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Sample records for in-situ decommissioning isd

  1. In-Situ Decommissioning

    Broader source: Energy.gov [DOE]

    In-Situ Decommissioning (ISD) is the permanent entombment of a facility that contains residual radiological and/or chemical contamination.  The ISD approach is a cost-effective alternative to both...

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

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

    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

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

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

    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. 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...

  5. 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)

  6. DOE EM Project Experience & Lessons Learned for In Situ Decommissioning

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

    (Feb. 2013) | Department of Energy EM Project Experience & Lessons Learned for In Situ Decommissioning (Feb. 2013) DOE EM Project Experience & Lessons Learned for In Situ Decommissioning (Feb. 2013) 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 Situ Decommissioning (ISD) projects at DOE facilities. As current and projected

  7. 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

  8. 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

  9. 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

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

    Office of Environmental Management (EM)

    In-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 ...

  11. 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

  12. 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

  13. Technology Requirements for In-Situ Decommissioning Workshop...

    Office of Environmental Management (EM)

    ... ISD-Specific performance models are required to estimate sustained performance and are the means to integrate the wide-range data set to validate andor adjust performance ...

  14. 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

  15. 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

  16. EM-20 ISD Report

    Office of Environmental Management (EM)

    Project Experience & Lessons Learned for In Situ Decommissioning Prepared By U.S. Department of Energy Office of Environmental Management Office of D&D and FE, EM-13 This page is deliberately blank. DOE EM Project Experience for In Situ Decommissioning i Contents Acronyms .................................................................................................................................................... vii 1. Introduction

  17. DEVELOPMENT OF A SENSOR NETWORK TEST BED FOR ISD MATERIALS AND STRUCUTRAL CONDITION MONITORING

    SciTech Connect (OSTI)

    Zeigler, K.; Ferguson, B.; Karapatakis, D.; Herbst, C.; Stripling, C.

    2011-07-06

    The P Reactor at the Savannah River Site is one of the first reactor facilities in the US DOE complex that has been placed in its end state through in situ decommissioning (ISD). The ISD end state consists of a grout-filled concrete civil structure within the concrete frame of the original building. To evaluate the feasibility and utility of remote sensors to provide verification of ISD system conditions and performance characteristics, an ISD Sensor Network Test Bed has been designed and deployed at the Savannah River National Laboratory. The test bed addresses the DOE-EM Technology Need to develop a remote monitoring system to determine and verify ISD system performance. Commercial off-the-shelf sensors have been installed on concrete blocks taken from walls of the P Reactor Building. Deployment of this low-cost structural monitoring system provides hands-on experience with sensor networks. The initial sensor system consists of: (1) Groutable thermistors for temperature and moisture monitoring; (2) Strain gauges for crack growth monitoring; (3) Tiltmeters for settlement monitoring; and (4) A communication system for data collection. Preliminary baseline data and lessons learned from system design and installation and initial field testing will be utilized for future ISD sensor network development and deployment.

  18. 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].

  19. DOE EM Project Experience & Lessons Learned for In Situ Decommissionin...

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

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

  20. Ruffling of Metalloporphyrins Bound to IsdG And IsdI, Two Heme Degrading Enzymes in Staphylococcus Aureus

    SciTech Connect (OSTI)

    Lee, W.C.; Reniere, M.L.; Skaar, E.P.; Murphy, M.E.P.

    2009-05-19

    IsdG and IsdI are paralogous proteins that are intracellular components of a complex heme uptake system in Staphylococcus aureus. IsdG and IsdI were shown previously to reductively degrade hemin. Crystal structures of the apoproteins show that these proteins belong to a newly identified heme degradation family distinct from canonical eukaryotic and prokaryotic heme oxygenases. Here we report the crystal structures of an inactive N7A variant of IsdG in complex with Fe{sup 3+}-protoporphyrin IX (IsdG-hemin) and of IsdI in complex with cobalt protoporphyrin IX (IsdI-CoPPIX) to 1.8 {angstrom} or better resolution. These structures show that the metalloporphyrins are buried into similar deep clefts such that the propionic acids form salt bridges to two Arg residues. His{sup 77} (IsdG) or His{sup 76} (IsdI), a critical residue required for activity, is coordinated to the Fe{sup 3+} or Co{sup 3+} atoms, respectively. The bound porphyrin rings form extensive steric interactions in the binding cleft such that the rings are highly distorted from the plane. This distortion is best described as ruffled and places the {beta}- and {delta}-meso carbons proximal to the distal oxygen-binding site. In the IsdG-hemin structure, Fe{sup 3+} is pentacoordinate, and the distal side is occluded by the side chain of Ile{sup 55}. However, in the structure of IsdI-CoPPIX, the distal side of the CoPPIX accommodates a chloride ion in a cavity formed through a conformational change in Ile{sup 55}. The chloride ion participates in a hydrogen bond to the side chain amide of Asn{sup 6}. Together the structures suggest a reaction mechanism in which a reactive peroxide intermediate proceeds with nucleophilic oxidation at the {beta}- or {delta}-meso carbon of the hemin.

  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. DRAFT EM SSAB Chairs Meeting Waste Disposition Strategies Update

    Office of Environmental Management (EM)

    Decommissioning | Department of Energy Environmental Management Strategy and Experience for In-Situ Decommissioning DOE Environmental Management Strategy and Experience for In-Situ Decommissioning 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 Management (EM) lexicon; however, ISD is not a revolutionary concept. Since the 1970s, the U.S. Nuclear

  3. Supercomputer decommissioning

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

    All Issues submit Roadrunner supercomputer: Rest in pieces Decommissioning a classified ... critical information by removing their memory and repurposing the rest of the equipment. ...

  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. Decommissioning Handbook

    Office of Energy Efficiency and Renewable Energy (EERE)

    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...

  6. 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: September 1, 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

  7. 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.

  8. Decommissioning an Active Historical Reactor Facility at the Savannah River Site - 13453

    SciTech Connect (OSTI)

    Bergren, Christopher L.; Long, J. Tony; Blankenship, John K.; Adams, Karen M.

    2013-07-01

    action for the In Situ Decommissioning (ISD) of the 105-C Disassembly Basin. ISD consisted of stabilization/isolation of remaining contaminated water, sediment, activated reactor equipment, and scrap metal by filling the DB with underwater non-structural grout to the appropriate (-4.877 meter) grade-level, thence with dry area non-structural grout to the final -10 centimeter level. The roof over the DB was preserved due to its potential historical significance and to prevent the infiltration of precipitation. Forced evaporation was the form of treatment implemented to remove the approximately 9.1 M liters of contaminated basin water. Using specially formulated grouts, irradiated materials and sediment were treated by solidification/isolation thus reducing their mobility, reducing radiation exposure and creating an engineered barrier thereby preventing access to the contaminants. Grouting provided a low permeability barrier to minimize any potential transport of contaminants to the aquifer. Efforts were made to preserve the historical significance of the Reactor in accordance with the National Historic Preservation Act. ISD provides a cost effective means to isolate and contain residual radioactivity from past nuclear operations allowing natural radioactive decay to reduce hazards to manageable levels. This method limits release of radiological contamination to the environment, minimizes radiation exposure to workers, prevents human/animal access to the hazardous substances, and allows for ongoing monitoring of the decommissioned facility. Field construction was initiated in August 2011; evaporator operations commenced January 2012 and ended July 2012 with over 9 M liters of water treated/removed. Over 8,525 cubic meters of grout were placed, completing in August 2012. The project completed with an excellent safety record, on schedule and under budget. (authors)

  9. 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.

  10. Portsmouth Decontamination & Decommissioning

    Broader source: Energy.gov [DOE]

    The Decontamination & Decommissioning (D&D) Program at the Portsmouth Site addresses potential future demolition and disposal of approximately 415 facilities (including buildings, utilities...

  11. Decommissioning Benchmarking Study Final Report

    Office of Energy Efficiency and Renewable Energy (EERE)

    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...

  12. 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

  13. Hallam, Nebraska, Decommissioned Reactor Site

    Office of Legacy Management (LM)

    Fact Sheet D&D D&D Hallam, Nebraska, Decommissioned Reactor Site This fact sheet provides information about the Hallam, Nebraska, Decommissioned Reactor Site. This site is managed by the U.S. Department of Energy Office of Legacy Management under the Defense Decontamination and Decommissioning (D&D) Program. Location of the Hallam Decommissioned Reactor Site Description and History The Hallam decommissioned reactor site is in southeastern Nebraska, approximately 19 miles south of

  14. Decommissioning Plan RM

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

    ... In a decommissioning project the disposition of waste can be a significant portion of the project costs and both the cost and logistics of waste management must be adequately ...

  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. Decommissioning Under CERCLA Information Sheet

    Broader source: Energy.gov [DOE]

    This Question and Answer (Q&A) Sheet discusses the use of removal authority in the conduct of decommissioning activities, consistent with the Policy on Decommissioning of Department of Energy...

  18. Shippingport Station Decommissioning Project

    SciTech Connect (OSTI)

    McKernan, M.L.

    1989-12-22

    The Shippingport Atomic Power Station was located on the Ohio River in Shippingport Borough (Beaver County), Pennsylvania, USA. The US Atomic Energy Commission (AEC) constructed the plant in the mid-1950s on a seven and half acre parcel of land leased from Duquesne Light Company (DLC). The purposes were to demonstrate and to develop Pressurized Water Recovery technology and to generate electricity. DLC operated the Shippingport plant under supervision of (the successor to AEC) the Department of Energy (DOE)-Naval Reactors (NR) until operations were terminated on October 1, 1982. NR concluded end-of-life testing and defueling in 1984 and transferred the Station's responsibility to DOE Richland Operations Office (RL), Surplus Facility Management Program Office (SFMPO5) on September 5, 1984. SFMPO subsequently established the Shippingport Station Decommissioning Project and selected General Electric (GE) as the Decommissioning Operations Contractor. This report is intended to provide an overview of the Shippingport Station Decommissioning Project.

  19. 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.

  20. 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.

  1. In situ groundwater bioremediation

    SciTech Connect (OSTI)

    Hazen, Terry C.

    2009-02-01

    In situ groundwater bioremediation of hydrocarbons has been used for more than 40 years. Most strategies involve biostimulation; however, recently bioaugmentation have been used for dehalorespiration. Aquifer and contaminant profiles are critical to determining the feasibility and strategy for in situ groundwater bioremediation. Hydraulic conductivity and redox conditions, including concentrations of terminal electron acceptors are critical to determine the feasibility and strategy for potential bioremediation applications. Conceptual models followed by characterization and subsequent numerical models are critical for efficient and cost effective bioremediation. Critical research needs in this area include better modeling and integration of remediation strategies with natural attenuation.

  2. 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.

  3. 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.

  4. In situ reactor

    DOE Patents [OSTI]

    Radtke, Corey William; Blackwelder, David Bradley

    2004-01-27

    An in situ reactor for use in a geological strata, is described and which includes a liner defining a centrally disposed passageway and which is placed in a borehole formed in the geological strata; and a sampling conduit is received within the passageway defined by the liner and which receives a geological specimen which is derived from the geological strata, and wherein the sampling conduit is in fluid communication with the passageway defined by the liner.

  5. 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.

  6. In situ measurement system

    DOE Patents [OSTI]

    Lord, D.E.

    1980-11-24

    A multipurpose in situ underground measurement system comprising a plurality of long electrical resistance elements in the form of rigid reinforcing bars, each having an open loop hairpin configuration of shorter length than the other resistance elements. The resistance elements are arranged in pairs in a unitized structure, and grouted in place in the underground volume. Measurement means are provided for obtaining for each pair the electrical resistance of each element and the difference in electrical resistance of the paired elements, which difference values may be used in analytical methods involving resistance as a function of temperature. A scanner means sequentially connects the resistance-measuring apparatus to each individual pair of elements. A source of heating current is also selectively connectable for heating the elements to an initial predetermined temperature prior to electrical resistance measurements when used as an anemometer.

  7. 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.

  8. 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.

  9. In Situ Nuclear Characterization Infrastructure

    SciTech Connect (OSTI)

    James A. Smith; J. Rory Kennedy

    2011-11-01

    To be able to evolve microstructure with a prescribed in situ process, an effective measurement infrastructure must exist. This interdisciplinary infrastructure needs to be developed in parallel with in situ sensor technology. This paper discusses the essential elements in an effective infrastructure.

  10. 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.

  11. 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.

  12. In situ microbial filter used for bioremediation

    DOE Patents [OSTI]

    Carman, M. Leslie; Taylor, Robert T.

    2000-01-01

    An improved method for in situ microbial filter bioremediation having increasingly operational longevity of an in situ microbial filter emplaced into an aquifer. A method for generating a microbial filter of sufficient catalytic density and thickness, which has increased replenishment interval, improved bacteria attachment and detachment characteristics and the endogenous stability under in situ conditions. A system for in situ field water remediation.

  13. Triplex in-situ hybridization

    DOE Patents [OSTI]

    Fresco, Jacques R.; Johnson, Marion D.

    2002-01-01

    Disclosed are methods for detecting in situ the presence of a target sequence in a substantially double-stranded nucleic acid segment, which comprises: a) contacting in situ under conditions suitable for hybridization a substantially double-stranded nucleic acid segment with a detectable third strand, said third strand being capable of hybridizing to at least a portion of the target sequence to form a triple-stranded structure, if said target sequence is present; and b) detecting whether hybridization between the third strand and the target sequence has occured.

  14. 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

  15. Portsmouth Decontamination and Decommissioning Record of Decision |

    Energy Savers [EERE]

    Department of Energy Decontamination and Decommissioning Record of Decision Portsmouth Decontamination and Decommissioning Record of Decision The Ohio Environmental Protection Agency (Ohio EPA) and the U.S. Department of Energy (DOE) have agreed upon a plan to demolish the large process buildings and other facilities undergoing decontamination and decommissioning (D&D) at the Portsmouth Gaseous Diffusion Plant. The Record of Decision (ROD) for the Process Buildings and Complex Facilities

  16. 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...

  17. Confidentiality Agreement between the Nuclear Decommissioning...

    Office of Environmental Management (EM)

    the US Department of Energy and UK Nuclear Decommissioning Authority Waste Management Nuclear Materials & Waste Tank Waste and Waste Processing Waste Disposition Packaging and ...

  18. 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...

  19. In situ biofilm coupon device

    DOE Patents [OSTI]

    Peyton, Brent M.; Truex, Michael J.

    1997-01-01

    An apparatus for characterization of in-situ microbial biofilm populations in subsurface groundwater. The device permits biofilm-forming microorganisms to adhere to packing material while emplaced in a groundwater strata, so that the packing material can be later analyzed for quantity and type of microorganisms, growth rate, and nutrient requirements.

  20. In situ biofilm coupon device

    DOE Patents [OSTI]

    Peyton, B.M.; Truex, M.J.

    1997-06-24

    An apparatus is disclosed for characterization of in-situ microbial biofilm populations in subsurface groundwater. The device permits biofilm-forming microorganisms to adhere to packing material while emplaced in a groundwater strata, so that the packing material can be later analyzed for quantity and type of microorganisms, growth rate, and nutrient requirements. 3 figs.

  1. Management of Decommissioning on a Multi-Facility Site (Conference...

    Office of Scientific and Technical Information (OSTI)

    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 ...

  2. 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...

  3. 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.

  4. 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.

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

    Office of Energy Efficiency and Renewable Energy (EERE)

    On October 19-22, 2010, an independent expert panel of scientists and engineers met to assist the Department of Energy (DOE) and the Savannah River National Laboratory in developing a technical...

  6. Confidentiality Agreement between the Nuclear Decommissioning Authority and

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

    US Department of Energy | Department of Energy Services » Communication & Engagement » International Programs » Confidentiality Agreement between the Nuclear Decommissioning Authority and US Department of Energy Confidentiality Agreement between the Nuclear Decommissioning Authority and US Department of Energy Confidentiality Agreement between the Nuclear Decommissioning Authority in UK and US Department of Energy Confidentiality Agreement between the Nuclear Decommissioning Authority

  7. 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.

  8. Noise canceling in-situ detection

    DOE Patents [OSTI]

    Walsh, David O.

    2014-08-26

    Technologies applicable to noise canceling in-situ NMR detection and imaging are disclosed. An example noise canceling in-situ NMR detection apparatus may comprise one or more of a static magnetic field generator, an alternating magnetic field generator, an in-situ NMR detection device, an auxiliary noise detection device, and a computer.

  9. In-Situ Electron Microscopy of Electrical Energy Storage Materials...

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

    More Documents & Publications In-Situ Electron Microscopy of Electrical Energy Storage Materials In-Situ Electron Microscopy of Electrical Energy Storage Materials In-situ ...

  10. 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

  11. 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.

  12. TA-2 Water Boiler Reactor Decommissioning Project

    SciTech Connect (OSTI)

    Durbin, M.E.; Montoya, G.M.

    1991-06-01

    This final report addresses the Phase 2 decommissioning of the Water Boiler Reactor, biological shield, other components within the biological shield, and piping pits in the floor of the reactor building. External structures and underground piping associated with the gaseous effluent (stack) line from Technical Area 2 (TA-2) Water Boiler Reactor were removed in 1985--1986 as Phase 1 of reactor decommissioning. The cost of Phase 2 was approximately $623K. The decommissioning operation produced 173 m{sup 3} of low-level solid radioactive waste and 35 m{sup 3} of mixed waste. 15 refs., 25 figs., 3 tabs.

  13. Guides: Design/Engineering for Deactivation & Decommissioning

    Broader source: Energy.gov [DOE]

    To ensure development of appropriate levels of engineering detail, DOE-EM’s Office of Deactivation and Decommissioning and Facility Engineering (EM-13) has prepared this guidance for  tailoring a D...

  14. Power Burst Facility (PBF) Reactor Reactor Decommissioning

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

    Click here to view Click here to view Reactor Decommissioning Click on an image to enlarge A crane removes the reactor vessel from the Power Burst Facility (top), then places it ...

  15. Safety of Decommissioning of Nuclear Facilities

    SciTech Connect (OSTI)

    Batandjieva, B.; Warnecke, E.; Coates, R.

    2008-01-15

    Full text of publication follows: ensuring safety during all stages of facility life cycle is a widely recognised responsibility of the operators, implemented under the supervision of the regulatory body and other competent authorities. As the majority of the facilities worldwide are still in operation or shutdown, there is no substantial experience in decommissioning and evaluation of safety during decommissioning in majority of Member States. The need for cooperation and exchange of experience and good practices on ensuring and evaluating safety of decommissioning was one of the outcomes of the Berlin conference in 2002. On this basis during the last three years IAEA initiated a number of international projects that can assist countries, in particular small countries with limited resources. The main IAEA international projects addressing safety during decommissioning are: (i) DeSa Project on Evaluation and Demonstration of Safety during Decommissioning; (ii) R{sup 2}D{sup 2}P project on Research Reactors Decommissioning Demonstration Project; and (iii) Project on Evaluation and Decommissioning of Former Facilities that used Radioactive Material in Iraq. This paper focuses on the DeSa Project activities on (i) development of a harmonised methodology for safety assessment for decommissioning; (ii) development of a procedure for review of safety assessments; (iii) development of recommendations on application of the graded approach to the performance and review of safety assessments; and (iv) application of the methodology and procedure to the selected real facilities with different complexities and hazard potentials (a nuclear power plant, a research reactor and a nuclear laboratory). The paper also outlines the DeSa Project outcomes and planned follow-up activities. It also summarises the main objectives and activities of the Iraq Project and introduces the R{sup 2}D{sup 2} Project, which is a subject of a complementary paper.

  16. Russian nuclear-powered submarine decommissioning

    SciTech Connect (OSTI)

    Bukharin, O.; Handler, J.

    1995-11-01

    Russia is facing technical, economic and organizational difficulties in dismantling its oversized and unsafe fleet of nuclear powered submarines. The inability of Russia to deal effectively with the submarine decommissioning crisis increases the risk of environmental disaster and may hamper the implementation of the START I and START II treaties. This paper discusses the nuclear fleet support infrastructure, the problems of submarine decommissioning, and recommends international cooperation in addressing these problems.

  17. In-situ spectrophotometric probe

    DOE Patents [OSTI]

    Prather, W.S.

    1992-12-15

    A spectrophotometric probe is described for in situ absorption spectra measurements comprising a first optical fiber carrying light from a remote light source, a second optical fiber carrying light to a remote spectrophotometer, the proximal ends of the first and second optical fibers parallel and co-terminal, a planoconvex lens to collimate light from the first optical fiber, a reflecting grid positioned a short distance from the lens to reflect the collimated light back to the lens for focusing on the second optical fiber. The lens is positioned with the convex side toward the optical fibers. A substrate for absorbing analyte or an analyte and reagent mixture may be positioned between the lens and the reflecting grid. 5 figs.

  18. In-situ measurement system

    DOE Patents [OSTI]

    Lord, David E.

    1983-01-01

    A multipurpose in situ underground measurement system comprising a plurality of long electrical resistance elements in the form of rigid reinforcing bars, each having an open loop "hairpin" configuration of shorter length than the other resistance elements. The resistance elements are arranged in pairs in a unitized structure, and grouted in place in the underground volume. The electrical resistance of each element and the difference in electrical resistance of the paired elements are obtained, which difference values may be used in analytical methods involving resistance as a function of temperature. A scanner sequentially connects the resistance-measuring apparatus to each individual pair of elements. A source of heating current is also selectively connectable for heating the elements to an initial predetermined temperature prior to electrical resistance measurements when used as an anemometer.

  19. In-situ spectrophotometric probe

    DOE Patents [OSTI]

    Prather, William S.

    1992-01-01

    A spectrophotometric probe for in situ absorption spectra measurements comprising a first optical fiber carrying light from a remote light source, a second optical fiber carrying light to a remote spectrophotometer, the proximal ends of the first and second optical fibers parallel and coterminal, a planoconvex lens to collimate light from the first optical fiber, a reflecting grid positioned a short distance from the lens to reflect the collimated light back to the lens for focussing on the second optical fiber. The lens is positioned with the convex side toward the optical fibers. A substrate for absorbing analyte or an analyte and reagent mixture may be positioned between the lens and the reflecting grid.

  20. Amplification of chromosomal DNA in situ

    DOE Patents [OSTI]

    Christian, Allen T.; Coleman, Matthew A.; Tucker, James D.

    2002-01-01

    Amplification of chromosomal DNA in situ to increase the amount of DNA associated with a chromosome or chromosome region is described. The amplification of chromosomal DNA in situ provides for the synthesis of Fluorescence in situ Hybridization (FISH) painting probes from single dissected chromosome fragments, the production of cDNA libraries from low copy mRNAs and improved in Comparative Genomic Hybridization (CGH) procedures.

  1. Decommissioning of the Iraq former nuclear complex

    SciTech Connect (OSTI)

    Abbas, Mohammed; Helou, Tuama; Ahmead, Bushra; Al-Atia, Mousa; Al-Mubarak, Mowaffak; Danneels, Jeffrey; Cochran, John; Sorenson, Ken; Coates, Roger

    2007-07-01

    Available in abstract form only. Full text of publication follows: A number of sites in Iraq have some degree of radiological contamination and require decommissioning and remediation in order to ensure radiological safety. Many of these sites in Iraq are located at the nuclear research centre at Al Tuwaitha. The International Atomic Energy Agency (IAEA) Board of Governors has approved a project to assist the Government of Iraq in the evaluation and decommissioning of former facilities that used radioactive materials. The project is divided into three phases: Phase 1: collect and analyze all available data and conduct training of the Iraqi staff, Phase 2: develop a decommissioning and remediation plan, and Phase 3: implement field activities relating to decommissioning, remediation and site selection suitable for final disposal of waste. Four working groups have been established to complete the Phase 1 work and significant progress has been made in drafting a new nuclear law which will provide the legal basis for the licensing of the decommissioning of the former nuclear complex. Work is also underway to collect and analysis existing date, to prioritize future activities and to develop a waste management strategy. This will be a long-term and costly project. (authors)

  2. 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.

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

    Office of Scientific and Technical Information (OSTI)

    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 ...

  4. Method for in situ combustion

    DOE Patents [OSTI]

    Pasini, III, Joseph; Shuck, Lowell Z.; Overbey, Jr., William K.

    1977-01-01

    This invention relates to an improved in situ combustion method for the recovery of hydrocarbons from subterranean earth formations containing carbonaceous material. The method is practiced by penetrating the subterranean earth formation with a borehole projecting into the coal bed along a horizontal plane and extending along a plane disposed perpendicular to the plane of maximum permeability. The subterranean earth formation is also penetrated with a plurality of spaced-apart vertical boreholes disposed along a plane spaced from and generally parallel to that of the horizontal borehole. Fractures are then induced at each of the vertical boreholes which project from the vertical boreholes along the plane of maximum permeability and intersect the horizontal borehole. The combustion is initiated at the horizontal borehole and the products of combustion and fluids displaced from the earth formation by the combustion are removed from the subterranean earth formation via the vertical boreholes. Each of the vertical boreholes are, in turn, provided with suitable flow controls for regulating the flow of fluid from the combustion zone and the earth formation so as to control the configuration and rate of propagation of the combustion zone. The fractures provide a positive communication with the combustion zone so as to facilitate the removal of the products resulting from the combustion of the carbonaceous material.

  5. Frontiers of in situ electron microscopy

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Zheng, Haimei; Zhu, Yimei; Meng, Shirley Ying

    2015-01-01

    In situ transmission electron microscopy (TEM) has become an increasingly important tool for materials characterization. It provides key information on the structural dynamics of a material during transformations and the correlation between structure and properties of materials. With the recent advances in instrumentation, including aberration corrected optics, sample environment control, the sample stage, and fast and sensitive data acquisition, in situ TEM characterization has become more and more powerful. In this article, a brief review of the current status and future opportunities of in situ TEM is included. It also provides an introduction to the six articles covered by inmore » this issue of MRS Bulletin explore the frontiers of in situ electron microscopy, including liquid and gas environmental TEM, dynamic four-dimensional TEM, nanomechanics, ferroelectric domain switching studied by in situ TEM, and state-of-the-art atomic imaging of light elements (i.e., carbon atoms) and individual defects.« less

  6. 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.

  7. Decontamination & Decommissioning/ Facilities Engineering (D&D/FE)

    Broader source: Energy.gov [DOE]

    As the DOE complex sites prepare for closure, a large number of buildings and facilities must be deactivated and decommissioned.

  8. West Valley Demonstration Project Phase I Decommissioning - Facility...

    Office of Environmental Management (EM)

    West Valley Demonstration Project Phase I Decommissioning - Facility Disposition Partnering Performance Agreement The Department of Energy, West Valley Demonstration Project ...

  9. Shippingport Station Decommissioning Project. Final project report

    SciTech Connect (OSTI)

    McKernan, M.L.

    1989-12-22

    The Shippingport Atomic Power Station was located on the Ohio River in Shippingport Borough (Beaver County), Pennsylvania, USA. The US Atomic Energy Commission (AEC) constructed the plant in the mid-1950s on a seven and half acre parcel of land leased from Duquesne Light Company (DLC). The purposes were to demonstrate and to develop Pressurized Water Recovery technology and to generate electricity. DLC operated the Shippingport plant under supervision of (the successor to AEC) the Department of Energy (DOE)-Naval Reactors (NR) until operations were terminated on October 1, 1982. NR concluded end-of-life testing and defueling in 1984 and transferred the Station`s responsibility to DOE Richland Operations Office (RL), Surplus Facility Management Program Office (SFMPO5) on September 5, 1984. SFMPO subsequently established the Shippingport Station Decommissioning Project and selected General Electric (GE) as the Decommissioning Operations Contractor. This report is intended to provide an overview of the Shippingport Station Decommissioning Project.

  10. 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

  11. 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.

  12. EM-20 ISD Report

    Office of Environmental Management (EM)

    ......... 99 A.1 Purpose ......NEPA National Environmental Policy Act NFPA National Fire Protection Association NTCRA ...

  13. 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).

  14. 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.

  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 of Shippingport commercial reactor

    SciTech Connect (OSTI)

    Schreiber, J.

    1989-11-01

    To a certain degree, the decontamination and decommissioning (D and D) of the Shippingport reactor was a joint venture with Duquesne Light Company. The structures that were to be decommissioned were to be removed to at least three feet below grade. Since the land had been leased from Duquesne Light, there was an agreement with them to return the land to them in a radiologically safe condition. The total enclosure volume for the steam and nuclear containment systems was about 1.3 million cubic feet, more than 80% of which was below ground. Engineering plans for the project were started in July of 1980 and the final environmental impact statement (EIS) was published in May of 1982. The plant itself was shut down in October of 1982 for end-of-life testing and defueling. The engineering services portion of the decommissioning plans was completed in September of 1983. DOE moved onto the site and took over from the Navy in September of 1984. Actual physical decommissioning began after about a year of preparation and was completed about 44 months later in July of 1989. This paper describes the main parts of D and D.

  17. 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.

  18. DOE In Situ Remediation Integrated Program. In situ manipulation technologies subprogram plan

    SciTech Connect (OSTI)

    Yow, J.L. Jr.

    1993-12-22

    The In Situ Remediation Integrated Program (ISRP) supports and manages a balanced portfolio of applied research and development activities in support of DOE environmental restoration and waste management needs. ISRP technologies are being developed in four areas: containment, chemical and physical treatment, in situ bioremediation, and in situ manipulation (including electrokinetics). the focus of containment is to provide mechanisms to stop contaminant migration through the subsurface. In situ bioremediation and chemical and physical treatment both aim to destroy or eliminate contaminants in groundwater and soils. In situ manipulation (ISM) provides mechanisms to access contaminants or introduce treatment agents into the soil, and includes other technologies necessary to support the implementation of ISR methods. Descriptions of each major program area are provided to set the technical context of the ISM subprogram. Typical ISM needs for major areas of in situ remediation research and development are identified.

  19. Development of Numerical Simulation Capabilities for In Situ...

    Office of Scientific and Technical Information (OSTI)

    for In Situ Heating of Oil Shale Citation Details In-Document Search Title: Development of Numerical Simulation Capabilities for In Situ Heating of Oil Shale Authors: Hoda, ...

  20. In-Situ Electron Microscopy of Electrical Energy Storage Materials...

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

    More Documents & Publications In-Situ Electron Microscopy of Electrical Energy Storage Materials In-Situ Electron Microscopy of Electrical Energy Storage Materials Investigations ...

  1. In Situ Ambient Pressure X-ray Photoelectron Spectroscopy Studies...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: In Situ Ambient Pressure X-ray ... Citation Details In-Document Search Title: In Situ Ambient ... Resource Relation: Journal Name: Scientific Reports; Journal ...

  2. In Situ Transmission Electron Microscopy. (Conference) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    In Situ Transmission Electron Microscopy. Citation Details In-Document Search Title: In Situ Transmission Electron Microscopy. Abstract not provided. Authors: Jungjohann, Katherine ...

  3. In-Situ, Real Time Measurement of Elemental Constituents | Department...

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

    In-Situ, Real Time Measurement of Elemental Constituents In-Situ, Real Time Measurement of Elemental Constituents New Laser System Provides Real-Time Measurements for Improved ...

  4. In-situ characterization and diagnostics of mechanical degradation...

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

    In-situ characterization and diagnostics of mechanical degradation in electrodes In-situ characterization and diagnostics of mechanical degradation in electrodes 2011 DOE Hydrogen ...

  5. In situ transmission electron microscopy investigation of the...

    Office of Scientific and Technical Information (OSTI)

    Published Article: In situ transmission electron microscopy investigation of the interfacial reaction between Ni and Al during rapid heating in a nanocalorimeter Title: In situ...

  6. Documentation of INL's In Situ Oil Shale Retorting Water Usage...

    Office of Scientific and Technical Information (OSTI)

    Documentation of INL's In Situ Oil Shale Retorting Water Usage System Dynamics Model Citation Details In-Document Search Title: Documentation of INL's In Situ Oil Shale Retorting ...

  7. 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.

  8. In-situ gamma-PHA measurements to support unconditional release of 235-F chiller units

    SciTech Connect (OSTI)

    Salaymeh, S.R.

    2000-02-17

    The Analytical Development Section of Savannah River Technology Center (SRTC) was requested by the Facility Decommission Division (FDD) to conduct in-situ gamma-ray pulse height analysis measurements to support the unconditional release of 235-F chiller units. The chiller units were used to cool process water in the 235-F facility. The measurements' main goal is to confirm that there is no process-related contaminants present on the chillers. For each of the two F-area clean water chillers, the authors have acquired ten gamma-ray pulse height analysis spectra. This report will discuss the purpose of the measurements, the experimental setup, data acquisition, calculations and results, and a conclusion of the study.

  9. Capturing Process Knowledge for Facility Deactivation and Decommissioning |

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

    Department of Energy Capturing Process Knowledge for Facility Deactivation and Decommissioning Capturing Process Knowledge for Facility Deactivation and Decommissioning 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 needs. Capturing Process Knowledge for Facility Deactivation and Decommissioning (252.61 KB) More Documents & Publications

  10. In-situ vitrification of waste materials

    DOE Patents [OSTI]

    Powell, James R.; Reich, Morris; Barletta, Robert

    1997-11-14

    A method for the in-situ vitrification of waste materials in a disposable can that includes an inner container and an outer container is disclosed. The method includes the steps of adding frit and waste materials to the inner container, removing any excess water, heating the inner container such that the frit and waste materials melt and vitrify after cooling, while maintaining the outer container at a significantly lower temperature than the inner container. The disposable can is then cooled to ambient temperatures and stored. A device for the in-situ vitrification of waste material in a disposable can is also disclosed.

  11. In-situ vitrification of waste materials

    DOE Patents [OSTI]

    Powell, J.R.; Reich, M.; Barletta, R.

    1997-10-14

    A method for the in-situ vitrification of waste materials in a disposable can that includes an inner container and an outer container is disclosed. The method includes the steps of adding frit and waste materials to the inner container, removing any excess water, heating the inner container such that the frit and waste materials melt and vitrify after cooling, while maintaining the outer container at a significantly lower temperature than the inner container. The disposable can is then cooled to ambient temperatures and stored. A device for the in-situ vitrification of waste material in a disposable can is also disclosed. 7 figs.

  12. 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.

  13. 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...

  14. DOE Policy on Decommissioning DOE Facilities Under CERCLA

    Broader source: Energy.gov [DOE]

    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...

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

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

    This policy and any internal procedures adopted for its implementation are intended exclusively for employees of the ... EPA and DOE to develop an approach to decommissioning that ...

  16. 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.

  17. 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

  18. In situ bioremediation. When does it work

    SciTech Connect (OSTI)

    Not Available

    1993-01-01

    The study narrows the focus to two critical facets of bioremediation. First, it addresses the use of microorganisms to remove contamination from ground water and soils that remain in place (i.e., in situ) during the cleanup. This focus distinguishes in situ bioremediation of the sub-surface from significantly different applications of bioremediation, such as to treat oil tanker spills, wastewaters, or sludges. Second, the primary object of the study is to provide guidance on how to evaluate when an in situ bioremediation process is working or has worked. This focus is most important because the in situ environment is highly complex and very difficult to observe. Therefore, tools from several scientific and engineering disciplines must be used in a sophisticated manner if the success of a bioremediation effort is to be evaluated. Guidance is acutely needed today because most people faced with making decisions about bioremediation projects do not have the interdisciplinary knowledge to integrate all of the necessary tools. (Copyright (c) 1993 by the National Academy of Sciences.)

  19. Technology, safety and costs of decommissioning a reference boiling water reactor power station: Technical support for decommissioning matters related to preparation of the final decommissioning rule

    SciTech Connect (OSTI)

    Konzek, G.J.; Smith, R.I.

    1988-07-01

    Preparation of the final Decommissioning Rule by the Nuclear Regulatory Commission (NRC) staff has been assisted by Pacific Northwest Laboratory (PNL) staff familiar with decommissioning matters. These efforts have included updating previous cost estimates developed during the series of studies of conceptually decommissioning reference licensed nuclear facilities for inclusion in the Final Generic Environmental Impact Statement (FGEIS) on decommissioning; documenting the cost updates; evaluating the cost and dose impacts of post-TMI-2 backfits on decommissioning; developing a revised scaling formula for estimating decommissioning costs for reactor plants different in size from the reference boiling water reactor (BWR) described in the earlier study; and defining a formula for adjusting current cost estimates to reflect future escalation in labor, materials, and waste disposal costs. This report presents the results of recent PNL studies to provide supporting information in three areas concerning decommissioning of the reference BWR: updating the previous cost estimates to January 1986 dollars; assessing the cost and dose impacts of post-TMI-2 backfits; and developing a scaling formula for plants different in size than the reference plant and an escalation formula for adjusting current cost estimates for future escalation.

  20. In Situ Remediation Integrated Program: Technology summary

    SciTech Connect (OSTI)

    Not Available

    1994-02-01

    The In Situ Remediation Integrated Program (ISR IP) was instituted out of recognition that in situ remediation could fulfill three important criteria: significant cost reduction of cleanup by eliminating or minimizing excavation, transportation, and disposal of wastes; reduced health impacts on workers and the public by minimizing exposure to wastes during excavation and processing; and remediation of inaccessible sites, including: deep subsurfaces, in, under, and around buildings. Buried waste, contaminated soils and groundwater, and containerized wastes are all candidates for in situ remediation. Contaminants include radioactive wastes, volatile and non-volatile organics, heavy metals, nitrates, and explosive materials. The ISR IP intends to facilitate development of in situ remediation technologies for hazardous, radioactive, and mixed wastes in soils, groundwater, and storage tanks. Near-term focus is on containment of the wastes, with treatment receiving greater effort in future years. ISR IP is an applied research and development program broadly addressing known DOE environmental restoration needs. Analysis of a sample of 334 representative sites by the Office of Environmental Restoration has shown how many sites are amenable to in situ remediation: containment--243 sites; manipulation--244 sites; bioremediation--154 sites; and physical/chemical methods--236 sites. This needs assessment is focused on near-term restoration problems (FY93--FY99). Many other remediations will be required in the next century. The major focus of the ISR EP is on the long term development of permanent solutions to these problems. Current needs for interim actions to protect human health and the environment are also being addressed.

  1. Non-destructive in-situ method and apparatus for determining radionuclide depth in media

    DOE Patents [OSTI]

    Xu, X. George; Naessens, Edward P.

    2003-01-01

    A non-destructive method and apparatus which is based on in-situ gamma spectroscopy is used to determine the depth of radiological contamination in media such as concrete. An algorithm, Gamma Penetration Depth Unfolding Algorithm (GPDUA), uses point kernel techniques to predict the depth of contamination based on the results of uncollided peak information from the in-situ gamma spectroscopy. The invention is better, faster, safer, and/cheaper than the current practice in decontamination and decommissioning of facilities that are slow, rough and unsafe. The invention uses a priori knowledge of the contaminant source distribution. The applicable radiological contaminants of interest are any isotopes that emit two or more gamma rays per disintegration or isotopes that emit a single gamma ray but have gamma-emitting progeny in secular equilibrium with its parent (e.g., .sup.60 Co, .sup.235 U, and .sup.137 Cs to name a few). The predicted depths from the GPDUA algorithm using Monte Carlo N-Particle Transport Code (MCNP) simulations and laboratory experiments using .sup.60 Co have consistently produced predicted depths within 20% of the actual or known depth.

  2. FAMS DECOMMISSIONING END-STATE ALTERNATIVE EVALUATION

    SciTech Connect (OSTI)

    Grimm, B; Stephen Chostner, S; Brenda Green, B

    2006-05-25

    Nuclear Material Management (NMM) completed a comprehensive study at the request of the Department of Energy Savannah River Operations Office (DOE-SR) in 2004 (Reference 11.1). The study evaluated the feasibility of removal and/or mitigation of the Pu-238 source term in the F-Area Material Storage (FAMS) facility during on-going material storage operations. The study recommended different options to remove and/or mitigate the Pu-238 source term depending on its location within the facility. During April 2005, the Department of Energy (DOE) sent a letter of direction (LOD) to Washington Savannah River Company (WSRC) directing WSRC to implement a new program direction that would enable an accelerated shutdown and decommissioning of FAMS (Reference 11.2). Further direction in the LOD stated that effective December 1, 2006 the facility will be transitioned to begin deactivation and decommissioning (D&D) activities. To implement the LOD, Site D&D (SDD) and DOE agreed the planning end-state would be demolition of the FAMS structure to the building slab. SDD developed the D&D strategy, preliminary cost and schedule, and issued the deactivation project plan in December 2005 (Reference 11.3). Due to concerns and questions regarding the FAMS planning end-state and in support of the project's Critical Decision 1, an alternative study was performed to evaluate the various decommissioning end-states and the methods by which those end-states are achieved. This report documents the results of the alternative evaluation which was performed in a structured decision-making process as outlined in the E7 Manual, Procedure 2.15, ''Alternative Studies'' (Reference 11.4).

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

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

    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

  4. 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)

  5. Inherently safe in situ uranium recovery

    SciTech Connect (OSTI)

    Krumhansl, James L; Brady, Patrick V

    2014-04-29

    An in situ recovery of uranium operation involves circulating reactive fluids through an underground uranium deposit. These fluids contain chemicals that dissolve the uranium ore. Uranium is recovered from the fluids after they are pumped back to the surface. Chemicals used to accomplish this include complexing agents that are organic, readily degradable, and/or have a predictable lifetime in an aquifer. Efficiency is increased through development of organic agents targeted to complexing tetravalent uranium rather than hexavalent uranium. The operation provides for in situ immobilization of some oxy-anion pollutants under oxidizing conditions as well as reducing conditions. The operation also artificially reestablishes reducing conditions on the aquifer after uranium recovery is completed. With the ability to have the impacted aquifer reliably remediated, the uranium recovery operation can be considered inherently safe.

  6. Microsoft Word - In-Situ_Zno bh

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

    Nucleation and Growth of Electrodeposited ZnO Visualized by in-Situ X-ray Microscopy Electrodeposition (ED) of ZnO has been widely used to deposit transparent conducting films for optoelectronic applications. The film quality, and consequently the performance of the film, is highly dependent on both the nucleation and growth of ZnO. Current studies employ ex-situ experiments where the film is deposited, dried, and prepared for electron imaging. However, such techniques may introduce artefacts

  7. Priorities for In-situ Aerosol Measurements

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

    Priorities for In-situ Aerosol Measurements Parameters * Aerosol light absorption coefficient - spectral, including UV, vis, and IR - as f(RH), and at ambient RH * Phase function - or relevant integral properties (how many?) * Ice nuclei * Scattering vs. RH, for RH>90% * CCN, as f(S, D p ) * Size distribution * Chemical composition - for determining climate forcing, vs. radiative effect Calibration * Number concentration * Size and shape * Light absorption reference method Characterization *

  8. 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.

  9. 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.

  10. 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)

  11. In Situ Characterizations of New Battery Materials and the Studies...

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

    In Situ Characterizations of New Battery Materials and the Studies of High Energy Density Li-Air Batteries In Situ Characterizations of New Battery Materials and the Studies of ...

  12. Laboratory support for in situ gasification reaction kinetics...

    Office of Scientific and Technical Information (OSTI)

    CARBONACEOUS MATERIALS; CHALCOGENIDES; DECOMPOSITION; ENERGY SOURCES; FOSSIL FUELS; FUELS; IN-SITU PROCESSING; KINETICS; OXIDES; OXYGEN COMPOUNDS; PROCESSING; REACTION ...

  13. Gasification of chars produced under simulated in situ processing...

    Office of Scientific and Technical Information (OSTI)

    ELECTRON MICROSCOPY; CARBONACEOUS MATERIALS; DECOMPOSITION; ENERGY SOURCES; FOSSIL FUELS; FUELS; IN-SITU PROCESSING; KINETICS; MICROSCOPY; PROCESSING; REACTION KINETICS; ...

  14. Laboratory support for in situ gasification reaction kinetics...

    Office of Scientific and Technical Information (OSTI)

    COMPOUNDS; CARBONACEOUS MATERIALS; CHALCOGENIDES; DECOMPOSITION; ENERGY SOURCES; FOSSIL FUELS; FUELS; IN-SITU PROCESSING; KINETICS; OXIDES; OXYGEN COMPOUNDS; PROCESSING; REACTION ...

  15. Gasification of chars produced under simulated in situ processing...

    Office of Scientific and Technical Information (OSTI)

    COAL; CRYOGENIC FLUIDS; DECOMPOSITION; ELEMENTS; ENERGY SOURCES; FLUIDS; FOSSIL FUELS; FUELS; GASES; GASIFICATION; HYDROCARBONS; IN-SITU PROCESSING; KINETICS; MICROSCOPY; ...

  16. 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.

  17. 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.

  18. 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.

  19. Inherently safe in situ uranium recovery (Patent) | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    Inherently safe in situ uranium recovery Citation Details In-Document Search Title: Inherently safe in situ uranium recovery An in situ recovery of uranium operation involves...

  20. Calibrating feedwater flow nozzles in-situ

    SciTech Connect (OSTI)

    Caudill, M.; Diaz-Tous, I.; Murphy, S.; Leggett, M.; Crandall, C.

    1996-05-01

    This paper presents a new method for in-situ calibration of feedwater flow nozzles wherein feedwater flow is determined indirectly by performing a high accuracy heat balance around the highest-pressure feedwater heater. It is often difficult to reliably measure feedwater flow. Over the life of a power plant, the feedwater nozzle can accumulate deposits, erode, or suffer other damage that can render the original nozzle calibration inaccurate. Recalibration of installed feedwater flow nozzles is expensive and time consuming. Traditionally, the nozzle is cut out of the piping and sent to a laboratory for recalibration, which can be an especially difficult, expensive, and time-consuming task when involving high pressure feedwater lines. ENCOR-AMERICA, INC. has developed an accurate and cost-effective method of calibrating feedwater nozzles in-situ as previously reported at the 1994 EPRI Heat Rate Improvement Conference. In this method, feedwater flow and differential pressure across the nozzle are measured concurrently. The feedwater flow is determined indirectly by performing a heat balance around the highest-pressure feedwater heater. Extraction steam to the feedwater heater is measured by use of a high accuracy turbine flowmeter. The meters used have been calibrated at an independent laboratory with a primary or secondary device traceable to the NIST. In this paper, a new variation on the above method is reported. The new approach measures the heater drains and vent flows instead of the extraction steam flow. Test theory and instrumentation will be discussed. Results of in-situ feedwater nozzle calibration tests performed at two units owned by Tri-State Generation and Transmission Association will be presented.

  1. Spatially controlled, in situ synthesis of polymers

    DOE Patents [OSTI]

    Caneba, Gerard T.; Tirumala, Vijaya Raghavan; Mancini, Derrick C.; Wang, Hsien-Hau

    2005-03-22

    An in situ polymer microstructure formation method. The monomer mixture is polymerized in a solvent/precipitant through exposure to ionizing radiation in the absence any chemical mediators. If an exposure mask is employed to block out certain regions of the radiation cross section, then a patterned microstructure is formed. The polymerization mechanism is based on the so-called free-radical retrograde-precipitation polymerization process, in which polymerization occurs while the system is phase separating above the lower critical solution temperature. This method was extended to produce a crosslinked line grid-pattern of poly (N-isopropylacrylamide), which has been known to have thermoreversible properties.

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

    Broader source: Energy.gov [DOE]

    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...

  3. GAS TURBINE REHEAT USING IN SITU COMBUSTION

    SciTech Connect (OSTI)

    D.M. Bachovchin; T.E. Lippert; R.A. Newby P.G.A. Cizmas

    2004-05-17

    In situ reheat is an alternative to traditional gas turbine reheat design in which fuel is fed through airfoils rather than in a bulky discrete combustor separating HP and LP turbines. The goals are to achieve increased power output and/or efficiency without higher emissions. In this program the scientific basis for achieving burnout with low emissions has been explored. In Task 1, Blade Path Aerodynamics, design options were evaluated using CFD in terms of burnout, increase of power output, and possible hot streaking. It was concluded that Vane 1 injection in a conventional 4-stage turbine was preferred. Vane 2 injection after vane 1 injection was possible, but of marginal benefit. In Task 2, Combustion and Emissions, detailed chemical kinetics modeling, validated by Task 3, Sub-Scale Testing, experiments, resulted in the same conclusions, with the added conclusion that some increase in emissions was expected. In Task 4, Conceptual Design and Development Plan, Siemens Westinghouse power cycle analysis software was used to evaluate alternative in situ reheat design options. Only single stage reheat, via vane 1, was found to have merit, consistent with prior Tasks. Unifying the results of all the tasks, a conceptual design for single stage reheat utilizing 24 holes, 1.8 mm diameter, at the trailing edge of vane 1 is presented. A development plan is presented.

  4. Inherently safe in situ uranium recovery.

    SciTech Connect (OSTI)

    Krumhansl, James Lee; Beauheim, Richard Louis; Brady, Patrick Vane; Arnold, Bill Walter; Kanney, Joseph F.; McKenna, Sean Andrew

    2009-05-01

    Expansion of uranium mining in the United States is a concern to some environmental groups and sovereign Native American Nations. An approach which may alleviate some problems is to develop inherently safe in situ uranium recovery ('ISR') technologies. Current ISR technology relies on chemical extraction of trace levels of uranium from aquifers that, once mined, can still contain dissolved uranium and other trace metals that are a health concern. Existing ISR operations are few in number; however, high uranium prices are driving the industry to consider expanding operations nation-wide. Environmental concerns and enforcement of the new 30 ppb uranium drinking water standard may make opening new mining operations more difficult and costly. Here we propose a technological fix: the development of inherently safe in situ recovery (ISISR) methods. The four central features of an ISISR approach are: (1) New 'green' leachants that break down predictably in the subsurface, leaving uranium, and associated trace metals, in an immobile form; (2) Post-leachant uranium/metals-immobilizing washes that provide a backup decontamination process; (3) An optimized well-field design that increases uranium recovery efficiency and minimizes excursions of contaminated water; and (4) A combined hydrologic/geochemical protocol for designing low-cost post-extraction long-term monitoring. ISISR would bring larger amounts of uranium to the surface, leave fewer toxic metals in the aquifer, and cost less to monitor safely - thus providing a 'win-win-win' solution to all stakeholders.

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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)

  10. In-situ continuous water analyzing module

    DOE Patents [OSTI]

    Thompson, Cyril V.; Wise, Marcus B.

    1998-01-01

    An in-situ continuous liquid analyzing system for continuously analyzing volatile components contained in a water source comprises: a carrier gas supply, an extraction container and a mass spectrometer. The carrier gas supply continuously supplies the carrier gas to the extraction container and is mixed with a water sample that is continuously drawn into the extraction container. The carrier gas continuously extracts the volatile components out of the water sample. The water sample is returned to the water source after the volatile components are extracted from it. The extracted volatile components and the carrier gas are delivered continuously to the mass spectometer and the volatile components are continuously analyzed by the mass spectrometer.

  11. In-situ continuous water monitoring system

    DOE Patents [OSTI]

    Thompson, C.V.; Wise, M.B.

    1998-03-31

    An in-situ continuous liquid monitoring system for continuously analyzing volatile components contained in a water source comprises: a carrier gas supply, an extraction container and a mass spectrometer. The carrier gas supply continuously supplies the carrier gas to the extraction container and is mixed with a water sample that is continuously drawn into the extraction container by the flow of carrier gas into the liquid directing device. The carrier gas continuously extracts the volatile components out of the water sample. The water sample is returned to the water source after the volatile components are extracted from it. The extracted volatile components and the carrier gas are delivered continuously to the mass spectrometer and the volatile components are continuously analyzed by the mass spectrometer. 2 figs.

  12. In-situ continuous water monitoring system

    DOE Patents [OSTI]

    Thompson, Cyril V.; Wise, Marcus B.

    1998-01-01

    An in-situ continuous liquid monitoring system for continuously analyzing volatile components contained in a water source comprises: a carrier gas supply, an extraction container and a mass spectrometer. The carrier gas supply continuously supplies the carrier gas to the extraction container and is mixed with a water sample that is continuously drawn into the extraction container by the flow of carrier gas into the liquid directing device. The carrier gas continuously extracts the volatile components out of the water sample. The water sample is returned to the water source after the volatile components are extracted from it. The extracted volatile components and the carrier gas are delivered continuously to the mass spectrometer and the volatile components are continuously analyzed by the mass spectrometer.

  13. High resolution in situ ultrasonic corrosion monitor

    DOE Patents [OSTI]

    Grossman, Robert J.

    1985-01-01

    An ultrasonic corrosion monitor is provided which produces an in situ measurement of the amount of corrosion of a monitoring zone or zones of an elongate probe placed in the corrosive environment. A monitoring zone is preferably formed between the end of the probe and the junction of the zone with a lead-in portion of the probe. Ultrasonic pulses are applied to the probe and a determination made of the time interval between pulses reflected from the end of the probe and the junction referred to, both when the probe is uncorroded and while it is corroding. Corresponding electrical signals are produced and a value for the normalized transit time delay derived from these time interval measurements is used to calculate the amount of corrosion.

  14. High resolution in situ ultrasonic corrosion monitor

    DOE Patents [OSTI]

    Grossman, R.J.

    1984-01-10

    An ultrasonic corrosion monitor is provided which produces an in situ measurement of the amount of corrosion of a monitoring zone or zones of an elongate probe placed in the corrosive environment. A monitoring zone is preferably formed between the end of the probe and the junction of the zone with a lead-in portion of the probe. Ultrasonic pulses are applied to the probe and a determination made of the time interval between pulses reflected from the end of the probe and the junction referred to, both when the probe is uncorroded and while it is corroding. Corresponding electrical signals are produced and a value for the normalized transit time delay derived from these time interval measurements is used to calculate the amount of corrosion.

  15. 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.

  16. In-Situ Electron Microscopy of Electrical Energy Storage Materials |

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

    Department of Energy 1 DOE Hydrogen and Fuel Cells Program, and Vehicle Technologies Program Annual Merit Review and Peer Evaluation es095_unocic_2011_o.pdf (1.17 MB) More Documents & Publications In-Situ Electron Microscopy of Electrical Energy Storage Materials In-Situ Electron Microscopy of Electrical Energy Storage Materials In-situ characterization and diagnostics of mechanical degradation in electrodes

  17. 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.

  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. First in-situ images of void collapse in explosives

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

    First in-situ images of void collapse in explosives Los Alamos researchers and collaborators demonstrated a crucial diagnostic for studying how voids affect explosives under...

  20. Iran Thomas Auditorium, 8600 Materials For Energy: In Situ Synchrotron...

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

    For Energy: In Situ Synchrotron X-Ray Studies for Materials Design and Discovery Stephen K. Streiffer Deputy Associate Laboratory Director Physical Sciences and Engineering...

  1. Fractured rock stress-permeability relationships from in situ...

    Office of Scientific and Technical Information (OSTI)

    Fractured rock stress-permeability relationships from in situ data and effects of temperature and chemical-mechanical couplings Citation Details In-Document Search Title: Fractured...

  2. Gasification of chars produced under simulated in situ processing...

    Office of Scientific and Technical Information (OSTI)

    Country of Publication: United States Language: English Subject: 01 COAL, LIGNITE, AND PEAT; CHARS; GASIFICATION; COAL; PYROLYSIS; IN-SITU GASIFICATION; MATHEMATICAL MODELS; ...

  3. A Sealed Liquid Cell for In Situ Transmission Electron Microscopy...

    Office of Scientific and Technical Information (OSTI)

    A Sealed Liquid Cell for In Situ Transmission Electron Microscopy of Controlled Electrochemical Processes Citation Details In-Document Search Title: A Sealed Liquid Cell for In ...

  4. Optimal Scheduling of In-situ Analysis Workflows and Independent...

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

    Optimal Scheduling of In-situ Analysis Workflows and Independent Parallel IO Streams for Large-scale Scientific Simulations Event Sponsor: Argonne Leadership Computing Facility...

  5. Development of Numerical Simulation Capabilities for In Situ...

    Office of Scientific and Technical Information (OSTI)

    Numerical Simulation Capabilities for In Situ Heating of Oil Shale Hoda, Nazish ExxonMobil Upstream Research Company, Houston, TX, USA; Fang, Chen ExxonMobil Upstream Research...

  6. Thin-film lithiation structural transformations imaged in situ...

    Office of Scientific and Technical Information (OSTI)

    by liquid cell transmission electron microscopy. Citation Details In-Document Search Title: Thin-film lithiation structural transformations imaged in situ by liquid cell ...

  7. In situ observations and tuning of physical and chemical phenomena...

    Office of Scientific and Technical Information (OSTI)

    on the surfaces of strongly correlated oxides Citation Details In-Document Search Title: In situ observations and tuning of physical and chemical phenomena on the surfaces of ...

  8. Atomic Layer Deposition and in Situ Characterization of Ultraclean...

    Office of Scientific and Technical Information (OSTI)

    Hydroxide Citation Details In-Document Search Title: Atomic Layer Deposition and in Situ Characterization of Ultraclean Lithium Oxide and Lithium Hydroxide Authors: Kozen,...

  9. Development of Numerical Simulation Capabilities for In Situ...

    Office of Scientific and Technical Information (OSTI)

    Development of Numerical Simulation Capabilities for In Situ Heating of Oil Shale Citation Details In-Document Search Title: Development of Numerical Simulation Capabilities for In ...

  10. Application of In-situ Electrochemical Liquid Cells for Electrical...

    Office of Scientific and Technical Information (OSTI)

    Title: Application of In-situ Electrochemical Liquid Cells for Electrical Energy Storage Research Authors: Unocic, Raymond R 1 ; Sun, Xiao-Guang 1 ; Dudney, Nancy J 1 ; ...

  11. Documentation of INL's In Situ Oil Shale Retorting Water Usage...

    Office of Scientific and Technical Information (OSTI)

    Oil Shale Retorting Water Usage System Dynamics Model Citation Details In-Document Search Title: Documentation of INL's In Situ Oil Shale Retorting Water Usage System Dynamics ...

  12. Electrical Properties of a Polymeric Nanocomposite with In-Situ...

    Office of Scientific and Technical Information (OSTI)

    Synthesized Nanoparticles Citation Details In-Document Search Title: Electrical Properties of a Polymeric Nanocomposite with In-Situ Synthesized Nanoparticles Authors: Tuncer, ...

  13. In-Situ Catalytic Fast Pyrolysis Technology Pathway (Technical...

    Office of Scientific and Technical Information (OSTI)

    This technology pathway case investigates converting woody biomass using in-situ catalytic ... Sponsoring Org: USDOE Office of Energy Efficiency and Renewable Energy Biomass Program ...

  14. In situ transmission electron microscopy investigation of the...

    Office of Scientific and Technical Information (OSTI)

    In situ transmission electron microscopy investigation of the interfacial reaction between Ni and Al during rapid heating in a nanocalorimeter Grapes, Michael D. Department of...

  15. Site-Specific Synthesis and In Situ Immobilization of Fluorescent...

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

    Site-Specific Synthesis and In Situ Immobilization of Fluorescent Silver Nanoclusters on DNA Nanoscaffolds by Use of the Tollens Reaction Authors: Pal, S., Varghese, R., Deng, Z.,...

  16. Thermographic In-Situ Process Monitoring of the Electron Beam...

    Office of Scientific and Technical Information (OSTI)

    Thermographic In-Situ Process Monitoring of the Electron Beam Melting Technology used in Additive Manufacturing Dinwiddie, Ralph Barton ORNL ORNL; Dehoff, Ryan R ORNL ORNL;...

  17. In-Situ Catalytic Fast Pyrolysis Technology Pathway | Department...

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

    needs that should be pursued for this pathway to be competitive with petroleum-derived blendstocks have been identified. In-Situ Catalytic Fast Pyrolysis Technology Pathway...

  18. An Injectable Apatite PRB for In Situ Strontium-90 Immobilization...

    Office of Scientific and Technical Information (OSTI)

    Title: An Injectable Apatite PRB for In Situ Strontium-90 Immobilization. Abstract not provided. Authors: Moore, Robert C. ; Vermeul, Vince ; Szecsody, Jim ; Fritz, Brad ; ...

  19. In-situ characterization of plasma modified surfaces by vibrational...

    Office of Scientific and Technical Information (OSTI)

    of plasma modified surfaces by vibrational sum frequency generation spectroscopy. Citation Details In-Document Search Title: In-situ characterization of plasma modified surfaces ...

  20. 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)

  1. MAGNESIUM MONO POTASSIUM PHOSPHATE GROUT FOR P-REACTOR VESSEL IN-SITU DECOMISSIONING

    SciTech Connect (OSTI)

    Langton, C.; Stefanko, D.

    2011-01-05

    The objective of this report is to document laboratory testing of magnesium mono potassium phosphate grouts for P-Reactor vessel in-situ decommissioning. Magnesium mono potassium phosphate 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 (pH of about 12.4). A less alkaline material ({<=} 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. Information concerning access points into the P-Reactor vessel and amount of aluminum metal in the vessel is provided elsewhere. Fresh and cured properties were measured for: (1) commercially blended magnesium mono potassium phosphate packaged grouts, (2) commercially available binders blended with inert fillers at SRNL, (3) grouts prepared from technical grade MgO and KH{sub 2}PO{sub 4} and inert fillers (quartz sands, Class F fly ash), and (4) Ceramicrete{reg_sign} magnesium mono potassium phosphate-based grouts prepared at Argonne National Laboratory. Boric acid was evaluated as a set retarder in the magnesium mono potassium phosphate mixes.

  2. 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.

  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. In situ wettability determination improves formation evalution

    SciTech Connect (OSTI)

    Desbrandes, R. )

    1989-08-01

    Wettability is an important petrophysic parameter which affects capillary pressure, relative permeability, electric properties, water cut production, waterflood behavior, and enhanced recovery. This article describes in situ wettability laboratory experiments and field studies. A laboratory model has been built with a 12-ft long 4-in. clear plastic pipe. A 1 7/8-in. slotted plastic liner has been placed on one side. Ottawa sand F-95 has been packed in the annulus either nontreated, in its naturally water wet condition, or after a silane treatment to render it oil wet. Provided in the sand pack for measurement are 12 pressure pickups with an accurate Omega digital pressure gage. A typical pressure profile recorded during oil drive in a water saturated water wet sand pack is shown. The front was left to stabilize for 60 days. A pressure profile recorded during a water drive in an oil saturated oil wet sand pack is shown. The abrupt change from the water pressure gradient can be seen clearly for the water wet and the oil wet sand. It occurs exactly as expected. The measurements show that the change occurs in less than 4 in. which is the distance between two pressure pickups.

  5. Some implications of in situ uranium mining technology development

    SciTech Connect (OSTI)

    Cowan, C.E.; Parkhurst, M.A.; Cole, R.J.; Keller, D.; Mellinger, P.J.; Wallace, R.W.

    1980-09-01

    A technology assessment was initiated in March 1979 of the in-situ uranium mining technology. This report explores the impediments to development and deployment of this technology and evaluates the environmental impacts of a generic in-situ facility. The report is divided into the following sections: introduction, technology description, physical environment, institutional and socioeconomic environment, impact assessment, impediments, and conclusions. (DLC)

  6. Experience with in situ measurement of rock deformability

    SciTech Connect (OSTI)

    Bieniawski, Z.T.

    1981-07-01

    Although in situ tests have the advantage of involving a large volume or rock tested under the same environmental conditions as are prevailing in the rock mass, such tests are expensive and time consuming. In addition, there are a number of controversial questions pertinent to in situ tests.

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

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

    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. Statement of Intent No. 2 between DOE and the Nuclear Decommissioning Authority (236.93 KB)

  8. 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.

  9. 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.

  10. Technology demonstrations in the Decontamination and Decommissioning Focus Area

    SciTech Connect (OSTI)

    Bossart, S.J.

    1996-02-01

    This paper describes three large-scale demonstration projects sponsored jointly by the Decontamination and Decommissioning Focus Area (DDFA), and the three US Department of Energy (DOE) Operations Offices that successfully offered to deactivate or decommission (D&D) one of its facilities using a combination of innovative and commercial D&D technologies. The paper also includes discussions on recent technology demonstrations for an Advanced Worker Protection System, an Electrohydraulic Scabbling System, and a Pipe Explorer{trademark}. The references at the conclusion of this paper should be consulted for more detailed information about the large-scale demonstration projects and recent technology demonstrations sponsored by the DDFA.

  11. MENDING THE IN SITU MANIPULATION BARRIER

    SciTech Connect (OSTI)

    PETERSEN, S.W.

    2006-02-06

    In early 2004, the U.S. Department of Energy (DOE) Richland and Fluor Hanford requested technical assistance from the DOE Headquarters EM-23 Technical Assistance Program to provide a team of technical experts to develop recommendations for mending the In Situ Redox Manipulation (ISRM) Barrier in the 100-D Area of the Hanford Site in Washington State. To accommodate this request, EM-23 provided support to convene a group of technical experts from industry, a national laboratory, and a DOE site to participate in a 2 1/2-day workshop with the objective of identifying and recommending options to enhance the performance of the 100-D Area reactive barrier and of a planned extension to the northeast. This report provides written documentation of the team's findings and recommendations. In 1995, a plume of dissolved hexavalent chromium [Cr(VI)], which resulted from operation of the D/DR Reactors at the Hanford site, was discovered along the Columbia River shoreline and in the 100-D Area. Between 1999 and 2003, a reactive barrier using the In Situ Redox Manipulation (ISRM) technology, was installed a distance of 680 meters along the river to reduce the Cr(VI) in the groundwater. The ISRM technology creates a treatment zone within the aquifer by injection of sodium dithionite, a strong reducing agent that scavenges dissolved oxygen (DO) from the aquifer and reduces ferric iron [Fe(III)], related metals, and oxy-ions. The reduction of Fe(III) to ferrous [Fe(II)] iron provides the primary reduction capacity to reduce Cr(VI) to the +3 state, which is less mobile and less toxic. Bench-scale and field-scale treatability tests were initially conducted to demonstrate proof-of principle and to provide data for estimation of barrier longevity. These calculations estimated barrier longevity in excess of twenty years. However, several years after initial and secondary treatment, groundwater in a number of wells has been found to contain elevated chromium (Cr) concentrations, indicating

  12. Decommissioning Project of Bohunice A1 NPP

    SciTech Connect (OSTI)

    Stubna, M.; Pekar, A.; Moravek, J.; Spirko, M.

    2002-02-26

    1977 to terminate plant operation. The decision on the A1 plant decommissioning was issued in 1979.

  13. Site A/Plot M, Illinois, Decommissioned Reactor Site Fact Sheet

    Office of Legacy Management (LM)

    Site A/Plot M, Illinois, Decommissioned Reactor Site This fact sheet provides information about the Site A/Plot M, Illinois, Decommissioned Reactor Site. 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 Site A/Plot M, Illinois, Decommissioned Reactor Site Site Description and History The Site A/Plot M decommissioned reactor site is located in the Palos Forest Preserve in

  14. In-situ Characterization of Highly Reversible Phase Transformation by

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

    Synchrotron X-ray Laue Microdiffraction In-situ Characterization of Highly Reversible Phase Transformation by Synchrotron X-ray Laue Microdiffraction In-situ Characterization of Highly Reversible Phase Transformation by Synchrotron X-ray Laue Microdiffraction Print Monday, 23 May 2016 09:50 In situ measurement of the orientation matrices for the austenite and martensite phases of the alloy Cu25Au30Zn45 across the interface was performed by synchrotron x-ray Laue microdiffraction at the ALS.

  15. NOVEL IN-SITU METAL AND MINERAL EXTRACTION TECHNOLOGY

    SciTech Connect (OSTI)

    Glenn O'Gorman; Hans von Michaelis; Gregory J. Olson

    2004-09-22

    This white paper summarizes the state of art of in-situ leaching of metals and minerals, and describes a new technology concept employing improved fragmentation of ores underground in order to prepare the ore for more efficient in-situ leaching, combined with technology to continuously improve solution flow patterns through the ore during the leaching process. The process parameters and economic benefits of combining the new concept with chemical and biological leaching are described. A summary is provided of the next steps required to demonstrate the technology with the goal of enabling more widespread use of in-situ leaching.

  16. 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.

  17. 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.

  18. Annual report Rockwell International Hot Laboratory decommissioning GFY 1994

    SciTech Connect (OSTI)

    L. D. Felten

    1995-04-26

    OAK-B135 This document presents a summary of the activities conducted during GFY 1994 on decontamination and decommissioning of the Rockwell International Hot Laboratory. This is a multi-year program to decontaminate the RIHL facility to levels that allow release for unrestricted use.

  19. 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.

  20. 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.

  1. Technology, safety, and costs of decommissioning a reference large irradiator and reference sealed sources

    SciTech Connect (OSTI)

    Haffner, D.R.; Villelgas, A.J.

    1996-01-01

    This report contains the results of a study sponsored by the US Nuclear Regulatory Commission (NRC) to examine the decommissioning of large radioactive irradiators and their respective facilities, and a broad spectrum of sealed radioactive sources and their respective devices. Conceptual decommissioning activities are identified, and the technology, safety, and costs (in early 1993 dollars) associated with decommissioning the reference large irradiator and sealed source facilities are evaluated. The study provides bases and background data for possible future NRC rulemaking regarding decommissioning, for evaluation of the reasonableness of planned decommissioning actions, and for determining if adequate funds are reserved by the licensees for decommissioning of their large irradiator or sealed source facilities. Another purpose of this study is to provide background and information to assist licensees in planning and carrying out the decommissioning of their sealed radioactive sources and respective facilities.

  2. 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

  3. Atmospheric discharges from nuclear facilities during decommissioning: German experiences

    SciTech Connect (OSTI)

    Braun, H.; Goertz, R.; Weil, L.

    1997-08-01

    In Germany, a substantial amount of experience is available with planning, licensing and realization of decommissioning projects. In total, a number of 18 nuclear power plants including prototype facilities as well as 6 research reactors and 3 fuel cycle facilities have been shut down finally and are at different stages of decommissioning. Only recently the final {open_quotes}green field{close_quotes} stage of the Niederaichbach Nuclear Power Plant total dismantlement project has been achieved. From the regulatory point of view, a survey of the decommissioning experience in Germany is presented highlighting the aspects of production and retention of airborne radioactivity. Nuclear air cleaning technology, discharge limits prescribed in licences and actual discharges are presented. As compared to operation, the composition of the discharged radioactivity is different as well as the off-gas discharge rate. In practically all cases, there is no significant amount of short-lived radionuclides. The discussion further includes lessons learned, for example inadvertent discharges of radionuclides expected not to be in the plants inventory. It is demonstrated that, as for operation of nuclear power plants, the limits prescribed in the Ordinance on Radiological Protection can be met using existing air cleaning technology, Optimization of protection results in public exposures substantially below the limits. In the frame of the regulatory investigation programme a study has been conducted to assess the airborne radioactivity created during certain decommissioning activities like decontamination, segmentation and handling of contaminated or activated parts. The essential results of this study are presented, which are supposed to support planning for decommissioning, for LWRs, Co-60 and Cs-137 are expected to be the dominant radionuclides in airborne discharges. 18 refs., 2 figs., 1 tab.

  4. Analysis of In situ Observations of Cloud Microphysics from M...

    Office of Scientific and Technical Information (OSTI)

    Cloud Microphysics from M-PACE Final Report, DOE Grant Agreement No. DE-FG02-06ER64168 Citation Details In-Document Search Title: Analysis of In situ Observations of Cloud ...

  5. Documentation of INL's In Situ Oil Shale Retorting Water Usage...

    Office of Scientific and Technical Information (OSTI)

    Documentation of INL's In Situ Oil Shale Retorting Water Usage System Dynamics Model Earl D Mattson; Larry Hull 02 PETROLEUM water water A system dynamic model was construction to...

  6. Thermographic In-Situ Process Monitoring of the Electron Beam...

    Office of Scientific and Technical Information (OSTI)

    However, in-situ process monitoring is difficult due to metallization on inside surfaces caused by evaporation and condensation of metal from the melt pool. This work describes a ...

  7. Vehicle Technologies Office Merit Review 2014: Advanced in situ...

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

    battery materials. es059yang2014p.pdf (5.88 MB) More Documents & Publications Vehicle Technologies Office Merit Review 2015: Advanced In-Situ Diagnostic Techniques for Battery ...

  8. In situ Characterizations of New Battery Materials and the Studies...

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

    Characterization of New Cathode Materials using Synchrotron-based X-ray Techniques and the Studies of Li-Air Batteries In Situ Characterizations of New Battery Materials and the ...

  9. In situ quantification of genomic instability in breast cancer progression

    SciTech Connect (OSTI)

    Ortiz de Solorzano, Carlos; Chin, Koei; Gray, Joe W.; Lockett, Stephen J.

    2003-05-15

    Genomic instability is a hallmark of breast and other solid cancers. Presumably caused by critical telomere reduction, GI is responsible for providing the genetic diversity required in the multi-step progression of the disease. We have used multicolor fluorescence in situ hybridization and 3D image analysis to quantify genomic instability cell-by-cell in thick, intact tissue sections of normal breast epithelium, preneoplastic lesions (usual ductal hyperplasia), ductal carcinona is situ or invasive carcinoma of the breast. Our in situ-cell by cell-analysis of genomic instability shows an important increase of genomic instability in the transition from hyperplasia to in situ carcinoma, followed by a reduction of instability in invasive carcinoma. This pattern suggests that the transition from hyperplasia to in situ carcinoma corresponds to telomere crisis and invasive carcinoma is a consequence of telomerase reactivation afertelomere crisis.

  10. Documentation of INL's In Situ Oil Shale Retorting Water Usage...

    Office of Scientific and Technical Information (OSTI)

    A system dynamic model was construction to evaluate the water balance for in-situ oil ... and a remediation phase water to remove heat and solutes from the subsurface as well as ...

  11. In-Situ Mercury Remediation - Energy Innovation Portal

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

    In-Situ Mercury Remediation Brookhaven National Laboratory Contact BNL About This Technology Technology Marketing Summary In Situ Mercury Stabilization (ISMS) is a method that can remove toxic mercury from soil, sediment, sludge, and other industrial waste. Description ISMS includes a device and method for remediation of mercury contamination in which mercury is first concentrated by inserting rods of sulfur reagent into the waste. Mercury is drawn to specially designed treatment rods, which

  12. Inherently Safe In-Situ Uranium Recovery - Energy Innovation Portal

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

    Industrial Technologies Industrial Technologies Advanced Materials Advanced Materials Find More Like This Return to Search Inherently Safe In-Situ Uranium Recovery Sandia National Laboratories Contact SNL About This Technology Publications: PDF Document Publication Market Sheet (1,140 KB) Technology Marketing SummaryAs uranium mining continues to grow in the United States, so does the concerns over its environmental impact. An approach that may alleviate some of these problems may be in situ

  13. IN SITU FIELD TESTING OF PROCESSES

    SciTech Connect (OSTI)

    J.S.Y. YANG

    2004-11-08

    The purpose of this scientific analysis report is to update and document the data and subsequent analyses from ambient field-testing activities performed in underground drifts and surface-based boreholes through unsaturated zone (UZ) tuff rock units. In situ testing, monitoring, and associated laboratory studies are conducted to directly assess and evaluate the waste emplacement environment and the natural barriers to radionuclide transport at Yucca Mountain. This scientific analysis report supports and provides data to UZ flow and transport model reports, which in turn contribute to the Total System Performance Assessment (TSPA) of Yucca Mountain, an important document for the license application (LA). The objectives of ambient field-testing activities are described in Section 1.1. This report is the third revision (REV 03), which supercedes REV 02. The scientific analysis of data for inputs to model calibration and validation as documented in REV 02 were developed in accordance with the Technical Work Plan (TWP) ''Technical Work Plan for: Performance Assessment Unsaturated Zone'' (BSC 2004 [DIRS 167969]). This revision was developed in accordance with the ''Technical Work Plan for: Unsaturated Zone Flow Analysis and Model Report Integration'' (BSC 2004 [DIRS 169654], Section 1.2.4) for better integrated, consistent, transparent, traceable, and more complete documentation in this scientific analysis report and associated UZ flow and transport model reports. No additional testing or analyses were performed as part of this revision. The list of relevant acceptance criteria is provided by ''Technical Work Plan for: Unsaturated Zone Flow Analysis and Model Report Integration'' (BSC 2004 [DIRS 169654]), Table 3-1. Additional deviations from the TWP regarding the features, events, and processes (FEPs) list are discussed in Section 1.3. Documentation in this report includes descriptions of how, and under what conditions, the tests were conducted. The descriptions and

  14. Platforms and Methods for In Situ Characterization of Li-ion...

    Office of Scientific and Technical Information (OSTI)

    Platforms and Methods for In Situ Characterization of Li-ion Battery Materials. Citation Details In-Document Search Title: Platforms and Methods for In Situ Characterization of...

  15. Evaluation of In-Situ Tritium Transport Parameters for Type 316...

    Office of Environmental Management (EM)

    In-Situ Tritium Transport Parameters for Type 316 Stainless Steel during Irradiation Evaluation of In-Situ Tritium Transport Parameters for Type 316 Stainless Steel during ...

  16. 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.

  17. Frontiers of in situ electron microscopy

    SciTech Connect (OSTI)

    Zheng, Haimei; Zhu, Yimei; Meng, Shirley Ying

    2015-01-01

    In situ transmission electron microscopy (TEM) has become an increasingly important tool for materials characterization. It provides key information on the structural dynamics of a material during transformations and the correlation between structure and properties of materials. With the recent advances in instrumentation, including aberration corrected optics, sample environment control, the sample stage, and fast and sensitive data acquisition, in situ TEM characterization has become more and more powerful. In this article, a brief review of the current status and future opportunities of in situ TEM is included. It also provides an introduction to the six articles covered by in this issue of MRS Bulletin explore the frontiers of in situ electron microscopy, including liquid and gas environmental TEM, dynamic four-dimensional TEM, nanomechanics, ferroelectric domain switching studied by in situ TEM, and state-of-the-art atomic imaging of light elements (i.e., carbon atoms) and individual defects.

  18. Decontamination and decommissioning of the Mayaguez (Puerto Rico) facility

    SciTech Connect (OSTI)

    Jackson, P.K.; Freemerman, R.L.

    1989-11-01

    On February 6, 1987 the US Department of Energy (DOE) awarded the final phase of the decontamination and decommissioning of the nuclear and reactor facilities at the Center for Energy and Environmental Research (CEER), in Mayaguez, Puerto Rico. Bechtel National, Inc., was made the decontamination and decommissioning (D and D) contractor. The goal of the project was to enable DOE to proceed with release of the CEER facility for use by the University of Puerto Rico, who was the operator. This presentation describes that project and lesson learned during its progress. The CEER facility was established in 1957 as the Puerto Rico Nuclear Center, a part of the Atoms for Peace Program. It was a nuclear training and research institution with emphasis on the needs of Latin America. It originally consisted of a 1-megawatt Materials Testing Reactor (MTR), support facilities and research laboratories. After eleven years of operation the MTR was shutdown and defueled. A 2-megawatt TRIGA reactor was installed in 1972 and operated until 1976, when it woo was shutdown. Other radioactive facilities at the center included a 10-watt homogeneous L-77 training reactor, a natural uranium graphite-moderated subcritical assembly, a 200KV particle accelerator, and a 15,000 Ci Co-60 irradiation facility. Support facilities included radiochemistry laboratories, counting rooms and two hot cells. As the emphasis shifted to non-nuclear energy technology a name change resulted in the CEER designation, and plans were started for the decontamination and decommissioning effort.

  19. 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)

  20. U.S. Department of Energy 2012 Annual Inspection - Piqua, OH, Decommissioned Reactor Site

    Office of Legacy Management (LM)

    Piqua, OH, Decommissioned Reactor Site May 2012 Page 1 2012 Annual Inspection and Radiological Survey Results for the Piqua, Ohio, Decommissioned Reactor Site Summary The former Piqua Nuclear Power Facility (PNPF), a decommissioned nuclear power demonstration facility, was inspected on April 10, 2012. The site, located on the east bank of the Great Miami River in Piqua, Ohio, is in good physical condition. There is no requirement for a follow-up inspection. The former PNPF consists of a reactor

  1. 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.

  2. Decontamination and decommissioning of the Shippingport Atomic Power Station - a retrospective

    SciTech Connect (OSTI)

    Usher, J.M. ); Yannitell, D.M. )

    1992-01-01

    The 72 MW Shippingport Atomic Power Station (SAPS) first achieved criticality in December 1957 and was operated thereafter for almost 25 years. During the period October 1984 to December 1989, the U.S. Department of Energy (DOE) carried out the Shippingport Decommissioning Project, marking the world's first commercial sized nuclear power plant decommissioning. The experience gained from this project established the foundation for engineering, planning, and cost estimating for future decommissioning projects.

  3. Robot-Assisted Antegrade In-Situ Fenestrated Stent Grafting

    SciTech Connect (OSTI)

    Riga, Celia V. Bicknell, Colin D.; Wallace, Daniel; Hamady, Mohamad; Cheshire, Nicholas

    2009-05-15

    To determine the technical feasibility of a novel approach of in-situ fenestration of aortic stent grafts by using a remotely controlled robotic steerable catheter system in the porcine model. A 65-kg pig underwent robot-assisted bilateral antegrade in-situ renal fenestration of an abdominal aortic stent graft with subsequent successful deployment of a bare metal stent into the right renal artery. A 16-mm iliac extension covered stent served as the porcine aortic endograft. Under fluoroscopic guidance, the graft was punctured with a 20-G customized diathermy needle that was introduced and kept in place by the robotic arm. The needle was exchanged for a 4 x 20 mm cutting balloon before successful deployment of the renal stent. Robot-assisted antegrade in-situ fenestration is technically feasible in a large mammalian model. The robotic system enables precise manipulation, stable positioning, and minimum instrumentation of the aorta and its branches while minimizing radiation exposure.

  4. In-Situ Electrochemical Transmission Electron Microscopy for Battery Research

    SciTech Connect (OSTI)

    Mehdi, Beata L; Gu, Meng; Parent, Lucas; Xu, WU; Nasybulin, Eduard; Chen, Xilin; Unocic, Raymond R; Xu, Pinghong; Welch, David; Abellan, Patricia; Zhang, Ji-Guang; Liu, Jun; Wang, Chongmin; Arslan, Ilke; Evans, James E; Browning, Nigel

    2014-01-01

    The recent development of in-situ liquid stages for (scanning) transmission electron microscopes now makes it possible for us to study the details of electrochemical processes under operando conditions. As electrochemical processes are complex, care must be taken to calibrate the system before any in-situ/operando observations. In addition, as the electron beam can cause effects that look similar to electrochemical processes at the electrolyte/electrode interface, an understanding of the role of the electron beam in modifying the operando observations must also be understood. In this paper we describe the design, assembly, and operation of an in-situ electrochemical cell, paying particular attention to the method for controlling and quantifying the experimental parameters. The use of this system is then demonstrated for the lithiation/delithiation of silicon nanowires.

  5. Method for enhanced longevity of in situ microbial filter used for bioremediation

    DOE Patents [OSTI]

    Carman, M. Leslie; Taylor, Robert T.

    1999-01-01

    An improved method for in situ microbial filter bioremediation having increasingly operational longevity of an in situ microbial filter emplaced into an aquifer. A method for generating a microbial filter of sufficient catalytic density and thickness, which has increased replenishment interval, improved bacteria attachment and detachment characteristics and the endogenous stability under in situ conditions. A system for in situ field water remediation.

  6. System for enhanced longevity of in situ microbial filter used for bioremediation

    DOE Patents [OSTI]

    Carman, M. Leslie; Taylor, Robert T.

    2000-01-01

    An improved method for in situ microbial filter bioremediation having increasingly operational longevity of an in situ microbial filter emplaced into an aquifer. A method for generating a microbial filter of sufficient catalytic density and thickness, which has increased replenishment interval, improved bacteria attachment and detachment characteristics and the endogenous stability under in situ conditions. A system for in situ field water remediation.

  7. 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)

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. First in-situ images of void collapse in explosives

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

    First in-situ images of void collapse in explosives First in-situ images of void collapse in explosives Los Alamos researchers and collaborators demonstrated a crucial diagnostic for studying how voids affect explosives under shock loading. July 24, 2014 Dynamic x-ray image of void collapse in shocked explosive. The void (bright spot in the center) collapses as the shock wave passes through it. Dynamic x-ray image of void collapse in shocked explosive. The void (bright spot in the center)

  15. Electrochemical cell for in-situ x-ray characterization

    SciTech Connect (OSTI)

    Doughty, D.H.; Ingersoll, D.; Rodriguez, M.A.

    1998-08-04

    An electrochemical cell suitable for in-situ XRD analysis is presented. Qualitative information such as phase formation and phase stability can be easily monitored using the in-situ cell design. Quantitative information such as lattice parameters and kinetic behavior is also straightforward. Analysis of the LiMn&sub2;O&sub4; spinel using this cell design shows that the lattice undergoes two major structural shrinkages at approx. 4.0 V and approx. 4.07 V during charging. These shrinkages correlate well with the two electrochemical waves observed and indicate the likelihood of two separate redox processes which charging and discharging.

  16. Method of making in-situ whisker reinforced glass ceramic

    DOE Patents [OSTI]

    Brown, Jesse J.; Hirschfeld, Deidre A.; Lee, K. H.

    1993-02-16

    A heat processing procedure is used to create reinforcing whiskers of TiO.sub.2 in glass-ceramic materials in the LAS and MAS family. The heat processing procedure has particular application in creating TiO.sub.2 in-situ in a modified .beta.-eucryptite system.

  17. In-Situ Catalytic Fast Pyrolysis Technology Pathway

    Broader source: Energy.gov [DOE]

    This technology pathway case investigates converting woody biomass using in-situ catalytic fast pyrolysis followed by upgrading to gasoline-, diesel-, and jet-range hydrocarbon blendstocks. Technical barriers and key research needs that should be pursued for this pathway to be competitive with petroleum-derived blendstocks have been identified.

  18. In-situ remediation system for groundwater and soils

    DOE Patents [OSTI]

    Corey, J.C.; Kaback, D.S.; Looney, B.B.

    1991-01-01

    The present invention relates to a system for in-situ remediation of contaminated groundwater and soil. In particular the present invention relates to stabilizing toxic metals in groundwater and soil. The United States Government has rights in this invention pursuant to Contract No. DE-AC09-89SR18035 between the US Department of Energy and Westinghouse Savannah River Company.

  19. In-Situ Catalytic Fast Pyrolysis Technology Pathway

    SciTech Connect (OSTI)

    Biddy, M.; Dutta, A.; Jones, S.; Meyer, A.

    2013-03-01

    This technology pathway case investigates converting woody biomass using in-situ catalytic fast pyrolysis followed by upgrading to gasoline-, diesel-, and jet-range hydrocarbon blendstocks. Technical barriers and key research needs that should be pursued for this pathway to be competitive with petroleum-derived blendstocks have been identified.

  20. 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

  1. 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)

  2. 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)

  3. 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.

  4. 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

  5. Decommissioning Small Research and Training Reactors; Experience on Three Recent University Projects - 12455

    SciTech Connect (OSTI)

    Gilmore, Thomas; DeWitt, Corey; Miller, Dustin; Colborn, Kurt

    2012-07-01

    Decommissioning small reactors within the confines of an active University environment presents unique challenges. These range from the radiological protection of the nearby University population and grounds, to the logistical challenges of working in limited space without benefit of the established controlled, protected, and vital areas common to commercial facilities. These challenges, and others, are discussed in brief project histories of three recent (calendar year 2011) decommissioning activities at three University training and research reactors. These facilities include three separate Universities in three states. The work at each of the facilities addresses multiple phases of the decommissioning process, from initial characterization and pre-decommissioning waste removal, to core component removal and safe storage, through to complete structural dismantlement and site release. The results of the efforts at each University are presented, along with the challenges that were either anticipated or discovered during the decommissioning efforts, and results and lessons learned from each of the projects. (authors)

  6. Technology, safety and costs of decommissioning a reference boiling water reactor power station: Comparison of two decommissioning cost estimates developed for the same commercial nuclear reactor power station

    SciTech Connect (OSTI)

    Konzek, G.J.; Smith, R.I. )

    1990-12-01

    This study presents the results of a comparison of a previous decommissioning cost study by Pacific Northwest Laboratory (PNL) and a recent decommissioning cost study of TLG Engineering, Inc., for the same commercial nuclear power reactor station. The purpose of this comparative analysis on the same plant is to determine the reasons why subsequent estimates for similar plants by others were significantly higher in cost and external occupational radiation exposure (ORE) than the PNL study. The primary purpose of the original study by PNL (NUREG/CR-0672) was to provide information on the available technology, the safety considerations, and the probable costs and ORE for the decommissioning of a large boiling water reactor (BWR) power station at the end of its operating life. This information was intended for use as background data and bases in the modification of existing regulations and in the development of new regulations pertaining to decommissioning activities. It was also intended for use by utilities in planning for the decommissioning of their nuclear power stations. The TLG study, initiated in 1987 and completed in 1989, was for the same plant, Washington Public Supply System's Unit 2 (WNP-2), that PNL used as its reference plant in its 1980 decommissioning study. Areas of agreement and disagreement are identified, and reasons for the areas of disagreement are discussed. 31 refs., 3 figs., 22 tabs.

  7. In Situ Analytical Electron Microscopy for Probing Nanoscale Electrochemistry

    SciTech Connect (OSTI)

    Graetz J.; Meng, Y.S.; McGilvray, T.; Yang, M.-C.; Gostovic, D.; Wang, F.; Zeng, D.; Zhu, Y.

    2011-10-31

    Oxides and their tailored structures are at the heart of electrochemical energy storage technologies and advances in understanding and controlling the dynamic behaviors in the complex oxides, particularly at the interfaces, during electrochemical processes will catalyze creative design concepts for new materials with enhanced and better-understood properties. Such knowledge is not accessible without new analytical tools. New innovative experimental techniques are needed for understanding the chemistry and structure of the bulk and interfaces, more importantly how they change with electrochemical processes in situ. Analytical Transmission Electron Microscopy (TEM) is used extensively to study electrode materials ex situ and is one of the most powerful tools to obtain structural, morphological, and compositional information at nanometer scale by combining imaging, diffraction and spectroscopy, e.g., EDS (energy dispersive X-ray spectrometry) and Electron Energy Loss Spectrometry (EELS). Determining the composition/structure evolution upon electrochemical cycling at the bulk and interfaces can be addressed by new electron microscopy technique with which one can observe, at the nanometer scale and in situ, the dynamic phenomena in the electrode materials. In electrochemical systems, for instance in a lithium ion battery (LIB), materials operate under conditions that are far from equilibrium, so that the materials studied ex situ may not capture the processes that occur in situ in a working battery. In situ electrochemical operation in the ultra-high vacuum column of a TEM has been pursued by two major strategies. In one strategy, a 'nano-battery' can be fabricated from an all-solid-state thin film battery using a focused ion beam (FIB). The electrolyte is either polymer based or ceramic based without any liquid component. As shown in Fig. 1a, the interfaces between the active electrode material/electrolyte can be clearly observed with TEM imaging, in contrast to the

  8. 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)

  9. 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)

  10. 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.

  11. Resource book: Decommissioning of contaminated facilities at Hanford

    SciTech Connect (OSTI)

    Not Available

    1991-09-01

    In 1942 Hanford was commissioned as a site for the production of weapons-grade plutonium. The years since have seen the construction and operation of several generations of plutonium-producing reactors, plants for the chemical processing of irradiated fuel elements, plutonium and uranium processing and fabrication plants, and other facilities. There has also been a diversification of the Hanford site with the building of new laboratories, a fission product encapsulation plant, improved high-level waste management facilities, the Fast Flux test facility, commercial power reactors and commercial solid waste disposal facilities. Obsolescence and changing requirements will result in the deactivation or retirement of buildings, waste storage tanks, waste burial grounds and liquid waste disposal sites which have become contaminated with varying levels of radionuclides. This manual was established as a written repository of information pertinent to decommissioning planning and operations at Hanford. The Resource Book contains, in several volumes, descriptive information of the Hanford Site and general discussions of several classes of contaminated facilities found at Hanford. Supplementing these discussions are appendices containing data sheets on individual contaminated facilities and sites at Hanford. Twelve appendices are provided, corresponding to the twelve classes into which the contaminated facilities at Hanford have been organized. Within each appendix are individual data sheets containing administrative, geographical, physical, radiological, functional and decommissioning information on each facility within the class. 68 refs., 54 figs., 18 tabs.

  12. In situ remediation technologies for mercury-contaminated soil

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    He, Feng; Gao, Jie; Pierce, Eric; Strong, P. J.; Wang, Hailong; Liang, Liyuan

    2015-04-09

    A pollutant that poses significant risks to humans and the environment is mercury from anthropogenic activities. In soils, mercury remediation can be technically challenging and costly, depending on the subsurface mercury distribution, the types of mercury species, and the regulatory requirements. Our paper introduces the chemistry of mercury and its implications for in situ mercury remediation, which is followed by a detailed discussion of several in situ Hg remediation technologies in terms of applicability, cost, advantages, and disadvantages. The effect of Hg speciation on remediation performance, as well as Hg transformation during different remediation processes, was detailed. Thermal desorption, electrokinetic,more » and soil flushing/washing treatments are removal technologies that mobilize and capture insoluble Hg species, while containment, solidification/stabilization, and vitrification immobilize Hg by converting it to less soluble forms. We also discussed two emerging technologies, phytoremediation and nanotechnology, in this review.« less

  13. In situ remediation technologies for mercury-contaminated soil

    SciTech Connect (OSTI)

    He, Feng; Gao, Jie; Pierce, Eric; Strong, P. J.; Wang, Hailong; Liang, Liyuan

    2015-04-09

    A pollutant that poses significant risks to humans and the environment is mercury from anthropogenic activities. In soils, mercury remediation can be technically challenging and costly, depending on the subsurface mercury distribution, the types of mercury species, and the regulatory requirements. Our paper introduces the chemistry of mercury and its implications for in situ mercury remediation, which is followed by a detailed discussion of several in situ Hg remediation technologies in terms of applicability, cost, advantages, and disadvantages. The effect of Hg speciation on remediation performance, as well as Hg transformation during different remediation processes, was detailed. Thermal desorption, electrokinetic, and soil flushing/washing treatments are removal technologies that mobilize and capture insoluble Hg species, while containment, solidification/stabilization, and vitrification immobilize Hg by converting it to less soluble forms. We also discussed two emerging technologies, phytoremediation and nanotechnology, in this review.

  14. Methods and systems for in-situ electroplating of electrodes

    SciTech Connect (OSTI)

    Zappi, Guillermo Daniel; Zarnoch, Kenneth Paul; Huntley, Christian Andrew; Swalla, Dana Ray

    2015-06-02

    The present techniques provide electrochemical devices having enhanced electrodes with surfaces that facilitate operation, such as by formation of a porous nickel layer on an operative surface, particularly of the cathode. The porous metal layer increases the surface area of the electrode, which may result in increasing the efficiency of the electrochemical devices. The formation of the porous metal layer is performed in situ, that is, after the assembly of the electrodes into an electrochemical device. The in situ process offers a number of advantages, including the ability to protect the porous metal layer on the electrode surface from damage during assembly of the electrochemical device. The enhanced electrode and the method for its processing may be used in any number of electrochemical devices, and is particularly well suited for electrodes in an electrolyzer useful for splitting water into hydrogen and oxygen.

  15. In situ electrochemical dilatometry of carbide-derived carbons

    SciTech Connect (OSTI)

    Hantel, M M; Presser, Volker; Gogotsi, Yury

    2011-01-01

    The long life durability and extraordinary stability of supercapacitors are ascribed to the common concept that the charge storage is purely based on double-layer charging. Therefore the ideal supercapacitor electrode should be free of charge induced microscopic structural changes. However, recent in-situ investigations on different carbon materials for supercapacitor electrodes have shown that the charge and discharge is accompanied by dimensional changes of the electrode up to several percent. This work studies the influence of the pore size on the expansion behavior of carbon electrodes derived from titanium carbide-derived carbons with an average pore size between 5 and 8 Using tetraethylammonium tetrafluoroborate in acetonitrile, the swelling of the electrodes was measured by in situ dilatometry. The experiments revealed an increased expansion on the negatively charged electrode for pores below 6 , which could be described with pore swelling.

  16. Ignition technique for an in situ oil shale retort

    DOE Patents [OSTI]

    Cha, Chang Y.

    1983-01-01

    A generally flat combustion zone is formed across the entire horizontal cross-section of a fragmented permeable mass of formation particles formed in an in situ oil shale retort. The flat combustion zone is formed by either sequentially igniting regions of the surface of the fragmented permeable mass at successively lower elevations or by igniting the entire surface of the fragmented permeable mass and controlling the rate of advance of various portions of the combustion zone.

  17. In situ structural characterization of metal catalysts and materials using

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

    XAFS spectroscopy in combination with complementary techniques. | Stanford Synchrotron Radiation Lightsource In situ structural characterization of metal catalysts and materials using XAFS spectroscopy in combination with complementary techniques. Wednesday, October 17, 2012 - 1:00pm SSRL Bldg. 137, Room 322 The availability of third generation light sources has greatly enhanced the opportunities for invesigating chemical change in real time.1 This presentation describes studies carried out

  18. NREL: Photovoltaics Research - NREL Scientists Use In-Situ Characterization

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

    to Explain Perovskite Solar Cell Growth and Processing Scientists Use In-Situ Characterization to Explain Perovskite Solar Cell Growth and Processing June 6, 2016 NREL scientists have helped to establish research capabilities to address several important scientific and practical questions concerning perovskite solar cells. Perovskites are an important class of next-generation photovoltaic materials exhibiting impressive light absorption, high device efficiencies, and low-cost,

  19. Battery intercalation strategy: in-situ electrochemical liquid cell TEM

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

    study and high quality single layer nanosheets preparation | Stanford Synchrotron Radiation Lightsource Battery intercalation strategy: in-situ electrochemical liquid cell TEM study and high quality single layer nanosheets preparation Wednesday, September 7, 2016 - 3:00pm SLAC, Redtail Hawk Conference Room 108A Speaker: Zhiyuan Zeng, LBL Program Description Battery intercalation is the reversible inclusion or insertion of a molecule (or ion) into compounds with layered structures, which is

  20. LANSCE | Lujan Center | Highlights | In situ neutron diffraction study of

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

    CO clathrate hydrate In situ neutron diffraction study of CO clathrate hydrate The structure of a CO clathrate hydrate has been studied for the first time using high-P low-T neutron diffraction. Clathrate Rietveld analysis shows that lattice parameter a (SII cubic clathrate structure) increases with increasing temperature. CO molecules are positionally disordered and off-centered in both large and small cages. Each large cage is occupied by two CO molecules while each small cage is occupied

  1. In Situ Biological Uranium Remediation within a Highly Contaminated Aquifer

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

    In Situ Biological Uranium Remediation within a Highly Contaminated Aquifer Matthew Ginder-Vogel1, Wei-Min Wu1, Jack Carley2, Phillip Jardine2, Scott Fendorf1 and Craig Criddle1 1Stanford University, Stanford, CA 2Oak Ridge National Laboratory, Oak Ridge, TN Microbial Respiration Figure 1. Uranium(VI) reduction is driven by microbial respiration resulting in the precipitation of uraninite. Uranium contamination of ground and surface waters has been detected at numerous sites throughout the

  2. In-Situ Catalytic Fast Pyrolysis Technology Pathway

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

    In-Situ Catalytic Fast Pyrolysis Technology Pathway Mary Biddy and Abhijit Dutta National Renewable Energy Laboratory Susanne Jones and Aye Meyer Pacific Northwest National Laboratory NREL is a national laboratory of the U.S. Department of Energy, Office of Energy Efficiency & Renewable Energy, operated by the Alliance for Sustainable Energy, LLC, under contract DE-AC36-08GO28308. Pacific Northwest National Laboratory is operated by Battelle for the United States Department of Energy under

  3. 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

  4. Development of the integrated in situ lasagna process

    SciTech Connect (OSTI)

    Ho, S.; Athmer, C.; Sheridan, P.

    1995-10-01

    Contamination in deep, low permeability soils poses a significant technical challenge to in-situ remediation efforts. Poor accessibility to the contaminants and difficulty in uniform delivery of treatment reagents have rendered existing in-situ methods such as bioremediation, vapor extraction, and pump and treat rather ineffective when applied to low permeability soils present at many contaminated sites. Recently the use of electrokinetics as an in situ method for soil remediation has received increasing attention due to its unique applicability to low-permeability soils. Electrokinetics includes the transport of water (electroosmosis) as well as ions (electromigration) as a result of an applied electric field. For remedial applications, water is typically introduced into the soil at the anode to replenish the water flowing towards the cathode due to electroosmosis. The water flow is utilized to flush organic contaminants from the subsurface soil to the ground surface at the cathode region for further treatment or disposal. This report describes a treatment process under development termed the LASAGNA process which incorporates electrokinetics, along with the establishment of degradation zones, for pollutant removal.

  5. In Situ Remediation Integrated Program: FY 1994 program summary

    SciTech Connect (OSTI)

    1995-04-01

    The US Department of Energy (DOE) established the Office of Technology Development (EM-50) as an element of the Office of Environmental Management (EM) in November 1989. In an effort to focus resources and address priority needs, EM-50 introduced the concept of integrated programs (IPs) and integrated demonstrations (IDs). The In Situ Remediation Integrated Program (ISR IP) focuses research and development on the in-place treatment of contaminated environmental media, such as soil and groundwater, and the containment of contaminants to prevent the contaminants from spreading through the environment. Using in situ remediation technologies to clean up DOE sites minimizes adverse health effects on workers and the public by reducing contact exposure. The technologies also reduce cleanup costs by orders of magnitude. This report summarizes project work conducted in FY 1994 under the ISR IP in three major areas: treatment (bioremediation), treatment (physical/chemical), and containment technologies. Buried waste, contaminated soils and groundwater, and containerized waste are all candidates for in situ remediation. Contaminants include radioactive waste, volatile and nonvolatile organics, heavy metals, nitrates, and explosive materials.

  6. Regulation of in situ to invasive breast carcinoma transition

    SciTech Connect (OSTI)

    Polyak, Kornelia; Hu, Min; Yao, Jun; Carroll, Danielle K.; Weremowicz, Stanislawa; Chen, Haiyan; Carrasco, Daniel; Richardson, Andrea; Violette, Shelia; Gelman, Rebecca S.; Bissell, Mina J.; Schnitt, Stuart; Polyak, Kornelia

    2008-05-07

    The transition of ductal carcinoma in situ (DCIS) to invasive carcinoma is a key event in breast tumor progression that is poorly understood. Comparative molecular analysis of tumor epithelial cells from in situ and invasive tumors has failed to identify consistent tumor stage-specific differences. However, the myoepithelial cell layer, present only in DCIS, is a key distinguishing and diagnostic feature. To determine the contribution of non-epithelial cells to tumor progression, we analyzed the role of myoepithelial cells and fibroblasts in the progression of in situ carcinomas using a xenograft model of human DCIS. Progression to invasion was promoted by fibroblasts, but inhibited by normal myoepithelial cells. The invasive tumor cells from these progressed lesions formed DCIS rather than invasive cancers when re-injected into naive mice. Molecular profiles of myoepithelial and epithelial cells isolated from primary normal and cancerous human breast tissue samples corroborated findings obtained in the xenograft model. These results provide the proof of principle that breast tumor progression could occur in the absence of additional genetic alterations and that tumor growth and progression could be controlled by replacement of normal myoepithelial inhibitory signals.

  7. Regulation of In Situ to Invasive Breast CarcinomaTransition

    SciTech Connect (OSTI)

    Hu, Min; Carroll, Danielle K.; Weremowicz, Stanislawa; Chen,Haiyan; Carrasco, Daniel; Richardson, Andrea; Bissell, Mina; Violette,Shelia; Gelman, Rebecca S.; Schnitt, Stuart; Polyak, Kornelia

    2007-03-13

    The transition of ductal carcinoma in situ (DCIS) to invasive carcinoma is a key event in breast tumor progression that is poorly understood. Comparative molecular analysis of tumor epithelial cells from in situ and invasive tumors has failed to identify consistent tumor stage-specific differences. However, the myoepithelial cell layer, present only in DCIS, is a key distinguishing and diagnostic feature. To determine the contribution of non-epithelial cells to tumor progression, we analyzed the role of myoepithelial cells and fibroblasts in the progression of in situ carcinomas using a xenograft model of human DCIS. Progression to invasion was promoted by fibroblasts, but inhibited by normal myoepithelial cells. The invasive tumor cells from these progressed lesions formed DCIS rather than invasive cancers when re-injected into naive mice. Molecular profiles of myoepithelial and epithelial cells isolated from primary normal and cancerous human breast tissue samples corroborated findings obtained in the xenograft model. These results provide the proof of principle that breast tumor progression could occur in the absence of additional genetic alterations and that tumor growth and progression could be controlled by replacement of normal myoepithelial inhibitory signals.

  8. In Situ X-Ray Scattering Helps Optimize Printed Solar Cells

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

    In Situ X-Ray Scattering Helps Optimize Printed Solar Cells In Situ X-Ray Scattering Helps Optimize Printed Solar Cells Print Wednesday, 25 February 2015 00:00 Plastic solar cells...

  9. In-situ, Real-Time Monitoring of Mechanical and Chemical Structure...

    Office of Scientific and Technical Information (OSTI)

    Conference: In-situ, Real-Time Monitoring of Mechanical and Chemical Structure Changes in ... Citation Details In-Document Search Title: In-situ, Real-Time Monitoring of Mechanical and ...

  10. In meso in situ serial X-ray crystallography of soluble and membrane...

    Office of Scientific and Technical Information (OSTI)

    In meso in situ serial X-ray crystallography of soluble and membrane proteins Citation Details In-Document Search Title: In meso in situ serial X-ray crystallography of soluble and ...

  11. Li electrodeposition dynamics visualized in-situ via a TEM liquid...

    Office of Scientific and Technical Information (OSTI)

    visualized in-situ via a TEM liquid cell. Citation Details In-Document Search Title: Li electrodeposition dynamics visualized in-situ via a TEM liquid cell. Abstract not provided. ...

  12. Water Usage for In-Situ Oil Shale Retorting - A Systems Dynamics...

    Office of Scientific and Technical Information (OSTI)

    Water Usage for In-Situ Oil Shale Retorting - A Systems Dynamics Model Citation Details In-Document Search Title: Water Usage for In-Situ Oil Shale Retorting - A Systems Dynamics ...

  13. Water Usage for In-Situ Oil Shale Retorting - A Systems Dynamics...

    Office of Scientific and Technical Information (OSTI)

    Water Usage for In-Situ Oil Shale Retorting - A Systems Dynamics Model Citation Details In-Document Search Title: Water Usage for In-Situ Oil Shale Retorting - A Systems Dynamics Model ...

  14. Parallel In Situ Indexing for Data-intensive Computing

    SciTech Connect (OSTI)

    Kim, Jinoh; Abbasi, Hasan; Chacon, Luis; Docan, Ciprian; Klasky, Scott; Liu, Qing; Podhorszki, Norbert; Shoshani, Arie; Wu, Kesheng

    2011-09-09

    As computing power increases exponentially, vast amount of data is created by many scientific re- search activities. However, the bandwidth for storing the data to disks and reading the data from disks has been improving at a much slower pace. These two trends produce an ever-widening data access gap. Our work brings together two distinct technologies to address this data access issue: indexing and in situ processing. From decades of database research literature, we know that indexing is an effective way to address the data access issue, particularly for accessing relatively small fraction of data records. As data sets increase in sizes, more and more analysts need to use selective data access, which makes indexing an even more important for improving data access. The challenge is that most implementations of in- dexing technology are embedded in large database management systems (DBMS), but most scientific datasets are not managed by any DBMS. In this work, we choose to include indexes with the scientific data instead of requiring the data to be loaded into a DBMS. We use compressed bitmap indexes from the FastBit software which are known to be highly effective for query-intensive workloads common to scientific data analysis. To use the indexes, we need to build them first. The index building procedure needs to access the whole data set and may also require a significant amount of compute time. In this work, we adapt the in situ processing technology to generate the indexes, thus removing the need of read- ing data from disks and to build indexes in parallel. The in situ data processing system used is ADIOS, a middleware for high-performance I/O. Our experimental results show that the indexes can improve the data access time up to 200 times depending on the fraction of data selected, and using in situ data processing system can effectively reduce the time needed to create the indexes, up to 10 times with our in situ technique when using identical parallel settings.

  15. Method for enhanced longevity of in situ microbial filter used for bioremediation

    DOE Patents [OSTI]

    Carman, M.L.; Taylor, R.T.

    1999-03-30

    An improved method is disclosed for in situ microbial filter bioremediation having increasingly operational longevity of an in situ microbial filter emplaced into an aquifer. A method is presented for generating a microbial filter of sufficient catalytic density and thickness, which has increased replenishment interval, improved bacteria attachment and detachment characteristics and the endogenous stability under in situ conditions. A system is also disclosed for in situ field water remediation. 31 figs.

  16. The Crystallization of PEDOT:PSS Polymeric Electrodes Probed In Situ during

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

    Printing Crystallization of PEDOT:PSS Polymeric Electrodes Probed In Situ during Printing The Crystallization of PEDOT:PSS Polymeric Electrodes Probed In Situ during Printing Print Wednesday, 15 July 2015 00:00 Organic electronics have emerged into a highly interesting field of research with a great variety of applications. P. Müller-Buschbaum and co-workers demonstrate the importance of in situ investigations during the printing process of organic electronics. In situ grazing-incidence

  17. Two-level, horizontal free face mining system for in situ oil shale retorts

    SciTech Connect (OSTI)

    Cha, C.Y.; Ricketts, T.E.

    1986-09-16

    A method is described for forming an in-situ oil shale retort within a retort site in a subterranean formation containing oil shale, such an in-situ oil shale retort containing a fragmented permeable mass of formation particles containing oil shale formed within upper, lower and side boundaries of an in-situ oil shale retort site.

  18. 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.

  19. Compositions produced using an in situ heat treatment process

    DOE Patents [OSTI]

    Roes, Augustinus Wilhelmus Maria; Nair, Vijay; Munsterman, Erwin Hunh; Van Bergen, Petrus Franciscus; Van Den Berg, Franciscus Gondulfus Antonius

    2013-05-28

    Methods for treating a subsurface formation and compositions produced therefrom are described herein. At least one method for producing hydrocarbons from a subsurface formation includes providing heat to the subsurface formation using an in situ heat treatment process. One or more formation particles may be formed during heating of the subsurface formation. Fluid that includes hydrocarbons and the formation particles may be produced from the subsurface formation. The formation particles in the produced fluid may include cenospheres and have an average particle size of at least 0.5 micrometers.

  20. Compositions produced using an in situ heat treatment process

    DOE Patents [OSTI]

    Roes, Augustinus Wilhelmus Maria; Nair, Vijay; Munsterman, Erwin Henh; Van Bergen, Petrus Franciscus; Van Den Berg, Franciscus Gondulfus Antonius

    2009-10-20

    Systems, methods, and heaters for treating a subsurface formation are described herein. At least one method for producing hydrocarbons from a subsurface formation includes providing heat to the subsurface formation using an in situ heat treatment process. One or more formation particles may be formed during heating of the subsurface formation. Fluid that includes hydrocarbons and the formation particles may be produced from the subsurface formation. The formation particles in the produced fluid may include cenospheres and have an average particle size of at least 0.5 micrometers.

  1. Concurrent in situ ion irradiation transmission electron microscope

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Hattar, K.; Bufford, D. C.; Buller, D. L.

    2014-08-29

    An in situ ion irradiation transmission electron microscope has been developed and is operational at Sandia National Laboratories. This facility permits high spatial resolution, real time observation of electron transparent samples under ion irradiation, implantation, mechanical loading, corrosive environments, and combinations thereof. This includes the simultaneous implantation of low-energy gas ions (0.8–30 keV) during high-energy heavy ion irradiation (0.8–48 MeV). In addition, initial results in polycrystalline gold foils are provided to demonstrate the range of capabilities.

  2. Treatment of gas from an in situ conversion process

    DOE Patents [OSTI]

    Diaz, Zaida; Del Paggio, Alan Anthony; Nair, Vijay; Roes, Augustinus Wilhelmus Maria

    2011-12-06

    A method of producing methane is described. The method includes providing formation fluid from a subsurface in situ conversion process. The formation fluid is separated to produce a liquid stream and a first gas stream. The first gas stream includes olefins. At least the olefins in the first gas stream are contacted with a hydrogen source in the presence of one or more catalysts and steam to produce a second gas stream. The second gas stream is contacted with a hydrogen source in the presence of one or more additional catalysts to produce a third gas stream. The third gas stream includes methane.

  3. Method for in situ gasification of a subterranean coal bed

    DOE Patents [OSTI]

    Shuck, Lowell Z.

    1977-05-31

    The method of the present invention relates to providing controlled directional bores in subterranean earth formations, especially coal beds for facilitating in situ gasification operations. Boreholes penetrating the coal beds are interconnected by laser-drilled bores disposed in various arrays at selected angles to the major permeability direction in the coal bed. These laser-drilled bores are enlarged by fracturing prior to the gasification of the coal bed to facilitate the establishing of combustion zones of selected configurations in the coal bed for maximizing the efficiency of the gasification operation.

  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. 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.

  6. EM Renews Information-Sharing Agreement with United Kingdom's Nuclear Decommissioning Authority

    Broader source: Energy.gov [DOE]

    PHOENIX – EM’s top official this week renewed an agreement between DOE and the U.K.’s Nuclear Decommissioning Authority (NDA) that expands the scope of their information sharing.

  7. 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.

  8. Savannah River Site Removes Dome, Opening Reactor for Recovery Act Decommissioning

    Broader source: Energy.gov [DOE]

    American Recovery and Reinvestment Act workers achieved a significant milestone in the decommissioning of a Cold War reactor at the Savannah River Site this month after they safely removed its...

  9. 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...

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

    Broader source: Energy.gov [DOE]

    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.

  11. In Situ Remediation Integrated Program. In situ physical/chemical treatment technologies for remediation of contaminated sites: Applicability, developing status, and research needs

    SciTech Connect (OSTI)

    Siegrist, R.L.; Gates, D.D.; West, O.R.; Liang, L.; Donaldson, T.L.; Webb, O.F.; Corder, S.L.; Dickerson, K.S.

    1994-06-01

    The U.S. Department of Energy (DOE) In Situ Remediation Integrated Program (ISR IP) was established in June 1991 to facilitate the development and implementation of in situ remediation technologies for environmental restoration within the DOE complex. Within the ISR IP, four subareas of research have been identified: (1) in situ containment, (2) in situ physical/chemical treatment (ISPCT), (3) in situ bioremediation, and (4) subsurface manipulation/electrokinetics. Although set out as individual focus areas, these four are interrelated, and successful developments in one will often necessitate successful developments in another. In situ remediation technologies are increasingly being sought for environmental restoration due to the potential advantages that in situ technologies can offer as opposed to more traditional ex situ technologies. These advantages include limited site disruption, lower cost, reduced worker exposure, and treatment at depth under structures. While in situ remediation technologies can offer great advantages, many technology gaps exist in their application. This document presents an overview of ISPCT technologies and describes their applicability to DOE-complex needs, their development status, and relevant ongoing research. It also highlights research needs that the ISR IP should consider when making funding decisions.

  12. 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

  13. 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.

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

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

    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

  15. Methane ignition catalyzed by in situ generated palladium nanoparticles

    SciTech Connect (OSTI)

    Shimizu, T.; Abid, A.D.; Poskrebyshev, G.; Wang, H. [Department of Aerospace and Mechanical Engineering, University of Southern California, Los Angeles, CA 90089 (United States); Nabity, J.; Engel, J.; Yu, J. [TDA Research, Inc., 12345 W. 52nd Ave, Wheat Ridge, CO 80033 (United States); Wickham, D. [Reaction Systems, LLC, 19039 E. Plaza Drive, Suite 290, Parker, CO 80134 (United States); Van Devener, B.; Anderson, S.L. [Department of Chemistry, University of Utah, Salt Lake City, UT 84112 (United States); Williams, S. [Air Force Research Laboratory, Mail Stop RZA, 1950 Fifth Street, WPAFB, OH 45433 (United States)

    2010-03-15

    Catalytic ignition of methane over the surfaces of freely-suspended and in situ generated palladium nanoparticles was investigated experimentally and numerically. The experiments were conducted in a laminar flow reactor. The palladium precursor was a compound (Pd(THD){sub 2}, THD: 2,2,6,6-tetramethyl-3,5-heptanedione) dissolved in toluene and injected into the flow reactor as a fine aerosol, along with a methane-oxygen-nitrogen mixture. For experimental conditions chosen in this study, non-catalytic, homogeneous ignition was observed at a furnace temperature of {proportional_to}1123 K, whereas ignition of the same mixture with the precursor was found to be {proportional_to}973 K. In situ production of Pd/PdO nanoparticles was confirmed by scanning mobility, transmission electron microscopy and X-ray photoelectron spectroscopy analyses of particles collected at the reactor exit. The catalyst particle size distribution was log-normal. Depending on the precursor loading, the median diameter ranged from 10 to 30 nm. The mechanism behind catalytic ignition was examined using a combined gas-phase and gas-surface reaction model. Simulation results match the experiments closely and suggest that palladium nanocatalyst significantly shortens the ignition delay times of methane-air mixtures over a wide range of conditions. (author)

  16. Use of tensiometer for in situ measurement of nitrate leaching

    SciTech Connect (OSTI)

    Li, K.; Reddy, M.R.

    1999-07-01

    In order to monitor nitrate leaching from non-point source pollution, this study used tensiometers to measure in situ nitrate concentration and soil-moisture potential. Instead of filling the tensiometers with pure water, the study filled the tensiometers with nitrate ionic strength adjuster (ISA, 1 M (NH{sub 4}){sub 2}SO{sub 4}). After the installation of the tensiometers at various depths along soil profiles, a portable pressure transducer was used to measure the soil moisture potential, and a nitrate electrode attached to an ion analyzer was used to measure the nitrate concentration in situ. The measurement was continuous and non-destructive. To test this method in the laboratory, eight bottles filled with pure sand were treated with known nitrate solutions, and a tensiometer was placed in each bottle. Measurements were taken every day for 30 days. Laboratory test showed a linear relationship between the known nitrate concentration and the tensiometer readings (R{sup 2} = 0.9990). Then a field test was conducted in a watermelon field with green manure mulch. Field data indicated a potential of nitrate leaching below the soil depth of 100 cm when crop uptake of nutrients was low.

  17. In-situ calibration of feedwater flow nozzles

    SciTech Connect (OSTI)

    Murphy, S.; Mateos, M.; Crandall, C.

    1995-06-01

    Feedwater flow is often the most difficult power-plant parameter to measure reliably. Over the life of a power plant, the feedwater nozzle can accumulate deposits, erode, or suffer other damage that can render the original nozzle calibration inaccurate. Recalibration of installed feedwater flow nozzles is expensive and time consuming. Traditionally, the nozzle is cut out of the thick wall feedwater piping and send to a laboratory for recalibration--an especially difficult, expensive, and time-consuming task in high-pressure lines. ENCOR-AMERICA, Inc. has developed an accurate and cost-effective method of in-situ calibration of feedwater nozzles by measuring (concurrently) feedwater flow and differential pressure across the nozzle at various flow rates. During the tests, feedwater flow is determined indirectly. Extraction steam to the highest pressure feedwater heater is measured by use of a high-accuracy turbine flowmeter. This meter is calibrated in an independent laboratory with a primary or secondary device traceable to the National Institute of Standards and Technology (NIST). The feedwater flow is then calculated by performing a heat balance around the feedwater heater. This paper discusses test theory and instrumentation. Also presented are test results of an in-situ feedwater nozzle calibration test performed at Montana Power Company`s Colstrip Unit 2 Power Plant.

  18. TEM in situ lithiation of tin nanoneedles for battery applications

    SciTech Connect (OSTI)

    Janish, Matthew T.; Mackay, David T.; Liu, Yang; Jungjohann, Katherine L.; Carter, C. Barry; Norton, M. Grant

    2015-08-12

    Materials such as tin (Sn) and silicon that alloy with lithium (Li) have attracted renewed interest as anode materials in Li-ion batteries. Although their superior capacity to graphite and other intercalation materials has been known for decades, their mechanical instability due to extreme volume changes during cycling has traditionally limited their commercial viability. This limitation is changing as processes emerge that produce nanostructured electrodes. The nanostructures can accommodate the repeated expansion and contraction as Li is inserted and removed without failing mechanically. Recently, one such nano-manufacturing process, which is capable of depositing coatings of Sn “nanoneedles” at low temperature with no template and at industrial scales, has been described. The present work is concerned with observations of the lithiation and delithiation behavior of these Sn nanoneedles during in situ experiments in the transmission electron microscope, along with a brief review of how in situ TEM experiments have been used to study the lithiation of Li-alloying materials. Individual needles are successfully lithiated and delithiated in solid-state half-cells against a Li-metal counter-electrode. Furthermore the microstructural evolution of the needles is discussed, including the transformation of one needle from single-crystal Sn to polycrystalline Sn–Li and back to single-crystal Sn.

  19. TEM in situ lithiation of tin nanoneedles for battery applications

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Janish, Matthew T.; Mackay, David T.; Liu, Yang; Jungjohann, Katherine L.; Carter, C. Barry; Norton, M. Grant

    2015-08-12

    Materials such as tin (Sn) and silicon that alloy with lithium (Li) have attracted renewed interest as anode materials in Li-ion batteries. Although their superior capacity to graphite and other intercalation materials has been known for decades, their mechanical instability due to extreme volume changes during cycling has traditionally limited their commercial viability. This limitation is changing as processes emerge that produce nanostructured electrodes. The nanostructures can accommodate the repeated expansion and contraction as Li is inserted and removed without failing mechanically. Recently, one such nano-manufacturing process, which is capable of depositing coatings of Sn “nanoneedles” at low temperature withmore » no template and at industrial scales, has been described. The present work is concerned with observations of the lithiation and delithiation behavior of these Sn nanoneedles during in situ experiments in the transmission electron microscope, along with a brief review of how in situ TEM experiments have been used to study the lithiation of Li-alloying materials. Individual needles are successfully lithiated and delithiated in solid-state half-cells against a Li-metal counter-electrode. Furthermore the microstructural evolution of the needles is discussed, including the transformation of one needle from single-crystal Sn to polycrystalline Sn–Li and back to single-crystal Sn.« less

  20. Chemically assisted in situ recovery of oil shale

    SciTech Connect (OSTI)

    Ramierz, W.F.

    1993-12-31

    The purpose of the research project was to investigate the feasibility of the chemically assisted in situ retort method for recovering shale oil from Colorado oil shale. The chemically assisted in situ procedure uses hydrogen chloride (HCl), steam (H{sub 2}O), and carbon dioxide (CO{sub 2}) at moderate pressure to recovery shale oil from Colorado oil shale at temperatures substantially lower than those required for the thermal decomposition of kerogen. The process had been previously examined under static, reaction-equilibrium conditions, and had been shown to achieve significant shale oil recoveries from powdered oil shale. The purpose of this research project was to determine if these results were applicable to a dynamic experiment, and achieve penetration into and recovery of shale oil from solid oil shale. Much was learned about how to perform these experiments. Corrosion, chemical stability, and temperature stability problems were discovered and overcome. Engineering and design problems were discovered and overcome. High recovery (90% of estimated Fischer Assay) was observed in one experiment. Significant recovery (30% of estimated Fischer Assay) was also observed in another experiment. Minor amounts of freed organics were observed in two more experiments. Penetration and breakthrough of solid cores was observed in six experiments.

  1. 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)

  2. 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

  3. Waste Management Strategy for Dismantling Waste to Reduce Costs for Power Plant Decommissioning - 13543

    SciTech Connect (OSTI)

    Larsson, Arne; Lidar, Per; Bergh, Niklas; Hedin, Gunnar

    2013-07-01

    Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named 'ndcon' to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid interruptions. Bottle

  4. 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.

  5. Time resolved electron microscopy for in situ experiments

    SciTech Connect (OSTI)

    Campbell, Geoffrey H. McKeown, Joseph T.; Santala, Melissa K.

    2014-12-15

    Transmission electron microscopy has functioned for decades as a platform for in situ observation of materials and processes with high spatial resolution. Yet, the dynamics often remain elusive, as they unfold too fast to discern at these small spatial scales under traditional imaging conditions. Simply shortening the exposure time in hopes of capturing the action has limitations, as the number of electrons will eventually be reduced to the point where noise overtakes the signal in the image. Pulsed electron sources with high instantaneous current have successfully shortened exposure times (thus increasing the temporal resolution) by about six orders of magnitude over conventional sources while providing the necessary signal-to-noise ratio for dynamic imaging. We describe here the development of this new class of microscope and the principles of its operation, with examples of its application to problems in materials science.

  6. In situ formation of phosphate barriers in soil

    DOE Patents [OSTI]

    Moore, Robert C.

    2002-01-01

    Reactive barriers and methods for making reactive barriers in situ in soil for sequestering soil ontaminants including actinides and heavy metals. The barrier includes phosphate, and techniques are disclosed for forming specifically apatite barriers. The method includes injecting dilute reagents into soil in proximity to a contamination plume or source such as a waste drum to achieve complete or partial encapsulation of the waste. Controlled temperature and pH facilitates rapid formation of apatite, for example, where dilute aqueous calcium chloride and dilute aqueous sodium phosphate are the selected reagents. Mixing of reagents to form precipitate is mediated and enhanced through movement of reagents in soil as a result of phenomena including capillary action, movement of groundwater, soil washing and reagent injection pressure.

  7. In-Situ Contained And Of Volatile Soil Contaminants

    DOE Patents [OSTI]

    Varvel, Mark Darrell

    2005-12-27

    The invention relates to a novel approach to containing and removing toxic waste from a subsurface environment. More specifically the present invention relates to a system for containing and removing volatile toxic chemicals from a subsurface environment using differences in surface and subsurface pressures. The present embodiment generally comprises a deep well, a horizontal tube, at least one injection well, at least one extraction well and a means for containing the waste within the waste zone (in-situ barrier). During operation the deep well air at the bottom of well (which is at a high pressure relative to the land surface as well as relative to the air in the contaminated soil) flows upward through the deep well (or deep well tube). This stream of deep well air is directed into the horizontal tube, down through the injection tube(s) (injection well(s)) and into the contaminate plume where it enhances volatization and/or removal of the contaminants.

  8. In-Situ Containment and Extraction of Volatile Soil Contaminants

    DOE Patents [OSTI]

    Varvel, Mark Darrell

    2005-12-27

    The invention relates to a novel approach to containing and removing toxic waste from a subsurface environment. More specifically the present invention relates to a system for containing and removing volatile toxic chemicals from a subsurface environment using differences in surface and subsurface pressures. The present embodiment generally comprises a deep well, a horizontal tube, at least one injection well, at least one extraction well and a means for containing the waste within the waste zone (in-situ barrier). During operation the deep well air at the bottom of well (which is at a high pressure relative to the land surface as well as relative to the air in the contaminated soil) flows upward through the deep well (or deep well tube). This stream of deep well air is directed into the horizontal tube, down through the injection tube(s) (injection well(s)) and into the contaminate plume where it enhances volatization and/or removal of the contaminants.

  9. In situ conversion process utilizing a closed loop heating system

    DOE Patents [OSTI]

    Sandberg, Chester Ledlie; Fowler, Thomas David; Vinegar, Harold J.; Schoeber, Willen Jan Antoon Henri

    2009-08-18

    An in situ conversion system for producing hydrocarbons from a subsurface formation is described. The system includes a plurality of u-shaped wellbores in the formation. Piping is positioned in at least two of the u-shaped wellbores. A fluid circulation system is coupled to the piping. The fluid circulation system is configured to circulate hot heat transfer fluid through at least a portion of the piping to form at least one heated portion of the formation. An electrical power supply is configured to provide electrical current to at least a portion of the piping located below an overburden in the formation to resistively heat at least a portion of the piping. Heat transfers from the piping to the formation.

  10. In-situ characterization technique for screening contaminated soils

    SciTech Connect (OSTI)

    Jaselskis, E.J.; Anderson, M.S.; D`Silva, A.P.; Baldwin, D.P.; Zamzow, D.S.

    1995-07-01

    An innovative field sampling system for screening contaminated soils has been developed using laser ablation coupled with inductively coupled plasma-atomic emission spectrometry (LA-ICP-AES) technology. This sampling approach provides in-situ real-time analysis of trace inorganic elements and is conducted through a mobile testing facility that consists of an instrumentation vehicle called the Mobile Demonstration Laboratory for Environmental Screening Technologies (MDLEST) and an attached trailer called the Robotic Sampling Accessory (RSA). The RSA provides automated sampling capabilities through an attached three-degree-of-freedom robot that is equipped with a surface-sampling probe. The MDLEST-RSA was successfully tested at a Department of Energy (DOE) site in Fernald, Ohio, during the fall of 1992. This paper provides a description of the analysis technique, the MDLEST and RSA, and results of the field demonstration. In addition, benefits, limitations, and future plans are also discussed.

  11. Apparatus for in situ cleaning of carbon contaminated surfaces

    DOE Patents [OSTI]

    Klebanoff, Leonard E.; Grunow, Philip; Graham, Jr., Samuel

    2004-08-10

    Activated gaseous species generated adjacent a carbon contaminated surface affords in-situ cleaning. A device for removing carbon contamination from a surface of the substrate includes (a) a housing defining a vacuum chamber in which the substrate is located; (b) a source of gaseous species; and (c) a source of electrons that are emitted to activate the gaseous species into activated gaseous species. The source of electrons preferably includes (i) a filament made of a material that generates thermionic electron emissions; (ii) a source of energy that is connected to the filament; and (iii) an electrode to which the emitted electrons are attracted. The device is particularly suited for photolithography systems with optic surfaces, e.g., mirrors, that are otherwise inaccessible unless the system is dismantled.

  12. In-situ groundwater remediation by selective colloid mobilization

    DOE Patents [OSTI]

    Seaman, J.C.; Bertch, P.M.

    1998-12-08

    An in-situ groundwater remediation pump and treat technique is described which is effective for reclamation of aquifers that have been contaminated with a mixed, metal-containing waste, and which promotes selective mobilization of metal oxide colloids with a cationic surfactant, preferably a quaternary alkylammonium surfactant, without significantly reducing formation permeability that often accompanies large-scale colloid dispersion, thus increasing the efficiency of the remediation effort by enhancing the capture of strongly sorbing contaminants associated with the oxide phases. The resulting suspension can be separated from the bulk solution with controlled pH adjustments to destabilize the oxide colloids, and a clear supernatant which results that can be recycled through the injection well without further waste treatment. 3 figs.

  13. Design considerations for heavy oil in situ pilots

    SciTech Connect (OSTI)

    Peachey, B.R.; Nodwell, J.A.

    1982-01-01

    Although the primary objectives of heavy oil in situ pilots are reservoir oriented in terms of production rate and recovery efficiency, considerable development of surface engineering technology is a necessary aspect of pilot operations. Esso's basic design philosophy is to use state-of-the-art technology with onsite operator interaction to sequentially develop improvements in surface equipment and processes without comprising reservoir based research objectives. This work reviews Esso's operating experience and technical developments in pilot design at Cold Lake, Alta. The considerations which led to the design basis for the Cold Lake commercial project are examined in the areas of well layout, steam and production distribution system design, oil and water separation, and produced water treatment.

  14. Gas Turbine Reheat Using In-Situ Combustion

    SciTech Connect (OSTI)

    T.E. Lippert; D.M. Bachovchin

    2004-03-31

    Siemens Westinghouse Power Corporation (SWPC) is developing in-situ reheat (fuel injection via airfoil injection) as a means for increasing cycle efficiency and power output, with possibly reduced emissions. In addition to kinetic modeling and experimental task, CFD modeling (by Texas A&M) of airfoil injection and its effects on blade aerodynamics and turbine performance. This report discusses validation of the model against single-vane combustion test data from Siemens Westinghouse, and parametric studies of injection reheat in a modern turbine. The best location for injection is at the trailing edge of the inlet guide vane. Combustion is incomplete at trailing edges of subsequent vanes. Recommendations for further development are presented.

  15. Method for in-situ calibration of electrophoretic analysis systems

    DOE Patents [OSTI]

    Liu, Changsheng; Zhao, Hequan

    2005-05-08

    An electrophoretic system having a plurality of separation lanes is provided with an automatic calibration feature in which each lane is separately calibrated. For each lane, the calibration coefficients map a spectrum of received channel intensities onto values reflective of the relative likelihood of each of a plurality of dyes being present. Individual peaks, reflective of the influence of a single dye, are isolated from among the various sets of detected light intensity spectra, and these can be used to both detect the number of dye components present, and also to establish exemplary vectors for the calibration coefficients which may then be clustered and further processed to arrive at a calibration matrix for the system. The system of the present invention thus permits one to use different dye sets to tag DNA nucleotides in samples which migrate in separate lanes, and also allows for in-situ calibration with new, previously unused dye sets.

  16. NMR apparatus for in situ analysis of fuel cells

    DOE Patents [OSTI]

    Gerald, II, Rex E; Rathke, Jerome W

    2012-11-13

    The subject apparatus is a fuel cell toroid cavity detector for in situ analysis of samples through the use of nuclear magnetic resonance. The toroid cavity detector comprises a gas-tight housing forming a toroid cavity where the housing is exposed to an externally applied magnetic field B.sub.0 and contains fuel cell component samples to be analyzed. An NMR spectrometer is electrically coupled and applies a radiofrequency excitation signal pulse to the detector to produce a radiofrequency magnetic field B.sub.1 in the samples and in the toroid cavity. Embedded coils modulate the static external magnetic field to provide a means for spatial selection of the recorded NMR signals.

  17. In-Situ Data for Microphysical Retrievals: TC4, 2007

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Mace, Gerald

    2016-04-01

    This data set is derived from measurements collected in situ by the NASA DC8 during the Tropical Cloud Climate Composition Coupling Experiment (TC4) that was conducted during July and August, 2007 (Toon et al., 2010). During this experiment the DC8 was based in San Jose, Costa Rica and sampled clouds in the maritime region of the Eastern Pacific and adjoining continental areas. The primary objective of the DC8 during this deployment was to sample ice clouds associated with convective activity. While the vast majority of the data are from ice-phase clouds that have recent association with convection, other types of clouds such as boundary layer clouds and active convection were also sampled and are represented in this data set. The derived data set, as compiled in this delivery, includes approximately 15,000 5-second averaged measurements collected by the NASA DC8.

  18. In-situ groundwater remediation by selective colloid mobilization

    DOE Patents [OSTI]

    Seaman, John C. (New Ellenton, SC); Bertch, Paul M. (Aiken, SC)

    1998-01-01

    An in-situ groundwater remediation pump and treat technique effective for reclamation of aquifers that have been contaminated with a mixed, metal-containing waste, which promotes selective mobilization of metal oxide colloids with a cationic surfactant, preferably a quaternary alkylammonium surfactant, without significantly reducing formation permeability that often accompanies large-scale colloid dispersion, thus increasing the efficiency of the remediation effort by enhancing the capture of strongly sorbing contaminants associated with the oxide phases. The resulting suspension can be separated from the bulk solution with controlled pH adjustments to destabilize the oxide colloids, and a clear supernatant which results that can be recycled through the injection well without further waste treatment.

  19. In-Situ Catalytic Fast Pyrolysis Technology Pathway

    SciTech Connect (OSTI)

    Biddy, Mary J.; Dutta, Abhijit; Jones, Susanne B.; Meyer, Pimphan A.

    2013-03-31

    In support of the Bioenergy Technologies Office, the National Renewable Energy Laboratory (NREL) and the Pacific Northwest National Laboratory (PNNL) are undertaking studies of biomass conversion technologies to hydrocarbon fuels to identify barriers and target research toward reducing conversion costs. Process designs and preliminary economic estimates for each of these pathway cases were developed using rigorous modeling tools (Aspen Plus and Chemcad). These analyses incorporated the best information available at the time of development, including data from recent pilot and bench-scale demonstrations, collaborative industrial and academic partners, and published literature and patents. This pathway case investigates converting woody biomass using in-situ catalytic fast pyrolysis followed by upgrading to gasoline, diesel, and jet range blendstocks. Technical barriers and key research needs that should be pursued for this pathway to be competitive with petroleum-derived blendstocks have been identified.

  20. Used to Calibrate Thermistors on In Situ Permeable Flow Sensors

    Energy Science and Technology Software Center (OSTI)

    1996-12-01

    The software package is comprised of three programs which together are used to calibrate thermistors in an In Situ Permable Flow Sensor. TBATH controls a temperature controlled bath/circulator. The code monitors the temperature of a set of previously calibrated thermistors located in a tank through which the fluid from the bath is circulated. After the temperature has reached and maintained thermal equilibrium for a specified period of time, the bath/circulator is instructed by the programmore » to change the temperature set point to the next specified temperature. An arbitrary number of temperature calibration points can be specified allowing thermistors to be calibrated on a continuous basis without human intervention. CALIB is used to merge two data files that are collected during a temperature calibration run. During calibration of the thermistors on an In Situ Permeable Flow Sensor, the known temperatures in the temperaure controlled tank are recorded in one computer file in one format while the electrical resistance of the thermistors being calibrated is collected in a different file with a different format. This software reads in the two files and writes out a third file with all of the data in it that is required to calculate the calibration coefficients of the thermistors on the probe. POLYFIT is used to calculate the calibration coefficients which permit the temperature of a thermistor to ba calculated from its electrical resistance. During calibration of a thermistor, the electrical resistance of the thermistor is measured at four or more known temperatures and the data sent to this software. The program calculates the coefficients of a fourth order polynomial relating the inverse of the absolute temperature to the natural log of the electrical resistance. Once these coefficients are known, the polynomial can be evaluated with any measured electrical resistance to calculate the equivalent temperature.« less

  1. In situ destruction of contaminants via hydrous pyrolysis/

    SciTech Connect (OSTI)

    Aines, R D; Carrigan, C; Chiarappa, M; Eaker, C; Hudson, B; Knauss, K; Leif, R; Newmark, R L; Richards, J; Sciarotta, T; Tompson, A; Weidner, R.

    1998-12-01

    A field test of hydrous pyrolysis/oxidation (HPO) was conducted during the summer of 1997, during a commercial application of thermal remediation (Dynamic Underground Stripping (DUS)) at the Visalia Pole Yard (a super-fund site) in southern California. At Visalia, Southern California Edison Co. is applying the DUS thermal remediation method to clean up a large (4.3 acre) site contaminated with pole-treating compounds. This is a full-scale cleanup, during which initial extraction of contaminants is augmented by combined steam/air injection in order to enhance the destruction of residual contaminants by HPO. Laboratory results indicate that the contaminants at Visaha react at similar rates to TCE, which has been the focus of extensive laboratory work (Knauss et al., 1998a-c). Field experimental results from this application yield valuable information (1) confirming the destruction of contaminants in soil and groundwater by HPO, (2) validating the predictive models used to design HP0 steam injection systems, (3) demonstrating that accurate field measurements of the critical fluid parameters can be obtained using existing monitoring wells and (4) obtaining a reasonable prediction of the cost and effectiveness of HPO, working at a commercial scale and with commercial partners. The goal of our additional study and demonstration in conjunction with Edison has been to obtain early proof of hydrous pyrolysis/oxidation in the field, and validate our predictive models and monitoring strategies. This demonstration provides valuable economic and practicability data obtained on a commercial scale, with more detailed field validation than is commonly available on a commercially-conducted cleanup. The results of LLNL s field experiments constrain the destruction rates throughout the site, and enable site management to make accurate estimates of total in situ destruction based on the recovered carbon. As of October, 1998, over 900,000 lb of contaminant have been removed from the

  2. Portsmouth RI/FS Report for the Process Buildings and Complex Facilities Decontamination and Decommissioning Evaluation Project

    Office of Energy Efficiency and Renewable Energy (EERE)

    This remedial investigation/feasibility study (RI/FS), the Remedial Investigation and Feasibility Study Report for the Process Buildings and Complex Facilities Decontamination and Decommissioning...

  3. 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

  4. 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

  5. Action Memorandum for Decommissioning of TAN-607 Hot Shop Area

    SciTech Connect (OSTI)

    M. A. Pinzel

    2007-05-01

    The Department of Energy is documenting the selection of an alternative for the TAN-607 Hot Shop Area using a Comprehensive Environmental Response, Compensation, and Liability Act non-time-critical removal action (NTCRA). The scope of the removal action is limited to TAN-607 Hot Shop Area. An engineering evaluation/cost analysis (EE/CA) has assisted the Department of Energy Idaho Operations Office in identifuomg the most effective method for performing the decommissioning of this structure whose mission has ended. TAN-607 Hot Shop Area is located at Test Area North Technical Support Facility within the Idaho National Laboratory Site. The selected alternative consists of demolishing the TAN-607 aboveground structures and components, removing belowground noninert components (e.g. wood products), and removing the radiologically contaminated debris that does not meet remedial action objectives (RAOs), as defined in the Record of Decision Amendment for the V-Tanks and Explanation of Significant Differences for the PM-2A Tanks at Test Area North, Operable Unit 1-10.

  6. 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.

  7. 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.

  8. Project Overview: Successful Field-Scale In Situ Thermal NAPL Remediation |

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

    Department of Energy Project Overview: Successful Field-Scale In Situ Thermal NAPL Remediation Project Overview: Successful Field-Scale In Situ Thermal NAPL Remediation Paper presented at the Third International Conference on Oxidation and Reduction Technologies for Soil and Groundwater. October 2004, San Diego, California. Michael Butherus, David S. Ingle, Randall Juhlin, Joseph Daniel Project Overview: Successful Field-Scale In Situ Thermal NAPL Remediation (305.82 KB) More Documents &

  9. Successful Field-Scale In Situ Thermal NAPL Remediation at the Young -

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

    Rainey STAR Center | Department of Energy Successful Field-Scale In Situ Thermal NAPL Remediation at the Young - Rainey STAR Center Successful Field-Scale In Situ Thermal NAPL Remediation at the Young - Rainey STAR Center Proceedings of the Fourth International Conference on Remediation of Chlorinated and Recalcitrant Compounds. May 2004, Monterey, California. Randall Juhlin, Michael Butherus, Joseph Daniel, David S. Ingle, Dr. Gorm Heron, Dr. Bruce McGee Successful Field-Scale In Situ

  10. The Windscale Advanced Gas Cooled Reactor (WAGR) Decommissioning Project A Close Out Report for WAGR Decommissioning Campaigns 1 to 10 - 12474

    SciTech Connect (OSTI)

    Halliwell, Chris

    2012-07-01

    The reactor core of the Windscale Advanced Gas-Cooled Reactor (WAGR) has been dismantled as part of an ongoing decommissioning project. The WAGR operated until 1981 as a development reactor for the British Commercial Advanced Gas cooled Reactor (CAGR) power programme. Decommissioning began in 1982 with the removal of fuel from the reactor core which was completed in 1983. Subsequently, a significant amount of engineering work was carried out, including removal of equipment external to the reactor and initial manual dismantling operations at the top of the reactor, in preparation for the removal of the reactor core itself. Modification of the facility structure and construction of the waste packaging plant served to provide a waste route for the reactor components. The reactor core was dismantled on a 'top-down' basis in a series of 'campaigns' related to discrete reactor components. This report describes the facility, the modifications undertaken to facilitate its decommissioning and the strategies employed to recognise the successful decommissioning of the reactor. Early decommissioning tasks at the top of the reactor were undertaken manually but the main of the decommissioning tasks were carried remotely, with deployment systems comprising of little more than crane like devices, intelligently interfaced into the existing structure. The tooling deployed from the 3 tonne capacity (3te) hoist consisted either purely mechanical devices or those being electrically controlled from a 'push-button' panel positioned at the operator control stations, there was no degree of autonomy in the 3te hoist or any of the tools deployed from it. Whilst the ATC was able to provide some tele-robotic capabilities these were very limited and required a good degree of driver input which due to the operating philosophy at WAGR was not utilised. The WAGR box proved a successful waste package, adaptable through the use of waste box furniture specific to the waste-forms generated throughout

  11. POLICY ANALYSIS OF PRODUCED WATER ISSUES ASSOCIATED WITH IN-SITU...

    Office of Scientific and Technical Information (OSTI)

    Other: POLICY ANALYSIS OF PRODUCED WATER ISSUES ASSOCIATED WITH IN-SITU THERMAL TECHNOLOGIES Citation Details In-Document Search Title: POLICY ANALYSIS OF PRODUCED WATER ISSUES ...

  12. Bioenergy Technologies Office R&D Pathways: In-Situ Catalytic Fast Pyrolysis

    Broader source: Energy.gov [DOE]

    The in-situ catalytic fast pyrolysis pathway involves rapidly heating biomass with a catalyst to create bio-oils, which can be used to produce biofuel blendstocks.

  13. In Situ SAXS Studies of Structural Relaxation of an Ordered Block...

    Office of Scientific and Technical Information (OSTI)

    Flow Citation Details In-Document Search Title: In Situ SAXS Studies of Structural Relaxation of an Ordered Block Copolymer Melt Following Cessation of Uniaxial Extensional Flow ...

  14. In-Situ Liquid (ec)-TEM Cell Shows Dendrite Formation, Providing...

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

    Providing New Insights into Lithium Batteries (Top) In-situ liquid electrochemical ... changing our view of dendrite formation and the safety of lithium-ion batteries. ...

  15. Seeing Gold Nanoparticles Self-Assemble with in situ Liquid Transmissi...

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

    Seeing Gold Nanoparticles Self-Assemble with in situ Liquid Transmission Electron Microscopy December 15, 2014 Tweet EmailPrint Scientific Achievement The self-assembly of gold...

  16. Bioenergy Technologies Office R&D Pathways: In-Situ Catalytic...

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

    phase separates into aqueous and organic phases * The organic fraction of bio-oil ... of the upgrading step chemistry and optimum catalystoperating conditions for in-situ. ...

  17. Gas cell for in situ soft X-ray transmission-absorption spectroscopy...

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

    cell for in situ soft X-ray transmission-absorption spectroscopy of materials Previous ... Abstract: A simple gas cell design, constructed primarily from commercially available ...

  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

  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. DEACTIVATION AND DECOMMISSIONING (D AND D) TECHNOLOGY INTEGRATION

    SciTech Connect (OSTI)

    M.A. Ebadian, Ph.D.

    1999-01-01

    As part of the ongoing task of making Deactivation and Decommissioning (D&D) operations more efficient, this subtask has addressed the need to integrate existing characterization technologies with decontamination technologies in order to provide real-time data on the progress of contamination removal. Specifically, technologies associated with concrete decontamination and/or removal have been examined with the goal of integrating existing technologies and commercializing the resulting hybrid. The Department of Energy (DOE) has estimated that 23 million cubic meters of concrete will require disposition as 1200 buildings undergo the D&D process. All concrete removal to be performed will also necessitate extensive use of characterization techniques. The in-process characterization presents the most potential for improvement and cost-savings as compared to other types. Current methods for in-process characterization usually require cessation of work to allow for radiation surveys to assess the rate of decontamination. Combining together decontamination and characterization technologies would allow for in-process evaluation of decontamination efforts. Since the present methods do not use in-process evaluations for the progress of decontamination, they may allow for ''overremoval'' of materials (removal of contaminated along with non-contaminated materials). Overremoval increases the volume of waste and therefore the costs associated with disposal. Integrating technologies would facilitate the removal of only contaminated concrete and reduce the total volume of radioactive waste, which would be disposed of. This would eventually ensure better productivity and time savings. This project presents a general procedure to integrate the above-mentioned technologies in the form of the Technology Integration Module (TIM) along with combination lists of commercially available decontamination and characterization technologies. The scope of the project has also been expanded by FIU

  2. 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.

  3. 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

  4. Monitoring pavement response and performance using in-situ instrumentation

    SciTech Connect (OSTI)

    Chen, D.H.; Bilyeu, J.; Hugo, F.

    1999-07-01

    The purpose of this paper is to present the effectiveness of in-situ instrumentation on diagnosing the pavement layer conditions under full-scale accelerated traffic loading. The test section is an in-service pavement (US281) in Jacksboro, Texas. Multi-Depth Deflectometers (MDDs) are used to measure both permanent deformations and transient deflections, caused by accelerated traffic loading and Falling Weight Deflectometers (MDDs) are used to measure both permanent deformations and transient deflections, caused by accelerated traffic loading and Falling Weight Deflectometer (FWD) tests. Four different FWD loads of 25, 40, 52, and 67 kN were applied in close proximity to the MDDs at various traffic loading intervals to determine pavement conditions. It was found that the majority of rutting occurred in the newly recycled asphalt mix. The aged ({gt}40 years) underlying base and subgrade layers contributed less than 30% to overall rutting. Only the top recycled Asphalt layer underwent notable deterioration due to traffic loading. Up to 1.5 million axle repetitions, the test pad responded to FWD load almost linearly, not only over the whole pavement system but also within individual layers. However, under higher FWD loads, the percentage of total deflection contributed by the subgrade increased.

  5. Characterization of in situ oil shale retorts prior to ignition

    DOE Patents [OSTI]

    Turner, Thomas F.; Moore, Dennis F.

    1984-01-01

    Method and system for characterizing a vertical modified in situ oil shale retort prior to ignition of the retort. The retort is formed by mining a void at the bottom of a proposed retort in an oil shale deposit. The deposit is then sequentially blasted into the void to form a plurality of layers of rubble. A plurality of units each including a tracer gas cannister are installed at the upper level of each rubble layer prior to blasting to form the next layer. Each of the units includes a receiver that is responsive to a coded electromagnetic (EM) signal to release gas from the associated cannister into the rubble. Coded EM signals are transmitted to the receivers to selectively release gas from the cannisters. The released gas flows through the retort to an outlet line connected to the floor of the retort. The time of arrival of the gas at a detector unit in the outlet line relative to the time of release of gas from the cannisters is monitored. This information enables the retort to be characterized prior to ignition.

  6. Applications of Strand-Specific in situ Hybridization

    SciTech Connect (OSTI)

    Goodwin, E.H.; Meyne, J.; Bailey, S.M.; Quigley, D.; Smith, L.; Tennyson, R.

    1997-01-01

    This is the final report of a three-year, Laboratory-Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). Fluorescence in situ hybridization (FISH) is used to determine the location of specific DNA sequences on chromosomes. It is an effective tool in genomic mapping and is finding increasing use in medical diagnosis. A ''strand-specific'' version of FISH has been developed in the Life Sciences Division of LANL. The new procedure, named CO-FISH, reveals not only location but also the 5'-to-3'direction of a target sequence, such as the sense strand of a gene. This project was designed to investigate applications of the new technique. Strand-specific FISH was found to be useful and informative for genomic mapping of repetitive DNA sequences. The method provide a valuable new tool for investigating the mechanisms of aneuploidy inducing agents and the cytogenetic phenomena called lateral asymmetry. Finally, using strand-specific FISH, the authors were able to detect certain types of chromosome aberrations (isochromosomes, inversions and Robertsonian translocations) that can be difficult to observe with standard techniques.

  7. In situ recycling of contaminated soil uses bioremediation

    SciTech Connect (OSTI)

    Shevlin, P.J.; Reel, D.A.

    1996-04-01

    OxyChem Pipeline Operations, primarily an ethylene and propylene products mover, has determined that substantial savings can be realized by adopting a bioremediation maintenance and recycling approach to hydrocarbon-contaminated soil. By this method, the soil can be recycled in situ, or in containers. To implement the soil-recycling program, OxyChem elected to use a soil remediator and natural absorbent product, Oil Snapper. This field maintenance material, based on an Enhanced Urea Technology, provides a diet to stimulate the growth of hydrocarbon-eating microbes. It works well either with indigenous soil microbes or with commercial microbes. The product is carried in field vehicles, which makes it immediately available when leaks or spills are discovered. Procedure for clean-up is to apply product and mix it into affected soil. Thus the contaminant is contained, preventing further migration; the contaminant is dispersed throughout the product, making it more accessible to the microbes; nutrients are immediately available to the microbes; and the material contributes aeration and moisture-retention properties.

  8. Method for in-situ cleaning of carbon contaminated surfaces

    DOE Patents [OSTI]

    Klebanoff, Leonard E.; Grunow, Philip; Graham, Jr., Samuel

    2006-12-12

    Activated gaseous species generated adjacent a carbon contaminated surface affords in-situ cleaning. A device for removing carbon contamination from a surface of the substrate includes (a) a housing defining a vacuum chamber in which the substrate is located; (b) a source of gaseous species; and (c) a source of electrons that are emitted to activate the gaseous species into activated gaseous species. The source of electrons preferably includes (i) a filament made of a material that generates thermionic electron emissions; (ii) a source of energy that is connected to the filament; and (iii) an electrode to which the emitted electrons are attracted. The device is particularly suited for photolithography systems with optic surfaces, e.g., mirrors, that are otherwise inaccessible unless the system is dismantled. A method of removing carbon contaminants from a substrate surface that is housed within a vacuum chamber is also disclosed. The method employs activated gaseous species that react with the carbon contaminants to form carbon containing gaseous byproducts.

  9. In-Situ Microbial Conversion of Sequestered Greenhouse Gases

    SciTech Connect (OSTI)

    Scott, A R; Mukhopadhyay, M; Balin, D F

    2012-09-06

    The objectives of the project are to use microbiological in situ bioconversion technology to convert sequestered or naturally-occurring greenhouse gases, including carbon dioxide and carbon monoxide, into methane and other useful organic compounds. The key factors affecting coal bioconversion identified in this research include (1) coal properties, (2) thermal maturation and coalification process, (3) microbial population dynamics, (4) hydrodynamics (5) reservoir conditions, and (6) the methodology of getting the nutrients into the coal seams. While nearly all cultures produced methane, we were unable to confirm sustained methane production from the enrichments. We believe that the methane generation may have been derived from readily metabolized organic matter in the coal samples and/or biosoluble organic material in the coal formation water. This raises the intriguing possibility that pretreatment of the coal in the subsurface to bioactivate the coal prior to the injection of microbes and nutrients might be possible. We determined that it would be more cost effective to inject nutrients into coal seams to stimulate indigenous microbes in the coal seams, than to grow microbes in fermentation vats and transport them to the well site. If the coal bioconversion process can be developed on a larger scale, then the cost to generate methane could be less than $1 per Mcf

  10. In situ repair of a failed compression fitting

    DOE Patents [OSTI]

    Wolbert, R.R.; Jandrasits, W.G.

    1985-08-05

    A method and apparatus for the in situ repair of a failed compression fitting is provided. Initially, a portion of a guide tube is inserted coaxially in the bore of the compression fitting and locked therein. A close fit dethreading device is then coaxially mounted on the guide tube to cut the threads from the fitting. Thereafter, the dethreading device and guide tube are removed and a new fitting is inserted onto the dethreaded fitting with the body of the new fitting overlaying the dethreaded portion. Finally, the main body of the new fitting is welded to the main body of the old fitting whereby a new threaded portion of the replacement fitting is precisely coaxial with the old threaded portion. If needed, a bushing is located on the dethreaded portion which is sized to fit snugly between the dethreaded portion and the new fitting. Preferably, the dethreading device includes a cutting tool which is moved incrementally in a radial direction whereby the threads are cut from the threaded portion of the failed fitting in increments.

  11. In situ repair of a failed compression fitting

    DOE Patents [OSTI]

    Wolbert, Ronald R.; Jandrasits, Walter G.

    1986-01-01

    A method and apparatus for the in situ repair of a failed compression fitg is provided. Initially, a portion of a guide tube is inserted coaxially in the bore of the compression fitting and locked therein. A close fit dethreading device is then coaxially mounted on the guide tube to cut the threads from the fitting. Thereafter, the dethreading device and guide tube are removed and a new fitting is inserted onto the dethreaded fitting with the body of the new fitting overlaying the dethreaded portion. Finally, the main body of the new fitting is welded to the main body of the old fitting whereby a new threaded portion of the replacement fitting is precisely coaxial with the old threaded portion. If needed, a bushing is located on the dethreaded portion which is sized to fit snugly between the dethreaded portion and the new fitting. Preferably, the dethreading device includes a cutting tool which is moved incrementally in a radial direction whereby the threads are cut from the threaded portion of the failed fitting in increments.

  12. In situ remediation process using divalent metal cations

    DOE Patents [OSTI]

    Brady, Patrick V.; Khandaker, Nadim R.; Krumhansl, James L.; Teter, David M.

    2004-12-14

    An in situ process for treating ambient solid materials (e.g., soils, aquifer solids, sludges) by adding one or more divalent metal cations to the ambient solid material. The added divalent metal cations, such as Cu.sup.2+ or Zn.sup.2+, combine with metal oxide/hydroxides (e.g., ferric oxide/hydroxide or aluminum oxide/hydroxide) already present in the ambient solid material to form an effective sorbent material having a large number of positively-charged surface complexes that binds and immobilizes anionic contaminant species (e.g., arsenic or chromate). Divalent metal cations can be added, for example, by injecting an aqueous solution of CuSO.sub.4 into an aquifer contaminated with arsenic or chromate. Also, sludges can be stabilized against leaching of anionic contaminants through the addition of divalent metal cations. Also, an inexpensive sorbent material can be easily formed by mixing divalent metal cations with soil that has been removed from the ground.

  13. In-situ remediation system for groundwater and soils

    DOE Patents [OSTI]

    Corey, J.C.; Kaback, D.S.; Looney, B.B.

    1993-11-23

    A method and system are presented for in-situ remediation of contaminated groundwater and soil where the contaminants, such as toxic metals, are carried in a subsurface plume. The method comprises selection and injection into the soil of a fluid that will cause the contaminants to form stable, non-toxic compounds either directly by combining with the contaminants or indirectly by creating conditions in the soil or changing the conditions of the soil so that the formation of stable, non-toxic compounds between the contaminants and existing substances in the soil are more favorable. In the case of non-toxic metal contaminants, sulfides or sulfates are injected so that metal sulfides or sulfates are formed. Alternatively, an inert gas may be injected to stimulate microorganisms in the soil to produce sulfides which, in turn, react with the metal contaminants. Preferably, two wells are used, one to inject the fluid and one to extract the unused portion of the fluid. The two wells work in combination to create a flow of the fluid across the plume to achieve better, more rapid mixing of the fluid and the contaminants. 4 figures.

  14. In-situ droplet monitoring for self-tuning spectrometers

    DOE Patents [OSTI]

    Montaser, Akbar; Jorabchi, Kaveh; Kahen, Kaveh

    2010-09-28

    A laser scattering based imaging technique is utilized in order to visualize the aerosol droplets in an inductively coupled plasma (ICP) torch from an aerosol source to the site of analytical measurements. The resulting snapshots provide key information about the spatial distribution of the aerosol introduced by direct and indirect injection devices: 1) a direct injection high efficiency nebulizer (DIHEN); 2) a large-bore DIHEN (LB-DIHEN); and 3) a PFA microflow nebulizer with a PFA Scott-type spray chamber. Moreover, particle image velocimetry (PIV) is used to study the in-situ behavior of the aerosol before interaction with, for example, plasma, while the individual surviving droplets are explored by particle tracking velocimetry (PTV). Further, the velocity distribution of the surviving droplets demonstrates the importance of the initial droplet velocities in complete desolvation of the aerosol for optimum analytical performance in ICP spectrometries. These new observations are important in the design of the next-generation direct injection devices for lower sample consumption, higher sensitivity, lower noise levels, suppressed matrix effects, and for developing smart spectrometers. For example, a controller can be provided to control the output of the aerosol source by controlling the configuration of the source or the gas flow rate via feedback information concerning the aerosol.

  15. Method for in situ biological conversion of coal to methane

    DOE Patents [OSTI]

    Volkwein, Jon C.

    1995-01-01

    A method and apparatus are provided for the in situ biological conversion of coal to methane comprising culturing on a coal-containing substrate a consortium of microorganisms capable of degrading the coal into methane under suitable conditions. This consortium of microorganisms can be obtained from an underground cavity such as an abandoned mine which underwent a change from being supplied with sewage to where no sewage was present, since these conditions have favored the development of microorganisms capable of using coal as a carbon source and converting coal to methane. The consortium of microorganisms obtained from such abandoned coal mines can be isolated and introduced to hard-to-reach coal-containing substrates which lack such microorganisms and which would otherwise remain unrecoverable. The present invention comprises a significant advantage in that useable energy can be obtained from a number of abandoned mine sites or other areas wherein coal is no longer being recovered, and such energy can be obtained in a safe, efficient, and inexpensive manner.

  16. In-situ remediation system for groundwater and soils

    DOE Patents [OSTI]

    Corey, John C.; Kaback, Dawn S.; Looney, Brian B.

    1993-01-01

    A method and system for in-situ remediation of contaminated groundwater and soil where the contaminants, such as toxic metals, are carried in a subsurface plume. The method comprises selection and injection into the soil of a fluid that will cause the contaminants to form stable, non-toxic compounds either directly by combining with the contaminants or indirectly by creating conditions in the soil or changing the conditions of the soil so that the formation of stable, non-toxic compounds between the contaminants and existing substances in the soil are more favorable. In the case of non-toxic metal contaminants, sulfides or sulfates are injected so that metal sulfides or sulfates are formed. Alternatively, an inert gas may be injected to stimulate microorganisms in the soil to produce sulfides which, in turn, react with the metal contaminants. Preferably, two wells are used, one to inject the fluid and one to extract the unused portion of the fluid. The two wells work in combination to create a flow of the fluid across the plume to achieve better, more rapid mixing of the fluid and the contaminants.

  17. Gas injection to inhibit migration during an in situ heat treatment process

    DOE Patents [OSTI]

    Kuhlman, Myron Ira; Vinegar; Harold J.; Baker, Ralph Sterman; Heron, Goren

    2010-11-30

    Methods of treating a subsurface formation are described herein. Methods for treating a subsurface treatment area in a formation may include introducing a fluid into the formation from a plurality of wells offset from a treatment area of an in situ heat treatment process to inhibit outward migration of formation fluid from the in situ heat treatment process.

  18. Waterflood improvement in the Permian Basin: Impact of in-situ-stress evaluations

    SciTech Connect (OSTI)

    Nolen-Hoeksema, R.C.; Avasthi, J.M. ); Pape, W.C. ); El Rabaa, A.W. )

    1994-11-01

    The authors evaluated in-situ-stress magnitudes and directions to support waterflood improvement programs in McElroy field and North Westbrook Unit. In-situ-stress and hydraulic-fracture directions coincided with directional floodwater effects. This information contributed to successful waterflood realignment programs.

  19. 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

  20. Engineering feasibility analysis for in-situ stabilization of Canonsburg residues. [UMTRA project

    SciTech Connect (OSTI)

    Not Available

    1982-01-01

    The US Department of Energy is considering several methods for carrying out remedial actions in Canonsburg, Pennsylvania, at the site of an inactive uranium-processing mill. The main objective of this study is to determine the feasibility of in-situ stabilization as the remedial action. In-situ stabilization is an alternative to site decontamination and offsite disposal. The problems associated with offsite hauling of large quantities of contaminated material and with the location and development of a new disposal site could be avoided by the implementation of an in-situ stabilization concept. In addition, the in-situ approach would be more cost-effective than offsite disposal. This study will establish that a technically feasible and implementable in-situ stabilization concept can be developed that meets regulatory requirements and is cost effective. This study in no way commits the DOE to implement any specific actions described herein. 11 refs., 30 figs., 24 tabs.

  1. 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.

  2. 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.

  3. Action Memorandum for General Decommissioning Activities under the Idaho Cleanup Project

    SciTech Connect (OSTI)

    S. L. Reno

    2006-10-26

    This Action Memorandum documents the selected alternative to perform general decommissioning activities at the Idaho National Laboratory (INL) under the Idaho Cleanup Project (ICP). Preparation of this Action Memorandum has been performed in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended by the "Superfund Amendments and Reauthorization Act of 1986", and in accordance with the "National Oil and Hazardous Substances Pollution Contingency Plan". An engineering evaluation/cost analysis (EE/CA) was prepared and released for public comment and evaluated alternatives to accomplish the decommissioning of excess buildings and structures whose missions havve been completed.

  4. 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)

  5. 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

  6. Waste In-Situ Stabilization/Entombment Research and Development Project

    SciTech Connect (OSTI)

    Birk, Sandra Margaret; Hanson, Robert Gail; Vernon, Donald Keith

    2000-09-01

    The technical basis and stakeholder acceptance of entombment technology is necessary before entombment becomes a decontamination and decommissioning (D&D) option for nuclear reactors. The authors present a research and development (R&D) approach addressing technical basis and stakeholder acceptance of entombment technology. The approach includes a consortium and the conceptual R&D program.

  7. Development of a Microchannel In Situ Propellant Production System

    SciTech Connect (OSTI)

    Brooks, Kriston P.; Rassat, Scot D.; TeGrotenhuis, Ward E.

    2005-09-01

    An in situ propellant production (ISPP) plant on future Mars robotic missions can produce oxygen (O2) and methane (CH4) that can be used for propellant for the return voyage. By producing propellants from Mars atmospheric carbon dioxide (CO2) and hydrogen (H2) brought from Earth, the initial mass launched in low Earth orbit can be reduced by 20% to 45%, as compared to carrying all of the propellant for a round-trip mission to the Mars surface from Earth. Pacific Northwest National Laboratory used microchannel architecture to develop a Mars-based In Situ Propellant Production (ISPP) system. This three year research and development effort focused on process intensification and system miniaturization of three primary subsystems: a thermochemical compressor, catalytic reactors, and components for separating gas phases from liquid phases. These systems were designed based on a robotic direct return mission scenario, but can be scaled up to human flight missions by simply numbering up the microchannel devices. The thermochemical compression was developed both using absorption and adsorption. A multichannel adsorption system was designed to meet the full-scale CO2 collection requirements using temperature swing adsorption. Each stage is designed to achieve a 10x compression of CO2. A compression ratio to collect Martian atmospheric CO2 at ~0.8 kPa and compress it to at least 100 kPa can be achieved with two adsorption stages in series. A compressor stage incorporates eight thermally coupled adsorption cells at various stages in the adsorption/desorption cycle to maximize the recuperation of thermal energy and provide a nearly continuous flow of CO2 to the downstream reactors. The thermochemically compressed CO2 is then mixed with hydrogen gas and fed to two reactors: a Sabatier Reaction unit and a Reverse Water/Gas Shift unit. The microchannel architecture allows better heat control than is possible in an adiabatic system, resulting in significantly higher conversion. The

  8. In Situ Sensors for the Chemical Industry- Final Report

    SciTech Connect (OSTI)

    Tate, J.D.; Knittel, Trevor

    2006-06-30

    The project focused on analytical techniques that can be applied in situ. The innovative component of this project is the focus on achieving a significant breakthrough in two of the three primary Process Analytical (PA) fields. PA measurements can roughly be broken down into: ? Single component measurements, ? Multiple component measurements and ? Multiple component isomer analysis. This project targeted single component measurements and multiple component measurements with two basic technologies, and to move these measurements to the process, achieving many of the process control needs. During the project the following achievements were made: ? Development of a low cost Tunable Diode Laser (TDL) Analyzer system for measurement of 1) Oxygen in process and combustion applications, 2) part per million (ppm) H2O impurities in aggressive service, 3) ppm CO in large scale combustion systems. This product is now commercially available ? Development of a process pathlength enhanced (high sensitivity) Laser Based Analyzer for measurement of product impurities. This product is now commercially available. ? Development of signal processing methods to eliminate measurement errors in complex and changing backgrounds (critical to chemical industry measurements). This development is incorporated into 2 commercially available products. ? Development of signal processing methods to allow multi-component measurements in complex chemical streams. This development is incorporated into 2 commercially available products. ? Development of process interface designs to allow in-situ application of TDL technology in aggressive (corrosive, high temperature, high pressure) commonly found in chemical processes. This development is incorporated in the commercially available ASI TDL analyzer. ? Field proving of 3 laser-based analyzer systems in process control and combustion applications at Dow Chemical. Laser based analyzers have been available for >5yrs, however significant product price

  9. Degradation of Bimetallic Model Electrocatalysts ___ an in situ XAS Study

    SciTech Connect (OSTI)

    Friebel, Daniel

    2011-06-22

    One of the major challenges in the development of clean energy fuel cells is the performance degradation of the electrocatalyst, which, apart from poisoning effects, can suffer from corrosion due to its exposure to a harsh environment under high potentials. In this communication, we demonstrate how interactions of Pt with a transition metal support affect not only, as commonly intended, the catalytic activity, but also the reactivity of Pt towards oxide formation or dissolution. We use two well-defined single-crystal model systems, Pt/Rh(111) and Pt/Au(111) and a unique x-ray spectroscopy technique with enhanced energy resolution to monitor the potential-dependent oxidation state of Pt, and find two markedly different oxidation mechanisms on the two different substrates. This information can be of great significance for future design of more active and more stable catalysts. We have studied the potential-induced degradation of Pt monolayer model electrocatalysts on Rh(111) and Au(111) single-crystal substrates. The anodic formation of Pt oxides was monitored using in situ high energy resolution fluorescence detection x-ray absorption spectroscopy (HERFD XAS). Although Pt was deposited on both substrates in a three-dimensional island growth mode, we observed remarkable differences during oxide formation that can only be understood in terms of strong Pt-substrate interactions throughout the Pt islands. Anodic polarization of Pt/Rh(111) up to +1.6 V vs. RHE (reversible hydrogen electrode) leads to formation an incompletely oxidized passive layer, whereas formation of PtO2 and partial Pt dissolution is observed for Pt/Au(111).

  10. Cold cap subsidence for in situ vitrification and electrodes therefor

    DOE Patents [OSTI]

    Buelt, James L.; Carter, John G.; Eschbach, Eugene A.; FitzPatrick, Vincent F.; Koehmstedt, Paul L.; Morgan, William C.; Oma, Kenton H.; Timmerman, Craig L.

    1992-01-01

    An electrode for use in in situ vitrification of soil comprises a molybdenum rod received within a conductive sleeve or collar formed of graphite. Electrodes of this type are placed on either side of a region containing buried waste material and an electric current is passed therebetween for vitrifying the soil between the electrodes. The graphite collar enhances the thermal conductivity of the electrode, bringing heat to the surface, and preventing the formation of a cold cap of material above the ground surface. The annulus between the molybdenum rod electrode and the graphite collar is filled with a conductive ceramic powder of a type that sinters upon the molybdenum rod, protecting the same from oxidation as the graphite material is consumed, or a metal powder which liquifies at operating temperatures. The molybdenum rod in the former case may be coated with an oxidation protectant, e.g. of molybdenum disilicide. As insulative blanket is suitably placed on the surface of the soil during processing to promote subsidence by allowing off-gassing and reducing surface heat loss. In other embodiments, connection to vitrification electrodes is provided below ground level to avoid loss of connection due to electrodes deterioration, or a sacrificial electrode may be employed when operation is started. Outboard electrodes can be utilized to square up the vitrified area. Further, the center of the molybdenum rod can be made hollow and filled with a powdered metal, such as copper, which liquifies at operating temperatures. In one embodiment, the molybdenum rod and the graphite collar are physically joined at the bottom.

  11. In situ characterization of nanoscale catalysts during anodic redox processes

    SciTech Connect (OSTI)

    Sharma, Renu; Crozier, Peter; Adams, James

    2013-09-19

    Controlling the structure and composition of the anode is critical to achieving high efficiency and good long-term performance. In addition to being a mixed electronic and ionic conductor, the ideal anode material should act as an efficient catalyst for oxidizing hydrogen, carbon monoxide and dry hydrocarbons without de-activating through either sintering or coking. It is also important to develop novel anode materials that can operate at lower temperatures to reduce costs and minimized materials failure associated with high temperature cycling. We proposed to synthesize and characterize novel anode cermets materials based on ceria doped with Pr and/or Gd together with either a Ni or Cu metallic components. Ceria is a good oxidation catalyst and is an ionic conductor at room temperature. Doping it with trivalent rare earths such as Pr or Gd retards sintering and makes it a mixed ion conductor (ionic and electronic). We have developed a fundamental scientific understanding of the behavior of the cermet material under reaction conditions by following the catalytic oxidation process at the atomic scale using a powerful Environmental Scanning Transmission Electron Microscope (ESTEM). The ESTEM allowed in situ monitoring of structural, chemical and morphological changes occurring at the cermet under conditions approximating that of typical fuel-cell operation. Density functional calculations were employed to determine the underlying mechanisms and reaction pathways during anode oxidation reactions. The dynamic behavior of nanoscale catalytic oxidation of hydrogen and methane were used to determine: ? Fundamental processes during anodic reactions in hydrogen and carbonaceous atmospheres ? Interfacial effects between metal particles and doped ceria ? Kinetics of redox reaction in the anode material

  12. 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.

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

    Broader source: Energy.gov [DOE]

    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.

  14. 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

  15. 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.

  16. In-situ, Real-Time Monitoring of Mechanical and Chemical Structure Changes

    Office of Scientific and Technical Information (OSTI)

    in a V2O5 Battery Electrode Using a MEMS Optical Sensor (Conference) | SciTech Connect In-situ, Real-Time Monitoring of Mechanical and Chemical Structure Changes in a V2O5 Battery Electrode Using a MEMS Optical Sensor Citation Details In-Document Search Title: In-situ, Real-Time Monitoring of Mechanical and Chemical Structure Changes in a V2O5 Battery Electrode Using a MEMS Optical Sensor This work presents the first demonstration of a MEMS optical sensor for in-situ, real-time monitoring of

  17. Magic angle spinning nuclear magnetic resonance apparatus and process for high-resolution in situ investigations

    SciTech Connect (OSTI)

    Hu, Jian Zhi; Sears, Jr., Jesse A.; Hoyt, David W.; Mehta, Hardeep S.; Peden, Charles H. F.

    2015-11-24

    A continuous-flow (CF) magic angle sample spinning (CF-MAS) NMR rotor and probe are described for investigating reaction dynamics, stable intermediates/transition states, and mechanisms of catalytic reactions in situ. The rotor includes a sample chamber of a flow-through design with a large sample volume that delivers a flow of reactants through a catalyst bed contained within the sample cell allowing in-situ investigations of reactants and products. Flow through the sample chamber improves diffusion of reactants and products through the catalyst. The large volume of the sample chamber enhances sensitivity permitting in situ .sup.13C CF-MAS studies at natural abundance.

  18. ARM - PI Product - In-Situ Data for Microphysical Retrievals: TC4, 2007

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

    ProductsIn-Situ Data for Microphysical Retrievals: TC4, 2007 Citation DOI: 10.5439/1244832 [ What is this? ] ARM Data Discovery Browse Data Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send PI Product : In-Situ Data for Microphysical Retrievals: TC4, 2007 [ ARM research ] This data set is derived from measurements collected in situ by the NASA DC8 during the Tropical Cloud Climate Composition Coupling Experiment (TC4) that was conducted during July

  19. Experiments at Scale with In-Situ Visualization Using ParaView/Catalyst in RAGE

    SciTech Connect (OSTI)

    Kares, Robert John

    2014-10-31

    In this paper I describe some numerical experiments performed using the ParaView/Catalyst in-situ visualization infrastructure deployed in the Los Alamos RAGE radiation-hydrodynamics code to produce images from a running large scale 3D ICF simulation on the Cielo supercomputer at Los Alamos. The detailed procedures for the creation of the visualizations using ParaView/Catalyst are discussed and several images sequences from the ICF simulation problem produced with the in-situ method are presented. My impressions and conclusions concerning the use of the in-situ visualization method in RAGE are discussed.

  20. In-situ gamma-analysis support for Phase I, Middlesex cleanup project, Middlesex, New Jersey

    SciTech Connect (OSTI)

    Reiman, R.T.

    1983-07-01

    At the request of the Department of Energy, the Energy Measurements Group of EG and G participated in the Remedial Action program for the former Middlesex Sampling Plant and associated properties at Middlesex, New Jersey from July to November 1980. EG and G provided real time analysis of the radiological character of the soil of each property included in the Phase I cleanup before, during, and after decontamination. The method used for the analysis was in situ gamma spectroscopy employing a high purity germanium detector. This report describes the in situ system and displays the results of the in situ measurements before and after decontamination of the properties surveyed during Phase I.

  1. 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.

  2. 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)

  3. 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.

  4. 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.

  5. In-situ Measurement of Low-Z Material Coating Thickness on High...

    Office of Scientific and Technical Information (OSTI)

    2 PPPL- 5042 In-situ Measurement of Low-Z Material Coating Thickness on High Z Substrate for Tokamaks D. Mueller, A.L. Roquemore, M. Jaworski, C.H. Skinner, J. Miller, A. Creely, ...

  6. Development of CFD-Based Simulation Tools for In-Situ Thermal...

    Office of Scientific and Technical Information (OSTI)

    Processing of Oil ShaleSands Citation Details In-Document Search Title: Development of CFD-Based Simulation Tools for In-Situ Thermal Processing of Oil ShaleSands In our ...

  7. In-Situ Data for Microphysical Retrievals: TC4, 2007 (Dataset...

    Office of Scientific and Technical Information (OSTI)

    This data set is derived from measurements collected in situ by the NASA DC8 during the Tropical Cloud Climate Composition Coupling Experiment (TC4) that was conducted during July ...

  8. Development of Counted Single Donor Devices using in-situ Single...

    Office of Scientific and Technical Information (OSTI)

    Development of Counted Single Donor Devices using in-situ Single Ion Detectors on the SNL NanoImplanter. Citation Details In-Document Search Title: Development of Counted Single ...

  9. in situ plasma removal of surface contaminants from ion trap electrodes

    SciTech Connect (OSTI)

    Haltli, Raymond A.

    2015-04-01

    This research resulted in a construction and implementation of an in situ plasma discharge to remove surface contaminants from electrodes in an ion trapping experimental system is presented with results.

  10. Water Usage for In-Situ Oil Shale Retorting - A Systems Dynamics...

    Office of Scientific and Technical Information (OSTI)

    Water Usage for In-Situ Oil Shale Retorting - A Systems Dynamics Model Earl D. Mattson; Larry Hull; Kara Cafferty 02 PETROLEUM Water Water A system dynamic model was construction...

  11. Development of CFD-Based Simulation Tools for In-Situ Thermal...

    Office of Scientific and Technical Information (OSTI)

    CFD-Based Simulation Tools for In-Situ Thermal Processing of Oil ShaleSands None 04 OIL SHALES AND TAR SANDS In our research, we are taking the novel approach of developing and...

  12. In Situ Formation of Calcium Apatite in Soil for Sequestering Contaminants in Soil and Groundwater

    SciTech Connect (OSTI)

    Moore, Robert; Szecsody, Jim; Thompson, Mike

    2015-10-20

    A new method for in situ formation of a calcium apatite permeable reactive barrier that is a groundbreaking technology for containing radioactive/heavy metal contaminants threatening groundwater supplies.

  13. Vehicle Technologies Office Merit Review 2015: In-Situ Solvothermal Synthesis of Novel High Capacity Cathodes

    Broader source: Energy.gov [DOE]

    Presentation given by Brookhaven National Laboratory at 2015 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Office Annual Merit Review and Peer Evaluation Meeting about in-situ...

  14. In-situ TEM study of sodiation and failure mechanism of Sb anodes...

    Office of Scientific and Technical Information (OSTI)

    Title: In-situ TEM study of sodiation and failure mechanism of Sb anodes. Abstract not provided. Authors: XueHai Tan ; Jungjohann, Katherine Leigh ; Mook, William ; David Mitlin ...

  15. New insights from in-situ electron microscopy into capacity loss...

    Office of Scientific and Technical Information (OSTI)

    Li-ion batteries with Al anodes. Citation Details In-Document Search Title: New insights from in-situ electron microscopy into capacity loss mechanisms in Li-ion batteries with Al ...

  16. New insights from in-situ electron microscopy into capacity loss...

    Office of Scientific and Technical Information (OSTI)

    batteries with Al anodes. Citation Details In-Document Search Title: New insights from in-situ electron microscopy into capacity loss mechanisms in all-solid-state Li-ion batteries ...

  17. Performance, power, and energy of in-situ and post-processing visualization

    SciTech Connect (OSTI)

    Adhinarayanan, Vignesh

    2015-10-05

    The goal of this project was to "study the performance, power, and energy trade-offs among traditional post-processing, modern post-processing, and in-situ visualization pipelines."

  18. Water Usage for In-Situ Oil Shale Retorting - A Systems Dynamics...

    Office of Scientific and Technical Information (OSTI)

    A system dynamic model was construction to evaluate the water balance for in-situ oil ... and a remediation phase water to remove heat and solutes from the subsurface as well as ...

  19. Borehole Imaging of In Situ Stress Tests at Mirror Lake Research...

    Open Energy Info (EERE)

    at Mirror Lake Research Site Citation U.S. Geological Survey. Borehole Imaging of In Situ Stress Tests at Mirror Lake Research Site Internet. 2013. U.S. Geological Survey. cited...

  20. In situ calibration of inductively coupled plasma-atomic emission and mass spectroscopy

    DOE Patents [OSTI]

    Braymen, S.D.

    1996-06-11

    A method and apparatus are disclosed for in situ addition calibration of an inductively coupled plasma atomic emission spectrometer or mass spectrometer using a precision gas metering valve to introduce a volatile calibration gas of an element of interest directly into an aerosol particle stream. The present in situ calibration technique is suitable for various remote, on-site sampling systems such as laser ablation or nebulization. 5 figs.

  1. Determination of Total Lipids as Fatty Acid Methyl Esters (FAME) by in situ

    Office of Scientific and Technical Information (OSTI)

    Transesterification: Laboratory Analytical Procedure (LAP) (Technical Report) | SciTech Connect Determination of Total Lipids as Fatty Acid Methyl Esters (FAME) by in situ Transesterification: Laboratory Analytical Procedure (LAP) Citation Details In-Document Search Title: Determination of Total Lipids as Fatty Acid Methyl Esters (FAME) by in situ Transesterification: Laboratory Analytical Procedure (LAP) This procedure is based on a whole biomass transesterification of lipids to fatty acid

  2. Microbial and Chemical Enhancement of In-Situ Carbon Mineralization in

    Office of Scientific and Technical Information (OSTI)

    Geological Formation (Technical Report) | SciTech Connect Technical Report: Microbial and Chemical Enhancement of In-Situ Carbon Mineralization in Geological Formation Citation Details In-Document Search Title: Microbial and Chemical Enhancement of In-Situ Carbon Mineralization in Geological Formation Predictions of global energy usage suggest a continued increase in carbon emissions and rising concentrations of CO{sub 2} in the atmosphere unless major changes are made to the way energy is

  3. Method and Apparatus for In-Situ Real Time Characterization of Energy

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

    Storage and Energy Conversion Devices - Energy Innovation Portal Energy Storage Energy Storage Find More Like This Return to Search Method and Apparatus for In-Situ Real Time Characterization of Energy Storage and Energy Conversion Devices Opening the door to real time battery health assessment Idaho National Laboratory Contact INL About This Technology Publications: PDF Document Publication Technology Fact Sheet (1,110 KB) Impedance Measurement Box in situ testing Impedance Measurement Box

  4. Thermographic In-Situ Process Monitoring of the Electron Beam Melting

    Office of Scientific and Technical Information (OSTI)

    Technology used in Additive Manufacturing (Conference) | SciTech Connect Thermographic In-Situ Process Monitoring of the Electron Beam Melting Technology used in Additive Manufacturing Citation Details In-Document Search Title: Thermographic In-Situ Process Monitoring of the Electron Beam Melting Technology used in Additive Manufacturing Oak Ridge National Laboratory (ORNL) has been utilizing the ARCAM electron beam melting technology to additively manufacture complex geometric structures

  5. In-Situ Liquid (ec)-TEM Cell Shows Dendrite Formation, Providing New

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

    Insights into Lithium Batteries - Joint Center for Energy Storage Research March 3, 2014, Research Highlights In-Situ Liquid (ec)-TEM Cell Shows Dendrite Formation, Providing New Insights into Lithium Batteries (Top) In-situ liquid electrochemical (ec)-TEM cell uses two silicon microchips to create a three-electrode electrochemical cell with silicon nitride membranes that seal battery electrolytes. This enables charge/discharge cycling of the battery inside the high vacuum of a transmission

  6. In-Situ Production of Microbial Pigments for Metal and Actinide

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

    Immobilization - Energy Innovation Portal In-Situ Production of Microbial Pigments for Metal and Actinide Immobilization Unique in-situ method shown to dramatically reduce the mobility of contaminants in the soil without need for excavation Savannah River National Laboratory Contact SRNL About This Technology The stimulation of melanin production by subsurface bacteria offers a means to accelerate the immobilization rates of metal and radionuclide contaminants in the subsurface, even at low

  7. Laboratory Product Speciation Studies of the LNT + in situ SCR NOx Emission

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

    Control Concept | Department of Energy Product Speciation Studies of the LNT + in situ SCR NOx Emission Control Concept Laboratory Product Speciation Studies of the LNT + in situ SCR NOx Emission Control Concept Understanding the detailed chemistry of Nox Reduction across the combined LNT+SCR system. deer10_crocker.pdf (827.9 KB) More Documents & Publications Development of Optimal Catalyst Designs and Operating Strategies for Lean NOx Reduction in Coupled LNT-SCR Systems Lean NOx

  8. Novel Sensor for the In Situ Measurement of Uranium Fluxes

    SciTech Connect (OSTI)

    Hatfield, Kirk

    2015-02-10

    The goal of this project was to develop a sensor that incorporates the field-tested concepts of the passive flux meter to provide direct in situ measures of flux for uranium and groundwater in porous media. Measurable contaminant fluxes [J] are essentially the product of concentration [C] and groundwater flux or specific discharge [q ]. The sensor measures [J] and [q] by changes in contaminant and tracer amounts respectively on a sorbent. By using measurement rather than inference from static parameters, the sensor can directly advance conceptual and computational models for field scale simulations. The sensor was deployed in conjunction with DOE in obtaining field-scale quantification of subsurface processes affecting uranium transport (e.g., advection) and transformation (e.g., uranium attenuation) at the Rifle IFRC Site in Rifle, Colorado. Project results have expanded our current understanding of how field-scale spatial variations in fluxes of uranium, groundwater and salient electron donor/acceptors are coupled to spatial variations in measured microbial biomass/community composition, effective field-scale uranium mass balances, attenuation, and stability. The coupling between uranium, various nutrients and micro flora can be used to estimate field-scale rates of uranium attenuation and field-scale transitions in microbial communities. This research focuses on uranium (VI), but the sensor principles and design are applicable to field-scale fate and transport of other radionuclides. Laboratory studies focused on sorbent selection and calibration, along with sensor development and validation under controlled conditions. Field studies were conducted at the Rifle IFRC Site in Rifle, Colorado. These studies were closely coordinated with existing SBR (formerly ERSP) projects to complement data collection. Small field tests were conducted during the first two years that focused on evaluating field-scale deployment procedures and validating sensor performance under

  9. Decommissioning the physics laboratory, building 777-10A, at the Savannah River Site (SRS)

    SciTech Connect (OSTI)

    Musall, John C.; Cope, Jeff L.

    2008-01-15

    SRS recently completed a four year mission to decommission {approx}250 excess facilities. As part of that effort, SRS decommissioned a 48,000 ft{sup 2} laboratory that housed four low-power test reactors, formerly used by SRS to determine reactor physics. This paper describes and reviews the decommissioning, with a focus on component segmentation and handling (i.e. hazardous material removal, demolition, and waste handling). The paper is intended to be a resource for engineers, planners, and project managers, who face similar decommissioning challenges. Building 777-10A, located at the south end of SRS's A/M-Area, was built in 1953 and had a gross area of {approx}48,000 ft{sup 2}. Building 777-10A had two main areas: a west wing, which housed four experimental reactors and associated equipment; and an east wing, which housed laboratories, and shops, offices. The reactors were located in two separate areas: one area housed the Process Development Pile (PDP) reactor and the Lattice Test Reactor (LTR), while the second area housed the Standard Pile (SP) and the Sub-critical Experiment (SE) reactors. The west wing had five levels: three below and three above grade (floor elevations of -37', -28', -15', 0', +13'/+16' and +27' (roof elevation of +62')), while the east wing had two levels: one below and one above grade (floor elevations of -15' and 0' (roof elevation of +16')). Below-grade exterior walls were constructed of reinforced concrete, {approx}1' thick. In general, above-grade exterior walls were steel frames covered by insulation and corrugated, asbestos-cement board. The two interior walls around the PDP/LTR were reinforced concrete {approx}5' thick and {approx}30' high, while the SP/SE reactors resided in a reinforced, concrete cell with 3.5'-6' thick walls/roof. All other interior walls were constructed of metal studs covered with either asbestos-cement or gypsum board. In general, the floors were constructed of reinforced concrete on cast-in-place concrete

  10. 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.

  11. 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.

  12. 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

  13. 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

  14. 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

  15. 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.

  16. 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.

  17. 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.

  18. 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).

  19. 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)

  20. The independent verification process in decommissioning, decontamination, and reutilization activities - description, benefits, and lessons learned

    SciTech Connect (OSTI)

    Egidi, P.V.

    1997-06-01

    Oak Ridge National Laboratory Environmental Technology Section has been performing Independent Verification (IV) activities for U.S. DOE sites since 1986. DOE has successfully used IV in the Uranium Mill Tailings Remedial Action Program, Decontamination and Decommissioning projects, and Formerly Utilized Sites Remedial Action Projects/Surplus Facilities Management Program. Projects that have undergone IV range from small residential properties to large, industrial sites. The IV process provides a third-party review conducted by an independent organization. The purpose is to verify accuracy and completeness of contractor field measurements and final documentation, evaluate the credibility of procedures, and independently assess post-cleanup conditions versus decommissioning project plans and release criteria. Document reviews of plans, dose models, procedures, and reports are some IV activities undertaken. Independent measurements are also collected during field visits to confirm the contractor`s findings. Corrective actions for discrepancies are suggested if necessary. Finally, archival and reporting of the final site environmental conditions for project closeout and certification are completed. The IV contractor reports to DOE headquarters and acts as a quality assurance feedback mechanism. An IV also provides additional assurance that projects are planned, carried out, and documented properly. Decommissioning projects benefit from the IV process by: (1) cost and time savings from early identification of potential problems, (2) assurance that cleanup meets regulatory guidelines, and (3) technical reviews and consultation with experts in field instrumentation, sampling strategy, etc. Some lessons learned from the IV process include avoiding: (1) improper survey techniques, (2) reporting data in units not comparable with guideline values, (3) premature release of surfaces, (4) poor decommissioning project planning, (5) misapplication of release guidelines. 20 refs.

  1. DEACTIVATION AND DECOMMISSIONING ENVIRONMENTAL STRATEGY FOR THE PLUTONIUM FINISHING PLANT COMPLEX, HANFORD NUCLEAR RESERVATION

    SciTech Connect (OSTI)

    Hopkins, A.M.; Heineman, R.; Norton, S.; Miller, M.; Oates, L.

    2003-02-27

    Maintaining compliance with environmental regulatory requirements is a significant priority in successful completion of the Plutonium Finishing Plant (PFP) Nuclear Material Stabilization (NMS) Project. To ensure regulatory compliance throughout the deactivation and decommissioning of the PFP complex, an environmental regulatory strategy was developed. The overall goal of this strategy is to comply with all applicable environmental laws and regulations and/or compliance agreements during PFP stabilization, deactivation, and eventual dismantlement. Significant environmental drivers for the PFP Nuclear Material Stabilization Project include the Tri-Party Agreement; the Resource Conservation and Recovery Act of 1976 (RCRA); the Comprehensive Environmental Response, Compensation and Liability Act of 1980 (CERCLA); the National Environmental Policy Act of 1969 (NEPA); the National Historic Preservation Act (NHPA); the Clean Air Act (CAA), and the Clean Water Act (CWA). Recent TPA negotiation s with Ecology and EPA have resulted in milestones that support the use of CERCLA as the primary statutory framework for decommissioning PFP. Milestones have been negotiated to support the preparation of Engineering Evaluations/Cost Analyses for decommissioning major PFP buildings. Specifically, CERCLA EE/CA(s) are anticipated for the following scopes of work: Settling Tank 241-Z-361, the 232-Z Incinerator, , the process facilities (eg, 234-5Z, 242, 236) and the process facility support buildings. These CERCLA EE/CA(s) are for the purpose of analyzing the appropriateness of the slab-on-grade endpoint Additionally, agreement was reached on performing an evaluation of actions necessary to address below-grade structures or other structures remaining after completion of the decommissioning of PFP. Remaining CERCLA actions will be integrated with other Central Plateau activities at the Hanford site.

  2. Decommissioning and Demolition of a Redundant UK Research Facility at AWE Aldermaston - 12453

    SciTech Connect (OSTI)

    Pritchard, Paul

    2012-07-01

    The redundant two-storey brick built research facility on the AWE Site at Aldermaston, UK is in the closing stages of decommissioning and demolition. The facility was used for a variety of purposes up to 1995 predominately involving the use of alpha-emitting isotopes. The two main areas of alpha-based contamination have been decommissioned with the removal of hot -boxes and fume cupboards on the ground floor and HEPA filter units and ventilation equipment on the first floor. Many of these activities were undertaken using both airline fed suits, (supplied via a free standing mobile unit), and full face respirators. Asbestos materials were located and cleared from the first floor by specialist contractor. All sections of active drain running from the building to the site active effluent disposal system were removed early in the program using established techniques with specialist monitoring equipment used to provide confidence in the data required for disposal of the decommissioning debris. In particular a dedicated High Resolution Gamma Spectrometer (radioactive materials scanning unit) was utilized to categorise waste drums and wrapped packages. The building has been decommissioned and the monitoring and sampling of the structure was completed in November 2011 - the results demonstrating that the building was clear of contamination in accordance with UK clearance and exemption requirements. The demolition plan was developed and implemented in December with site excavation of foundations and site clearance currently ongoing in preparation for final site backfill activities and project close. A number of useful lessons have been learnt during the operations and are set out at the rear of the main text. (authors)

  3. ESTABLISHING FINAL END STATE FOR A RETIRED NUCLEAR WEAPONS PRODUCTION REACTOR; COLLABORATION BETWEEN STAKEHOLDERS, REGULATORS AND THE FEDERAL GOVERNMENT

    SciTech Connect (OSTI)

    Bergren, C

    2009-01-16

    The Savannah River Site (SRS) is a 310-square-mile United States Department of Energy nuclear facility located along the Savannah River (SRS) near Aiken, South Carolina. Nuclear weapons material production began in the early 1950s, utilizing five production reactors. In the early 1990s all SRS production reactor operations were terminated. The first reactor closure end state declaration was recently institutionalized in a Comprehensive Environmental Response and Compensation and Liability Act (CERCLA) Early Action Record of Decision. The decision for the final closure of the 318,000 square foot 105-P Reactor was determined to be in situ decommissioning (ISD). ISD is an acceptable and cost effective alternative to off-site disposal for the reactor building, which will allow for consolidation of remedial action wastes generated from other cleanup activities within the P Area. ISD is considered protective by the regulators, U. S. Environmental Protection Agency (US EPA) and the South Carolina Department of Health and Environmental Control (SCDHEC), public and stakeholders as waste materials are stabilized/immobilized, and radioactivity is allowed to naturally decay, thus preventing future exposure to the environment. Stakeholder buy-in was critical in the upfront planning in order to achieve this monumental final decision. Numerous public meetings and workshops were held in two different states (covering a 200 mile radius) with stakeholder and SRS Citizens Advisory Board participation. These meetings were conducted over an eight month period as the end state decision making progressed. Information provided to the public evolved from workshop to workshop as data became available and public input from the public meetings were gathered. ISD is being considered for the balance of the four SRS reactors and other hardened facilities such as the chemical processing canyons.

  4. ESTABLISHING FINAL END STATE FOR A RETIRED NUCLEAR WEAPONS PRODUCTION REACTOR; COLLABORATION BETWEEN STAKEHOLDERS, REGULATORS, AND THE FEDERAL GOVERNMENT - 11052

    SciTech Connect (OSTI)

    Bergren, C.; Flora, M.; Belencan, H.

    2010-11-17

    The Savannah River Site (SRS) is a 310-square-mile United States Department of Energy nuclear facility located along the Savannah River (SRS) near Aiken, South Carolina. Nuclear weapons material production began in the early 1950s, utilizing five production reactors. In the early 1990s all SRS production reactor operations were terminated. The first reactor closure end state declaration was recently institutionalized in a Comprehensive Environmental Response and Compensation and Liability Act (CERCLA) Early Action Record of Decision. The decision for the final closure of the 318,000 square foot 105-P Reactor was determined to be in situ decommissioning (ISD). ISD is an acceptable and cost effective alternative to off-site disposal for the reactor building, which will allow for consolidation of remedial action wastes generated from other cleanup activities within the P Area. ISD is considered protective by the regulators, U. S. Environmental Protection Agency (US EPA) and the South Carolina Department of Health and Environmental Control (SCDHEC), public and stakeholders as waste materials are stabilized/immobilized, and radioactivity is allowed to naturally decay, thus preventing future exposure to the environment. Stakeholder buy-in was critical in the upfront planning in order to achieve this monumental final decision. Numerous public meetings and workshops were held in two different states (covering a 200 mile radius) with stakeholder and SRS Citizens Advisory Board participation. These meetings were conducted over an eight month period as the end state decision making progressed. Information provided to the public evolved from workshop to workshop as data became available and public input from the public meetings were gathered. ISD is being considered for the balance of the four SRS reactors and other hardened facilities such as the chemical Separation Facilities (canyons).

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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)

  12. 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.

  13. Experimental Investigation and High Resolution Simulation of In-Situ Combustion Processes

    SciTech Connect (OSTI)

    Margot Gerritsen; Tony Kovscek

    2008-04-30

    This final technical report describes work performed for the project 'Experimental Investigation and High Resolution Numerical Simulator of In-Situ Combustion Processes', DE-FC26-03NT15405. In summary, this work improved our understanding of in-situ combustion (ISC) process physics and oil recovery. This understanding was translated into improved conceptual models and a suite of software algorithms that extended predictive capabilities. We pursued experimental, theoretical, and numerical tasks during the performance period. The specific project objectives were (i) identification, experimentally, of chemical additives/injectants that improve combustion performance and delineation of the physics of improved performance, (ii) establishment of a benchmark one-dimensional, experimental data set for verification of in-situ combustion dynamics computed by simulators, (iii) develop improved numerical methods that can be used to describe in-situ combustion more accurately, and (iv) to lay the underpinnings of a highly efficient, 3D, in-situ combustion simulator using adaptive mesh refinement techniques and parallelization. We believe that project goals were met and exceeded as discussed.

  14. 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.

  15. 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.

  16. Note: Sample chamber for in situ x-ray absorption spectroscopy studies of battery materials

    SciTech Connect (OSTI)

    Pelliccione, CJ; Timofeeva, EV; Katsoudas, JP; Segre, CU

    2014-12-01

    In situ x-ray absorption spectroscopy (XAS) provides element-specific characterization of both crystalline and amorphous phases and enables direct correlations between electrochemical performance and structural characteristics of cathode and anode materials. In situ XAS measurements are very demanding to the design of the experimental setup. We have developed a sample chamber that provides electrical connectivity and inert atmosphere for operating electrochemical cells and also accounts for x-ray interactions with the chamber and cell materials. The design of the sample chamber for in situ measurements is presented along with example XAS spectra from anode materials in operating pouch cells at the Zn and Sn K-edges measured in fluorescence and transmission modes, respectively. (C) 2014 AIP Publishing LLC.

  17. In situ Raman spectroscopy for growth monitoring of vertically aligned multiwall carbon nanotubes in plasma reactor

    SciTech Connect (OSTI)

    Labbaye, T.; Gaillard, M.; Lecas, T.; Kovacevic, E.; Boulmer-Leborgne, Ch.; Guimbretière, G.; Canizarès, A.; Raimboux, N.; Simon, P.; Ammar, M. R.; Strunskus, T.

    2014-11-24

    Portable and highly sensitive Raman setup was associated with a plasma-enhanced chemical vapor deposition reactor enabling in situ growth monitoring of multi-wall carbon nanotubes despite the combination of huge working distance, high growth speed and process temperature and reactive plasma condition. Near Edge X-ray absorption fine structure spectroscopy was used for ex situ sample analysis as a complementary method to in situ Raman spectroscopy. The results confirmed the fact that the “alternating” method developed here can accurately be used for in situ Raman monitoring under reactive plasma condition. The original analytic tool can be of great importance to monitor the characteristics of these nanostructured materials and readily define the ultimate conditions for targeted results.

  18. Lithographically fabricated silicon microreactor for in situ characterization of heterogeneous catalystsEnabling correlative characterization techniques

    SciTech Connect (OSTI)

    Baier, S.; Rochet, A.; Hofmann, G.; Kraut, M.; Grunwaldt, J.-D.

    2015-06-15

    We report on a new modular setup on a silicon-based microreactor designed for correlative spectroscopic, scattering, and analytic on-line gas investigations for in situ studies of heterogeneous catalysts. The silicon microreactor allows a combination of synchrotron radiation based techniques (e.g., X-ray diffraction and X-ray absorption spectroscopy) as well as infrared thermography and Raman spectroscopy. Catalytic performance can be determined simultaneously by on-line product analysis using mass spectrometry. We present the design of the reactor, the experimental setup, and as a first example for an in situ study, the catalytic partial oxidation of methane showing the applicability of this reactor for in situ studies.

  19. In Situ Remediation Integrated Program, Evaluation and assessment of containment technology

    SciTech Connect (OSTI)

    Gerber, M.A.; Fayer, M.J.

    1994-04-01

    The In Situ Remediation Integrated Program (ISRIP) was established by the US Department of Energy (DOE) to advance the state-of-the art of innovative in situ remediation technologies to the point of demonstration and to broaden the applicability of these technologies to the widely varying site remediation requirements throughout the DOE complex. This program complements similar ongoing integrated demonstration programs being conducted at several DOE sites. The ISRIP has been conducting baseline assessments on in situ technologies to support program planning. Pacific Northwest Laboratory conducted an assessment and evaluation of subsurface containment barrier technology in support of ISRIP`s Containment Technology Subprogram. This report summarizes the results of that activity and provides a recommendation for priortizing areas in which additional research and development is needed to advance the technology to the point of demonstration in support of DOE`s site restoration activities.

  20. Miniaturized multipurpose cell for in situ investigation of sputtered thin films with x-ray techniques

    SciTech Connect (OSTI)

    Luetzenkirchen-Hecht, D.; Bruder, K.; Haake, U.; Keil, P.; Markert, C.; Ringpfeil, C.; Frahm, R.

    2005-07-15

    The design of a miniaturized sputter deposition chamber for the in situ study of thin film growth processes with x rays is reported. X-ray diffraction experiments, grazing incidence x-ray reflectometry, as well as x-ray fluorescence analysis are possible. Due to its compact design and low weight, the chamber can be used in conjunction with conventional x-ray reflectometers and laboratory x-ray diffractometers as well, i.e., very detailed in situ studies of reactive and nonreactive sputtering processes and the resulting film properties are possible. The construction of the chamber is described in detail and first results obtained in situ with different techniques are presented, indicating that experiments that were previously restricted to synchrotron radiation facilities are now possible even with laboratory equipment.

  1. Methods for characterizing subsurface volatile contaminants using in-situ sensors

    DOE Patents [OSTI]

    Ho, Clifford K.

    2006-02-21

    An inverse analysis method for characterizing diffusion of vapor from an underground source of volatile contaminant using data taken by an in-situ sensor. The method uses one-dimensional solutions to the diffusion equation in Cartesian, cylindrical, or spherical coordinates for isotropic and homogenous media. If the effective vapor diffusion coefficient is known, then the distance from the source to the in-situ sensor can be estimated by comparing the shape of the predicted time-dependent vapor concentration response curve to the measured response curve. Alternatively, if the source distance is known, then the effective vapor diffusion coefficient can be estimated using the same inverse analysis method. A triangulation technique can be used with multiple sensors to locate the source in two or three dimensions. The in-situ sensor can contain one or more chemiresistor elements housed in a waterproof enclosure with a gas permeable membrane.

  2. Recycling Of Uranium- And Plutonium-Contaminated Metals From Decommissioning Of The Hanau Fuel Fabrication Plant

    SciTech Connect (OSTI)

    Kluth, T.; Quade, U.; Lederbrink, F. W.

    2003-02-26

    Decommissioning of a nuclear facility comprises not only actual dismantling but also, above all, management of the resulting residual materials and waste. Siemens Decommissioning Projects (DP) in Hanau has been involved in this task since 1995 when the decision was taken to decommission and dismantle the Hanau Fuel Fabrication Plant. Due to the decommissioning, large amounts of contaminated steel scrap have to be managed. The contamination of this metal scrap can be found almost exclusively in the form of surface contamination. Various decontamination technologies are involved, as there are blasting and wiping. Often these methods are not sufficient to meet the free release limits. In these cases, SIEMENS has decided to melt the scrap at Siempelkamp's melting plant. The plant is licensed according to the German Radiation Protection Ordinance Section 7 (issue of 20.07.2001). The furnace is a medium frequency induction type with a load capacity of 3.2 t and a throughput of 2 t/h for steel melting. For safety reasons, the furnace is widely operated by remote handling. A highly efficient filter system of cyclone, bag filter and HEPA-filter in two lines retains the dust and aerosol activity from the off-gas system. The slag is solidified at the surface of the melt and gripped before pouring the liquid iron into a chill. Since 1989, in total 15,000 t have been molten in the plant, 2,000 t of them having been contaminated steel scrap from the decommissioning of fuel fabrication plants. Decontamination factors could be achieved between 80 and 100 by the high affinity of the uranium to the slag former. The activity is transferred to the slag up to nearly 100 %. Samples taken from metal, slag and dust are analyzed by gamma measurements of the 186 keV line of U235 and the 1001 keV line of Pa234m for U238. All produced ingots showed a remaining activity less than 1 Bq/g and could be released for industrial reuse.

  3. 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

  4. An integrated approach to monitoring a field test of in situ contaminant destruction

    SciTech Connect (OSTI)

    Aines, R D; Carrigan, C; Chiarappa, M; Eaker, C; Elsholtz, A; Hudson, G B; Leif, R; Newmark, R L

    1998-12-01

    The development of in situ thermal remediation techniques requires parallel development of techniques capable of monitoring the physical and chemical changes for purposes of process control. Recent research indicates that many common contaminants can be destroyed in situ by hydrous pyrolysis/oxidation (HPO), eliminating the need for costly surface treatment and disposal. Steam injection, combined with supplemental air, can create the conditions in which HP0 occurs. Field testing of this process, conducted in the summer of 1997, indicates rapid destruction of polycyclic aromatic hydrocarbons (PAHs). Previous work established a suite of underground geophysical imaging techniques capable of providing sufficient knowledge of the physical changes in the subsurface during thermal treatment at sufficient frequencies to be used to monitor and guide the heating and extraction processes. In this field test, electrical resistance tomography (ERT) and temperature measurements provided the primary information regarding the temporal and spatial distribution of the heated zones. Verifying the in situ chemical destruction posed new challenges. We developed field methods for sampling and analyzing hot water for contaminants, oxygen, intermediates and products of reaction. Since the addition of air or oxygen to the contaminated region is a critical aspect of HPO, noble gas tracers were used to identify fluids from different sources. The combination of physical monitoring with noble gas identification of the native and injected fluids and accurate fluid sampling resulted in an excellent temporal and spatial evaluation of the subsurface processes, from which the amount of in situ destruction occurring in the treated region could be quantified. The experimental field results constrain the destruction rates throughout the site, and enable site management to make accurate estimates of total in situ destruction based on the recovered carbon. As of October, 1998, over 400,000 kg (900

  5. Preparation of membranes using solvent-less vapor deposition followed by in-situ polymerization

    DOE Patents [OSTI]

    O'Brien, Kevin C.; Letts, Stephan A.; Spadaccini, Christopher M.; Morse, Jeffrey C.; Buckley, Steven R.; Fischer, Larry E.; Wilson, Keith B.

    2012-01-24

    A system of fabricating a composite membrane from a membrane substrate using solvent-less vapor deposition followed by in-situ polymerization. A first monomer and a second monomer are directed into a mixing chamber in a deposition chamber. The first monomer and the second monomer are mixed in the mixing chamber providing a mixed first monomer and second monomer. The mixed first monomer and second monomer are solvent-less vapor deposited onto the membrane substrate in the deposition chamber. The membrane substrate and the mixed first monomer and second monomer are heated to produce in-situ polymerization and provide the composite membrane.

  6. Preparation of membranes using solvent-less vapor deposition followed by in-situ polymerization

    DOE Patents [OSTI]

    O'Brien, Kevin C.; Letts, Stephan A.; Spadaccini, Christopher M.; Morse, Jeffrey C.; Buckley, Steven R.; Fischer, Larry E.; Wilson, Keith B.

    2010-07-13

    A system of fabricating a composite membrane from a membrane substrate using solvent-less vapor deposition followed by in-situ polymerization. A first monomer and a second monomer are directed into a mixing chamber in a deposition chamber. The first monomer and the second monomer are mixed in the mixing chamber providing a mixed first monomer and second monomer. The mixed first monomer and second monomer are solvent-less vapor deposited onto the membrane substrate in the deposition chamber. The membrane substrate and the mixed first monomer and second monomer are heated to produce in-situ polymerization and provide the composite membrane.

  7. ARM - PI Product - In-Situ Microphysics from the MPACE IOP

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

    ProductsIn-Situ Microphysics from the MPACE IOP ARM Data Discovery Browse Data Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send PI Product : In-Situ Microphysics from the MPACE IOP Best estimates of the size distributions of supercooled water droplets and ice crystals for mixed-phase clouds measured during M-PACE for spiral ascents/descents over Barrow and Oliktok Point, and for ramped ascents/descents between Barrow and Oliktok Point. Our best

  8. ARM - PI Product - In-Situ Microphysics from the RACORO IOP

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

    ProductsIn-Situ Microphysics from the RACORO IOP ARM Data Discovery Browse Data Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send PI Product : In-Situ Microphysics from the RACORO IOP These files were generated by Greg McFarquhar and Robert Jackson at the University of Illinois. Please contact mcfarq@atmos.uiuc.edu or rjackso2@atmos.uiuc.edu for more information or for assistance in interpreting the content of these files. We highly recommend that

  9. ARM - Field Campaign - In-situ Aerosol Profiles (Cessna Aerosol Flights)

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

    govCampaignsIn-situ Aerosol Profiles (Cessna Aerosol Flights) ARM Data Discovery Browse Data Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Campaign : In-situ Aerosol Profiles (Cessna Aerosol Flights) 2000.03.01 - 2007.10.31 Lead Scientist : John Ogren Data Availability As of 2007-01, data prior to 2006-01 are now available through the regular ARM archive in datastreams: sgpiapC1.a1 sgpiapavgC1.a1 Current data continues to be delivered to the

  10. ARM - Field Campaign - Surface Observation in Support of in-situ

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

    Observations within the Arctic Boundary Layer govCampaignsSurface Observation in Support of in-situ Observations within the Arctic Boundary Layer ARM Data Discovery Browse Data Related Campaigns Indirect and Semi-Direct Aerosol Campaign (ISDAC) 2008.04.01, Ghan, AAF Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Campaign : Surface Observation in Support of in-situ Observations within the Arctic Boundary Layer 2008.04.01 - 2008.05.31 Lead

  11. In-Situ XANES and EXAFS Analysis of Redox Active Fe Center Ionic Liquids -

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

    Joint Center for Energy Storage Research December 10, 2015, Research Highlights In-Situ XANES and EXAFS Analysis of Redox Active Fe Center Ionic Liquids (Top Left) Cyclic Voltammagram of Fe((OHCH2CH2)2NH)6-(CF3SO3)3 in disk electrode (solid) and in in-situ redox XANES cell (dashed). (Top Right) XANES spectra showing IL in fully oxidized and fully reduced states, showing change in Fe Kα edge on oxidation state change (Bottom) EXAFS data showing position of fully oxidized (Fe+3) state of IL,

  12. Dynamic Underground Stripping: In situ steam sweeping and electrical heating to remediate a deep hydrocarbon spill

    SciTech Connect (OSTI)

    Yow, J.L. Jr.; Aines, R.D.; Newmark, R.L.; Udell, K.S.; Ziagos, J.P.

    1994-07-01

    Dynamic Underground Stripping is a combination of in situ steam injection, electrical resistance heating, and fluid extraction for rapid removal and recovery of subsurface contaminants such as solvents or fuels. Underground imaging and other measurement techniques monitor the system in situ for process control. Field tests at a deep gasoline spill at Lawrence Livermore National Laboratory recovered over 7000 gallons of gasoline during several months of field operations. Preliminary analysis of system cost and performance indicate that Dynamic Underground Stripping compares favorably with conventional pump-and-treat and vacuum extraction schemes for removing non-aqueous phase liquids such as gasoline from deep subsurface plumes.

  13. In Situ X-Ray Scattering Helps Optimize Printed Solar Cells

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

    In Situ X-Ray Scattering Helps Optimize Printed Solar Cells In Situ X-Ray Scattering Helps Optimize Printed Solar Cells Print Wednesday, 25 February 2015 00:00 Plastic solar cells that can be printed on flexible sheets with an ink-like solution show a lot of potential as a source of lightweight, inexpensive renewable energy. However, much of the power-conversion efficiency of such cells gets lost in the translation from small-scale lab studies to large-scale manufacturing processes. To help gain

  14. In Situ and Ex Situ Studies of Platinum Nanocrystals: Growth and Evolution

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

    in Solution In Situ and Ex Situ Studies of Platinum Nanocrystals: Growth and Evolution in Solution figure 1 Figure 1. Time-resolved XRD results obtained for both low and high concentration reactions. (A) In situ XRD plots; the position of the (111) and (200) reflections for bulk fcc platinum is shown by the lines at bottom; (B) time evolution of area under the Pt(111) peak. I - IV denote the growth stages of the high concentration reaction; (C) evolution of X-ray correlation length (L)

  15. In situ 7Li and 133Cs NMR Investigations of the Role of Cs+ Additive in

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

    Lithium-Metal Deposition Processes - Joint Center for Energy Storage Research February 1, 2016, Research Highlights In situ 7Li and 133Cs NMR Investigations of the Role of Cs+ Additive in Lithium-Metal Deposition Processes In situ 7Li NMR spectra from live Li-metal batteries with and without Cs+ additives. At discharge voltage point "C," more microstructured lithium (260 ppm) is recharged back onto the opposite Li electrode to form smoothly deposited Li-metal structures (248 ppm)

  16. In-Situ TEM and DFT Study of Large Cation Transport and Failure Mechanism

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

    In Single SnO2 Nanowire - Joint Center for Energy Storage Research July 18, 2013, Research Highlights In-Situ TEM and DFT Study of Large Cation Transport and Failure Mechanism In Single SnO2 Nanowire (Top)Captured in-situ TEM movie frame showing the pristine SnO2 nanowire, displacement reaction upon Na insertion leads to two phases materials and the corresponding electron diffraction pattern. Upon desodiation, pore forms, leading to high impedence of the electrode. (Bottom) High resolution

  17. Report for in-situ 7Li NMR experiment in PNNL Phase -1

    SciTech Connect (OSTI)

    Hu, Jian Zhi

    2014-08-19

    To understand the detailed local structural evolution, an in-situ 7Li NMR study was performed. An operando identification of the lithium germanide phases under various cycling regimens permitted understanding of the kinetics of phase transition between different structural phases, including the amorphous phases, and how these correlated with capacity retention. Combining data from TEM and in-situ 7Li NMR, we discovered that the phase inter-conversion during cycling was mediated by co-existing amorphous and crystalline phases, and that the high capacity observed was correlated with an over-lithiated lithium germanide phase.

  18. Field demonstration and transition of SCAPS direct push VOC in-situ sensing technologies

    SciTech Connect (OSTI)

    William M. Davis

    1999-11-03

    This project demonstrated two in-situ volatile organic compound (VOC) samplers in combination with the direct sampling ion trap mass spectrometer (DSITMS). The technologies chosen were the Vadose Sparge and the Membrane Interface Probe (MIP) sensing systems. Tests at two demonstration sites showed the newer VOC technologies capable of providing in situ contaminant measurements at two to four times the rate of the previously demonstrated Hydrosparge sensor. The results of this project provide initial results supporting the utility of these new technologies to provide rapid site characterization of VOC contaminants in the subsurface.

  19. Kinetics of visible light photo-oxidation of Ge nanocrystals:Theory and in situ measurement

    SciTech Connect (OSTI)

    Sharp, I.D.; Xu, Q.; Yuan, C.W.; Beeman, J.W.; Ager III, J.W.; Chrzan, D.C.; Haller, E.E.

    2006-11-14

    Photo-oxidation of Ge nanocrystals illuminated with visible laser light under ambient conditions was investigated. The photo-oxidation kinetics were monitored by in situ measurement of the crystalline Ge volume fraction by Raman spectroscopy. The effects of laser power and energy on the extent of oxidation were measured using both in situ and ex situ Raman scattering techniques. A mechanistic model in which the tunneling of photo-excited carriers to the oxide surface for electron activated molecular oxygen dissociation is proposed. This quantitative model successfully describes all experimental photo-oxidation observations using physical parameters.

  20. In Situ Characterizations of New Battery Materials and the Studies of High

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

    Energy Density Li-Air Batteries | Department of Energy In Situ Characterizations of New Battery Materials and the Studies of High Energy Density Li-Air Batteries In Situ Characterizations of New Battery Materials and the Studies of High Energy Density Li-Air Batteries 2010 DOE Vehicle Technologies and Hydrogen Programs Annual Merit Review and Peer Evaluation Meeting, June 7-11, 2010 -- Washington D.C. es059_yang_2010_p.pdf (2.37 MB) More Documents & Publications Characterization of New

  1. A bias assessment for in-situ ultrasonic hardness testing of steel fasteners

    SciTech Connect (OSTI)

    Ratiu, M.D.; Moisidis, N.T.

    1996-12-31

    The problem of sub-standard and/or mismarked installed fasteners has received broad attention in quality control standard and largely discussed in technical publications and in public press. The Industrial Fastener Institute (IFI, 1988) released a detailed documented inspection program to ensure the delivery and the usage of appropriate fasteners, imposing mandatory traceability of the manufacturer marking and quality certification reports. For the billions of the existing installed bolts without reliable lot identification and/or quality certification, IFI recommends in-situ control using non-destructive testing and/or hardness measurements with portable testers. The ultrasonic indentation hardness (HU) with the Krautkramer portable tester--operating on the ultrasonic contact impedance method described by Kleesattel (Jankowski D.M., 1990)--is one of the more frequent equipment used in the in-situ control of steel products and machine elements. The advantages of the ultrasonic tester--low weight, direct hardness reading, easy to operate--have determined to be included also for the in-situ control of installed fasteners. However, the bias of this method was not analyzed; the practiced calibration of standard blocks is not conclusive for the comparison of the in-situ measured hardness with the standard reference value obtained using laboratory Rockwell hardness (HR) tester. The purpose of this paper is to point out the specific consistent/systematic differences between HU results and the reference standard HR, which defines the ruggedness and the bias of the ultrasonic method.

  2. Palladium deuteride formation in the cathode of an electrochemical cell: An in situ neutron diffraction study

    SciTech Connect (OSTI)

    Rotella, F.J.; Richardson, J.W. Jr.; Redey, L.; Felcher, G.P.; Hitterman, R.L.; Kleb, R.

    1991-01-01

    In this report, neutron diffraction of palladium cathodes is utilized to reveal palladium deuteride formation within the crystal structure of the metal. The experiment described in this report demonstrates the efficacy of neutron powder diffraction as a tool for structural studies of metal deuterides/hydrides and the feasibility of in situ diffraction measurements from a working electrochemical cell. (JL)

  3. Palladium deuteride formation in the cathode of an electrochemical cell: An in situ neutron diffraction study

    SciTech Connect (OSTI)

    Rotella, F.J.; Richardson, J.W. Jr.; Redey, L.; Felcher, G.P.; Hitterman, R.L.; Kleb, R.

    1991-12-31

    In this report, neutron diffraction of palladium cathodes is utilized to reveal palladium deuteride formation within the crystal structure of the metal. The experiment described in this report demonstrates the efficacy of neutron powder diffraction as a tool for structural studies of metal deuterides/hydrides and the feasibility of in situ diffraction measurements from a working electrochemical cell. (JL)

  4. In situ heat treatment process utilizing a closed loop heating system

    DOE Patents [OSTI]

    Vinegar, Harold J.; Nguyen, Scott Vinh

    2010-12-07

    Systems and methods for an in situ heat treatment process that utilizes a circulation system to heat one or more treatment areas are described herein. The circulation system may use a heated liquid heat transfer fluid that passes through piping in the formation to transfer heat to the formation. In some embodiments, the piping may be positioned in at least two of the wellbores.

  5. In situ calibration of inductively coupled plasma-atomic emission and mass spectroscopy

    DOE Patents [OSTI]

    Braymen, Steven D.

    1996-06-11

    A method and apparatus for in situ addition calibration of an inductively coupled plasma atomic emission spectrometer or mass spectrometer using a precision gas metering valve to introduce a volatile calibration gas of an element of interest directly into an aerosol particle stream. The present situ calibration technique is suitable for various remote, on-site sampling systems such as laser ablation or nebulization.

  6. Method for initiating in-situ vitrification using an impregnated cord

    DOE Patents [OSTI]

    Carter, John G.

    1991-01-01

    In-situ vitrification of soil is initiated by placing a cord of dielectric material impregnated with conductive material in thermally-conductive contact with the soil, and energizing the cord with an electric current for heating the cord and starting the vitrification process.

  7. Method for initiating in-situ vitrification using an impregnated cord

    DOE Patents [OSTI]

    Carter, J.G.

    1991-04-02

    In-situ vitrification of soil is initiated by placing a cord of dielectric material impregnated with conductive material in thermally-conductive contact with the soil, and energizing the cord with an electric current for heating the cord and starting the vitrification process. 1 figure.

  8. Experimental Investigation and High Resolution Simulator of In-Situ Combustion Processes

    SciTech Connect (OSTI)

    Margot Gerritsen; Anthony Kovscek

    2007-03-31

    Accurate simulation of in-situ combustion processes is computationally very challenging because the spatial and temporal scales over which the combustion process takes place are very small. In this current and fourteenth report, we report on our continued numerical experimentation with the Virtual Kinetic Cell and our continuing experimental program.

  9. Quantitative Imaging and In Situ Concentration Measurements of Quantum Dot Nanomaterials in Variably Saturated Porous Media

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Uyuşur, Burcu; Snee, Preston T.; Li, Chunyan; Darnault, Christophe J. G.

    2016-01-01

    Knowledge of the fate and transport of nanoparticles in the subsurface environment is limited, as techniques to monitor and visualize the transport and distribution of nanoparticles in porous media and measure their in situ concentrations are lacking. To address these issues, we have developed a light transmission and fluorescence method to visualize and measure in situ concentrations of quantum dot (QD) nanoparticles in variably saturated environments. Calibration cells filled with sand as porous medium and various known water saturation levels and QD concentrations were prepared. By measuring the intensity of the light transmitted through porous media exposed to fluorescent lightmore » and by measuring the hue of the light emitted by the QDs under UV light exposure, we obtained simultaneously in situ measurements of water saturation and QD nanoparticle concentrations with high spatial and temporal resolutions. Water saturation was directly proportional to the light intensity. A linear relationship was observed between hue-intensity ratio values and QD concentrations for constant water saturation levels. The advantages and limitations of the light transmission and fluorescence method as well as its implications for visualizing and measuring in situ concentrations of QDs nanoparticles in the subsurface environment are discussed.« less

  10. Proceedings: In Situ Contaminated Sediment Capping Workshop: Cincinnati, Ohio, May 12-14, 2003

    SciTech Connect (OSTI)

    2004-03-01

    The In Situ Contaminated Sediment Capping Workshop was designed to provide the most current information and bring about consensus in understanding of a technology that offers one of the few options for remediation of contaminated sediments. These electronic proceedings document workshop sessions on various capping issues, such as site assessment; cap suitability, performance, and design; site monitoring; and research and development in capping.

  11. In situ growth of copper nanocrystals from carbonaceous microspheres with electrochemical glucose sensing properties

    SciTech Connect (OSTI)

    Zhou, Xiaoliang; Yan, Zhengguang Han, Xiaodong

    2014-02-01

    Graphical abstract: In situ growth of copper nanoparticles from hydrothermal copper-containing carbonaceous microspheres was induced by annealing or electron beam irradiation. Obtained micro-nano carbon/copper composite microspheres show electrochemical glucose sensing properties. - Highlights: • We synthesized carbonaceous microspheres containing non-nanoparicle copper species through a hydrothermal route. • By annealing or electron beam irradiation, copper nanoparticles would form from the carbonaceous microspheres in situ. • By controlling the annealing temperature, particle size of copper could be controlled in the range of 50–500 nm. • The annealed carbon/copper hierarchical composite microspheres were used to fabricate an electrochemical glucose sensor. - Abstract: In situ growth of copper nanocrystals from carbon/copper microspheres was observed in a well-controlled annealing or an electron beam irradiation process. Carbonaceous microspheres containing copper species with a smooth appearance were yielded by a hydrothermal synthesis using copper nitrate and ascorbic acid as reactants. When annealing the carbonaceous microspheres under inert atmosphere, copper nanoparticles were formed on carbon microspheres and the copper particle sizes can be increased to a range of 50–500 nm by altering the heating temperature. Similarly, in situ formation of copper nanocrystals from these carbonaceous microspheres was observed on the hydrothermal product carbonaceous microspheres with electron beam irradiation in a vacuum transmission electron microscopy chamber. The carbon/copper composite microspheres obtained through annealing were used to modify a glassy carbon electrode and tested as an electrochemical glucose sensor.

  12. Evaluation of solvent-based in situ processes for upgrading and recovery of heavy oil bitumen

    SciTech Connect (OSTI)

    Duerksen, J.H.; Eloyan, A.

    1995-12-31

    Solvent-based in situ recovery processes have been proposed as lower cost alternatives to thermal processes for recovery of heavy oil and bitumen. Advantages of solvent based processes are: reduced steam requirements, reduced water treating, and in situ upgrading of the produced oil. Lab results and process calculations show that low-pressure, low-energy solvent-based in situ processes have considerable technical and economic potential for upgrading and recovery of bitumen and heavy oil. In a lab flow test using Athabasca tar sand and propane as solvent, 50 percent of the bitumen was recovered as upgraded oil. Relative to the raw bitumen, API gravity increased by about 10{degrees}API, viscosity was reduced 30-fold, sulfur content was reduced about 50 percent, and metals content was also substantially reduced. Process uncertainties that will have a major impact on economics are: (1) oil production rate, (2) oil recovery, (3) extent of in situ upgrading, and (4) solvent losses. Additional lab development and field testing are required to reduce these process uncertainties and to predict commercial-scale economics.

  13. BUILDING LATE-TYPE SPIRAL GALAXIES BY IN-SITU AND EX-SITU STAR FORMATION

    SciTech Connect (OSTI)

    Pillepich, Annalisa; Madau, Piero; Mayer, Lucio

    2015-02-01

    We analyze the formation and evolution of the stellar components in ''Eris'', a 120pc resolution cosmological hydrodynamic simulation of a late-type spiral galaxy. The simulation includes the effects of a uniform UV background, a delayed-radiative-cooling scheme for supernova feedback, and a star formation recipe based on a high gas density threshold. It allows a detailed study of the relative contributions of ''in-situ'' (within the main host) and ''ex-situ'' (within satellite galaxies) star formation to each major Galactic component in a close Milky Way analog. We investigate these two star-formation channels as a function of galactocentric distance, along different lines of sight above and along the disk plane, and as a function of cosmic time. We find that: (1) approximately 70% of today's stars formed in-situ; (2) more than two thirds of the ex-situ stars formed within satellites after infall; (3) the majority of ex-situ stars are found today in the disk and in the bulge; (4) the stellar halo is dominated by ex-situ stars, whereas in-situ stars dominate the mass profile at distances ? 5 kpc from the center at high latitudes; and (5) approximately 25% of the inner, r ? 20 kpc, halo is composed of in-situ stars that have been displaced from their original birth sites during Eris' early assembly history.

  14. INTERACTIONS BETWEEN CORONAL MASS EJECTIONS VIEWED IN COORDINATED IMAGING AND IN SITU OBSERVATIONS

    SciTech Connect (OSTI)

    Liu, Ying D.; Luhmann, Janet G.; Moestl, Christian; Martinez-Oliveros, Juan C.; Bale, Stuart D.; Lin, Robert P.; Harrison, Richard A.; Temmer, Manuela; Webb, David F.; Odstrcil, Dusan

    2012-02-20

    The successive coronal mass ejections (CMEs) from 2010 July 30 to August 1 present us the first opportunity to study CME-CME interactions with unprecedented heliospheric imaging and in situ observations from multiple vantage points. We describe two cases of CME interactions: merging of two CMEs launched close in time and overtaking of a preceding CME by a shock wave. The first two CMEs on August 1 interact close to the Sun and form a merged front, which then overtakes the July 30 CME near 1 AU, as revealed by wide-angle imaging observations. Connections between imaging observations and in situ signatures at 1 AU suggest that the merged front is a shock wave, followed by two ejecta observed at Wind which seem to have already merged. In situ measurements show that the CME from July 30 is being overtaken by the shock at 1 AU and is significantly compressed, accelerated, and heated. The interaction between the preceding ejecta and shock also results in variations in the shock strength and structure on a global scale, as shown by widely separated in situ measurements from Wind and STEREO B. These results indicate important implications of CME-CME interactions for shock propagation, particle acceleration, and space weather forecasting.

  15. Engineering Evaluation/Cost Analysis (EE/CA) for Decommissioning of TAN-607 Hot Shop Area

    SciTech Connect (OSTI)

    J. P. Floerke

    2007-02-05

    Test Area North (TAN) -607, the Technical Support Facility, is located at the north end of the Idaho National Laboratory (INL) Site. U.S. Department of Energy Idaho Operations Office (DOE-ID) is proposing to decommission the northern section of the TAN-607 facility, hereinafter referred to as TAN-607 Hot Shop Area, under a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) non-time-critical removal action (NTCRA). Despite significant efforts by the United States (U.S.) Department of Energy (DOE) to secure new business, no future mission has been identified for the TAN-607 Hot Shop Area. Its disposition has been agreed to by the Idaho State Historical Preservation Office documented in the Memorandum of Agreement signed October 2005 and it is therefore considered a surplus facility. A key element in DOE's strategy for surplus facilities is decommissioning to the maximum extent possible to ensure risk and building footprint reduction and thereby eliminating operations and maintenance cost. In addition, the DOE's 2006 Strategic Plan is ''complete cleanup of the contaminated nuclear weapons manufacturing and testing sites across the United States. DOE is responsible for the risk reduction and cleanup of the environmental legacy of the Nation's nuclear weapons program, one of the largest, most diverse, and technically complex environmental programs in the world. The Department will successfully achieve this strategic goal by ensuring the safety of the DOE employees and U.S. citizens, acquiring the best resources to complete the complex tasks, and managing projects throughout the United States in the most efficient and effective manner.'' TAN-607 is designated as a historical Signature Property by DOE Headquarters Advisory Council on Historic Preservation and, as such, public participation is required to determine the final disposition of the facility. The decommissioning action will place the TAN-607 Hot Shop Area in a final configuration that

  16. Revised analyses of decommissioning for the reference pressurized 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, Volume 1, 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, 1988), 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 {prime}978 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.

  17. 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.

  18. EM-54 Technology Development In Situ Remediation Integrated Program. Annual report

    SciTech Connect (OSTI)

    Not Available

    1993-08-01

    The Department of Energy (DOE) established the Office of Technology Development (EM-50) as an element of Environmental Restoration and Waste Management (EM) in November 1989. EM manages remediation of all DOE sites as well as wastes from current operations. The goal of the EM program is to minimize risks to human health, safety and the environment, and to bring all DOE sites into compliance with Federal, state, and local regulations by 2019. EM-50 is charged with developing new technologies that are safer, more effective and less expensive than current methods. The In Situ Remediation Integrated Program (the subject of this report) is part of EM-541, the Environmental Restoration Research and Development Division of EM-54. The In Situ Remediation Integrated Program (ISR IP) was instituted out of recognition that in situ remediation could fulfill three important criteria: Significant cost reduction of cleanup by eliminating or minimizing excavation, transportation, and disposal of wastes; reduced health impacts on workers and the public by minimizing exposure to wastes during excavation and processing; and remediation of inaccessible sites, including: deep subsurfaces; in, under, and around buildings. Buried waste, contaminated soils and groundwater, and containerized wastes are all candidates for in situ remediation. Contaminants include radioactive wastes, volatile and non-volatile organics, heavy metals, nitrates, and explosive materials. The ISR IP tends to facilitate development of in situ remediation technologies for hazardous, radioactive, and mixed wastes in soils, groundwater, and storage tanks. Near-term focus is on containment of the wastes, with treatment receiving greater effort in future years.

  19. 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.

  20. 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.

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. Decommissioning the Fuel Process Building, a Shift in Paradigm for Terminating Safeguards on Process Holdup

    SciTech Connect (OSTI)

    Ivan R. Thomas

    2010-07-01

    INMM Abstract 51st Annual Meeting Decommissioning the Fuel Process Building, a Shift in Paradigm for Terminating Safeguards on Process Holdup The Fuel Process Building at the Idaho Nuclear Technology and Engineering Center (INTEC) is being decommissioned after nearly four decades of recovering high enriched uranium from various government owned spent nuclear fuels. The separations process began with fuel dissolution in one of multiple head-ends, followed by three cycles of uranium solvent extraction, and ending with denitration of uranyl nitrate product. The entire process was very complex, and the associated equipment formed an extensive maze of vessels, pumps, piping, and instrumentation within several layers of operating corridors and process cells. Despite formal flushing and cleanout procedures, an accurate accounting for the residual uranium held up in process equipment over extended years of operation, presented a daunting safeguards challenge. Upon cessation of domestic reprocessing, the holdup remained inaccessible and was exempt from measurement during ensuing physical inventories. In decommissioning the Fuel Process Building, the Idaho Cleanup Project, which operates the INTEC, deviated from the established requirements that all nuclear material holdup be measured and credited to the accountability books and that all nuclear materials, except attractiveness level E residual holdup, be transferred to another facility. Instead, the decommissioning involved grouting the process equipment in place, rather than measuring and removing the contained holdup for subsequent transfer. The grouting made the potentially attractiveness level C and D holdup even more inaccessible, thereby effectually converting the holdup to attractiveness level E and allowing for termination of safeguards controls. Prior to grouting the facility, the residual holdup was estimated by limited sampling and destructive analysis of solutions in process lines and by acceptable knowledge

  6. 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

  7. 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.

  8. Evaluation of In Situ Grouting as a Potential Remediation Method for the Hanford Central Plateau Deep Vadose Zone

    SciTech Connect (OSTI)

    Truex, Michael J.; Pierce, Eric M.; Nimmons, Michael J.; Mattigod, Shas V.

    2011-01-11

    The Deep Vadose Zone Treatability Test Plan for the Hanford Central Plateau report identifies in situ grouting as a potential remediation technology for the deep vadose zone and includes a planned effort to evaluate in situ grouting to provide information for future feasibility studies. This report represents the first step in this evaluation effort.

  9. 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.

  10. In-Situ Measurements of Low Enrichment Uranium Holdup Process Gas Piping at K-25 - Paper for Waste Management Symposia 2010 East Tennessee Technology Park Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    Rasmussen B.

    2010-01-01

    This document is the final version of a paper submitted to the Waste Management Symposia, Phoenix, 2010, abstract BJC/OR-3280. The primary document from which this paper was condensed is In-Situ Measurement of Low Enrichment Uranium Holdup in Process Gas Piping at K-25 Using NaI/HMS4 Gamma Detection Systems, BJC/OR-3355. This work explores the sufficiency and limitations of the Holdup Measurement System 4 (HJVIS4) software algorithms applied to measurements of low enriched uranium holdup in gaseous diffusion process gas piping. HMS4 has been used extensively during the decommissioning and demolition project of the K-25 building for U-235 holdup quantification. The HMS4 software is an integral part of one of the primary nondestructive assay (NDA) systems which was successfully tested and qualified for holdup deposit quantification in the process gas piping of the K-25 building. The initial qualification focused on the measurement of highly enriched UO{sub 2}F{sub 2} deposits. The purpose of this work was to determine if that qualification could be extended to include the quantification of holdup in UO{sub 2}F{sub 2} deposits of lower enrichment. Sample field data are presented to provide evidence in support of the theoretical foundation. The HMS4 algorithms were investigated in detail and found to sufficiently compensate for UO{sub 2}F{sub 2} source self-attenuation effects, over the range of expected enrichment (4-40%), in the North and East Wings of the K-25 building. The limitations of the HMS4 algorithms were explored for a described set of conditions with respect to area source measurements of low enriched UO{sub 2}F{sub 2} deposits when used in conjunction with a 1 inch by 1/2 inch sodium iodide (NaI) scintillation detector. The theoretical limitations of HMS4, based on the expected conditions in the process gas system of the K-25 building, are related back to the required data quality objectives (DQO) for the NBA measurement system established for the K-25

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  16. 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.

  17. 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.

  18. 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

  19. 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

  20. Understanding catalyst behavior during in situ heating through simultaneous secondary and transmitted electron imaging

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Howe, Jane Y.; Allard, Jr., Lawrence Frederick; Demers, Hendrix; Bigelow, Wilbur C.; Steven H. Overbury

    2014-11-14

    In situ heating study via a simultaneous secondary electron (SE) and transmitted electron (TE) microscopy is extremely insightful because information from the surface (SE) and bulk (TE) can be readily obtained. The leached Au/Fe2O3 catalyst has voids on the surface of Fe2O3. Upon heating to 500 °C, voids shrank and disappeared, while internal Au species diffused to the surface to form new nanoparticles. Heating in vacuum reduced Fe2O3 to Fe3O4. Heating at 700 °C caused coalescence and growth of Au particles and formation of faceted Fe3O4 surfaces. We achieved 1.1 nm resolution in SE imaging during in situ heating.