Stakeholders The West Valley Site 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

  7. Applied Materials | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search Name: Applied Materials Address: 3050 Bowers Avenue Place: Santa Clara, California Zip: 95054 Sector: Solar Website: www.appliedmaterials.com...

  8. Decontamination and decommissioning of the Chemical Process Cell (CPC): Topical report for the period January 1985-March 1987

    SciTech Connect (OSTI)

    Meigs, R. A.

    1987-07-01

    To support interim storage of vitrified High-Level Waste (HLW) at the West Valley Demonstration Project, the shielded, remotely operated Chemical Process Cell (CPC) was decommissioned and decontaminated. All equipment was removed, packaged and stored for future size reduction and decontamination. Floor debris was sampled, characterized, and vacuumed into remotely handled containers. The cell walls, ceiling, and floor were decontaminated. Three 20 Mg (22.5 ton) concrete neutron absorber cores were cut with a high-pressure water/abrasive jet cutting system and packaged for disposal. All operations were performed remotely using two overhead bridge cranes which included two 1.8 Mg (2 ton) hoists, one 14.5 Mg (16 ton) hoist, and an electromechanical manipulator or an industrial robot mounted on a mobile platform. Initial general area dose rates in the cell ranged from 1 to 50 R/h. Target levels of less than 10 mR/h general area readings were established before decontamination and decommissioning was initiated; general area dose rates between 200 mR/h and 1200 mR/h were obtained at the completion of the decontamination work. 4 refs., 11 figs., 8 tabs.

  9. Assessment, evaluation, and testing of technologies for environmental restoration, decontamination, and decommissioning and high level waste management. Progress report

    SciTech Connect (OSTI)

    Uzochukwu, G.A.

    1997-12-31

    Nuclear and commercial non-nuclear technologies that have the potential of meeting the environmental restoration, decontamination and decommissioning, and high-level waste management objectives are being assessed and evaluated. A detailed comparison of innovative technologies available will be performed to determine the safest and most economical technology for meeting these objectives. Information derived from this effort will be matched with the multi-objectives of the environmental restoration, decontamination and decommissioning, and high-level waste management effort to ensure that the best, most economical, and the safest technologies are used in decision making at USDOE-SRS. Technology-related variables will be developed and the resulting data formatted and computerized for multimedia systems. The multimedia system will be made available to technology developers and evaluators to ensure that the best, most economical, and the safest technologies are used in decision making at USDOE-SRS. Technology-related variables will be developed and the resulting data formatted and computerized for multimedia systems. The multimedia system will be made available to technology developers and evaluators to ensure that the safest and most economical technologies are developed for use at SRS and other DOE sites.

  10. DECOMMISSIONING THE HIGH PRESSURE TRITIUM LABORATORY AT LOS ALAMOS NATIONAL LABORATORY

    SciTech Connect (OSTI)

    Peifer, M.J.; Rendell, K.; Hearnsberger, D.W.

    2003-02-27

    In May 0f 2000, the Cerro Grande wild land fire burned approximately 48,000 acres in and around Los Alamos. In addition to the many buildings that were destroyed in the town site, many structures were also damaged and destroyed within the 43 square miles that comprise the Los Alamos National Laboratory (LANL). A special Act of Congress provided funding to remove Laboratory structures that were damaged by the fire, or that could be threatened by subsequent catastrophic wild land fires. The High Pressure Tritium Laboratory (HPTL) is located at Technical Area (TA) 33, building 86 in the far southeast corner of the Laboratory property. It is immediately adjacent to Bandelier National Park. Because it was threatened by both the Cerro Grande fire in 2000, and the 16,000- acre Dome fire in 1996, the former tritium processing facility was placed on the list of facilities scheduled for Decontamination and Decommissioning under the Cerro Grande Rehabilitation Project. The work was performed through the Facilities and Waste Operations (FWO) Division and is integrated with other Laboratory D&D efforts. The primary demolition contractor was Clauss Construction of San Diego, California. Earth Tech Global Environmental Services of San Antonio, Texas was sub-contracted to Clauss Construction, and provided radiological decontamination support to the project. Although the forty-seven year old facility had been in a state of safe-shutdown since operations ceased in 1990, a significant amount of tritium remained in the rooms where process systems were located. Tritium was the only radiological contaminant associated with this facility. Since no specific regulatory standards have been set for the release of volumetrically contaminated materials, concentration guidelines were derived in order to meet other established regulatory criteria. A tritium removal system was developed for this project with the goal of reducing the volume of tritium concentrated in the concrete of the building. The derived concentration guidelines, combined with the tritium removal system that was developed for this project, provided a significant timesaving for decontamination as well as an overall cost savings for waste disposal.

  11. USE OF CEMENTITIOUS MATERIALS FOR SRS REACTOR FACILITY IN-SITU DECOMMISSIONING - 11620

    SciTech Connect (OSTI)

    Langton, C.; Stefanko, D.; Serrato, M.; Blankenship, J.; Griffin, W.; Waymer, J.; Matheny, D.; Singh, D.

    2010-12-07

    The United States Department of Energy (US DOE) concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate in tact, structurally sound facilities that are no longer needed for their original purpose of, i.e., producing (reactor facilities), processing (isotope separation facilities) or storing radioactive materials. The Savannah River Site 105-P and 105-R Reactor Facility ISD requires about 250,000 cubic yards of grout to fill the below grade structure. The fills are designed to prevent subsidence, reduce water infiltration, and isolate contaminated materials. This work is being performed as a Comprehensive Environmental Response, Compensations and Liability Act (CERCLA) action and is part of the overall soil and groundwater completion projects for P- and R-Areas. Cementitious materials were designed for the following applications: (1) Below grade massive voids/rooms: Portland cement-based structural flowable fills for - Bulk filling, Restricted placement and Underwater placement. (2) Special below grade applications for reduced load bearing capacity needs: Cellular portland cement lightweight fill (3) Reactor vessel fills that are compatible with reactive metal (aluminum metal) components in the reactor vessels: Calcium sulfoaluminate flowable fill, and Magnesium potassium phosphate flowable fill. (4) Caps to prevent water infiltration and intrusion into areas with the highest levels of radionuclides: Portland cement based shrinkage compensating concrete. A system engineering approach was used to identify functions and requirements of the fill and capping materials. Laboratory testing was performed to identify candidate formulations and develop final design mixes. Scale-up testing was performed to verify material production and placement as well as fresh and cured properties. The 105-P and 105-R ISD projects are currently in progress and are expected to be complete in 2012. The focus of this paper is to describe the (1) grout mixes for filling the reactor vessels, and (2) a specialty grout mix to fill a selected portion of the P-Reactor Disassembly Basin. Details of the grout mixes designed for ISD of he SRS Reactor Disassembly Basins and below grade portions of the 105-Buildings was described elsewhere. Material property test results, placement strategies, full-scale production and delivery systems will also be described.

  12. Applied Materials | Argonne National Laboratory

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

    Applied Materials Argonne's nanocomposite charge drain coatings represent a significant breakthrough in the effort to develop microelectromechanical systems, or MEMS. Argonne's nanocomposite charge drain coatings represent a significant breakthrough in the effort to develop microelectromechanical systems, or MEMS. Argonne is a leading technology developer with the advanced manufacturing industry and government sponsors and clients. The emphasis is on applied technology demonstration that often

  13. Annual summary report on the Decontamination and Decommissioning Program at the Oak Ridge Y-12 Plant for the period ending September 30, 1992. Environmental Restoration Program

    SciTech Connect (OSTI)

    Not Available

    1993-02-01

    The Y-12 Decontamination and Decommissioning (D&D) Program provides for the ultimate disposition of plant process buildings and their supporting facilities. The overall objective is to enable the Y-12 Plant to meet applicable environmental regulations and Department of Energy (DOE) orders to protect human health and the environment from contaminated facilities through decommissioning activities. This objective is met by providing for the surveillance and maintenance (S&M) of accepted standby or shutdown facilities awaiting decommissioning; planning for decommissioning of these facilities; and implementing a program to accomplish the safe, cost-effective, and orderly disposition of contaminated facilities. The Y-12 D&D Program was organized during FY 1992 to encompass the needs of surplus facilities at the Y-12 Plant. The need existed for a program which would include Weapons Program facilities as well as other facilities used by several programs within the Y-12 Plant. Building 9201-4 (Alpha 4) is the only facility that is formally in the D&D Program. Funding for the work completed in FY 1992 was shared by the Environmental Restoration and Waste Management Program (EW-20) and Weapons Operations (GB-92). This report summarizes the FY 1992 D&D activities associated with Building 9201-4. A section is provided for each task; the tasks include surveillance, routine and special maintenance, safety, and D&D planning.

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

    SciTech Connect (OSTI)

    Milchikov, A.; Hund, G.; Davidko, M.

    1999-10-20

    The primary objectives of this project are to learn how to plan and execute the Technology Scanning and Assessment (TSA) approach by conducting a project and to be able to provide the approach as a capability to the Chernobyl Nuclear Power Plant (ChNPP) and potentially elsewhere. A secondary objective is to learn specifics about decommissioning and in particular about radiological surveying to be performed prior to decommissioning to help ChNPP decision makers. TSA is a multi-faceted capability that monitors and analyzes scientific, technical, regulatory, and business factors and trends for decision makers and company leaders. It is a management tool where information is systematically gathered, analyzed, and used in business planning and decision making. It helps managers by organizing the flow of critical information and provides managers with information they can act upon. The focus of this TSA project is on radiological surveying with the target being ChNPP's Unit 1. This reactor was stopped on November 30, 1996. At this time, Ukraine failed to have a regulatory basis to provide guidelines for nuclear site decommissioning. This situation has not changed as of today. A number of documents have been prepared to become a basis for a combined study of the ChNPP Unit 1 from the engineering and radiological perspectives. The results of such a study are expected to be used when a detailed decommissioning plan is created.

  15. Applied Sedimentology | Open Energy Information

    Open Energy Info (EERE)

    Sedimentology Jump to: navigation, search OpenEI Reference LibraryAdd to library Book: Applied Sedimentology Author R.C. Salley Published Academic Press, 2000 DOI Not Provided...

  16. Physical Chemistry and Applied Spectroscopy

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

    PCS Physical Chemistry and Applied Spectroscopy We perform basic and applied research in support of the Laboratory's national security mission and serve a wide range of customers. Contact Us Group Leader Kirk Rector Deputy Group Leader Jeff Pietryga Group Office (505) 667-7121 Postdoctoral researcher Young-Shin Park characterizing emission spectra of LEDs in the Los Alamos National Laboratory optical laboratory. Postdoctoral researcher Young-Shin Park characterizing emission spectra of LEDs in

  17. Information Science, Computing, Applied Math

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

    Information Science, Computing, Applied Math /science-innovation/_assets/images/icon-science.jpg Information Science, Computing, Applied Math National security depends on science and technology. The United States relies on Los Alamos National Laboratory for the best of both. No place on Earth pursues a broader array of world-class scientific endeavors. Computer, Computational, and Statistical Sciences (CCS)» High Performance Computing (HPC)» Extreme Scale Computing, Co-design» supercomputing

  18. Environmental Regulation of the Nuclear Industry in England and Wales in an era of Restructuring and Accelerated Decommissioning

    SciTech Connect (OSTI)

    Parker, I.W.; Weedon, C. J.

    2006-07-01

    In 2005 a large part of the UK Nuclear Industry was restructured with a new national body, the Nuclear Decommissioning Authority (NDA), being responsible for all the assets and liabilities of the nationally owned reactors and fuel cycle facilities. The former owners are now operating and in many cases decommissioning the facilities under contract to the NDA. As the body responsible for enforcing most environmental legislation in England and Wales, the Environment Agency has reviewed its regulatory approach to the Industry. This is to ensure that our responsibility to protect and enhance the environment is met whilst considering appropriately other key drivers impacting on all sectors of environmental regulation. Factors influencing this review include: - Greater public interest and concern over nuclear issues; - Greater transparency of strategies, plans and decisions in the nuclear industry; - The need to ensure that sustainable protection of the environment remains a constant feature of environmental regulation; - The need for a proportionate approach to regulation in the non-prescriptive UK legislative system; - Being effective and efficient in a period when all types of regulation are under Government and public scrutiny; - The aim of the NDA to achieve safe, secure, cost-effective, accelerated and environmentally responsible decommissioning and clean up in part by competing the management of the facilities. This has involved - Constructive liaison with the NDA both before and after its commencement to ensure we are both aware of each other's concerns; - Taking a strong influencing role at strategic and operational levels; - Putting in position arrangements for our involvement in the competitive process; - Liaison at an early stage with the industry's plans for future work; - Establishing greater clarity in our strategy and plans, notably with re-examination of the requirements of our authorisations and permits; - Establishing a new assessment resource (the Nuclear Waste Assessment Team, NWAT) to enable us to examine proposals for waste management while awaiting the establishment of a national strategy; - Seeking the modernising of legislation and exerting pressure on UK government for relevant legislative/policy changes; - Improved links to safety and security regulators; - Developing our own Environmental Assessment Principles to assist regulators and the industry on the issues to be addressed; - Speeding up, where possible, our processes for determination of applications and transfers of authorisations, to allow industry restructuring. The position is dynamic and we continue to work with Industry, the NDA and other regulators to ensure we meet our respective goals. (authors)

  19. Revised analyses of decommissioning for the reference boiling water reactor power station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure: Appendices, draft report for comment. Volume 2

    SciTech Connect (OSTI)

    Smith, R.I.; Bierschbach, M.C.; Konzek, G.J.

    1994-09-01

    On June 27, 1988, the U.S. Nuclear Regulatory Commission (NRC) published in the Federal Register (53 FR 24018) the final rule for the General Requirements for Decommissioning Nuclear Facilities. With the issuance of the final rule, owners and operators of licensed nuclear power plants are required to prepare, and submit to the NRC for review, decommissioning plans and cost estimates. The NRC staff is in need of updated bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to update the needed bases documentation. This report presents the results of a review and reevaluation of the PNL 1980 decommissioning study of the Washington Public Power Supply System`s WNP-2, including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives, which now include an initial 5-7 year period during which time the spent fuel is stored in the spent fuel pool prior to beginning major disassembly or extended safe storage of the plant. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste. Costs for labor, materials, transport, and disposal activities are given in 1993 dollars. Sensitivities of the total license termination cost to the disposal costs at different low-level radioactive waste disposal sites, to different depths of contaminated concrete surface removal within the facilities, and to different transport distances are also examined.

  20. Summary of events and geotechnical factors leading to decommissioning of the Strategic Petroleum Reserve (SPR) facility at Weeks Island, Louisiana

    SciTech Connect (OSTI)

    Neal, J.T.; Bauer, S.J.; Ehgartner, B.L.

    1996-10-01

    A sinkhole discovered over the edge of the Strategic Petroleum Reserve storage facility at Weeks Island salt dome, Louisiana, led to decommissioning the site during 1995--1998, following extensive diagnostics in 1994. The sinkhole resulted from mine-induced fractures in the salt which took may years to develop, eventually causing fresh water to leak into the storage chamber and dissolve the overlying salt, thus causing overburden collapse into the void. Prior to initiating the oil removal, a freeze wall was constructed at depth around the sinkhole in 1995 to prevent water inflow; a freeze plug will remain in place until the mine is backfilled with brine in 1997--8, and stability is reached. Residual oil will be removed; environmental monitoring has been initiated and will continue until the facility is completely plugged and abandoned, and environmental surety is achieved.

  1. Environmental assessment for the construction, operation, and decommissioning of the Waste Segregation Facility at the Savannah River Site

    SciTech Connect (OSTI)

    1998-01-01

    This Environmental Assessment (EA) has been prepared by the Department of Energy (DOE) to assess the potential environmental impacts associated with the construction, operation and decontamination and decommissioning (D&D) of the Waste Segregation Facility (WSF) for the sorting, shredding, and compaction of low-level radioactive waste (LLW) at the Savannah River Site (SRS) located near Aiken, South Carolina. The LLW to be processed consists of two waste streams: legacy waste which is currently stored in E-Area Vaults of SRS and new waste generated from continuing operations. The proposed action is to construct, operate, and D&D a facility to process low-activity job-control and equipment waste for volume reduction. The LLW would be processed to make more efficient use of low-level waste disposal capacity (E-Area Vaults) or to meet the waste acceptance criteria for treatment at the Consolidated Incineration Facility (CIF) at SRS.

  2. 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)

  3. CRC handbook of applied thermodynamics

    SciTech Connect (OSTI)

    Palmer, D.A. . Research and Development Dept.)

    1987-01-01

    The emphasis of this book is on applied thermodynamics, featuring the stage of development of a process rather than the logical development of thermodynamic principles. It is organized according to the types of problems encountered in industry, such as probing research, process assessment, and process development. The applied principles presented can be used in most areas of industry including oil and gas production and processing, chemical processing, power generation, polymer production, food processing, synthetic fuels production, specialty chemicals and pharmaceuticals production, bioengineered processes, etc.

  4. Researcher, Los Alamos National Laboratory - Applied Physics...

    National Nuclear Security Administration (NNSA)

    Applied Physics Division | National Nuclear Security Administration Facebook Twitter ... Researcher, Los Alamos National Laboratory - Applied Physics Division Stephen Becker ...

  5. Summer of Applied Geophysical Experience

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

    Summer of Applied Geophysical Experience (SAGE) 2016 - Our 34 rd Year! SAGE is a 3-4 week research and education program in exploration geophysics for graduate, undergraduate students, and working professionals based in Santa Fe, NM, U.S.A. Application deadline March 27, 2016, 5:00pm MDT SAGE students, faculty, teaching assistants, and visiting scientists acquire, process and interpret reflection/refraction seismic, magnetotelluric (MT)/electromagnetic (EM), ground penetrating radar (GPR),

  6. Applied Mathematics and Plasma Physics

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

    5 Applied Mathematics and Plasma Physics Maintaining mathematic, theory, modeling, and simulation capabilities in a broad set of areas Leadership Group Leader Pieter Swart Email Deputy Group Leader (Acting) Luis Chacon Email Contact Us Administrator Charlotte Lehman Email Electron density simulation Electron density from an orbital-free quantum molecular dynamics simulation for a warm dense plasma of deuterium at density 10 g/cc and temperature 10 eV. Mathematical, theory, modeling, and

  7. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 18. Part 1A: Citations with abstracts, sections 1 through 9

    SciTech Connect (OSTI)

    1997-09-01

    This bibliography contains 3,638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D and D), uranium mill tailings management, and site remedial actions. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration program; (2) DOE D and D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized Sites Remedial Action Program; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluation; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues.

  8. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 18. Part 1B: Citations with abstracts, sections 10 through 16

    SciTech Connect (OSTI)

    1997-09-01

    This bibliography contains 3,638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D and D), uranium mill tailings management, and site remedial actions. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration Program; (2) DOE D and D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized sites Remedial Action Program; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluation; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues.

  9. DECOMMISSIONING DOCUMENTS Decommissioning Handbook The Decommissioning Handbook has

    Office of Environmental Management (EM)

    Department of Energy EAC 2008 Meetings » DECEMBER 11, 2008 MEETING OF THE ELECTRICITY ADVISORY COMMITTEE DECEMBER 11, 2008 MEETING OF THE ELECTRICITY ADVISORY COMMITTEE DECEMBER 11, 2008 MEETING OF THE ELECTRICITY ADVISORY COMMITTEE DATE Thursday, December 11, 2008, 9:00 a.m. - 4:00 p.m. LOCATION Marriott Crystal City at Reagan National Airport; 1999 Jefferson Davis Highway; Arlington, Virginia; Potomac Salon D-E OVERVIEW The Department of Energy's Electricity Advisory Committee held its

  10. International combustion engines; Applied thermosciences

    SciTech Connect (OSTI)

    Ferguson, C.R.

    1985-01-01

    Focusing on thermodynamic analysis - from the requisite first law to more sophisticated applications - and engine design, this book is an introduction to internal combustion engines and their mechanics. It covers the many types of internal combustion engines, including spark ignition, compression ignition, and stratified charge engines, and examines processes, keeping equations of state simple by assuming constant specific heats. Equations are limited to heat engines and later applied to combustion engines. Topics include realistic equations of state, stroichiometry, predictions of chemical equilibrium, engine performance criteria, and friction, which is discussed in terms of the hydrodynamic theory of lubrication and experimental methods such as dimensional analysis.

  11. Decommissioning of German Research Reactors Under the Governance of the Federal Ministry of Education and Research - 12154

    SciTech Connect (OSTI)

    Weigl, M. [Karlsruhe Institute of Technology, Projekttraeger Karlsruhe (PTKA-WTE), Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany)

    2012-07-01

    Since 1956, nuclear research and development (R and D) in Germany has been supported by the Federal Government. The goal was to help German industry to become competitive in all fields of nuclear technology. National research centers were established and demonstration plants were built. In the meantime, all these facilities were shut down and are now in a state of decommissioning and dismantling (D and D). Meanwhile, Germany is one of the leading countries in the world in the field of D and D. Two big demonstration plants, the Niederaichbach Nuclear Power Plant (KKN) a heavy-water cooled pressure tube reactor with carbon-dioxide cooling and the Karlstein Superheated Steam Reactor (HDR) a boiling light water reactor with a thermal power of 100 MW, are totally dismantled and 'green field' is reached. Another big project was finished in 2008. The Forschungs-Reaktor Juelich 1 (FRJ1), a research reactor with a thermal power of 10 MW was completely dismantled and in September 2008 an oak tree was planted on a green field at the site, where the FRJ1 was standing before. This is another example for German success in the field of D and D. Within these projects a lot of new solutions and innovative techniques were tested, which were developed at German universities and in small and medium sized companies mostly funded by the Federal Ministry of Education and Research (BMBF). Some examples are underwater-cutting technologies like plasma arc cutting and contact arc metal cutting. This clearly shows that research on the field of D and D is important for the future. Moreover, these research activities are important to save the know-how in nuclear engineering in Germany and will enable enterprises to compete on the increasing market of D and D services. The author assumes that an efficient decommissioning of nuclear installations will help stabilize the credibility of nuclear energy. Some critics of nuclear energy are insisting that a return to 'green field sites' is not possible. The successful completion of two big D and D projects (HDR and KKN), which reached green field conditions, are showing quite the contrary. Moreover, research on D and D technologies offers the possibility to educate students on a field of nuclear technology, which will be very important in the future. In these days D and D companies are seeking for a lot of young engineers and this will not change in the coming years. (authors)

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

    SciTech Connect (OSTI)

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

    2012-01-18

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

  13. Fukushima Daiichi Unit 1 Accident Progression Uncertainty Analysis and Implications for Decommissioning of Fukushima Reactors - Volume I.

    SciTech Connect (OSTI)

    Gauntt, Randall O.; Mattie, Patrick D.

    2016-01-01

    Sandia National Laboratories (SNL) has conducted an uncertainty analysis (UA) on the Fukushima Daiichi unit (1F1) accident progression with the MELCOR code. The model used was developed for a previous accident reconstruction investigation jointly sponsored by the US Department of Energy (DOE) and Nuclear Regulatory Commission (NRC). That study focused on reconstructing the accident progressions, as postulated by the limited plant data. This work was focused evaluation of uncertainty in core damage progression behavior and its effect on key figures-of-merit (e.g., hydrogen production, reactor damage state, fraction of intact fuel, vessel lower head failure). The primary intent of this study was to characterize the range of predicted damage states in the 1F1 reactor considering state of knowledge uncertainties associated with MELCOR modeling of core damage progression and to generate information that may be useful in informing the decommissioning activities that will be employed to defuel the damaged reactors at the Fukushima Daiichi Nuclear Power Plant. Additionally, core damage progression variability inherent in MELCOR modeling numerics is investigated.

  14. BLENDED CALCIUM ALUMINATE-CALCIUM SULFATE CEMENT-BASED GROUT FOR P-REACTOR VESSEL IN-SITU DECOMMISSIONING

    SciTech Connect (OSTI)

    Langton, C.; Stefanko, D.

    2011-03-10

    The objective of this report is to document laboratory testing of blended calcium aluminate - calcium hemihydrate grouts for P-Reactor vessel in-situ decommissioning. Blended calcium aluminate - calcium hemihydrate cement-based grout was identified as candidate material for filling (physically stabilizing) the 105-P Reactor vessel (RV) because it is less alkaline than portland cement-based grout which has a pH greater than 12.4. In addition, blended calcium aluminate - calcium hemihydrate cement compositions can be formulated such that the primary cementitious phase is a stable crystalline material. A less alkaline material (pH {<=} 10.5) was desired to address a potential materials compatibility issue caused by corrosion of aluminum metal in highly alkaline environments such as that encountered in portland cement grouts [Wiersma, 2009a and b, Wiersma, 2010, and Serrato and Langton, 2010]. Information concerning access points into the P-Reactor vessel and amount of aluminum metal in the vessel is provided elsewhere [Griffin, 2010, Stefanko, 2009 and Wiersma, 2009 and 2010, Bobbitt, 2010, respectively]. Radiolysis calculations are also provided in a separate document [Reyes-Jimenez, 2010].

  15. Decommissioning and Dismantling of Liquid Waste Storage and Liquid Waste Treatment Facility from Paldiski Nuclear Site, Estonia

    SciTech Connect (OSTI)

    Varvas, M.; Putnik, H.; Johnsson, B.

    2006-07-01

    The Paldiski Nuclear Facility in Estonia, with two nuclear reactors was owned by the Soviet Navy and was used for training the navy personnel to operate submarine nuclear reactors. After collapse of Soviet Union the Facility was shut down and handed over to the Estonian government in 1995. In co-operation with the Paldiski International Expert Reference Group (PIERG) decommission strategy was worked out and started to implement. Conditioning of solid and liquid operational waste and dismantling of contaminated installations and buildings were among the key issues of the Strategy. Most of the liquid waste volume, remained at the Facility, was processed in the frames of an Estonian-Finnish co-operation project using a mobile wastewater purification unit NURES (IVO International OY) and water was discharged prior to the site take-over. In 1999-2002 ca 120 m{sup 3} of semi-liquid tank sediments (a mixture of ion exchange resins, sand filters, evaporator and flocculation slurry), remained after treatment of liquid waste were solidified in steel containers and stored into interim storage. The project was carried out under the Swedish - Estonian co-operation program on radiation protection and nuclear safety. Contaminated installations in buildings, used for treatment and storage of liquid waste (Liquid Waste Treatment Facility and Liquid Waste Storage) were then dismantled and the buildings demolished in 2001-2004. (authors)

  16. Building America Expert Meeting: Recommendations for Applying...

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

    Recommendations for Applying Water Heaters in Combination Space and Domestic Water Heating Systems Building America Expert Meeting: Recommendations for Applying Water Heaters in ...

  17. Applied Ventures LLC | Open Energy Information

    Open Energy Info (EERE)

    Applied Ventures LLC Name: Applied Ventures LLC Address: 3050 Bowers Avenue Place: Santa Clara, California Zip: 95054 Region: Southern CA Area Product: Venture capital. Number...

  18. Applied Materials Wind Turbine | Open Energy Information

    Open Energy Info (EERE)

    Wind Turbine Jump to: navigation, search Name Applied Materials Wind Turbine Facility Applied Materials Sector Wind energy Facility Type Community Wind Facility Status In Service...

  19. Applied Intellectual Capital AIC | Open Energy Information

    Open Energy Info (EERE)

    Intellectual Capital AIC Jump to: navigation, search Name: Applied Intellectual Capital (AIC) Place: California Zip: 94501-1010 Product: Applied Intellectual Capital (AIC) was...

  20. REGULATORY STRATEGIES TO MINIMIZE GENERATION OF REGULATED WASTES FROM CLEANUP, CONTINUED USE OR DECOMMISSIONING OF NUCLEAR FACILITIES CONTAMINATED WITH POLYCHLORINATED BIPHENYLS (PCBS) - 11198

    SciTech Connect (OSTI)

    Lowry, N.

    2010-11-05

    Disposal costs for liquid PCB radioactive waste are among the highest of any category of regulated waste. The high cost is driven by the fact that disposal options are extremely limited. Toxic Substances Control Act (TSCA) regulations require most liquids with PCBs at concentration of {ge} 50 parts-per-million to be disposed by incineration or equivalent destructive treatment. Disposal fees can be as high as $200 per gallon. This figure does not include packaging and the cost to transport the waste to the disposal facility, or the waste generator's labor costs for managing the waste prior to shipment. Minimizing the generation of liquid radioactive PCB waste is therefore a significant waste management challenge. PCB spill cleanups often generate large volumes of waste. That is because the removal of PCBs typically requires the liberal use of industrial solvents followed by a thorough rinsing process. In a nuclear facility, the cleanup process may be complicated by the presence of radiation and other occupational hazards. Building design and construction features, e.g., the presence of open grating or trenches, may also complicate cleanup. In addition to the technical challenges associated with spill cleanup, selection of the appropriate regulatory requirements and approach may be challenging. The TSCA regulations include three different sections relating to the cleanup of PCB contamination or spills. EPA has also promulgated a separate guidance policy for fresh PCB spills that is published as Subpart G of 40 CFR 761 although it is not an actual regulation. Applicability is based on the circumstances of each contamination event or situation. Other laws or regulations may also apply. Identification of the allowable regulatory options is important. Effective communication with stakeholders, particularly regulators, is just as important. Depending on the regulatory path that is taken, cleanup may necessitate the generation of large quantities of regulated waste. Allowable options must be evaluated carefully in order to reduce compliance risks, protect personnel, limit potential negative impacts on facility operations, and minimize the generation of wastes subject to TSCA. This paper will identify critical factors in selecting the appropriate TSCA regulatory path in order to minimize the generation of radioactive PCB waste and reduce negative impacts to facilities. The importance of communicating pertinent technical issues with facility staff, regulatory personnel, and subsequently, the public, will be discussed. Key points will be illustrated by examples from five former production reactors at the DOE Savannah River Site. In these reactors a polyurethane sealant was used to seal piping penetrations in the biological shield walls. During the intense neutron bombardment that occurred during reactor operation, the sealant broke down into a thick, viscous material that seeped out of the piping penetrations over adjacent equipment and walls. Some of the walls were painted with a PCB product. PCBs from the paint migrated into the degraded sealant, creating PCB 'spill areas' in some of these facilities. The regulatory cleanup approach selected for each facility was based on its operational status, e.g., active, inactive or undergoing decommissioning. The selected strategies served to greatly minimize the generation of radioactive liquid PCB waste. It is expected that this information would be useful to other DOE sites, DOD facilities, and commercial nuclear facilities constructed prior to the 1979 TSCA ban on most manufacturing and uses of PCBs.

  1. Sorption (Kd) measurements on cinder block and grout in support of dose assessments for Zion Nuclear Station decommissioning

    SciTech Connect (OSTI)

    Milian L.; Sullivan T.

    2014-06-24

    The Zion Nuclear Power Station is being decommissioned. ZionSolutions proposes to leave much of the below grade structures in place and to fill them with a backfill to provide structural support. Backfills under consideration include clean concrete demolition debris from the above grade parts of the facility, a flowable grout, cinder block construction debris and sand. A previous study (Yim, 2012) examined the sorption behavior of five nuclides (Fe-55, Co-60, Ni-63, Sr-85, and Cs-137) on concrete and local soils. This study, commissioned by ZionSolutions and conducted by the Brookhaven National Laboratory (BNL) examines the sorption behavior on cinder block and grout materials. Specifically, this study measured the distribution coefficient for four radionuclides of concern using site-groundwater and cinder block from the Zion site and a flowable grout. The distributions coefficient is a measure of the amount of the radionuclide that will remain sorbed to the solid material that is present relative to the amount that will remain in solution. A high distribution coefficient indicates most of the radionuclide will remain on the solid material and will not be available for transport by the groundwater. The radionuclides examined in this set of tests were Co-60, Ni-63, Sr-85, and Cs-137. Tests were performed following ASTM C1733-10, Standard Test Methods for Distribution Coefficients of Inorganic Species by the Batch Method. Sr-85 was used in the testing as an analogue for Sr-90 because it behaves similarly with respect to sorption and has a gamma emission that is easier to detect than the beta emission from Sr-90.

  2. Pilot-scale treatability testing -- Recycle, reuse, and disposal of materials from decontamination and decommissioning activities: Soda blasting demonstration

    SciTech Connect (OSTI)

    1995-08-01

    The US Department of Energy (DOE) is in the process of defining the nature and magnitude of decontamination and decommissioning (D and D) obligations at its sites. With disposal costs rising and available storage facilities decreasing, DOE is exploring and implementing new waste minimizing D and D techniques. Technology demonstrations are being conducted by LMES at a DOE gaseous diffusion processing plant, the K-25 Site, in Oak Ridge, Tennessee. The gaseous diffusion process employed at Oak Ridge separated uranium-235 from uranium ore for use in atomic weapons and commercial reactors. These activities contaminated concrete and other surfaces within the plant with uranium, technetium, and other constituents. The objective of current K-25 D and D research is to make available cost-effective and energy-efficient techniques to advance remediation and waste management methods at the K-25 Site and other DOE sites. To support this objective, O`Brien and Gere tested a decontamination system on K-25 Site concrete and steel surfaces contaminated with radioactive and hazardous waste. A scouring system has been developed that removes fixed hazardous and radioactive surface contamination and minimizes residual waste. This system utilizes an abrasive sodium bicarbonate medium that is projected at contaminated surfaces. It mechanically removes surface contamination while leaving the surface intact. Blasting residuals are captured and dissolved in water and treated using physical/chemical processes. Pilot-scale testing of this soda blasting system and bench and pilot-scale treatment of the generated residuals were conducted from December 1993 to September 1994.

  3. Alternatives evaluation and decommissioning study on shielded transfer tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    DeVore, J.R.; Hinton, R.R.

    1994-08-01

    The shielded transfer tanks (STTs) are five obsolete cylindrical shipping casks which were used to transport high specific activity radioactive solutions by rail during the 1960s and early 1970s. The STTs are currently stored at the Oak Ridge National Laboratory under a shed roof. This report is an evaluation to determine the preferred alternative for the final disposition of the five STTs. The decommissioning alternatives assessed include: (1) the no action alternative to leave the STTs in their present location with continued surveillance and maintenance; (2) solidification of contents within the tanks and holding the STTs in long term retrievable storage; (3) sale of one or more of the used STTs to private industry for use at their treatment facility with the remaining STTs processed as in Alternative 4; and (4) removal of tank contents for de-watering/retrievable storage, limited decontamination to meet acceptance criteria, smelting the STTs to recycle the metal through the DOE contaminated scrap metal program, and returning the shielding lead to the ORNL lead recovery program because the smelting contractor cannot reprocess the lead. To completely evaluate the alternatives for the disposition of the STTs, the contents of the tanks must be characterized. Shielding and handling requirements, risk considerations, and waste acceptance criteria all require that the radioactive inventory and free liquids residual in the STTs be known. Because characterization of the STT contents in the field was not input into a computer model to predict the probable inventory and amount of free liquid. The four alternatives considered were subjected to a numerical scoring procedure. Alternative 4, smelting the STTs to recycle the metal after removal/de-watering of the tank contents, had the highest score and is, therefore, recommended as the preferred alternative. However, if a buyer for one or more STT could be found, it is recommended that Alternative 3 be reconsidered.

  4. Decommissioning of German Nuclear Research Facilities under the Governance of the Federal Ministry of Education and Research

    SciTech Connect (OSTI)

    Weigl, M. [Forschungszentrum Karlsruhe GmbH, Projekttragerforschungszentrum Karlsruhe (PTKA-WTE), Karlsruhe (Germany)

    2008-07-01

    Since the announcement of the first nuclear program in 1956, nuclear R and D in Germany has been supported by the Federal Government under four nuclear programs and later on under more general energy R and D programs. The original goal was to help German industry to achieve safe, low-cost generation of energy and self-sufficiency in the various branches of nuclear technology, including the fast breeder reactor and the fuel cycle. Several national research centers were established to host or operate experimental and demonstration plants. These are mainly located at the sites of the national research centers at Juelich and Karlsruhe. In the meantime, all these facilities were shut down and most of them are now in a state of decommissioning and dismantling (D and D). Meanwhile, Germany is one of the leading countries in the world in the field of D and D. Two big demonstration plants, the Niederaichbach Nuclear Power Plant (KKN) a heavy-water cooled pressure tube reactor with carbon-dioxide cooling and the Karlstein Superheated Steam Reactor (HDR) a boiling light water reactor with a thermal power of 100 MW, are totally dismantled and 'green field' is reached. For two other projects the return to 'green field' sites will be reached by the end of this decade. These are the dismantling of the Multi-Purpose Research Reactor (MZFR) and the Compact Sodium Cooled Reactor (KNK) both located at the Forschungszentrum Karlsruhe. Within these projects a lot of new solutions und innovative techniques were tested, which were developed at German universities and in small and medium sized companies mostly funded by the Federal Ministry of Education and Research (BMBF). For example, high performance underwater cutting technologies like plasma arc cutting and contact arc metal cutting. (authors)

  5. Applied Mathematics Conferences and Workshops | U.S. DOE Office...

    Office of Science (SC) Website

    Applied Mathematics Applied Mathematics Conferences And Workshops Advanced Scientific Computing Research (ASCR) ASCR Home About Research Applied Mathematics Applied Mathematics ...

  6. Annual summary report of the Decontamination and Decommissioning Surveillance and Maintenance Program at Oak Ridge National Laboratory for period ending September 30, 1994

    SciTech Connect (OSTI)

    Anderson, L.A.; Burwinkle, T.W.; Ford, M.K.; Gaddis, H.R.; Holder, L. Jr.; Mandry, G.J.; Nelson, T.R.; Patton, B.D.

    1995-03-01

    The Surplus Facilities Management Program (SFMP) was established at Oak Ridge National Laboratory (ORNL) in 1976 to provide collective management of all surplus sites under ORNL`s control on the Oak Ridge Reservation. Presently, over 50 facilities, grouped into projects, are currently managed by the Decontamination and Decommissioning Program, the successor program to the SFMP. Support includes (1) surveillance and maintenance planning; (2) routine surveillance and maintenance; and (3) special maintenance projects. This report documents routine surveillance and maintenance, special projects, and special maintenance performed on these facilities for the period of October 1993 through September 1994.

  7. Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 6, Decontamination and decommissioning, accident management, TMI-2

    SciTech Connect (OSTI)

    Weiss, A. J.

    1988-02-01

    This six-volume report contains 140 papers out of the 164 that were presented at the Fifteenth Water Reactor Safety Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 26-29, 1987. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. This report, Volume 6, discusses decontamination and decommissioning, accident management, and the Three Mile Island-2 reactor accident. Thirteen reports have been cataloged separately.

  8. Apply for Beam Time | Advanced Photon Source

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

    All About Proposals Users Home Apply for Beam Time Deadlines Proposal Types Concepts, Definitions, and Help My APS Portal My APS Portal Apply for Beam Time Next Proposal Deadline...

  9. How to Apply for the ENERGY STAR®

    Broader source: Energy.gov [DOE]

    Join us to learn about applying for ENERGY STAR Certification in Portfolio Manager. Understand the value of the ENERGY STAR certification, see the step-by-step process of applying, and gain tips to...

  10. Decommissioning of the Dragon High Temperature Reactor (HTR) Located at the Former United Kingdom Atomic Energy Authority (UKAEA) Research Site at Winfrith - 13180

    SciTech Connect (OSTI)

    Smith, Anthony A.

    2013-07-01

    The Dragon Reactor was constructed at the United Kingdom Atomic Energy Research Establishment at Winfrith in Dorset through the late 1950's and into the early 1960's. It was a High Temperature Gas Cooled Reactor (HTR) with helium gas coolant and graphite moderation. It operated as a fuel testing and demonstration reactor at up to 20 MW (Thermal) from 1964 until 1975, when international funding for this project was terminated. The fuel was removed from the core in 1976 and the reactor was put into Safestore. To meet the UK's Nuclear Decommissioning Authority (NDA) objective to 'drive hazard reduction' [1] it is necessary to decommission and remediate all the Research Sites Restoration Ltd (RSRL) facilities. This includes the Dragon Reactor where the activated core, pressure vessel and control rods and the contaminated primary circuit (including a {sup 90}Sr source) still remain. It is essential to remove these hazards at the appropriate time and return the area occupied by the reactor to a safe condition. (author)

  11. Y-12 Plant decontamination and decommissioning technology logic diagram for Building 9201-4. Volume 3: Technology evaluation data sheets; Part A: Characterization, dismantlement

    SciTech Connect (OSTI)

    1994-09-01

    The Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4 (TLD) was developed to provide a decision-support tool that relates decontamination and decommissioning (D and D) problems at Bldg. 9201-4 to potential technologies that can remediate these problems. The TLD uses information from the Strategic Roadmap for the Oak Ridge Reservation, the Oak Ridge K-25 Site Technology Logic Diagram, the Oak Ridge National Laboratory Technology Logic Diagram, and a previous Hanford logic diagram. This TLD identifies the research, development, demonstration, testing, and evaluation needed for sufficient development of these technologies to allow for technology transfer and application to D and D and waste management (WM) activities. It is essential that follow-on engineering studies be conducted to build on the output of this project. These studies will begin by selecting the most promising technologies identified in the TLD and by finding an optimum mix of technologies that will provide a socially acceptable balance between cost and risk. This report consists of the characterization and dismantlement data sheets.

  12. SOME RECENT TECHNOLOGY DEVELOPMENTS FROM THE UK'S NATIONAL NUCLEAR LABORATORY TO ENABLE HAZARD CHARACTERISATION FOR NUCLEAR DECOMMISSIONING APPLICATIONS

    SciTech Connect (OSTI)

    Farfan, E.; Foley, T.

    2010-02-11

    Under its programme of self investment Internal Research and Development (IR&D), the UK's National Nuclear Laboratory (NNL) is addressing the requirement for development in technology to enable hazard characterisation for nuclear decommissioning applications. Three such examples are described here: (1) RadBall developed by the NNL (patent pending) is a deployable baseball-sized radiation mapping device which can, from a single location, locate and quantify radiation hazards. RadBall offers a means to collect information regarding the magnitude and distribution of radiation in a given cell, glovebox or room to support the development of a safe, cost effective decontamination strategy. RadBall requires no electrical supplies and is relatively small, making it easy to be deployed and used to map radiation hazards in hard to reach areas. Recent work conducted in partnership with the Savannah River National Laboratory (SRNL) is presented. (2) HiRAD (patent pending) has been developed by the NNL in partnership with Tracerco Ltd (UK). HiRAD is a real-time, remotely deployed, radiation detection device designed to operate in elevated levels of radiation (i.e. thousands and tens of thousands of Gray) as seen in parts of the nuclear industry. Like the RadBall technology, the HiRAD system does not require any electrical components, the small dimensions and flexibility of the device allow it to be positioned in difficult to access areas (such as pipe work). HiRAD can be deployed as a single detector, a chain, or as an array giving the ability to monitor large process areas. Results during the development and deployment of the technology are presented. (3) Wireless Sensor Network is a NNL supported development project led by the University of Manchester (UK) in partnership with Oxford University (UK). The project is concerned with the development of wireless sensor network technology to enable the underwater deployment and communication of miniaturised probes allowing pond monitoring and mapping. The potential uses, within the nuclear sector alone, are both numerous and significant in terms of the proceeding effort to clean up the UK's nuclear waste legacy.

  13. ASSESSMENT OF THE POTENTIAL FOR HYDROGEN GENERATION DURING DEACTIVATION AND DECOMMISSIONING OF REACTOR VESSELS AT THE SAVANNAH RIVER SITE

    SciTech Connect (OSTI)

    Wiersma, B.; Serrato, M.; Langton, C.

    2010-11-10

    The R- and P-reactor vessels at the Savannah River Site (SRS) are being prepared for deactivation and decommissioning (D&D). D&D activities will consist primarily of physically isolating and stabilizing the reactor vessel by filling it with a grout material. The reactor vessels contain aluminum alloy materials, which pose a concern in that aluminum corrodes rapidly when it comes in contact with the alkaline grout. A product of the corrosion reaction is hydrogen gas and therefore potential flammability issues were assessed. A model was developed to calculate the hydrogen generation rate as the reactor is being filled with the grout material. Three options existed for the type of grout material for D&D of the reactor vessels. The grout formulation options included ceramicrete (pH 6-8), a calcium aluminate sulfate (CAS) based cement (pH 10), or Portland cement grout (pH 12.4). Corrosion data for aluminum in concrete were utilized as input for the model. The calculations considered such factors as the surface area of the aluminum components, the open cross-sectional area of the reactor vessel, the rate at which the grout is added to the reactor vessel, and temperature. Given the hydrogen generation rate, the hydrogen concentration in the vapor space of the reactor vessel above the grout was calculated. This concentration was compared to the lower flammability limit for hydrogen. The assessment concluded that either ceramicrete or the CAS grout may be used to safely grout the P-reactor vessel. The risk of accumulation of a flammable mixture of hydrogen between the grout-air interface and the top of the reactor is very low. Portland cement grout, on the other hand, for the same range of process parameters did not provide a margin of safety against the accumulation of flammable gas in the reactor vessel during grouting operations in the P-reactor vessel. Therefore, it was recommended that this grout not be utilized for this task. On the other hand, the R-reactor vessel contained significantly less aluminum surface area that the P-reactor vessel based on current facility process knowledge, surface observations, and drawings. Therefore, a Portland cement grout may be considered for grouting operations as well as the other grout formulations.

  14. Applied Field Research Initiative Deep Vadose Zone

    Office of Environmental Management (EM)

    Applied Field Research Initiative Deep Vadose Zone Located on the Hanford Site in Richland, Washington, the Deep Vadose Zone Applied Field Research Initiative (DVZ AFRI) was established to protect water resources by addressing the challenge of preventing contamination in the deep vadose zone from reaching groundwater. Led by the Pacific Northwest National Laboratory, the Initiative is a collaborative effort that leverages Department of Energy (DOE) investments in basic science and applied

  15. Apply for Your First NERSC Allocation

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

    Apply for Your First Allocation Apply for Your First NERSC Allocation Initial Steps Needed to Apply for Your First NERSC Allocation All work done at NERSC must be within the DOE Office of Science mission. See the Mission descriptions for each office at Allocations Overview and Eligibility. Prospective Principal Investigators without a NERSC login need to fill out two forms: The online ERCAP Access Request Form. If you wish to designate another person to fill out the request form you may

  16. Applied Materials Inc AMAT | Open Energy Information

    Open Energy Info (EERE)

    manufacturer of equipment used in solar (silicon, thin-film, BIPV), semiconductor, and LCD markets. References: Applied Materials Inc (AMAT)1 This article is a stub. You can...

  17. Applied Energy Management | Open Energy Information

    Open Energy Info (EERE)

    Energy Management Jump to: navigation, search Name: Applied Energy Management Place: Huntersville, North Carolina Zip: 28078 Sector: Efficiency, Renewable Energy Product: North...

  18. Applied Quantum Technology AQT | Open Energy Information

    Open Energy Info (EERE)

    Quantum Technology AQT Jump to: navigation, search Name: Applied Quantum Technology (AQT) Place: Santa Clara, California Zip: 95054 Product: California-based manufacturer of CIGS...

  19. FE Categorical Exclusions | Department of Energy

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

    ENI USA Gas Marketing, LLC CX(s) Applied: B5.7 Date: 04142015 Location(s): Multiple ... ENI USA Gas Marketing, LLC CX(s) Applied: B5.7 Date: 04142015 Location(s): Multiple ...

  20. Categorical Exclusion Determinations: North Dakota | Department...

    Energy Savers [EERE]

    ... Carbon Dioxide Storage Efficiency in Deep Saline Formations CX(s) Applied: A9 Date: 0423... University of North Dakota- Novel Dry Cooling Technology for Power Plants CX(s) Applied: ...

  1. Categorical Exclusion Determinations: Naval Nuclear Propulsion...

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

    Naval Reactors Facility (NRF) Storm Sewer West Main Replacement Project CX(s) Applied: ... Kesselring Site Gate 5 Project CX(s) Applied: B1.15 Date: 06052015 Location(s): None ...

  2. Categorical Exclusion Determinations: Indiana | Department of...

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

    Plant Award Number: DE-EE0006244 CX(s) Applied: A9, B3.6 Bioenergy Technology Office ... Award Number: DE-EE0006210 CX(s) Applied: B5.1, B5.17 Weatherization & ...

  3. Categorical Exclusion Determinations: B1.23 | Department of Energy

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

    E-Area Trailer and Handy House Demolition and Removal CX(s) Applied: B1.23 Date: 0520... Demolish and Dispose of Shed Located East of Test Reactor Area-607 CX(s) Applied: B1.23 ...

  4. Categorical Exclusion Determinations: Office of River Protection...

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

    CHPRC Cleanup Actions CX(s) Applied: B6.1 Date: 41849 Location(s): Washington Offices(s): ... Waste Site Retrieval Pilot Project CX(s) Applied: B3.6 Date: 07092014 Location(s): ...

  5. Categorical Exclusion Determinations: Fossil Energy | Department...

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

    ConocoPhillips Alaska Natural Gas Corporation CX(s) Applied: B5.7 Date: 242016 ... Bear Head LNG Corporation and Bear Head LNG (USA) CX(s) Applied: B5.7 Date: 1282016 ...

  6. Categorical Exclusion Determinations: Advanced Technology Vehicles...

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

    Reequipping and Engineering CX(s) Applied: B1.31, B5.1 Date: 09062011 ... Aptera All-Electric and Hybrid Electric Vehicles CX(s) Applied: B1.31, B5.1 Date: 0620...

  7. Nuclear Facilities and Applied Technologies at Sandia

    SciTech Connect (OSTI)

    Wheeler, Dave; Kaiser, Krista; Martin, Lonnie; Hanson, Don; Harms, Gary; Quirk, Tom

    2014-11-28

    The Nuclear Facilities and Applied Technologies organization at Sandia National Laboratories Technical Area Five (TA-V) is the leader in advancing nuclear technologies through applied radiation science and unique nuclear environments. This video describes the organizations capabilities, facilities, and culture.

  8. DOE/EA-1519: Environmental Assessment for the Proposed Decontamination and Decommissioning of the Zero Power Reactors (Building 315) at Argonne National Laboratory (April 2005)

    SciTech Connect (OSTI)

    N /A

    2005-04-30

    The U.S. Department of Energy (DOE) is proposing to decontaminate and decommission the Zero Power Reactor (ZPR) facilities located in Building 315 at Argonne National Laboratory (ANL) in Argonne, Illinois (Figure 1-1). The proposed action would occur in two phases: ZPR-6 would be the focus of Phase I and ZPR-9 would be the focus of Phase II. DOE has prepared this environmental assessment (EA) in accordance with the National Environmental Policy Act (NEPA), 42 U.S.C. {section} 4321 et seq., and applicable regulations (Title 40, Code of Federal Regulations [CFR] Parts 1500-1508 and 10 CFR Part 1021). This section describes the reactors and their current status.

  9. Pi in Applied Optics | GE Global Research

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

    Inside the Applied Optics Lab II Click to email this to a friend (Opens in new window) Share on Facebook (Opens in new window) Click to share (Opens in new window) Click to share on LinkedIn (Opens in new window) Click to share on Tumblr (Opens in new window) The sPI CAM: Inside the Applied Optics Lab II The sPI Cam visits the Applied Optics Lab to see how Mark Meyers, a physicist and optical engineer at GE Global Research, uses Pi. You Might Also Like lightning bolt We One-Upped Ben Franklin,

  10. Deep Vadose Zone-Applied Field Research Initiative Fiscal Year 2011 Annual Report

    SciTech Connect (OSTI)

    Wellman, Dawn M.; Johnson, Timothy C.; Smith, Ronald M.; Truex, Michael J.; Matthews, Hope E.

    2011-10-01

    This annual report describes the background of the Deep Vadose Zone-Applied Field Research Initiative, and some of the programmatic approaches and transformational technologies in groundwater and deep vadose zone remediation developed during fiscal year 2011. The Department of Energy (DOE) Office of Technology Innovation and Development's (OTID) mission is to transform science into viable solutions for environmental cleanup. In 2010, OTID developed the Impact Plan, Science and Technology to Reduce the Life Cycle Cost of Closure to outline the benefits of research and development of the lifecycle cost of cleanup across the DOE complex. This plan outlines OTID's ability to reduce by $50 billion, the $200 billion life-cycle cost in waste processing, groundwater and soil, nuclear materials, and deactivation and decommissioning. The projected life-cycle costs and return on investment are based on actual savings realized from technology innovation, development, and insertion into remedial strategies and schedules at the Fernald, Mound, and Ashtabula sites. To achieve our goals, OTID developed Applied Field Research Initiatives to facilitate and accelerate collaborative development and implementation of new tools and approaches that reduce risk, cost and time for site closure. The primary mission of the Deep Vadose Zone-Applied Field Research Initiative (DVZ-AFRI) is to protect our nation's water resources, keeping them clean and safe for future generations. The DVZ-AFRI was established for the DOE to develop effective, science-based solutions for remediating, characterizing, monitoring, and predicting the behavior and fate of deep vadose zone contamination. Subsurface contaminants include radionuclides, metals, organics, and liquid waste that originated from various sources, including legacy waste from the nation's nuclear weapons complexes. The DVZ-AFRI project team is translating strategy into action by working to solve these complex challenges in a collaborative environment that leverages technology and scientific expertise from DOE, Pacific Northwest National Laboratory, CH2M HILL Plateau Remediation Company, and the broad scientific research community. As project manager for the DVZ-AFRI, I have had the privilege this past year to team with creative, talented members of the scientific community nationwide to develop effective long-term solutions to address deep vadose zone contamination. This report highlights how the DVZ-AFRI project team is delivering results by achieving significant programmatic accomplishments, and developing and field-testing transformational technologies to address the nation's most pressing groundwater and vadose zone contamination problems.

  11. Overview of the NMSEA applied research program

    SciTech Connect (OSTI)

    Stickney, B.; Wilson, A.

    1980-01-01

    Recently the NMSEA has seen the need to augment its other informational programs with a program of in-house applied research. The reasoning behind this move is presented here along with and accounting of past research activities.

  12. SAGE, Summer of Applied Geophysical Experience

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

    Apply Who Qualifies Special Undergrad Information Contributors Faculty Past Programs Photo Gallery NSEC » CSES » SAGE SAGE, the Summer of Applied Geophysical Experience A National Science Foundation Research Experiences for Undergraduates program Contacts Institute Director Reinhard Friedel-Los Alamos SAGE Co-Director W. Scott Baldridge-Los Alamos SAGE Co-Director Larry Braile-Purdue University Professional Staff Assistant Georgia Sanchez (505) 665-0855 Email U.S. undergraduates

  13. Applying computationally efficient schemes for biogeochemical cycles

    Office of Scientific and Technical Information (OSTI)

    (ACES4BGC) (Technical Report) | SciTech Connect Applying computationally efficient schemes for biogeochemical cycles (ACES4BGC) Citation Details In-Document Search Title: Applying computationally efficient schemes for biogeochemical cycles (ACES4BGC) NCAR contributed to the ACES4BGC project through software engineering work on aerosol model implementation, build system and script changes, coupler enhancements for biogeochemical tracers, improvements to the Community Land Model (CLM) code and

  14. How to Apply | Department of Energy

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

    Postdoctoral Research Awards » How to Apply How to Apply Online Application Available at www.zintellect.com/Posting/Details/1997 Application deadline May 20, 2016. Familiarize yourself with the benefits, obligations, eligibility requirements, and evaluation criteria. Familiarize yourself with the requirements and obligations to determine whether your education and professional goals are well aligned with the EERE Postdoctoral Research Awards. Read the Evaluation Criteria that will be used to

  15. Apply to the Cyclotron Institute REU Program

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

    Apply Now Applying for the 2016 NSF-REU Nuclear Physics and Nuclear Chemistry Program at the Cyclotron Institute (APPLICATION DEADLINE IS FRIDAY, FEBRUARY 5th, 2016) Eligibility: Applicants must be US citizens or have permanent resident status. Applicants must have undergraduate status at the time of the program. (Students planning to receive a degree by May 2016 are not eligible). Applicants must have completed an introductory physics/chemistry course and have completed or be enrolled in an

  16. Method of applying coatings to substrates

    DOE Patents [OSTI]

    Hendricks, Charles D.

    1991-01-01

    A method for applying novel coatings to substrates is provided. The ends of multiplicity of rods of different materials are melted by focused beams of laser light. Individual electric fields are applied to each of the molten rod ends, thereby ejecting charged particles that include droplets, atomic clusters, molecules, and atoms. The charged particles are separately transported, by the accelerations provided by electric potentials produced by an electrode structure, to substrates where they combine and form the coatings. Layered and thickness graded coatings comprised of hithereto unavailable compositions, are provided.

  17. How to Apply for Senior Executive positions

    Broader source: Energy.gov [DOE]

    To apply vacancies for SENIOR EXECUTIVE SERVICE (SES) , SENIOR LEVEL (SL), SCIENTIFIC AND PROFESSIONAL (ST) positions within the Department of Energy please visit OPM's website: http://www.usajobs.gov. From this site, you may download announcements for vacancies of interest to you.

  18. Uniform insulation applied-B ion diode

    DOE Patents [OSTI]

    Seidel, David B.; Slutz, Stephen A.

    1988-01-01

    An applied-B field extraction ion diode has uniform insulation over an anode surface for increased efficiency. When the uniform insulation is accomplished with anode coils, and a charge-exchange foil is properly placed, the ions may be focused at a point on the z axis.

  19. Use of InSpector{sup TM} 1 1000 Instrument with LaBr{sub 3} for Nuclear Criticality Safety (NCS) Applications at the Westinghouse Hematite Decommissioning Project (HDP) - 13132

    SciTech Connect (OSTI)

    Pritchard, Megan; Guido, Joe

    2013-07-01

    The Westinghouse Hematite Decommissioning Project (HDP) is a former nuclear fuel cycle facility that is currently undergoing decommissioning. One aspect of the decommissioning scope is remediation of buried nuclear waste in unlined burial pits. The current Nuclear Criticality Safety program relies on application of criticality controls based on radiological setpoints from a 2 x 2 Sodium Iodide (NaI) detector. Because of the nature of the material buried (Low Enriched Uranium (LEU), depleted uranium, thorium, and radium) and the stringent threshold for application of criticality controls based on waste management (0.1 g {sup 235}U/L), a better method for {sup 235}U identification and quantification has been developed. This paper outlines the early stages of a quick, in-field nuclear material assay and {sup 235}U mass estimation process currently being deployed at HDP. Nuclear material initially classified such that NCS controls are necessary can be demonstrated not to require such controls and dispositioned as desired by project operations. Using Monte Carlo techniques and a high resolution Lanthanum Bromide (LaBr) detector with portable Multi-Channel Analyzer (MCA), a bounding {sup 235}U mass is assigned to basic geometries of nuclear material as it is excavated. The deployment of these methods and techniques has saved large amounts of time and money in the nuclear material remediation process. (authors)

  20. Revegetation Plan for Areas of the Fitzner-Eberhardt Arid Lands Ecology Reserve Affected by Decommissioning of Buildings and Infrastructure and Debris Clean-up Actions

    SciTech Connect (OSTI)

    Downs, Janelle L.; Durham, Robin E.; Larson, Kyle B.

    2011-01-01

    The U.S. Department of Energy (DOE), Richland Operations Office is working to remove a number of facilities on the Fitzner Eberhardt Arid Lands Ecology Reserve (ALE), which is part of the Hanford Reach National Monument. Decommissioning and removal of buildings and debris on ALE will leave bare soils and excavated areas that need to be revegetated to prevent erosion and weed invasion. Four main areas within ALE are affected by these activities (DOE 2009;DOE/EA-1660F): 1) facilities along the ridgeline of Rattlesnake Mountain, 2) the former Nike missile base and ALE HQ laboratory buildings, 3) the aquatic research laboratory at Rattlesnake Springs area, and 4) a number of small sites across ALE where various types of debris remain from previous uses. This revegetation plan addresses the revegetation and restoration of those land areas disturbed by decommissioning and removal of buildings, facilities and associated infrastructure or debris removal. The primary objective of the revegetation efforts on ALE is to establish native vegetation at each of the sites that will enhance and accelerate the recovery of the native plant community that naturally persists at that location. Revegetation is intended to meet the direction specified by the Environmental Assessment (DOE 2009; DOE/EA-1660F) and by Stipulation C.7 of the Memorandum of Agreement (MOA) for the Rattlesnake Mountain Combined Community Communication Facility and InfrastructureCleanup on the Fitzner/Eberhardt Arid Lands Ecology Reserve, Hanford Site, Richland Washington(DOE 2009; Appendix B). Pacific Northwest National Laboratory (PNNL) under contract with CH2M Hill Plateau Remediation Company (CPRC) and in consultation with the tribes and DOE-RL developed a site-specific strategy for each of the revegetation units identified within this document. The strategy and implementation approach for each revegetation unit identifies an appropriate native species mix and outlines the necessary site preparation activities and specific methods for seeding and planting at each area. evegetation work is scheduled to commence during the first quarter of FY 2011 to minimize the amount of time that sites are unvegetated and more susceptible to invasion by non-native weedy annual species.

  1. PROCESS KNOWLEDGE DATA GATHERING AND REPORTING IN SUPPORT OF DECOMMISSIONING Health Physics Society Annual Meeting West Palm Beach, Florida June 27, 2011

    SciTech Connect (OSTI)

    David A. King

    2011-06-27

    Summary of recent ORAU decommissioning activities at the Oak Ridge National Laboratory (ORNL) and the East Tennessee Technology Park (ETTP). Project objective was to generate approved Waste Lot Profiles for legacy facilities scheduled for demolition and shipment to the Environmental Management Waste Management Facility (EMWMF) or appropriate alternate facility. The form and content of process knowledge (PK) reports were developed with input from the EMWMF Waste Acceptance Criteria (WAC) Attainment Team and regulators. PK may be defined as the knowledge of the design and the history of operations that occurs during the life cycle of a facility (paraphrased from SRNL guidance) - similar to the MARSSIM historical site assessment. Some types of PK data used to decommission ORNL and ETTP facilities include: (1) Design drawings; (2) Historical documents [e.g., History of the Oak Ridge National Laboratory by Thomas (1963) and A Brief History of the Chemical Technical Division (ORNL/M-2733)]; (3) Historical photographs; (4) Radiological survey reports; (5) Facility-specific databases - (a) Spill history, (b) Waste Information Tracking System (WITS), and (c) Hazardous Materials Management Information System (HMMIS); (6) Facility walkdown summary reports; and (7) Living memory data. Facility walkdowns are critical for worker safety planning and to assure on-the-ground-conditions match historical descriptions. For Oak Ridge operations, investigators also document the nature and number of items requiring special handling or disposition planning, such as the following: (1) Items containing polychlorinated biphenyls, asbestos, lead, or refrigerants; (2) Items with physical WAC restriction (e.g., large items, pipes, and concrete); and (3) Too 'hot' for EMWMF. Special emphasis was made to interview facility managers, scientists, technicians, or anyone with direct knowledge of process-related activities. Interviews often led to more contact names and reports but also offered anecdotal accounts of releases, process-related operations, maintenance activities, and other relevant information not addressed in the written record. 'Fun' part of PK data gathering. Often got not-so-useful information such as, 'The operations manager was a jerk and we all hated him.' PK data are used to indicate the presence or absence of contaminants. Multiple lines of investigation are necessary for characterization planning and to help determine which disposal facility is best suited for targeted wastes. The model used by ORAU assisted remediation contractors and EMWMF managers by identifying anomalous waste and items requiring special handling.

  2. Summer of Applied Geophysical Experience Reading List

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

    Geophysical Experience Reading List Summer of Applied Geophysical Experience Reading List A National Science Foundation Research Experiences for Undergraduates program Contacts Institute Director Reinhard Friedel-Los Alamos SAGE Co-Director W. Scott Baldridge-Los Alamos SAGE Co-Director Larry Braile-Purdue University Professional Staff Assistant Georgia Sanchez (505) 665-0855 Keller, R., Khan, M. A., Morgan, P., et al., 1991, A Comparative Study of the Rio Grande and Kenya rifts, Tectonophys.,

  3. Applied Cathode Enhancement and Robustness Technologies (ACERT)

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

    Accelerators, Electrodynamics » ACERT Applied Cathode Enhancement and Robustness Technologies (ACERT) World leading experts from fields of accelerator design & testing, chemical synthesis of nanomaterials, and shielding application of nanomaterials. thumbnail of Nathan Moody Nathan Moody Principal Investigator (PI) Email ACERT Logo Team Our project team, a part of Los Alamos National Laboratory (LANL) comprised of world leading experts from fields of accelerator design & testing,

  4. Risk-based Prioritization of Facility Decommissioning and Environmental Restoration Projects in the National Nuclear Legacy Liabilities Program at the Chalk River Laboratory - 13564

    SciTech Connect (OSTI)

    Nelson, Jerel G.; Kruzic, Michael; Castillo, Carlos; Pavey, Todd; Alexan, Tamer; Bainbridge, Ian

    2013-07-01

    Chalk River Laboratory (CRL), located in Ontario Canada, has a large number of remediation projects currently in the Nuclear Legacy Liabilities Program (NLLP), including hundreds of facility decommissioning projects and over one hundred environmental remediation projects, all to be executed over the next 70 years. Atomic Energy of Canada Limited (AECL) utilized WorleyParsons to prioritize the NLLP projects at the CRL through a risk-based prioritization and ranking process, using the WorleyParsons Sequencing Unit Prioritization and Estimating Risk Model (SUPERmodel). The prioritization project made use of the SUPERmodel which has been previously used for other large-scale site prioritization and sequencing of facilities at nuclear laboratories in the United States. The process included development and vetting of risk parameter matrices as well as confirmation/validation of project risks. Detailed sensitivity studies were also conducted to understand the impacts that risk parameter weighting and scoring had on prioritization. The repeatable prioritization process yielded an objective, risk-based and technically defendable process for prioritization that gained concurrence from all stakeholders, including Natural Resources Canada (NRCan) who is responsible for the oversight of the NLLP. (authors)

  5. RESULTS OF IONSIV® IE-95 STUDIES FOR THE REMOVAL OF RADIOACTIVE CESIUM FROM K-EAST BASIN SPENT NUCLEAR FUEL POOL DURING DECOMMISSIONING ACTIVITIES

    SciTech Connect (OSTI)

    DUNCAN JB; BURKE SP

    2008-07-07

    This report delineates the results obtained from laboratory testing of IONISIV{reg_sign} IE-95 to determine the efficacy of the zeolite for the removal of radioactive cesium from the KE Basin water prior to transport to the Effluent Treatment Facility, as described in RPP-PLAN-36158, IONSIV{reg_sign} IE-95 Studies for the removal of Radioactive Cesium from KE Basin Spent Nuclear Fuel Pool during Decommissioning Activities. The spent nuclear fuel was removed from KE Basin and the remaining sludge was layered with a grout mixture consisting of 26% Lehigh Type I/II portland cement and 74% Boral Mohave type F fly ash with a water-to-cement ratio of 0.43. The first grout pour was added to the basin floor to a depth of approximately 14 in. covering an area of 12,000 square feet. A grout layer was also added to the sludge containers located in the attached Weasel and Technical View pits.

  6. Lessons Learned from the Application of Bulk Characterization to Individual Containers on the Brookhaven Graphite Research Reactor Decommissioning Project at Brookhaven National Laboratory - 12056

    SciTech Connect (OSTI)

    Kneitel, Terri; Rocco, Diane

    2012-07-01

    When conducting environmental cleanup or decommissioning projects, characterization of the material to be removed is often performed when the material is in-situ. The actual demolition or excavation and removal of the material can result in individual containers that vary significantly from the original bulk characterization profile. This variance, if not detected, can result in individual containers exceeding Department of Transportation regulations or waste disposal site acceptance criteria. Bulk waste characterization processes were performed to initially characterize the Brookhaven Graphite Research Reactor (BGRR) graphite pile and this information was utilized to characterize all of the containers of graphite. When the last waste container was generated containing graphite dust from the bottom of the pile, but no solid graphite blocks, the material contents were significantly different in composition from the bulk waste characterization. This error resulted in exceedance of the disposal site waste acceptance criteria. Brookhaven Science Associates initiated an in-depth investigation to identify the root causes of this failure and to develop appropriate corrective actions. The lessons learned at BNL have applicability to other cleanup and demolition projects which characterize their wastes in bulk or in-situ and then extend that characterization to individual containers. (authors)

  7. Record of the facility deactivation, decommissioning, and material disposition (D and D) workshop: A new focus for technology development, opportunities for industry/government collaboration

    SciTech Connect (OSTI)

    Bedick, R.C.; Bossart, S.J.; Hart, P.W.

    1995-07-01

    This workshop was held at the Morgantown Energy Technology Center (METC) in Morgantown, West Virginia, on July 11--12, 1995. The workshop sought to establish a foundation for continued dialogue between industry and the DOE to ensure that industry`s experiences, lessons learned, and recommendations are incorporated into D and D program policy, strategy, and plans. The mission of the D and D Focus Area is to develop improved technologies, processes and products, to characterize, deactivate, survey, maintain, decontaminate, dismantle, and dispose of DOE surplus structures, buildings, and contents. The target is a five-to-one return on investment through cost avoidance. The cornerstone of the D and D focus area activities is large-scale demonstration projects that actually decontaminate, decommission, and dispose of a building. The aim is to demonstrate innovative D and D technologies as part of an ongoing DOE D and D project. OTD would pay the incremental cost of demonstrating the innovative technologies. The goal is to have the first demonstration project completed within the next 2 years. The intent is to select projects, or a project, with visible impact so all of the stakeholders know that a building was removed, and demonstrate at a scale that is convincing to the customers in the EM program so they feel comfortable using it in subsequent D and D projects. The plan is to use a D and D integrating contractor who can then use the expertise in this project to use in jobs at other DOE sites.

  8. Applied Energy Programs, SPO-AE: LANL

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

    Kevin Ott 505-663-5537 Program Administrator Jutta Kayser 505-663-5649 Program Manager Karl Jonietz 505-663-5539 Program Manager Melissa Fox 505-663-5538 Budget Analyst Fawn Gore 505-665-0224 The Applied Energy Program Office (SPO-AE) manages Los Alamos National Laboratory programs funded by the Department of Energy's Offices of Energy Efficiency/Renewable Energy, Electricity Delivery and Energy Reliability, and Fossil Energy. With energy use increasing across the nation and the world, Los

  9. Apply for a Job | Argonne National Laboratory

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

    FAQs Answers to frequently asked questions about applying for a job at Argonne A Note About Privacy We do not ask you for personally identifiable information such as birthdate, social security number, or driver's license number. To ensure your privacy, please do not include such information in the documents that you upload to the system A Note About File Size Our application system has a file size limit of 820KB. While this is sufficient for the vast majority of documents, we have found that

  10. 2009 Applied and Environmental Microbiology GRC

    SciTech Connect (OSTI)

    Nicole Dubilier

    2009-07-12

    The topic of the 2009 Gordon Conference on Applied and Environmental Microbiology is: From Single Cells to the Environment. The Conference will present and discuss cutting-edge research on applied and environmental microbiology with a focus on understanding interactions between microorganisms and the environment at levels ranging from single cells to complex communities. The Conference will feature a wide range of topics such as single cell techniques (including genomics, imaging, and NanoSIMS), microbial diversity at scales ranging from clonal to global, environmental 'meta-omics', biodegradation and bioremediation, metal - microbe interactions, animal microbiomes and symbioses. The Conference will bring together investigators who are at the forefront of their field, and will provide opportunities for junior scientists and graduate students to present their work in poster format and exchange ideas with leaders in the field. Some poster presenters will be selected for short talks. The collegial atmosphere of this Conference, with extensive discussion sessions as well as opportunities for informal gatherings in the afternoons and evenings, provides an ideal setting for scientists from different disciplines to exchange ideas, brainstorm and discuss cross-disciplinary collaborations.

  11. FY 1990 Applied Sciences Branch annual report

    SciTech Connect (OSTI)

    Keyes, B.M.; Dippo, P.C.

    1991-11-01

    The Applied Sciences Branch actively supports the advancement of DOE/SERI goals for the development and implementation of the solar photovoltaic technology. The primary focus of the laboratories is to provide state-of-the-art analytical capabilities for materials and device characterization and fabrication. The branch houses a comprehensive facility which is capable of providing information on the full range of photovoltaic components. A major objective of the branch is to aggressively pursue collaborative research with other government laboratories, universities, and industrial firms for the advancement of photovoltaic technologies. Members of the branch disseminate research findings to the technical community in publications and presentations. This report contains information on surface and interface analysis, materials characterization, development, electro-optical characterization module testing and performance, surface interactions and FTIR spectroscopy.

  12. Testing and Performance Validation of a Sensitive Gamma Ray Camera Designed for Radiation Detection and Decommissioning Measurements in Nuclear Facilities-13044

    SciTech Connect (OSTI)

    Mason, John A.; Looman, Marc R.; Poundall, Adam J.; Towner, Antony C.N.; Creed, Richard; Pancake, Daniel

    2013-07-01

    This paper describes the measurements, testing and performance validation of a sensitive gamma ray camera designed for radiation detection and quantification in the environment and decommissioning and hold-up measurements in nuclear facilities. The instrument, which is known as RadSearch, combines a sensitive and highly collimated LaBr{sub 3} scintillation detector with an optical (video) camera with controllable zoom and focus and a laser range finder in one detector head. The LaBr{sub 3} detector has a typical energy resolution of between 2.5% and 3% at the 662 keV energy of Cs-137 compared to that of NaI detectors with a resolution of typically 7% to 8% at the same energy. At this energy the tungsten shielding of the detector provides a shielding ratio of greater than 900:1 in the forward direction and 100:1 on the sides and from the rear. The detector head is mounted on a pan/tile mechanism with a range of motion of ±180 degrees (pan) and ±90 degrees (tilt) equivalent to 4 π steradians. The detector head with pan/tilt is normally mounted on a tripod or wheeled cart. It can also be mounted on vehicles or a mobile robot for access to high dose-rate areas and areas with high levels of contamination. Ethernet connects RadSearch to a ruggedized notebook computer from which it is operated and controlled. Power can be supplied either as 24-volts DC from a battery or as 50 volts DC supplied by a small mains (110 or 230 VAC) power supply unit that is co-located with the controlling notebook computer. In this latter case both power and Ethernet are supplied through a single cable that can be up to 80 metres in length. If a local battery supplies power, the unit can be controlled through wireless Ethernet. Both manual operation and automatic scanning of surfaces and objects is available through the software interface on the notebook computer. For each scan element making up a part of an overall scanned area, the unit measures a gamma ray spectrum. Multiple radionuclides may be selected by the operator and will be identified if present. In scanning operation the unit scans a designated region and superimposes over a video image the distribution of measured radioactivity. For the total scanned area or object RadSearch determines the total activity of operator selected radionuclides present and the gamma dose-rate measured at the detector head. Results of hold-up measurements made in a nuclear facility are presented, as are test measurements of point sources distributed arbitrarily on surfaces. These latter results are compared with the results of benchmarked MCNP Monte Carlo calculations. The use of the device for hold-up and decommissioning measurements is validated. (authors)

  13. Applying physics, teamwork to fusion energy science | Princeton...

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

    Applying physics, teamwork to fusion energy science American Fusion News Category: Massachusetts Institute of Technology (MIT) Link: Applying physics, teamwork to fusion energy science

  14. D&D Toolbox Project - Technology Demonstration of Fixatives Applied...

    Office of Environmental Management (EM)

    platform(s) was demonstrated at the hot cell mockup facility at the FIU's Applied ... Demonstration of Fixatives Applied to Hot Cell Facilities via Remote Sprayer Platforms ...

  15. Sandian Named Fellow of the Society for Industrial and Applied...

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

    Named Fellow of the Society for Industrial and Applied Mathematics - Sandia Energy Energy ... Sandian Named Fellow of the Society for Industrial and Applied Mathematics HomeResearch & ...

  16. Energy Department Extends Deadline to Apply for START Tribal...

    Energy Savers [EERE]

    Extends Deadline to Apply for START Tribal Renewable Energy Project Development Assistance to May 22, 2015 Energy Department Extends Deadline to Apply for START Tribal Renewable...

  17. Applying the Battery Ownership Model in Pursuit of Optimal Battery...

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

    Applying the Battery Ownership Model in Pursuit of Optimal Battery Use Strategies Applying the Battery Ownership Model in Pursuit of Optimal Battery Use Strategies 2012 DOE ...

  18. Rational Catalyst Design Applied to Development of Advanced Oxidation...

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

    Rational Catalyst Design Applied to Development of Advanced Oxidation Catalysts for Diesel Emission Control Rational Catalyst Design Applied to Development of Advanced Oxidation ...

  19. James Webb Space Telescope: PM Lessons Applied - Eric Smith,...

    Energy Savers [EERE]

    James Webb Space Telescope: PM Lessons Applied - Eric Smith, Deputy Program Director, NASA James Webb Space Telescope: PM Lessons Applied - Eric Smith, Deputy Program Director,...

  20. Energy Department Announces Up to $14 Million for Applying Landscape...

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

    Up to 14 Million for Applying Landscape Design to Cellulosic Bioenergy Energy Department Announces Up to 14 Million for Applying Landscape Design to Cellulosic Bioenergy October ...

  1. Large Eddy Simulation (LES) Applied to Advanced Engine Combustion...

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

    Large Eddy Simulation (LES) Applied to Advanced Engine Combustion Research Large Eddy Simulation (LES) Applied to Low-Temperature and Diesel Engine Combustion Research Vehicle ...

  2. The Smart Grid Experience: Applying Results, Reaching Beyond...

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

    Grid Experience: Applying Results, Reaching Beyond - Summary of Conference Proceedings (December 2014) The Smart Grid Experience: Applying Results, Reaching Beyond - Summary of ...

  3. Tritium research activities in Safety and Tritium Applied Research...

    Office of Environmental Management (EM)

    research activities in Safety and Tritium Applied Research (STAR) facility, Idaho National Laboratory Tritium research activities in Safety and Tritium Applied Research (STAR)...

  4. An Evaluation of the Nonlinearity Correction Applied to Atmospheric...

    Office of Scientific and Technical Information (OSTI)

    An Evaluation of the Nonlinearity Correction Applied to Atmospheric Emitted Radiance ... Title: An Evaluation of the Nonlinearity Correction Applied to Atmospheric Emitted ...

  5. Statistical and Domain Analytics Applied to PV Module Lifetime...

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

    Statistical and Domain Analytics Applied to PV Module Lifetime and Degradation Science Statistical and Domain Analytics Applied to PV Module Lifetime and Degradation Science ...

  6. Artificial intelligence technologies applied to terrain analysis

    SciTech Connect (OSTI)

    Wright, J.C. ); Powell, D.R. )

    1990-01-01

    The US Army Training and Doctrine Command is currently developing, in cooperation with Los Alamos National Laboratory, a Corps level combat simulation to support military analytical studies. This model emphasizes high resolution modeling of the command and control processes, with particular attention to architectural considerations that enable extension of the model. A planned future extension is the inclusion of an computer based planning capability for command echelons that can be dynamical invoked during the execution of then model. Command and control is the process through which the activities of military forces are directed, coordinated, and controlled to achieve the stated mission. To perform command and control the commander must understand the mission, perform terrain analysis, understand his own situation and capabilities as well as the enemy situation and his probable actions. To support computer based planning, data structures must be available to support the computer's ability to understand'' the mission, terrain, own capabilities, and enemy situation. The availability of digitized terrain makes it feasible to apply artificial intelligence technologies to emulate the terrain analysis process, producing data structures for uses in planning. The work derived thus for to support the understanding of terrain is the topic of this paper. 13 refs., 5 figs., 6 tabs.

  7. CX-009418: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Electron Beam Melting CX(s) Applied: None applied. Date: 10/30/2012 Location(s): Missouri Offices(s): Kansas City Site Office

  8. CX-009420: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Additive Manufacturing Using EOSINT M280 CX(s) Applied: None applied. Date: 10/30/2012 Location(s): Missouri Offices(s): Kansas City Site Office

  9. CX-009419: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Magnetic Pulser CX(s) Applied: None applied. Date: 10/30/2012 Location(s): Missouri Offices(s): Kansas City Site Office

  10. X-Ray Photoelectron Spectroscopy (XPS) Applied to Soot & What...

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

    Photoelectron Spectroscopy (XPS) Applied to Soot & What It Can Do for You X-Ray Photoelectron Spectroscopy (XPS) Applied to Soot & What It Can Do for You Presentation given at DEER ...

  11. DOE - Office of Legacy Management -- Case School of Applied Science...

    Office of Legacy Management (LM)

    Case School of Applied Science Ohio State University - OH 0-01 FUSRAP Considered Sites Site: Case School of Applied Science, Ohio State University (OH.0-01 ) Eliminated from ...

  12. Applied Science and Technology Task Order Fiscal Year 2009 Year...

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

    9 Year-End Summary Report Applied Science and Technology Task Order Fiscal Year 2009 Year-End Summary Report Applied Science and Technology Task Order Fiscal Year 2009 Year-End ...

  13. Applied Science and Technology Task Order Fiscal Year 2008 Year...

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

    8 Year-End Summary Report Applied Science and Technology Task Order Fiscal Year 2008 Year-End Summary Report Applied Science and Technology Task Order Fiscal Year 2008 Year-End ...

  14. Applied Science and Technology Task Order Fiscal Year 2011 Year...

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

    1 Year-End Summary Report Applied Science and Technology Task Order Fiscal Year 2011 Year-End Summary Report Applied Science and Technology Task Order Fiscal Year 2011 Year-End ...

  15. Applied Science and Technology Task Order Fiscal Year 2010 Year...

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

    0 Year-End Summary Report Applied Science and Technology Task Order Fiscal Year 2010 Year-End Summary Report Applied Science and Technology Task Order Fiscal Year 2010 Year-End ...

  16. Oregon Learning About and Applying for Water Rights Webpage ...

    Open Energy Info (EERE)

    Learning About and Applying for Water Rights Webpage Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Oregon Learning About and Applying for Water...

  17. Applying for PMCDP/FPD Certification (initial) | Department of Energy

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

    Services » Career Development (PMCDP) » Applying for PMCDP/FPD Certification (initial) Applying for PMCDP/FPD Certification (initial) Certification applicants are nominated by their respective Program Secretarial Office (PSO) to apply for FPD certification - candidates may not apply without program sponsorship. Each participating program has a dedicated point of contact (POC) whose role is to support the FPD applicant in preparing their certification package. First time applicants, as well as

  18. Vehicle Technologies Office: Applied Battery Research | Department of

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

    Energy Applied Battery Research Vehicle Technologies Office: Applied Battery Research Applied battery research addresses the barriers facing the lithium-ion systems that are closest to meeting the technical energy and power requirements for hybrid electric vehicle (HEV) and electric vehicle (EV) applications. In addition, applied battery research concentrates on technology transfer to ensure that the research results and lessons learned are effectively provided to U.S. automotive and battery

  19. Attenuation-Based Remedies in the Subsurface Applied Field Research

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

    Initiative (ABRS AFRI) | Department of Energy Attenuation-Based Remedies in the Subsurface Applied Field Research Initiative (ABRS AFRI) Attenuation-Based Remedies in the Subsurface Applied Field Research Initiative (ABRS AFRI) Attenuation-Based Remedies in the Subsurface Applied Field Research Initiative (ABRS AFRI) Located at the Savannah River Site in Aiken, South Carolina, the Attenuation-Based Remedies in the Subsurface Applied Field Research Initiative (ABRS AFRI) was established to

  20. Aachen University of Applied Sciences | Open Energy Information

    Open Energy Info (EERE)

    Aachen University of Applied Sciences Place: Germany Sector: Services Product: General Financial & Legal Services ( Academic Research foundation ) References: Aachen...

  1. Applied Process Engineering Laborotory APEL | Open Energy Information

    Open Energy Info (EERE)

    Engineering Laborotory (APEL) Place: United States Sector: Services Product: General Financial & Legal Services ( Private family-controlled ) References: Applied Process...

  2. PLURAL METALLIC COATINGS ON URANIUM AND METHOD OF APPLYING SAME

    DOE Patents [OSTI]

    Gray, A.G.

    1958-09-16

    A method is described of applying protective coatings to uranlum articles. It consists in applying chromium plating to such uranium articles by electrolysis in a chromic acid bath and subsequently applying, to this minum containing alloy. This aluminum contalning alloy (for example one of aluminum and silicon) may then be used as a bonding alloy between the chromized surface and an aluminum can.

  3. Applied Mathematics | U.S. DOE Office of Science (SC)

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

    Applied Mathematics Advanced Scientific Computing Research (ASCR) ASCR Home About Research Applied Mathematics Applied Mathematics Conferences And Workshops Computer Science Next Generation Networking Scientific Discovery through Advanced Computing (SciDAC) ASCR SBIR-STTR Facilities Science Highlights Benefits of ASCR Funding Opportunities Advanced Scientific Computing Advisory Committee (ASCAC) Community Resources Contact Information Advanced Scientific Computing Research U.S. Department of

  4. Hallam, Nebraska, Decommissioned Reactor Site

    Office of Legacy Management (LM)

    Except for the concrete structure that housed the intermediate heat exchanger, the ... Hallam Site Intermediate Heat Exchanger Building (White Building). Grassy area covers the ...

  5. Building America Expert Meeting: Recommendations for Applying Water Heaters

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

    in Combination Space and Domestic Water Heating Systems | Department of Energy Recommendations for Applying Water Heaters in Combination Space and Domestic Water Heating Systems Building America Expert Meeting: Recommendations for Applying Water Heaters in Combination Space and Domestic Water Heating Systems This expert meeting was conducted by Building Science Corporation on July 31, 2011 in Westford, Massachusetts ; the topic of this meeting was 'Recommendations For Applying Water Heaters

  6. Opportunities to Apply Phase Change Materials to Building Enclosures

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

    Webinar | Department of Energy Opportunities to Apply Phase Change Materials to Building Enclosures Webinar Opportunities to Apply Phase Change Materials to Building Enclosures Webinar Slides from the Building America webinar on November 11, 2011. PDF icon webinar_pcm_enclosures_20111111.pdf More Documents & Publications Building America Webinar: Opportunities to Apply Phase Change Materials to Building Enclosures 2011 Residential Energy Efficiency Technical Update Meeting Summary

  7. Building America Webinar: Opportunities to Apply Phase Change Materials to

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

    Building Enclosures | Department of Energy to Apply Phase Change Materials to Building Enclosures Building America Webinar: Opportunities to Apply Phase Change Materials to Building Enclosures This webinar, presented by research team Fraunhofer Center for Sustainable Energy Systems (CSE), reviewed basic physical characteristics and thermal properties of phase change materials (PCMs) and provided guidance on how to effectively apply PCMs in buildings in the United States. File

  8. Apply for the Parallel Computing Summer Research Internship

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

    Parallel Computing » How to Apply Apply for the Parallel Computing Summer Research Internship Creating next-generation leaders in HPC research and applications development Program Co-Lead Robert (Bob) Robey Email Program Co-Lead Gabriel Rockefeller Email Program Co-Lead Hai Ah Nam Email Professional Staff Assistant Nicole Aguilar Garcia (505) 665-3048 Email Current application deadline is February 5, 2016 with notification by early March 2016. Who can apply? Upper division undergraduate

  9. Applied Materials Switzerland SA Formerly HCT Shaping Systems...

    Open Energy Info (EERE)

    Switzerland SA Formerly HCT Shaping Systems SA Jump to: navigation, search Name: Applied Materials Switzerland SA (Formerly HCT Shaping Systems SA) Place: Chezeaux, Switzerland...

  10. Building America Webinar: Opportunities to Apply Phase Change...

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

    Building America Webinar: Opportunities to Apply Phase Change Materials to Building Enclosures This webinar, presented by research team Fraunhofer Center for Sustainable Energy ...

  11. The generalized finite element method applied to the dynamic...

    Office of Scientific and Technical Information (OSTI)

    Title: The generalized finite element method applied to the dynamic response of heterogeneous media. Authors: Robbins, Joshua ; Voth, Thomas E. Publication Date: 2013-02-01 OSTI ...

  12. Webinar "Applying High Performance Computing to Engine Design...

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

    Webinar "Applying High Performance Computing to Engine Design Using Supercomputers" Share ... Study Benefits of Bioenergy Crop Integration Video: Biofuel technology at Argonne

  13. Identification of multi-modal plasma responses to applied magnetic...

    Office of Scientific and Technical Information (OSTI)

    Title: Identification of multi-modal plasma responses to applied magnetic perturbations using the plasma reluctance Authors: Logan, Nikolas C. 1 ; Paz-Soldan, Carlos 2 ; Park, ...

  14. Solar Applied Materials Technology Corp | Open Energy Information

    Open Energy Info (EERE)

    Name: Solar Applied Materials Technology Corp Place: Tainan, Taiwan Product: Taiwan's material process specialists with over 20 years experience and in the areas of sputtering...

  15. Modular Applied General Equilibrium Tool (MAGNET) | Open Energy...

    Open Energy Info (EERE)

    Related Tools CRiSTAL Forests MCA4Climate - Guidance for scientifically sound climate change planning Environmental Impact and Sustainability Applied General Equilibrium Model...

  16. Am Shav Technological Applied Development Center | Open Energy...

    Open Energy Info (EERE)

    Technological Applied Development Center Place: Israel Sector: Services Product: General Financial & Legal Services ( Private family-controlled ) References: Am-Shav...

  17. Crivelli, Silvia; Meza, Juan 60 APPLIED LIFE SCIENCES Ernest...

    Office of Scientific and Technical Information (OSTI)

    folding via divide-and-conquer optimization Oliva, Ricardo; Crivelli, Silvia; Meza, Juan 60 APPLIED LIFE SCIENCES Ernest Orlando Lawrence Berkeley NationalLaboratory, Berkeley, CA...

  18. ENERGY STAR Webinar: How to Apply for the ENERGY STAR

    Broader source: Energy.gov [DOE]

    The U.S. Environmental Protection Agency (EPA) is hosting a webinar on how to apply for ENERGY STAR certification in Portfolio Manager.

  19. Overview and Progress of the Applied Battery Research (ABR) Activity...

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

    More Documents & Publications Fabricate PHEV Cells for Testing & Diagnostics Overview and Progress of the Applied Battery Research (ABR) Activity Current Research Activities in ...

  20. Overview and Progress of the Applied Battery Research (ABR) Activity...

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

    of the Exploratory Technology Research Activity: Batteries for Advanced Transportation Technologies (BATT) Overview and Progress of the Applied Battery Research (ABR) Activity

  1. BLM Manual 2804: Applying for FLPMA Grants | Open Energy Information

    Open Energy Info (EERE)

    search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook: BLM Manual 2804: Applying for FLPMA GrantsPermittingRegulatory...

  2. Building America Whole-House Solutions for Existing Homes: Applying...

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

    Retrofit Programs - Central Florida (Fact Sheet) Building America Whole-House Solutions for Existing Homes: Applying Best Practices to Florida Local Government Retrofit ...

  3. Opportunities to Apply Phase Change Materials to Building Enclosures...

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

    Building America Webinar: Opportunities to Apply Phase Change Materials to Building Enclosures 2011 Residential Energy Efficiency Technical Update Meeting Summary Report: Denver, ...

  4. Applied Solar LLC formerly Open Energy Corp and Barnabus Energy...

    Open Energy Info (EERE)

    Open Energy Corp and Barnabus Energy Inc Jump to: navigation, search Name: Applied Solar LLC (formerly Open Energy Corp and Barnabus Energy Inc) Place: San Diego, California...

  5. Building America Whole-House Solutions for Existing Homes: Applying...

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

    Homes: Applying Best Practices to Florida Local Government Retrofit Programs - Central Florida (Fact Sheet) Building America Whole-House Solutions for Existing Homes: ...

  6. CX-008684: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Metaline Radio Station Upgrade Project CX(s) Applied: B1.19 Date: 07/11/2012 Location(s): Washington Offices(s): Bonneville Power Administration

  7. Categorical Exclusion Determinations: B4.9 | Department of Energy

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

    September 24, 2014 CX-012808: Categorical Exclusion Determination LURR 20140504 Ross Substation Comcast Fiber Installation CX(s) Applied: B4.9 Date: 41906 Location(s): ...

  8. CX-007382: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Compressed Natural Gas Manufacturing CX(s) Applied: B5.1 Date: 10/26/2011 Location(s): Wisconsin Offices(s): Golden Field Office

  9. CX-007650: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Control Room Consolidation CX(s) Applied: B2.2 Date: 12/29/2011 Location(s): South Carolina Offices(s): Savannah River Operations Office

  10. CX-011531: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    Targhee Substation Land Acquisition CX(s) Applied: B1.24 Date: 11/05/2013 Location(s): Idaho Offices(s): Bonneville Power Administration

  11. CX-012790: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    Haystack Butte Radio Site Land Acquisition CX(s) Applied: B1.24Date: 41939 Location(s): WashingtonOffices(s): Bonneville Power Administration

  12. CX-008250: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Geotechnical Core Drilling for USGS 138 CX(s) Applied: B3.1 Date: 04/18/2012 Location(s): Idaho Offices(s): Nuclear Energy

  13. CX-009850: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Pittsburgh Nanomaterials Preparation Lab CX(s) Applied: B3.6 Date: 01/29/2013 Location(s): Pennsylvania Offices(s): National Energy Technology Laboratory

  14. CX-007893: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    SunShot Massachusetts CX(s) Applied: A9, A11 Date: 02/10/2012 Location(s): Massachusetts Offices(s): Golden Field Office

  15. CX-012620: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Grout Preparation CX(s) Applied: B3.6Date: 41799 Location(s): South CarolinaOffices(s): Savannah River Operations Office

  16. CX-010578: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Celilo Converter Station Upgrades CX(s) Applied: B4.11 Date: 07/25/2013 Location(s): Oregon Offices(s): Bonneville Power Administration

  17. CX-008547: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    St. Petersburg Solar Pilot Project CX(s) Applied: B5.16 Date: 05/31/2012 Location(s): Florida Offices(s): Golden Field Office

  18. CX-008884: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Rattlesnake Butte Property Funding CX(s) Applied: B1.25 Date: 08/13/2012 Location(s): Oregon Offices(s): Bonneville Power Administration

  19. CX-008307: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Deepwater Reverse-Circulation Primary Cementing CX(s) Applied: A9 Date: 04/25/2012 Location(s): Texas Offices(s): National Energy Technology Laboratory

  20. CX-010618: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Midwest Region Alternative Fuels Project CX(s) Applied: 0 Date: 07/19/2013 Location(s): Missouri Offices(s): National Energy Technology Laboratory

  1. CX-008799: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Jack Case Showers Projects CX(s) Applied: B1.3 Date: 06/04/2012 Location(s): Tennessee Offices(s): Y-12 Site Office

  2. CX-011177: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Hebo Substation Access Road Maintenance CX(s) Applied: B1.3 Date: 09/13/2013 Location(s): Oregon Offices(s): Bonneville Power Administration

  3. CX-011676: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Office Trailer Relocation CX(s) Applied: B1.22 Date: 12/09/2013 Location(s): South Carolina Offices(s): Savannah River Operations Office

  4. CX-008215: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Small Hydropower Research and Development Technology Project CX(s) Applied: A9 Date: 04/03/2012 Location(s): Colorado Offices(s): Golden Field Office

  5. CX-011194: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Particle Physics Division Outback Garage CX(s) Applied: B1.15 Date: 09/19/2013 Location(s): Illinois Offices(s): Fermi Site Office

  6. CX-012561: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Replace Department of Energy Office Trailers CX(s) Applied: B1.15Date: 41871 Location(s): South CarolinaOffices(s): Savannah River Operations Office

  7. CX-011534: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Grays River Confluence Property Funding CX(s) Applied: B1.25 Date: 11/08/2013 Location(s): Washington Offices(s): Bonneville Power Administration

  8. CX-011110: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Advancements in Algal Biomass Yield CX(s) Applied: A9 Date: 08/29/2013 Location(s): Hawaii Offices(s): Golden Field Office

  9. CX-010763: Categorical Exclusion Determination | Department of...

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

    CX-010763: Categorical Exclusion Determination Nevada Desert Research Institute- Photovoltaic Installation CX(s) Applied: B5.16 Date: 07172013 Location(s): Nevada Offices(s):...

  10. CX-009237: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    The Dow Chemical Company CX(s) Applied: B5.7 Date: 10/02/2012 Location(s): Texas Offices(s): Fossil Energy

  11. CX-013619: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Upper Lemhi Conservation Easement Acquisition CX(s) Applied: B1.25Date: 05/26/2015 Location(s): IdahoOffices(s): Bonneville Power Administration

  12. CX-008161: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Prosser Hatchery Backup Generator Replacement CX(s) Applied: B1.31 Date: 04/16/2012 Location(s): Washington Offices(s): Bonneville Power Administration

  13. CX-012463: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Reliable SOFC Systems CX(s) Applied: A9, B3.6Date: 41877 Location(s): ConnecticutOffices(s): National Energy Technology Laboratory

  14. CX-013624: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Ahtanum Creek Property Acquisition Funding CX(s) Applied: B1.25Date: 05/04/2015 Location(s): WashingtonOffices(s): Bonneville Power Administration

  15. CX-012585: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Grit Blasting CX(s) Applied: B3.6Date: 41835 Location(s): South CarolinaOffices(s): Savannah River Operations Office

  16. CX-013432: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Process Demonstration Unit Support Structure CX(s) Applied: B1.15Date: 02/04/2015 Location(s): IdahoOffices(s): Idaho Operations Office

  17. CX-008875: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Bingen Substation Sectionalizing Switches Disposition CX(s) Applied: B1.24 Date: 08/27/2012 Location(s): Washington Offices(s): Bonneville Power Administration

  18. CX-011401: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Minto Lodge Rehabilitation CX(s) Applied: B5.1 Date: 11/19/2013 Location(s): Alaska Offices(s): Golden Field Office

  19. CX-013450: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Ellensburg Guy Wire Installation CX(s) Applied: B4.9Date: 03/06/2015 Location(s): WashingtonOffices(s): Bonneville Power Administration

  20. CX-013823: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Electric Vehicle Infrastructure (EVI) Laboratory Upgrades CX(s) Applied: B1.31Date: 06/18/2015 Location(s): IdahoOffices(s): Nuclear Energy

  1. CX-012789: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Building 440 CNM Clean Room Expansion CX(s) Applied: B3.15Date: 41906 Location(s): IllinoisOffices(s): Argonne Site Office

  2. CX-100400 Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Corrosion-resistant non-carbon electrocatalyst supports for PEFCs Award Number: DE- EE-0007272 CX(s) Applied: A9, B3.6

  3. CX-011822: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Light Willow Demonstration CX(s) Applied: B3.6 Date: 01/09/2014 Location(s): South Carolina Offices(s): Savannah River Operations Office

  4. Categorical Exclusion Determinations: Golden Field Office | Department...

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

    Categorical Exclusion Determination U.S. Department of Energy Collegiate Entrepreneurship Prize Award Number: TBD FOA CX(s) Applied: A9 Date: 12222014 Location(s): CO...

  5. CX-012656: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    North Bend Communication Site Engine Generator Replacement CX(s) Applied: B1.3Date: 41848 Location(s): WashingtonOffices(s): Bonneville Power Administration

  6. CX-003608: Categorical Exclusion Determination | Department of...

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

    CX-003608: Categorical Exclusion Determination Sustainable Algal Energy Production and Environmental Remediation CX(s) Applied: A9, B3.6 Date: 08252010 Location(s): Virginia ...

  7. CX-012278: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    Building 36 Use Permit CX(s) Applied: A9 Date: 06/23/2014 Location(s): Oregon Offices(s): National Energy Technology Laboratory

  8. CX-012434: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Low Cost Titanium Casting Technology CX(s) Applied: B3.6Date: 41878 Location(s): OhioOffices(s): National Energy Technology Laboratory

  9. CX-006646: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Restoration South of 54-TPX-10CX(s) Applied: B6.1Date: 02/09/2010Location(s): Casper, WyomingOffice(s): RMOTC

  10. CX-010717: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Moodys Radio Tower Land Acquisition CX(s) Applied: B1.24 Date: 07/15/2013 Location(s): Oklahoma Offices(s): Southwestern Power Administration

  11. CX-010155: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Augspurger Radio Tower Replacement Project CX(s) Applied: B1.19 Date: 04/03/2013 Location(s): Washington Offices(s): Bonneville Power Administration

  12. CX-008683: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Shaniko Radio Station Replacement Project CX(s) Applied: B1.19 Date: 07/11/2012 Location(s): Oregon Offices(s): Bonneville Power Administration

  13. CX-011190: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Alberton Communication Site Construction CX(s) Applied: B1.19 Date: 08/26/2013 Location(s): Montana Offices(s): Bonneville Power Administration

  14. CX-011237: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Lightspeed Networks Inc. Fiber Installation CX(s) Applied: B4.9 Date: 10/24/2013 Location(s): Oregon Offices(s): Bonneville Power Administration

  15. CX-012803: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Sacajawea Substation Expansion and Upgrade CX(s) Applied: B4.6Date: 41912 Location(s): WashingtonOffices(s): Bonneville Power Administration

  16. CX-012002: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Raver-Covington Conductor Replacement CX(s) Applied: B1.3 Date: 04/24/2014 Location(s): Washington Offices(s): Bonneville Power Administration

  17. CX-009423: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Relay and Switchboard Panel Replacements CX(s) Applied: B4.6 Date: 10/29/2012 Location(s): Arkansas Offices(s): Southwestern Power Administration

  18. CX-011214: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Sensitive Instrument Facility CX(s) Applied: B3.6 Date: 07/10/2013 Location(s): Iowa Offices(s): Ames Site Office

  19. CX-009398: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Domestic Source Recovery CX(s) Applied: B2.6 Date: 11/01/2012 Location(s): New Mexico Offices(s): Los Alamos Site Office

  20. CX-007587: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Gas Chromatography CX(s) Applied: B3.6 Date: 12/29/2011 Location(s): Oregon Offices(s): National Energy Technology Laboratory

  1. CX-010124: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Chromatography / Mass Spectrometry CX(s) Applied: B3.6 Date: 03/20/2013 Location(s): South Carolina Offices(s): Savannah River Operations Office

  2. CX-007399: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Offshore Wind Removing Market Barriers CX(s) Applied: A9, A11 Date: 12/20/2011 Location(s): Massachusetts Offices(s): Golden Field Office

  3. Categorical Exclusion Determinations: A12 | Department of Energy

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

    September 29, 2011 CX-006906: Categorical Exclusion Determination Electricity Delivery and Energy Reliability Assistance to State Regulatory Utility Commissioners CX(s) Applied: ...

  4. CX-010195: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Polymer Synthesis Lab - Modification CX(s) Applied: B3.6 Date: 04/15/2013 Location(s): Pennsylvania Offices(s): National Energy Technology Laboratory

  5. CX-012437: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    High Energy Density Lithium Battery CX(s) Applied: B3.6Date: 41878 Location(s): New YorkOffices(s): National Energy Technology Laboratory

  6. CX-012028: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    High Temperature Laboratory CX(s) Applied: B3.6 Date: 04/21/2014 Location(s): Oregon Offices(s): National Energy Technology Laboratory

  7. CX-013534: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    ENI USA Gas Marketing, LLC CX(s) Applied: B5.7Date: 04/14/2015 Location(s): Multiple LocationsOffices(s): Fossil Energy

  8. CX-009797: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Eni USA Gas Marketing, LLC CX(s) Applied: B5.7 Date: 02/06/2013 Location(s): Louisiana Offices(s): Fossil Energy

  9. CX-010338: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Eugene Substation Fiber Interconnection CX(s) Applied: B4.7 Date: 05/21/2013 Location(s): Oregon Offices(s): Bonneville Power Administration

  10. CX-010435: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    De Moss Substation Expansion CX(s) Applied: B4.6 Date: 06/03/2013 Location(s): Oregon Offices(s): Bonneville Power Administration

  11. CX-008146: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Advanced Formation Evaluator Tools (Haliburton) CX(s) Applied: B3.7 Date: 09/11/2011 Location(s): Wyoming Offices(s): RMOTC

  12. Categorical Exclusion Determinations: Idaho | Department of Energy

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

    ... June 18, 2015 CX-013839: Categorical Exclusion Determination Materials and Fuels Complex (MFC)-752 Analytical Laboratory Casting Laboratory Glovebox Heat Detection CX(s) Applied: ...

  13. CX-006681: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    New Drilling Location in Section 29CX(s) Applied: B3.1Date: 12/23/2009Location(s): Casper, WyomingOffice(s): RMOTC

  14. CX-013721: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Solar Vacuum Furnace CX(s) Applied: B3.6Date: 04/28/2015 Location(s): OregonOffices(s): National Energy Technology Laboratory

  15. CX-012188: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Emerald Ash Borer Control CX(s) Applied: B1.3 Date: 05/06/2014 Location(s): Illinois Offices(s): Argonne Site Office

  16. CX-011065: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Midwest Region Alternative Fuels Project CX(s) Applied: A1 Date: 08/29/2013 Location(s): Kansas Offices(s): National Energy Technology Laboratory

  17. CX-011788: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    I-75 Green Corridor Project CX(s) Applied: A1 Date: 02/10/2014 Location(s): Tennessee Offices(s): National Energy Technology Laboratory

  18. CX-007497: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    Clean Energy Coalition - Michigan Green Fleets CX(s) Applied: A1 Date: 12/06/2011 Location(s): Michigan Offices(s): National Energy Technology Laboratory

  19. CX-010938: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    Midwest Region Alternative Fuels Project CX(s) Applied: A1 Date: 09/17/2013 Location(s): Kansas, Kansas Offices(s): National Energy Technology Laboratory

  20. CX-011271: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    Idaho Petroleum Reduction Leadership Project CX(s) Applied: A1 Date: 09/30/2013 Location(s): Idaho Offices(s): National Energy Technology Laboratory

  1. CX-008588: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    St. Petersburg Solar Pilot Project CX(s) Applied: B5.1 Date: 07/19/2012 Location(s): Florida Offices(s): Golden Field Office

  2. CX-011634: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Closure Turf Installation CX(s) Applied: B6.1 Date: 08/27/2013 Location(s): Texas Offices(s): Pantex Site Office

  3. CX-008803: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Milling Machine Replacement Projects CX(s) Applied: B1.31 Date: 05/14/2012 Location(s): Tennessee Offices(s): Y-12 Site Office

  4. CX-012725: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Materials and Fuel Complex (MFC)-782 Fire Sprinkler Installation CX(s) Applied: B2.2Date: 41829 Location(s): IdahoOffices(s): Nuclear Energy

  5. CX-010756: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Solar Utility Network Deployment Acceleration CX(s) Applied: A9, A11 Date: 08/15/2013 Location(s): Virginia Offices(s): Golden Field Office

  6. CX-011102: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    American Solar Transformation Initiative CX(s) Applied: A11 Date: 08/09/2013 Location(s): California Offices(s): Golden Field Office

  7. CX-012531: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Distributed Wireless Antenna Sensors for Boiler Condition CX(s) Applied: B3.6Date: 41836 Location(s): CaliforniaOffices(s): National Energy Technology Laboratory

  8. CX-012539: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Distributed Wireless Antenna Sensors for Boiler Condition CX(s) Applied: B3.6Date: 41836 Location(s): TexasOffices(s): National Energy Technology Laboratory

  9. CX-008984: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    State Energy Program CX(s) Applied: A9, A11 Date: 08/29/2012 Location(s): Florida Offices(s): Golden Field Office

  10. CX-012798: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Davis Creek Tap Wood Pole Replacements CX(s) Applied: B1.3Date: 41915 Location(s): CaliforniaOffices(s): Bonneville Power Administration

  11. CX-007550: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Kearney - Waste Water Treatment Plant CX(s) Applied: B5.1 Date: 01/10/2012 Location(s): Missouri Offices(s): Golden Field Office

  12. CX-007549: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Harrisonville - Waste Water Treatment Plant CX(s) Applied: B5.1 Date: 01/10/2012 Location(s): Missouri Offices(s): Golden Field Office

  13. CX-008700: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Natapoc Property Funding CX(s) Applied: B1.25 Date: 06/12/2012 Location(s): Washington Offices(s): Bonneville Power Administration

  14. CX-009028: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Wisconsin Biodiesel Blending Program CX(s) Applied: B5.22 Date: 08/22/2012 Location(s): Wisconsin Offices(s): Golden Field Office

  15. CX-007856: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Sacramento Regional Energy Alliance CX(s) Applied: B5.23 Date: 01/27/2012 Location(s): California Offices(s): Golden Field Office

  16. CX-011625: Categorical Exclusion Determinationc

    Broader source: Energy.gov [DOE]

    9103 Second Floor Refurbishment CX(s) Applied: B1.3 Date: 06/05/2013 Location(s): Tennessee Offices(s): Y-12 Site Office

  17. CX-012495: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Building 6 Stack Replacement CX(s) Applied: B1.3Date: 41855 Location(s): West VirginiaOffices(s): National Energy Technology Laboratory

  18. CX-013324: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Wear Laboratory CX(s) Applied: A9, B3.6Date: 01/16/2015 Location(s): OregonOffices(s): National Energy Technology Laboratory

  19. CX-007423: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Highland Independent School District CX(s) Applied: B5.18 Date: 12/13/2011 Location(s): Texas Offices(s): Golden Field Office

  20. CX-007428: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Ralls Independent School District CX(s) Applied: B5.18 Date: 12/20/2011 Location(s): Texas Offices(s): Golden Field Office