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Sample records for test facility project

  1. Fast Flux Test Facility Closure Project - Project Management Plan

    SciTech Connect (OSTI)

    BEACH, R.R.

    2002-09-26

    The Fast Flux Test Facility (FFTF) Closure Project, Project Management Plan, Revision 5, provides the scope, cost, and schedule to achieve the most cost effective and expeditious closure of the FFTF to an assumed final end-state with the reactor vessel and the containment building, below the 5504 grade level, being entombed in place. Closure will be completed by December 2009 at a cost of $547 million.

  2. Project Profile: National Solar Thermal Test Facility

    Broader source: Energy.gov [DOE]

    The first solar receivers ever tested in the world were tested at the National Solar Thermal Test Facility (NSTTF). The receivers were each rated up to 5 megawatts thermal (MWt). Receivers with various working fluids have been tested here over the years, including air, water-steam, molten salt, liquid sodium, and solid particles. The NSTTF has also been used for a large variety of other tests, including materials tests, simulation of thermal nuclear pulses and aerodynamic heating, and ablator testing for NASA.

  3. Fast Flux Test Facility project plan. Revision 2

    SciTech Connect (OSTI)

    Hulvey, R.K.

    1995-11-01

    The Fast Flux Test Facility (FFTF) Transition Project Plan, Revision 2, provides changes to the major elements and project baseline for the deactivation activities necessary to transition the FFTF to a radiologically and industrially safe shutdown condition.

  4. Fast flux test facility, transition project plan

    SciTech Connect (OSTI)

    Guttenberg, S.

    1994-11-15

    The FFTF Transition Project Plan, Revision 1, provides changes and project baseline for the deactivation activities necessary to transition the FFTF to a radiologically and industrially safe shutdown condition.

  5. EA-1917: Wave Energy Test Facility Project, Newport, OR

    Broader source: Energy.gov [DOE]

    This EA will evaluate the potential environmental impacts of a Wave Energy Test Facility that will be located near Newport, Oregon. The testing facility will be located within Oregon territorial waters, near the Hatfield Marine Science Center and close to onshore roads and marine support services. The site will not only allow testing of new wave energy technologies, but will also be used to help study any potential environmental impacts on sediments, invertebrates and fish. The project is being jointly funded by the State of Oregon and DOE.

  6. Fast Flux Test Facility transition project resource loaded schedule. Revision 1

    SciTech Connect (OSTI)

    Hulvey, R.K.

    1994-10-31

    Revision 1 of the Fast Flux Test Facility (FFTF) Transition Project Resource Loaded Schedule (RLS) provides detail to manage the major elements, project baseline and cost estimate for the FFF Transition Project within the Advanced Reactors Transition Program, comprised of Activity Data Sheets (ADS) 6640, 6641, and 6642. The scope includes all work in the Budget and Reporting categories of Program Integration (PI), Surveillance and Maintenance (S and M), and Deactivation/Compliance (D/C). The transition activities are necessary to bring the FFTF and related facilities to a safe deactivation state, while maintaining worker health and safety. The scope of ADS 6640 and 6642 is the FFTF Transition Project while the scope of ADS 6641 is the Hanford Site Nuclear Energy Legacies.

  7. SLAC Accelerator Test Facilities

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

    FACET & TF Careers & Education Archived FACET User Facility Quick Launch About FACET & Test Facilities Expand About FACET & Test Facilities FACET & Test Facilities User Portal...

  8. Healy Clean Coal Project: Healy coal firing at TRW Cleveland Test Facility. Final report

    SciTech Connect (OSTI)

    Koyama, T.; Petrill, E.; Sheppard, D.

    1991-08-01

    A test burn of two Alaskan coals was conducted at TRW`s Cleveland test facility in support of the Healy Clean Coal Project, as part of Clean Coal Technology III Program in which a new power plant will be constructed using a TRW Coal Combustion System. This system features ash slagging technology combined with NO{sub x} and SO{sub x} control. The tests, funded by the Alaska Industrial Development and Export Authority (AIDEA) and TRW, were conducted to verify that the candidate Healy station coals could be successfully fired in the TRW coal combustor, to provide data required for scale-up to the utility project size requirements, and to produce sufficient flash-calcined material (FCM) for spray dryer tests to be conducted by Joy/NIRO. The tests demonstrated that both coals are viable candidates for the project, provided the data required for scale-up, and produced the FCM material. This report describes the modifications to the test facility which were required for the test burn, the tests run, and the results of the tests.

  9. Healy Clean Coal Project: Healy coal firing at TRW Cleveland Test Facility

    SciTech Connect (OSTI)

    Koyama, T.; Petrill, E.; Sheppard, D.

    1991-08-01

    A test burn of two Alaskan coals was conducted at TRW's Cleveland test facility in support of the Healy Clean Coal Project, as part of Clean Coal Technology III Program in which a new power plant will be constructed using a TRW Coal Combustion System. This system features ash slagging technology combined with NO{sub x} and SO{sub x} control. The tests, funded by the Alaska Industrial Development and Export Authority (AIDEA) and TRW, were conducted to verify that the candidate Healy station coals could be successfully fired in the TRW coal combustor, to provide data required for scale-up to the utility project size requirements, and to produce sufficient flash-calcined material (FCM) for spray dryer tests to be conducted by Joy/NIRO. The tests demonstrated that both coals are viable candidates for the project, provided the data required for scale-up, and produced the FCM material. This report describes the modifications to the test facility which were required for the test burn, the tests run, and the results of the tests.

  10. Conceptual Design Report: Nevada Test Site Mixed Waste Disposal Facility Project

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2009-01-31

    Environmental cleanup of contaminated nuclear weapons manufacturing and test sites generates radioactive waste that must be disposed. Site cleanup activities throughout the U.S. Department of Energy (DOE) complex are projected to continue through 2050. Some of this waste is mixed waste (MW), containing both hazardous and radioactive components. In addition, there is a need for MW disposal from other mission activities. The Waste Management Programmatic Environmental Impact Statement Record of Decision designates the Nevada Test Site (NTS) as a regional MW disposal site. The NTS has a facility that is permitted to dispose of onsite- and offsite-generated MW until November 30, 2010. There is not a DOE waste management facility that is currently permitted to dispose of offsite-generated MW after 2010, jeopardizing the DOE environmental cleanup mission and other MW-generating mission-related activities. A mission needs document (CD-0) has been prepared for a newly permitted MW disposal facility at the NTS that would provide the needed capability to support DOE's environmental cleanup mission and other MW-generating mission-related activities. This report presents a conceptual engineering design for a MW facility that is fully compliant with Resource Conservation and Recovery Act (RCRA) and DOE O 435.1, 'Radioactive Waste Management'. The facility, which will be located within the Area 5 Radioactive Waste Management Site (RWMS) at the NTS, will provide an approximately 20,000-cubic yard waste disposal capacity. The facility will be licensed by the Nevada Division of Environmental Protection (NDEP).

  11. Advanced Wind Energy Projects Test Facility Moving to Texas Tech University

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Department of Energy (DOE) Sandia National Laboratories (SNL) is moving its wind energy test facility to a new location near the campus of Texas Tech University in Lubbock, Texas.

  12. Cold Test Facility - Hanford Site

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

    Projects & Facilities Cold Test Facility About Us About Hanford Cleanup Hanford History Hanford Site Wide Programs Contact Us 100 Area 118-K-1 Burial Ground 200 Area 222-S Laboratory 242-A Evaporator 300 Area 324 Building 325 Building 400 Area/Fast Flux Test Facility 618-10 and 618-11 Burial Grounds 700 Area B Plant B Reactor C Reactor Canister Storage Building and Interim Storage Area Canyon Facilities Cold Test Facility D and DR Reactors Effluent Treatment Facility Environmental

  13. Waste Tank Size Determination for the Hanford River Protection Project Cold Test, Training, and Mockup Facility

    SciTech Connect (OSTI)

    Onishi, Yasuo; Wells, Beric E.; Kuhn, William L.

    2001-03-30

    The objective of the study was to determine the minimum tank size for the Cold Test Facility process testing of Hanford tank waste. This facility would support retrieval of waste in 75-ft-diameter DSTs with mixer pumps and SSTs with fluidic mixers. The cold test model will use full-scale mixer pumps, transfer pumps, and equipment with simulated waste. The study evaluated the acceptability of data for a range of tank diameters and depths and included identifying how the test data would be extrapolated to predict results for a full-size tank.

  14. Interim reclamation report, Basalt Waste Isolation Project Near Surface Test Facility 1990

    SciTech Connect (OSTI)

    Brandt, C.A.; Rickard, W.H. Jr.; Hefty, M.G.; Cadoret, N.A.

    1991-01-01

    This report describes the development of the reclamation project for the Hanford Site Near Surface Test Facility (NSTF), its implementation, and preliminary estimates of its success. The goal of the reclamation project is to return disturbed sites as nearly as practicable to their original conditions using native species. Gable Mountain is dominated by two plant communities: a big sagebrush (Artemisia tridentata) -- Sandberg's bluegrass (Poa sandbergii) community and a stiff sagebrush (Artemisia rigida) -- Sandberg's bluegrass community. Disassembly of the site installations began on March 15, 1988, and the site was returned to original contours by December 12, 1988. Two separate revegetation methods were employed at the NSTF to meet differing site constraints. Vegetative cover and density in the revegetation plots were assessed in April 1989 and again in June 1989 and 1990. It is extremely unlikely that the sand pit, borrow pit, box cuts, generator pad area, or ventilation fan area will reach the reclamation objectives set for these areas within the next 50 years without further intervention. These areas currently support few living plants. Vegetation on revegetated native soils appears to be growing as expected. Vegetation growth on the main waterline is well below the objective. To date, no shrubs have grown on the area, growth of native grasses is well below the objective, and much of the area has been covered with the pit run material, which may not support adequate growth. Without further treatments, the areas without the pit run material will likely revert to a nearly pure cheatgrass condition. 44 refs., 13 figs., 7 tabs.

  15. Projects & Facilities - Hanford Site

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

    300 Area 324 Building 325 Building 400 AreaFast Flux Test Facility 618-10 and 618-11 Burial Grounds 700 Area B Plant B Reactor C Reactor Canister Storage Building Canyon ...

  16. Lighting Test Facilities

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

    Lighting-Test-Facilities Sign In About | Careers | Contact | Investors | bpa.gov Search Policy & Reporting Expand Policy & Reporting EE Sectors Expand EE Sectors Technology &...

  17. ORP Projects & Facilities - Hanford Site

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

    Facilities Office of River Protection About ORP ORP Projects & Facilities Tank Farms Waste Treatment & Immobilization Plant 222-S Laboratory 242-A Evaporator Newsroom Contracts &...

  18. Kauai Test Facility

    SciTech Connect (OSTI)

    Hay, R.G.

    1982-01-01

    The Kauai Test Facility (KTF) is a Department of Energy rocket launch facility operated by Sandia National Laboratories. Originally it was constructed in support of the high altitude atmospheric nuclear test phase of operation Dominic in the early 1960's. Later, the facility went through extensive improvement and modernization to become an integral part of the Safeguard C readiness to resume nuclear testing program. Since its inception and build up, in the decade of the sixties and the subsequent upgrades of the seventies, range test activities have shifted from full scale test to emphasis on research and development of materials and components, and to making high altitude scientific measurements. Primarily, the facility is intended to be utilized in support of development programs at the DOE weapons laboratories, however, other organizations may make use of the facility on a non-interface basis. The physical components at KTF and their operation are described.

  19. Manhattan Project Signature Facilities | Department of Energy

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

    Manhattan Project » Manhattan Project Signature Facilities Manhattan Project Signature Facilities The "Gadget" device fully assembled atop the 100-foot firing tower, shortly before the Trinity test. July 15, 1945. The "Gadget" device fully assembled atop the 100-foot firing tower, shortly before the Trinity test. July 15, 1945. New! Manhattan Project National Historical Park New! K-25 Virtual Museum The Department of Energy, in the mid-1990s, developed a list of eight

  20. Hydrodynamic Testing Facilities Database | Open Energy Information

    Open Energy Info (EERE)

    Hydrodynamic Testing Facilities Database (Redirected from Hydrodynamic Testing Facilities) Jump to: navigation, search Facility Operators By viewing Hydrodynamic Testing Facilities...

  1. EERC pilot-scale CFBC evaluation facility Project CFB test results. Topical report, Task 7.30

    SciTech Connect (OSTI)

    Mann, M.D.; Hajicek, D.R.; Henderson, A.K.; Moe, T.A.

    1992-09-01

    Project CFB was initiated at the University of North Dakota Energy and Environmental Research Center (EERC) in May 1988. Specific goals of the project were to (1) construct a circulating fluidized-bed combustor (CFBC) facility representative of the major boiler vendors` designs with the capability of producing scalable data, (2) develop a database for use in making future evaluations of CFBC technology, and (3) provide a facility for evaluating fuels, free of vendor bias for use in the - energy industry. Five coals were test-burned in the 1-MWth unit: North Dakota and Asian lignites, a Wyoming subbituminous, and Colorado and Pennsylvania bituminous coats. A total of 54 steady-state test periods were conducted, with the key test parameters being the average combustor temperature, excess air, superficial gas velocity, calcium-to-sulfur molar ratio, and the primary air-to-secondary air split. The capture for a coal fired in a CFBC is primarily dependent upon the total alkali-to-sulfur ratio. The required alkali-to ratio for 90% sulfur retention ranged from 1.4 to 4.9, depending upon coal type. While an alkali-to-ratio of 4.9 was required to meet 90% sulfur retention for the Salt Creek coal versus 1.4 for the Asian lignite, the total amount of sorbent addition required is much less for the Salt Creek coal, 4.2 pound sorbent per million Btu coal input, versus 62 pound/million Btu for the Asian lignite. The bituminous coals tested show optimal capture at combustor temperatures of approximately 1550{degree}F, with low-rank coals having optimal sulfur capture approximately 100{degree}F lower.

  2. Central Receiver Test Facility

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

    Receiver Test Facility - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced

  3. Irradiation Test Plan for the ATR National Scientific User Facility - University of Wisconsin Pilot Project

    SciTech Connect (OSTI)

    Heather J. MacLean; Kumar Sridharan; Timothy A. Hyde

    2008-06-01

    The performance of advanced nuclear systems critically relies on the performance of the materials used for cladding, duct, and other structural components. In many proposed advanced systems, the reactor design pushes the temperature and the total radiation dose higher than typically seen in a light water reactor. Understanding the stability of these materials under radiation is critical. There are a large number of materials or material systems that have been developed for greater high temperature or high dose performance for which little or no information on radiation response exists. The goal of this experiment is to provide initial data on the radiation response of these materials. The objective of the UW experiment is to irradiate materials of interest for advanced reactor applications at a variety of temperatures (nominally 300°C, 400°C, 500°C, and 700°C) and total dose accumulations (nominally 3 dpa and 6 dpa). Insertion of this irradiation test is proposed for September 2008 (ATR Cycle 143A).

  4. Canastota Renewable Energy Facility Project

    SciTech Connect (OSTI)

    Blake, Jillian; Hunt, Allen

    2013-12-13

    The project was implemented at the Madison County Landfill located in the Town of Lincoln, Madison County, New York. Madison County has owned and operated the solid waste and recycling facilities at the Buyea Road site since 1974. At the onset of the project, the County owned and operated facilities there to include three separate landfills, a residential solid waste disposal and recycled material drop-off facility, a recycling facility and associated administrative, support and environmental control facilities. This putrescible waste undergoes anaerobic decomposition within the waste mass and generates landfill gas, which is approximately 50% methane. In order to recover this gas, the landfill was equipped with gas collection systems on both the east and west sides of Buyea Road which bring the gas to a central point for destruction. In order to derive a beneficial use from the collected landfill gases, the County decided to issue a Request for Proposals (RFP) for the future use of the generated gas.

  5. Recovery Act Workers Demolish Facility Tied to Project Pluto History |

    Office of Environmental Management (EM)

    Department of Energy Demolish Facility Tied to Project Pluto History Recovery Act Workers Demolish Facility Tied to Project Pluto History Workers recently razed a facility used in the historic Project Pluto, the latest American Recovery and Reinvestment Act accomplishment helping clean up traces of past nuclear testing at the Nevada National Security Site (NNSS). Recovery Act workers safely hauled the last demolition waste from the Pluto Disassembly Facility to disposal facilities Jan. 11.

  6. Geothermal Testing Facilities in an Oil Field

    Broader source: Energy.gov [DOE]

    Engineered Geothermal Systems, Low Temp, Exploration Demonstration. The proposed project is to develop a long term testing facility and test geothermal power units for the evaluation of electrical power generation from low-temperature and co-produced fluids. The facility will provide the ability to conduct both long and short term testing of different power generation configurations to determine reliability, efficiency and to provide economic evaluation data.

  7. Lead Coolant Test Facility Development Workshop

    SciTech Connect (OSTI)

    Paul A. Demkowicz

    2005-06-01

    A workshop was held at the Idaho National Laboratory on May 25, 2005, to discuss the development of a next generation lead or lead-alloy coolant test facility. Attendees included representatives from the Generation IV lead-cooled fast reactor (LFR) program, Advanced Fuel Cycle Initiative, and several universities. Several participants gave presentations on coolant technology, existing experimental facilities for lead and lead-alloy research, the current LFR design concept, and a design by Argonne National Laboratory for an integral heavy liquid metal test facility. Discussions were focused on the critical research and development requirements for deployment of an LFR demonstration test reactor, the experimental scope of the proposed coolant test facility, a review of the Argonne National Laboratory test facility design, and a brief assessment of the necessary path forward and schedule for the initial stages of this development project. This report provides a summary of the presentations and roundtable discussions.

  8. Test and User Facilities | NREL

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

    Test and User Facilities Our test and user facilities are available to industry and other organizations for researching, developing, and evaluating energy technologies. We can work with you to design the tests and operate the equipment. A | B | C | D | E | F | G | H | I | J | K | L | M | N | O | P | Q | R | S | T | U | V | W | X | Y | Z A Advanced Research Turbines B Battery Thermal and Life Test Facility Biochemical Conversion Pilot Plant C Controllable Grid Interface Test System D Distributed

  9. Hydrodynamic Testing Facilities Database | Open Energy Information

    Open Energy Info (EERE)

    Hydrodynamic Testing Facilities Database Jump to: navigation, search Facility Operators By viewing Hydrodynamic Testing Facilities in the list accompanying the map, one will be...

  10. Renewable Energy Projects at Federal Facilities | Department...

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

    Federal Energy Management Program (FEMP) tracks the following examples of renewable energy projects at federal facilities. To find a federal renewable energy project, browse the ...

  11. Central Receiver Test Facility

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

    Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel ... SubTER Carbon Sequestration Program Leadership EnergyWater Nexus EnergyWater History ...

  12. Massachusetts Large Blade Test Facility Final Report

    SciTech Connect (OSTI)

    Rahul Yarala; Rob Priore

    2011-09-02

    Project Objective: The Massachusetts Clean Energy Center (CEC) will design, construct, and ultimately have responsibility for the operation of the Large Wind Turbine Blade Test Facility, which is an advanced blade testing facility capable of testing wind turbine blades up to at least 90 meters in length on three test stands. Background: Wind turbine blade testing is required to meet international design standards, and is a critical factor in maintaining high levels of reliability and mitigating the technical and financial risk of deploying massproduced wind turbine models. Testing is also needed to identify specific blade design issues that may contribute to reduced wind turbine reliability and performance. Testing is also required to optimize aerodynamics, structural performance, encourage new technologies and materials development making wind even more competitive. The objective of this project is to accelerate the design and construction of a large wind blade testing facility capable of testing blades with minimum queue times at a reasonable cost. This testing facility will encourage and provide the opportunity for the U.S wind industry to conduct more rigorous testing of blades to improve wind turbine reliability.

  13. CMI Unique Facility: Filtration Test Facility | Critical Materials...

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

    Filtration Test Facility The Filtration Test Facility is one of half a dozen unique facilities developed by the Critical Materials Institute, an Energy Innovation Hub of the U.S....

  14. Vitrification facility at the West Valley Demonstration Project

    SciTech Connect (OSTI)

    DesCamp, V.A.; McMahon, C.L.

    1996-07-01

    This report is a description of the West Valley Demonstration Project`s vitrification facilities from the establishment of the West Valley, NY site as a federal and state cooperative project to the completion of all activities necessary to begin solidification of radioactive waste into glass by vitrification. Topics discussed in this report include the Project`s background, high-level radioactive waste consolidation, vitrification process and component testing, facilities design and construction, waste/glass recipe development, integrated facility testing, and readiness activities for radioactive waste processing.

  15. MHK Projects/Bonnybrook Wastewater Facility Project 2 | Open...

    Open Energy Info (EERE)

    Bonnybrook Wastewater Facility Project 2 < MHK Projects Jump to: navigation, search << Return to the MHK database homepage Loading map... "minzoom":false,"mappingservice":"googlem...

  16. Field test of a generic method for halogenated hydrocarbons: Semivost test at a chemical manufacturing facility. Final project report, August 1992-August 1993

    SciTech Connect (OSTI)

    McGaughey, J.F.; Bursey, J.T.; Merrill, R.G.

    1996-11-01

    The candidate methods for semivolatile organic compounds are SW-846 Sampling Method 0010 and Analytical Method 8270, which are applicable to stationary sources. Two field tests were conducted using quadruple sampling trains with dynamic spiking were performed according to the guidelines of EPA Method 301. The first field test was performed at a site with low levels of moisture. The second test reported here was conducted at a chemical manufacturing facility where chemical wastes were burned in a coal-fired boiler. Poor recoveries obtained for the spiked analytes at the second test were attributed to wet sorbent from the sampling train, use of methanol to effect complete transfer of wet sorbent from the sampling module, and use of extraction techniques which did not effect a complete separation of methylene chloride from methanol. A procedure to address problems with preparation of samples from Method 0010 is included in the report.

  17. National Ignition Facility project acquisition plan

    SciTech Connect (OSTI)

    Callaghan, R.W.

    1996-04-01

    The purpose of this National Ignition Facility Acquisition Plan is to describe the overall procurement strategy planned for the National Ignition Facility (NIF) Project. The scope of the plan describes the procurement activities and acquisition strategy for the following phases of the NIF Project, each of which receives either plant and capital equipment (PACE) or other project cost (OPC) funds: Title 1 and 2 design and Title 3 engineering (PACE); Optics manufacturing facilitization and pilot production (OPC); Convention facility construction (PACE); Procurement, installation, and acceptance testing of equipment (PACE); and Start-up (OPC). Activities that are part of the base Inertial Confinement Fusion (ICF) Program are not included in this plan. The University of California (UC), operating Lawrence Livermore National Laboratory (LLNL) and Los Alamos National Laboratory, and Lockheed-Martin, which operates Sandia National Laboratory (SNL) and the University of Rochester Laboratory for Laser Energetics (UR-LLE), will conduct the acquisition of needed products and services in support of their assigned responsibilities within the NIF Project structure in accordance with their prime contracts with the Department of Energy (DOE). LLNL, designated as the lead Laboratory, will have responsibility for all procurements required for construction, installation, activation, and startup of the NIF.

  18. Property:Testing Facilities | Open Energy Information

    Open Energy Info (EERE)

    Name Testing Facilities Property Type Page Retrieved from "http:en.openei.orgwindex.php?titleProperty:TestingFacilities&oldid595932" Feedback Contact needs updating...

  19. Accelerator Stewardship Test Facility Program - Elliptical Twin...

    Office of Scientific and Technical Information (OSTI)

    Accelerator Stewardship Test Facility Program - Elliptical Twin Cavity for Accelerator Applications Citation Details In-Document Search Title: Accelerator Stewardship Test Facility ...

  20. Sandia National Laboratories: Locations: Kauai Test Facility

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

    Kauai Test Facility Kauai photo The Kauai Test Facility (KTF) is a rocket launch range in Hawaii operated by Sandia for the Department of Energy. The facilities and personnel...

  1. The Great Plains Wind Power Test Facility

    SciTech Connect (OSTI)

    Schroeder, John

    2014-01-31

    This multi-year, multi-faceted project was focused on the continued development of a nationally-recognized facility for the testing, characterization, and improvement of grid-connected wind turbines, integrated wind-water desalination systems, and related educational and outreach topics. The project involved numerous faculty and graduate students from various engineering departments, as well as others from the departments of Geosciences (in particular the Atmospheric Science Group) and Economics. It was organized through the National Wind Institute (NWI), which serves as an intellectual hub for interdisciplinary and transdisciplinary research, commercialization and education related to wind science, wind energy, wind engineering and wind hazard mitigation at Texas Tech University (TTU). Largely executed by an academic based team, the project resulted in approximately 38 peer-reviewed publications, 99 conference presentations, the development/expansion of several experimental facilities, and two provisional patents.

  2. Albany Landfill Gas Utilization Project Biomass Facility | Open...

    Open Energy Info (EERE)

    Landfill Gas Utilization Project Biomass Facility Jump to: navigation, search Name Albany Landfill Gas Utilization Project Biomass Facility Facility Albany Landfill Gas Utilization...

  3. Lopez Landfill Gas Utilization Project Biomass Facility | Open...

    Open Energy Info (EERE)

    Lopez Landfill Gas Utilization Project Biomass Facility Jump to: navigation, search Name Lopez Landfill Gas Utilization Project Biomass Facility Facility Lopez Landfill Gas...

  4. NREL: Wind Research - Dynamometer Test Facilities

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

    Dynamometer Test Facilities Dynamometer test configuration for a wind turbine drivetrain. Enlarge image Dynamometers enable industry and testing agencies to verify the performance...

  5. Salt Waste Processing Facility, Construction Turnover to Testing and

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

    Commissioning Oversight | Department of Energy Construction Turnover to Testing and Commissioning Oversight Salt Waste Processing Facility, Construction Turnover to Testing and Commissioning Oversight This procedure establishes an oversight process for the Salt Waste Processing Facility Project Office (SWPFPO) Integrated Project Team (IPT) personnel assigned to perform oversight of system turnover from Construction to Commissioning and Testing. September 2015 PDF icon Procedure Key Resources

  6. NREL: Photovoltaics Research - Outdoor Test Facility

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

    Outdoor Test Facility Aerial photo of the Outdoor Test Facility. The Outdoor Test Facility at NREL is used to evaluate prototype, precommercial, and commercial modules. Outdoor Test Facility (OTF) researchers study and evaluate advanced or emerging PV technologies under simulated, accelerated indoor and outdoor, and prevailing outdoor conditions. One of the major roles of researchers at the OTF is to work with industry to develop uniform and consensus standards and codes for testing PV devices.

  7. Facility Interface Capability Assessment (FICA) project report

    SciTech Connect (OSTI)

    Pope, R.B.; MacDonald, R.R.; Viebrock, J.M.; Mote, N.

    1995-09-01

    The US Department of Energy`s (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing the Civilian Radioactive Waste Management System (CRWMS) to accept spent nuclear fuel from commercial facilities. The objective of the Facility Interface Capability Assessment (FICA) project was to assess the capability of each commercial spent nuclear fuel (SNF) storage facility, at which SNF is stored, to handle various SNF shipping casks. The purpose of this report is to present and analyze the results of the facility assessments completed within the FICA project. During Phase 1, the data items required to complete the facility assessments were identified and the database for the project was created. During Phase 2, visits were made to 122 facilities on 76 sites to collect data and information, the database was updated, and assessments of the cask-handling capabilities at each facility were performed. Each assessment of cask-handling capability contains three parts: the current capability of the facility (planning base); the potential enhanced capability if revisions were made to the facility licensing and/or administrative controls; and the potential enhanced capability if limited physical modifications were made to the facility. The main conclusion derived from the planning base assessments is that the current facility capabilities will not allow handling of any of the FICA Casks at 49 of the 122 facilities evaluated. However, consideration of potential revisions and/or modifications showed that all but one of the 49 facilities could be adapted to handle at least one of the FICA Casks. For this to be possible, facility licensing, administrative controls, and/or physical aspects of the facility would need to be modified.

  8. Cold moderator test facilities working group

    SciTech Connect (OSTI)

    Bauer, Guenter S.; Lucas, A. T.

    1997-09-01

    The working group meeting was chaired by Bauer and Lucas.Testing is a vital part of any cold source development project. This applies to specific physics concept verification, benchmarking in conjunction with computer modeling and engineering testing to confirm the functional viability of a proposed system. Irradiation testing of materials will always be needed to continuously extend a comprehensive and reliable information database. An ever increasing worldwide effort to enhance the performance of reactor and accelerator based neutron sources, coupled with the complexity and rising cost of building new generation facilities, gives a new dimension to cold source development and testing programs. A stronger focus is now being placed on the fine-tuning of cold source design to maximize its effectiveness in fully exploiting the facility. In this context, pulsed spallation neutron sources pose an extra challenge due to requirements regarding pulse width and shape which result from a large variety of different instrument concepts. The working group reviewed these requirements in terms of their consequences on the needs for testing equipment and compiled a list of existing and proposed facilities suitable to carry out the necessary development work.

  9. NREL: Research Facilities - Test and User Facilities

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

    for researching, developing, and evaluating renewable energy and energy efficiency technologies. Here you'll find an alphabetical listing and brief descriptions of NREL's test and...

  10. Director, Salt Waste Processing Facility Project Office

    Broader source: Energy.gov [DOE]

    This position is located within The Department of Energy (DOE) Savannah River (SR) Operations Office, Salt Waste Processing Facility Project Office (SWPFPO). SR is located in Aiken, South Carolina....

  11. Idaho Waste Vitrification Facilities Project Vitrified Waste Interim Storage Facility

    SciTech Connect (OSTI)

    Bonnema, Bruce Edward

    2001-09-01

    This feasibility study report presents a draft design of the Vitrified Waste Interim Storage Facility (VWISF), which is one of three subprojects of the Idaho Waste Vitrification Facilities (IWVF) project. The primary goal of the IWVF project is to design and construct a treatment process system that will vitrify the sodium-bearing waste (SBW) to a final waste form. The project will consist of three subprojects that include the Waste Collection Tanks Facility, the Waste Vitrification Facility (WVF), and the VWISF. The Waste Collection Tanks Facility will provide for waste collection, feed mixing, and surge storage for SBW and newly generated liquid waste from ongoing operations at the Idaho Nuclear Technology and Engineering Center. The WVF will contain the vitrification process that will mix the waste with glass-forming chemicals or frit and turn the waste into glass. The VWISF will provide a shielded storage facility for the glass until the waste can be disposed at either the Waste Isolation Pilot Plant as mixed transuranic waste or at the future national geological repository as high-level waste glass, pending the outcome of a Waste Incidental to Reprocessing determination, which is currently in progress. A secondary goal is to provide a facility that can be easily modified later to accommodate storage of the vitrified high-level waste calcine. The objective of this study was to determine the feasibility of the VWISF, which would be constructed in compliance with applicable federal, state, and local laws. This project supports the Department of Energys Environmental Management missions of safely storing and treating radioactive wastes as well as meeting Federal Facility Compliance commitments made to the State of Idaho.

  12. Cyclotron Institute Upgrade Project - Facilities - Cyclotron Institute

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

    Upgrade Overview / K150 Cyclotron / Light Ion Guide / Heavy Ion Guide / Negative Ion Source / CB-ECRIS Facility Upgrade White Paper Overview Picture of the experimental set up to measure beta-decay half-lives. On January 3, 2005 the Cyclotron Institute Upgrade Project (CIUP) began with the approval of the CIUP management plan by the Department of Energy Nuclear Physics Office. The project will extend to the first quarter of calendar year 2011. When completed, the upgraded facility will provide

  13. Dual Axis Radiographic Hydrodynamic Test Facility | National...

    National Nuclear Security Administration (NNSA)

    Dual Axis Radiographic Hydrodynamic Test Facility An integral part of the national ... radiographic images of the imploding test object, in which materials are moving at ...

  14. Tribal Renewable Energy Advanced Course: Facility Scale Project...

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

    Facility Scale Project Development Tribal Renewable Energy Advanced Course: Facility Scale Project Development Watch the DOE Office of Indian Energy renewable energy course ...

  15. Community- and Facility-Scale Tribal Renewable Energy Project...

    Energy Savers [EERE]

    and Facility-Scale Tribal Renewable Energy Project Development and Finance Workshop Agenda Community- and Facility-Scale Tribal Renewable Energy Project Development and Finance ...

  16. Idaho Spent Fuel Facility (ISFF) Project, Appropriate Acquisition...

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

    Idaho Spent Fuel Facility (ISFF) Project, Appropriate Acquisition Strategy Lessons Learned Report, NNSA, Feb 2010 Idaho Spent Fuel Facility (ISFF) Project, Appropriate Acquisition...

  17. Long-Baseline Neutrino Facility / Deep Underground Neutrino Project...

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

    Long-Baseline Neutrino Facility Deep Underground Neutrino Project (LBNF-DUNE) Long-Baseline Neutrino Facility Deep Underground Neutrino Project (LBNF-DUNE) Long-Baseline ...

  18. SLIDESHOW: America's Wind Testing Facilities

    Broader source: Energy.gov [DOE]

    A look at the nation's innovative wind facilities -- where researchers are speeding the adoption of next generation clean energy technologies.

  19. CMI Unique Facility: Pilot-Scale Separations Test Bed Facility | Critical

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

    Materials Institute Pilot-Scale Separations Test Bed Facility Pilot-scale separations test bed facility at Idaho National Laboratory A group tours the 30-stage mixer-settler during a meeting at Idaho National Laboratory. This technology was developed for a CMI project. The Pilot-Scale Separations Test Bed Facility is one of more than a dozen unique facilities developed by the Critical Materials Institute, an Energy Innovation Hub of the U.S. Department of Energy. Noting that the CMI Grand

  20. Projects | Argonne Leadership Computing Facility

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

    Projects bgclang Compiler Hal Finkel Cobalt Scheduler Bill Allcock, Paul Rich, Brian Toonen, Tom Uram GLEAN: Scalable In Situ Analysis and I/O Acceleration on Leadership Computing Systems Michael E. Papka, Venkat Vishwanath, Mark Hereld, Preeti Malakar, Joe Insley, Silvio Rizzi, Tom Uram Petrel: Data Management and Sharing Pilot Ian Foster, Michael E. Papka, Bill Allcock, Ben Allen, Rachana Ananthakrishnan, Lukasz Lacinski The Swift Parallel Scripting Language for ALCF Systems Michael Wilde,

  1. New Facility Will Test Disposal Cell Cover Renovation | Department...

    Office of Environmental Management (EM)

    Services New Facility Will Test Disposal Cell Cover Renovation New Facility Will Test Disposal Cell Cover Renovation New Facility Will Test Disposal Cell Cover Renovation PDF ...

  2. Geothermal Test Facility, California, Site Fact Sheet

    Office of Legacy Management (LM)

    Geothermal Test Facility, California, Site. The U.S. Department of Energy Office of Legacy Management is responsible for maintaining records for this site. Location of the Geothermal Test Facility, California, Site Overview The Bureau of Land Management (BLM) began studies of the geothermal resources of an area known as the East Mesa site in 1968. In 1978, the U.S. Department of Energy (DOE) became the exclusive operator of the site, which was called the Geothermal Test Facility, and negotiated

  3. Dual Axis Radiographic Hydrodynamic Test Facility

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

    Deputy Group Leader Tim Ferris (505) 665-2179 Email Hydrotests are critical in assessing nuclear weapons in nation's stockpile Dual Axis Radiographic Hydrodynamic Test facility ...

  4. Major Risk Factors to the Integrated Facility Disposition Project |

    Energy Savers [EERE]

    Department of Energy to the Integrated Facility Disposition Project Major Risk Factors to the Integrated Facility Disposition Project The scope of the Integrated Facility Disposition Project (IFDP) needs to comprehensively address a wide range of environmental management risks at the Oak Ridge Reservation (ORO). PDF icon Major Risk Factors to the Integrated Facility Disposition Project More Documents & Publications Major Risk Factors Integrated Facility Disposition Project - Oak Ridge

  5. EIS-0214: Northwest Regional Power Facility Project

    Broader source: Energy.gov [DOE]

    This environmental impact statement analyzes the WA Power LLC proposal to construct and operate a 838 megawatt gas-fired combustion turbine facility near the town of Creston, Washington. The project site is approtiately 1,200 acres, of which less than 140 acres be impacted.

  6. Facility for Advanced Accelerator Experimental Tests (FACET) | U.S. DOE

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

    Office of Science (SC) Facility for Advanced Accelerator Experimental Tests (FACET) High Energy Physics (HEP) HEP Home About Research Facilities User Facilities Fermilab Accelerator Complex Facility for Advanced Accelerator Experimental Tests (FACET) Accelerator Test Facility (ATF) Facility Ops Projects, Missions, and Status Science Highlights Benefits of HEP Funding Opportunities Advisory Committees Community Resources Contact Information High Energy Physics U.S. Department of Energy

  7. Accelerator Test Facility (ATF) | U.S. DOE Office of Science (SC)

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

    Accelerator Test Facility (ATF) High Energy Physics (HEP) HEP Home About Research Facilities User Facilities Fermilab Accelerator Complex Facility for Advanced Accelerator Experimental Tests (FACET) Accelerator Test Facility (ATF) Facility Ops Projects, Missions, and Status Science Highlights Benefits of HEP Funding Opportunities Advisory Committees Community Resources Contact Information High Energy Physics U.S. Department of Energy SC-25/Germantown Building 1000 Independence Ave., SW

  8. ZEST flight test experiments, Kauai Test Facility, Hawaii. Test report

    SciTech Connect (OSTI)

    Cenkci, M.J.

    1991-07-01

    The Strategic Defense Initiative Organization (SDIO) is proposing to execute two ZEST flight experiments to obtain information related to the following objectives: validation of payload modeling; characterization of a high energy release cloud; and documentation of scientific phenomena that may occur as a result of releasing a high energy cloud. The proposed action is to design, develop, launch, and detonate two payloads carrying high energy explosives. Activities required to support this proposal include: (1) execution of component assembly tests at Space Data Division (SDD) in Chandler, Arizona and Los Alamos National Laboratory (LANL) in Los Alamos, New Mexico, and (2) execution of pre-flight flight test activities at Kauai Test Facility.

  9. Sun{diamond}Lab test facilities

    SciTech Connect (OSTI)

    Not Available

    1998-04-01

    This country`s efforts to successfully develop and commercialize concentrating solar power (CSP) technologies depend on specialized research and testing capabilities. To Support this effort, the US Department of Energy`s Concentrating Solar Power Program maintains two major test facilities: the National Solar Thermal Test Facility at Sandia National Laboratories in Albuquerque, New Mexico, and the High Flux Solar Furnace at the National Renewable Energy Laboratory in Golden, Colorado. These test facilities combine to be instrumental in the development of parabolic dishes, troughs, and solar power towers.

  10. Sun{diamond}Lab test facilities

    SciTech Connect (OSTI)

    1998-04-01

    This country's efforts to successfully develop and commercialize concentrating solar power (CSP) technologies depend on specialized research and testing capabilities. To Support this effort, the US Department of Energy's Concentrating Solar Power Program maintains two major test facilities: the National Solar Thermal Test Facility at Sandia National Laboratories in Albuquerque, New Mexico, and the High Flux Solar Furnace at the National Renewable Energy Laboratory in Golden, Colorado. These test facilities combine to be instrumental in the development of parabolic dishes, troughs, and solar power towers.

  11. Key Energy-Saving Projects for Smaller Facilities | Department...

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

    Key Energy-Saving Projects for Smaller Facilities This presentation discusses how smaller industrial facilities can save energy and how the Industrial Assessment Centers can help. ...

  12. Tribal Renewable Energy Advanced Course: Facility Scale Project Development

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

    | Department of Energy Facility Scale Project Development Tribal Renewable Energy Advanced Course: Facility Scale Project Development Watch the DOE Office of Indian Energy renewable energy course entitled "Tribal Renewable Energy Project Development and Financing: Facility Scale" by clicking on the .swf file below. You can also download a PDF of the PPT slides. This course provides in-depth information on the process for developing facility-scale renewable energy projects on tribal

  13. DOE's New Large Blade Test Facility in Massachusetts Completes...

    Office of Environmental Management (EM)

    DOE's New Large Blade Test Facility in Massachusetts Completes First Commercial Blade Tests DOE's New Large Blade Test Facility in Massachusetts Completes First Commercial Blade ...

  14. PIA - Advanced Test Reactor National Scientific User Facility...

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

    Advanced Test Reactor National Scientific User Facility Users Week 2009 PIA - Advanced Test Reactor National Scientific User Facility Users Week 2009 PIA - Advanced Test Reactor ...

  15. National Solar Thermal Test Facility

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

    2 - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced Nuclear Energy Nuclear

  16. National Solar Thermal Test Facility

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

    3 - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced Nuclear Energy Nuclear

  17. A combined cycle engine test facility

    SciTech Connect (OSTI)

    Engers, R.; Cresci, D.; Tsai, C.

    1995-09-01

    Rocket-Based Combined-Cycle (RBCC) engines intended for missiles and/or space launch applications incorporate features of rocket propulsion systems operating in concert with airbreathing engine cycles. Performance evaluation of these types of engines, which are intended to operate from static sea level take-off to supersonic cruise or accerlerate to orbit, requires ground test capabilities which integrate rocket component testing with airbreathing engine testing. A combined cycle engine test facility has been constructed in the General Applied Science Laboratories, Inc. (GASL) Aeropropulsion Test Laboratory to meet this requirement. The facility was designed to support the development of an innovative combined cycle engine concept which features a rocket based ramjet combustor. The test requirements included the ability to conduct tests in which the propulsive force was generated by rocket only, the ramjet only and simultaneous rocket and ramjet power (combined cycle) to evaluate combustor operation over the entire engine cycle. The test facility provides simulation over the flight Mach number range of 0 to 8 and at various trajectories. The capabilities of the combined cycle engine test facility are presented.

  18. Recommissioning the K-1600 Seismic Test Facility

    SciTech Connect (OSTI)

    Wynn, C.C. ); Brewer, D.W. )

    1991-10-01

    The Center of Natural Phenomena Engineering (CNPE) was established under the technical direction of Dr. James E. Beavers with a mandate to assess, by analyses and testing, the seismic capacity of building structures that house sensitive processes at the Oak Ridge Y-12 Plant. This mandate resulted in a need to recommission the K-1600 Seismic Test Facility (STF) at the Oak Ridge K-25 Site, which had been shutdown for 6 years. This paper documents the history of the facility and fives some salient construction, operation, and performance details of its 8-ton, 20-foot center of gravity payload bi-axial seismic simulator. A log of activities involved in the restart of this valuable resource is included as Table 1. Some of problems and solutions associated with recommissioning the facility under a relatively limited budget are included. The unique attributes of the shake table are discussed. The original mission and performance requirements are compared to current expanded mission and performance capabilities. Potential upgrades to further improve the capabilities of the test facility as an adjunct to the CNPE are considered. Additional uses for the facility are proposed, including seismic qualification testing of devices unique to enrichment technologies and associated hazardous waste treatment and disposal processes. In summary, the STF restart in conjunction with CNPE has added a vital, and unique facility to the list of current national resources utilized for earthquake engineering research and development. 3 figs., 1 tab.

  19. Renewable Energy Project Development and Financing: Facility Scale

    Energy Savers [EERE]

    Facility Scale Detailed Hypothetical Example of How to Use Renewable Power in Your Small to Medium-Sized Tribal Facilities Course Outline What we will cover...  About the DOE Office of Indian Energy Education Initiative  Facility-Scale Process: Hypothetical Example - Project development and financing concepts - Project development and financing process and decision points - Facility-scale project as an investment (or commitment to an alternative utility payment) - How to pay for

  20. Knowledge Preservation at the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Wootan, David W.; Omberg, Ronald P.; Makenas, Bruce J.; Nielsen, Deborah L.; Nelson, Joseph V.; Polzin, David L.

    2012-01-30

    The Fast Flux Test Facility (FFTF) is the most recent Liquid Metal Reactor (LMR) to operate in the United States, from 1982 to 1992. The technologies employed in designing and constructing this reactor, along with information obtained from tests conducted during its operation, are currently being secured and archived by the Department of Energy's Office of Nuclear Energy. This report is one in a series documenting the overall project efforts to retrieve and preserve critical information related to advanced reactors

  1. Knowledge Preservation at the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Wootan, David W.; Omberg, Ronald P.; Makenas, Bruce J.; Nielsen, Deborah L.; Nelson, Joseph V.; Polzin, David L.

    2011-11-30

    The Fast Flux Test Facility (FFTF) is the most recent Liquid Metal Reactor (LMR) to operate in the United States, from 1982 to 1992. The technologies employed in designing and constructing this reactor, along with information obtained from tests conducted during its operation, are currently being secured and archived by the Department of Energy's Office of Nuclear Energy. This report provides a status update documenting the overall project efforts to retrieve and preserve critical information related to advanced reactors.

  2. Long-Baseline Neutrino Facility / Deep Underground Neutrino Project

    Energy Savers [EERE]

    (LBNF-DUNE) | Department of Energy Long-Baseline Neutrino Facility / Deep Underground Neutrino Project (LBNF-DUNE) Long-Baseline Neutrino Facility / Deep Underground Neutrino Project (LBNF-DUNE) Long-Baseline Neutrino Facility / Deep Underground Neutrino Project (LBNF-DUNE) Chris Mossey, Deputy Lab Director (Fermi) and Project Director for LBNF-DUNE March 23, 2016 PDF icon Presentation More Documents & Publications EA-1943: Final Environmental Assessment EA-1943: Draft Environmental

  3. Advanced Powertrain Research Facility Vehicle Test Cell Thermal...

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

    Powertrain Research Facility Vehicle Test Cell Thermal Upgrade Advanced Powertrain Research Facility Vehicle Test Cell Thermal Upgrade 2010 DOE Vehicle Technologies and Hydrogen...

  4. Sandia Energy - National Solar Thermal Testing Facility Beam...

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

    National Solar Thermal Testing Facility Beam Profiling Home Renewable Energy News Concentrating Solar Power Solar National Solar Thermal Testing Facility Beam Profiling Previous...

  5. DOE - Office of Legacy Management -- Geothermal Test Facility...

    Office of Legacy Management (LM)

    Geothermal Test Facility - 001 FUSRAP Considered Sites Site: Geothermal Test Facility (001) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site ...

  6. DARHT: Dual-Axis Radiographic Hydrodynamic Test Facility

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

    DARHT: Dual-Axis Radiographic Hydrodynamic Test Facility DARHT: Dual-Axis Radiographic Hydrodynamic Test Facility DARHT, supports a critical component of LANL's primary mission: to...

  7. Projects at the Component Development and Integration Facility. Quarterly technical progress report, January 1, 1994--March 31, 1994

    SciTech Connect (OSTI)

    Not Available

    1994-08-01

    This quarterly technical progress report presents progress on the projects at the Component Development and Integration Facility (CDIF) during the second quarter of FY94. The CDIF is a major US Department of Energy test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: Biomass Remediation Project; Heavy Metal-Contaminated Soil Project; MHD Shutdown; Mine Waste Technology Pilot Program; Plasma Projects; Resource Recovery Project; Sodium Sulfide/Ferrous Sulfate Project; and Spray Casting Project.

  8. Projects at the Component Development and Integration Facility. Quarterly technical progress report, October 1--December 31, 1992

    SciTech Connect (OSTI)

    Not Available

    1992-12-31

    This quarterly technical progress report presents progress on the projects at the component Development and Integration Facility (CDIF) during the first quarter of FY93. The CDIF is a major US Department of Energy (DOE) test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: MHD proof-of-concept project; mine waste pilot program; plasma projects; resource recovery project; sodium sulfide/ferrous sulfate project; soil washing project; and spray casting project.

  9. Projects at the Component Development and Integration Facility. Quarterly technical progress report, April 1--June 30, 1993

    SciTech Connect (OSTI)

    Not Available

    1993-12-01

    This quarterly technical progress report presents progress on the projects at the Component Development and Integration Facility (CDIF) during the third quarter of FY93. The CDIF is a major US Department of Energy test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: MHD Proof-of-Concept Project; Mine Waste Technology Program; Plasma Projects; Resource Recovery Project; Sodium Sulfide/Ferrous Sulfate Project; Soil Washing Project; and Spray Casting Project.

  10. National Ignition Facility project acquisition plan revision 1

    SciTech Connect (OSTI)

    Clobes, A.R.

    1996-10-01

    The purpose of this National Ignition Facility Acquisition Plan is to describe the overall procurement strategy planned for the National Ignition Facility M Project. It was prepared for the NIP Prood Office by the NIF Procurement Manager.

  11. Education & Collection Facility GSHP Demonstration Project

    SciTech Connect (OSTI)

    Joplin, Jeff

    2015-03-28

    The Denver Museum of Nature & Science (DMNS) designed and implemented an innovative ground source heat pump (GSHP) system for heating and cooling its new Education and Collection Facility (ECF) building addition. The project goal was to successfully design and install an open-loop GSHP system that utilized water circulating within an underground municipal recycled (non-potable) water system as the heat sink/source as a demonstration project. The expected results were to significantly reduce traditional GSHP installation costs while increasing system efficiency, reduce building energy consumption, require significantly less area and capital to install, and be economically implemented wherever access to a recycled water system is available. The project added to the understanding of GSHP technology by implementing the first GSHP system in the United States utilizing a municipal recycled water system as a heat sink/source. The use of this fluid through a GSHP system has not been previously documented. This use application presents a new opportunity for local municipalities to develop and expand the use of underground municipal recycled (non-potable) water systems. The installation costs for this type of technology in the building structure would be a cost savings over traditional GSHP costs, provided the local municipal infrastructure was developed. Additionally, the GSHP system functions as a viable method of heat sink/source as the thermal characteristics of the fluid are generally consistent throughout the year and are efficiently exchanged through the GSHP system and its components. The use of the recycled water system reduces the area required for bore or loop fields; therefore, presenting an application for building structures that have little to no available land use or access. This GSHP application demonstrates the viability of underground municipal recycled (non-potable) water systems as technically achievable, environmentally supportive, and an efficient system.

  12. Community- and Facility-Scale Tribal Renewable Energy Project Development

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

    and Finance Workshop: Colorado | Department of Energy and Facility-Scale Tribal Renewable Energy Project Development and Finance Workshop: Colorado Community- and Facility-Scale Tribal Renewable Energy Project Development and Finance Workshop: Colorado September 18, 2013 - 2:20pm Addthis September 18-20, 2013 Golden, Colorado National Renewable Energy Laboratory The Office of Indian Energy held a Community- and Facility-Scale Tribal Renewable Energy Project Development and Finance Workshop

  13. 2013 Community- and Facility-Scale Tribal Renewable Energy Project

    Energy Savers [EERE]

    Development and Finance Workshop Presentations and Agenda | Department of Energy Community- and Facility-Scale Tribal Renewable Energy Project Development and Finance Workshop Presentations and Agenda 2013 Community- and Facility-Scale Tribal Renewable Energy Project Development and Finance Workshop Presentations and Agenda Download the agenda and available presentations from guest speakers at the Office of Indian Energy's Community- and Facility-Scale Tribal Renewable Energy Project

  14. Direct sunlight facility for testing and research in HCPV

    SciTech Connect (OSTI)

    Sciortino, Luisa Agnello, Simonpietro Bonsignore, Gaetano; Cannas, Marco; Gelardi, Franco Mario; Napoli, Gianluca; Spallino, Luisa; Barbera, Marco; Buscemi, Alessandro; Montagnino, Fabio Maria; Paredes, Filippo; Candia, Roberto; Collura, Alfonso; Di Cicca, Gaspare; Cicero, Ugo Lo; Varisco, Salvo

    2014-09-26

    A facility for testing different components for HCPV application has been developed in the framework of 'Fotovoltaico ad Alta Efficienza' (FAE) project funded by the Sicilian Regional Authority (PO FESR Sicilia 2007/2013 4.1.1.1). The testing facility is equipped with an heliostat providing a wide solar beam inside the lab, an optical bench for mounting and aligning the HCPV components, electronic equipments to characterize the I-V curves of multijunction cells operated up to 2000 suns, a system to circulate a fluid in the heat sink at controlled temperature and flow-rate, a data logging system with sensors to measure temperatures in several locations and fluid pressures at the inlet and outlet of the heat sink, and a climatic chamber with large test volume to test assembled HCPV modules.

  15. Facility Software Quality Assurance (SQA) for Captal Project Critical

    Energy Savers [EERE]

    Decisions RM | Department of Energy Software Quality Assurance (SQA) for Captal Project Critical Decisions RM Facility Software Quality Assurance (SQA) for Captal Project Critical Decisions RM The purpose of this Software Quality Assurance for Capital Project Critical Decision Review Module (SQA RM) is to identify, integrate, and clarify, in one EM document, the SQA performance objectives, criteria, and guidance needed to review project documents and activities. PDF icon Facility Software

  16. Salt Waste Processing Facility, Construction Turnover to Testing...

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

    Salt Waste Processing Facility, Construction Turnover to Testing and Commissioning Oversight This procedure establishes an oversight process for the Salt Waste Processing Facility ...

  17. Pyrotek Graphitization Facility Expansion Project | Department of Energy

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

    1 DOE Hydrogen and Fuel Cells Program, and Vehicle Technologies Program Annual Merit Review and Peer Evaluation PDF icon arravt016_es_sekedat_2011_p.pdf More Documents & Publications Pyrotek Graphitization Facility Expansion Project Pyrotek Graphitization Facility Expansion Project EA-1720: Finding of No Significant Impact

  18. Startup Testing of the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Wootan, David W.; Butner, R. Scott; Omberg, Ronald P.; Makenas, Bruce J.; Nielsen, Deborah L.; Polzin, David L.

    2010-06-30

    This paper is one in a series documenting the current effort to retrieve, secure, and preserve critical information related to advanced reactors. . Information from this testing is being retrieved under the Fuel Cycle Research and Development (FCRD) program conducted by the Office of Nuclear Energy (NE) of the DOE. The Fast Flux Test Facility (FFTF) is the most recent Liquid Metal Reactor (LMR) to be designed, constructed, and operated by the U.S. Department of Energy (DOE).

  19. Renewable Energy Project Development and Financing: Facility...

    Energy Savers [EERE]

    ... * Review tribal facility electric cost data, regulations for permitting, and interconnection requirements * Assemble or communicate with the right team-those in positions or ...

  20. Project W-320, combined pump winch assembly test - Test report

    SciTech Connect (OSTI)

    Bellomy, J.R., Westinghouse Hanford

    1996-05-15

    Test report documenting results of the Project W-320 combined pump/winch test performed at Lawrence Pumps.

  1. National Biomedical Tracer Facility. Project definition study

    SciTech Connect (OSTI)

    Schafer, R.

    1995-02-14

    We request a $25 million government-guaranteed, interest-free loan to be repaid over a 30-year period for construction and initial operations of a cyclotron-based National Biomedical Tracer Facility (NBTF) in North Central Texas. The NBTF will be co-located with a linear accelerator-based commercial radioisotope production facility, funded by the private sector at approximately $28 million. In addition, research radioisotope production by the NBTF will be coordinated through an association with an existing U.S. nuclear reactor center that will produce research and commercial radioisotopes through neutron reactions. The combined facilities will provide the full range of technology for radioisotope production and research: fast neutrons, thermal neutrons, and particle beams (H{sup -}, H{sup +}, and D{sup +}). The proposed NBTF facility includes an 80 MeV, 1 mA H{sup -} cyclotron that will produce proton-induced (neutron deficient) research isotopes.

  2. 400 Area/Fast Flux Test Facility - Hanford Site

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

    325 Building 400 AreaFast Flux Test Facility 618-10 ... Test Facility D and DR Reactors Effluent Treatment ... (thermal) liquid-metal (sodium)-cooled nuclear research ...

  3. New Wind Test Facilities Open in Colorado and South Carolina...

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

    Wind Test Facilities Open in Colorado and South Carolina New Wind Test Facilities Open in Colorado and South Carolina January 1, 2014 - 12:00am Addthis Two of the world's largest ...

  4. PIA - Advanced Test Reactor National Scientific User Facility Users Week

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

    2009 | Department of Energy Advanced Test Reactor National Scientific User Facility Users Week 2009 PIA - Advanced Test Reactor National Scientific User Facility Users Week 2009 PIA - Advanced Test Reactor National Scientific User Facility Users Week 2009 PDF icon PIA - Advanced Test Reactor National Scientific User Facility Users Week 2009 More Documents & Publications PIA - INL SECURITY INFORMATION MANAGEMENT SYSTEM BUSINESS ENCLAVE PIA - INL Education Programs Business Enclav

  5. New Wind Test Facilities Open in Colorado and South Carolina

    Broader source: Energy.gov [DOE]

    Two state-of-the-art wind testing facilities will accelerate development and deployment of wind energy technologies.

  6. Testing the effectiveness of mobile home weatherization measures in a controlled environment: The SERI CMFERT (Collaborative Manufactured Buildings Facility for Energy Research and Training) Project

    SciTech Connect (OSTI)

    Judkoff, R.D.; Hancock, C.E.; Franconi, E.

    1990-03-01

    For several years the Solar Energy Research Institute has been testing the effectiveness of mobile home weatherization measures, with the support of the US DOE Office of State and Local Assistance Programs Weatherization Assistance Program, the DOE Office of Buildings and Community Systems, the seven states within the federal Weatherization Region 7, the Colorado Division of Housing, and the DOE Denver Support Office. During the winter of 1988--89, several weatherization measures were thermally tested on three mobile homes under controlled conditions inside a large environmental enclosure. The effects of each weatherization measure on conduction losses, infiltration losses, and combined furnace and duct-delivered heat efficiency were monitored. The retrofit options included air sealing, duct repair, furnace tune-up, interior storm panels, floor insulation, and roof insulation. The study demonstrated that cost-effective heating energy savings of about 20% to 50% are possible if weatherization techniques adapted to the special construction details in mobile homes are applied. 24 refs., 18 figs., 9 tabs.

  7. SLAC National Accelerator Laboratory FACET & TEST BEAM FACILITIES...

    Office of Scientific and Technical Information (OSTI)

    SLAC National Accelerator Laboratory FACET & TEST BEAM FACILITIES PROPOSAL Citation Details In-Document Search Title: SLAC National Accelerator Laboratory FACET & TEST BEAM ...

  8. Community Water Pump and Treatment Facility PV Solar Power Project

    Energy Savers [EERE]

    200,000 kWhyear PROJECT LOCATION SITE DETAILS Water Pump and Treatment Facility Sole provider of water to Pueblo and its 5,000 residents 1 pump house, 2 water ...

  9. Quality Assurance Project Plan for Facility Effluent Monitoring Plan activities

    SciTech Connect (OSTI)

    Frazier, T.P.

    1994-10-20

    This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the Facility Effluent Monitoring Plans, which are part of the overall Hanford Site Environmental Protection Plan. This plan specifically applies to the sampling and analysis activities and continuous monitoring performed for all Facility Effluent Monitoring Plan activities conducted by Westinghouse Hanford Company. It is generic in approach and will be implemented in conjunction with the specific requirements of the individual Facility Effluent Monitoring Plans.

  10. Alaska Facility- and Community-Scale Project Development Regional Energy

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

    Workshops | Department of Energy Facility- and Community-Scale Project Development Regional Energy Workshops Alaska Facility- and Community-Scale Project Development Regional Energy Workshops April 13, 2015 - 9:40am Addthis March 23-25, 2015 Bethel, Alaska University of Alaska Fairbanks March 26-27, 2015 Dillingham, Alaska University of Alaska, Bristol Bay Campus March 30-April 1, 2015 Juneau, Alaska University of Alaska Southeast The Office of Indian Energy hosted three back-to-back

  11. Major Risk Factors to the Integrated Facility Disposition Project

    Office of Environmental Management (EM)

    Oak Ridge Reservation Tennessee Major Risk Factors to the Integrated Facility Disposition Project (IFDP) Challenge The scope of the Integrated Facility Disposition Project (IFDP) needs to comprehensively address a wide range of environmental management risks at the Oak Ridge Reservation (ORO). These include: environmental remediation, regulatory compliance, deactivation and decommissioning (D&D) activities, and disposition of legacy materials and waste, along with the ongoing modernization,

  12. Workers Make History by Demolishing Manhattan Project Facilities |

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

    Department of Energy Workers Make History by Demolishing Manhattan Project Facilities Workers Make History by Demolishing Manhattan Project Facilities February 16, 2016 - 1:45pm Addthis Once K-27 is demolished, it will mark the first-ever cleanup of an entire gaseous diffusion complex anywhere. | Office of Environmental Management video David Sheeley David Sheeley Editor/Writer For the first time in history, workers will complete the demolition and cleanup of an entire gaseous diffusion

  13. Fast Flux Test Facility (FFTF) standby plan

    SciTech Connect (OSTI)

    Hulvey, R.K.

    1997-03-06

    The FFTF Standby Plan, Revision 0, provides changes to the major elements and project baselines to maintain the FFTF plant in a standby condition and to continue washing sodium from irradiated reactor fuel. The Plan is consistent with the Memorandum of Decision approved by the Secretary of Energy on January 17, 1997, which directed that FFTF be maintained in a standby condition to permit the Department to make a decision on whether the facility should play a future role in the Department of Energy`s dual track tritium production strategy. This decision would be made in parallel with the intended December 1998 decision on the selection of the primary, long- term source of tritium. This also allows the Department to review the economic and technical feasibility of using the FFTF to produce isotopes for the medical community. Formal direction has been received from DOE-RL and Fluor 2020 Daniel Hanford to implement the FFTF standby decision. The objective of the Plan is maintain the condition of the FFTF systems, equipment and personnel to preserve the option for plant restart within three and one-half years of a decision to restart, while continuing deactivation work which is consistent with the standby mode.

  14. MSG MONTICELLO PROJECTS FEDERAL FACILITY AGREEMENT REPORT

    Office of Legacy Management (LM)

    ... used to test sum stem 11112004 0 power pump activated pumps Ol I 11S2004 0 Oj I ... L.,:J - endmg Average wind speed. Prevailing wiud ...

  15. Projects at the Component Development and Integration Facility. Quarterly technical progress report, January 1--March 31, 1993

    SciTech Connect (OSTI)

    Not Available

    1993-09-01

    This quarterly technical progress report presents progress on several different projects at the Component Development and Integration Facility (CDIF) during the second quarter of FY93. The CDIF is a major US Department of Energy test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: MHD Proof-of-Concept Project; Mine Waste Technology Pilot Program; Plasma Furnace Projects for waste destruction; Resource Recovery Project; Sodium Sulfide/Ferrous Sulfate Project; Soil Washing Project for removal of radioactive materials; and Spray Casting Project.

  16. Category:Testing Facilities | Open Energy Information

    Open Energy Info (EERE)

    Scripps Channel 1 Scripps Channel 2 Scripps Flume Sectional Model Flume Facilities Sediment Basin Flume Sheets Wave Basin Ship Towing Tank Small Towing Tank Space Institute...

  17. Sandia National Laboratories participation in the National Ignition Facility project

    SciTech Connect (OSTI)

    Boyes, J.; Boyer, W.; Chael, J.; Cook, D.; Cook, W.; Downey, T.; Hands, J.; Harjes, C.; Leeper, R.; McKay, P.; Micano, P.; Olson, R.; Porter, J.; Quintenz, J.; Roberts, V.; Savage, M.; Simpson, W.; Seth, A.; Smith, R.; Wavrik, M.; Wilson, M.

    1996-08-01

    The National Ignition Facility is a $1.1B DOE Defense Programs Inertial Confinement Fusion facility supporting the Science Based Stockpile Stewardship Program. The goal of the facility is to achieve fusion ignition and modest gain in the laboratory. The NIF project is responsible for the design and construction of the 192 beam, 1.8 MJ laser necessary to meet that goal. - The project is a National project with participation by Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Sandia National Laboratory (SNL), the University of Rochester Laboratory for Laser Energetics (URLLE) and numerous industrial partners. The project is centered at LLNL which has extensive expertise in large solid state lasers. The other partners in the project have negotiated their participation based on the specific expertise they can bring to the project. In some cases, this negotiation resulted in the overall responsibility for a WBS element; in other cases, the participating laboratories have placed individuals in the project in areas that need their individual expertise. The main areas of Sandia`s participation are in the management of the conventional facility design and construction, the design of the power conditioning system, the target chamber system, target diagnostic instruments, data acquisition system and several smaller efforts in the areas of system integration and engineering analysis. Sandia is also contributing to the technology development necessary to support the project by developing the power conditioning system and several target diagnostics, exploring alternate target designs, and by conducting target experiments involving the ``foot`` region of the NIF power pulse. The project has just passed the mid-point of the Title I (preliminary) design phase. This paper will summarize Sandia`s role in supporting the National Ignition Facility and discuss the areas in which Sandia is contributing. 3 figs.

  18. Benchmarking transition costs for the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Hulvey, R.K.

    1996-12-31

    The Fast Flux Test Facility (FFTF) is a government-owned, 400-MW(thermal), sodium-cooled test reactor operated by Westinghouse Hanford Company. The reactor is shut down and is undergoing a transition to a long-term surveillance and maintenance state. The mission strategy for the FFTF transition project is to place the FFTF in a radiologically and industrially safe condition, completing the transition phase activities as soon as possible to drive down the current annual surveillance and maintenance costs from approximately $26 million/yr to roughly $1.5 million/yr. The effort to establish the shutdown and transition costs for this 7-yr, $260 million activity is a first of a kind for the U.S. Department of Energy (DOE).

  19. Upgrade of the cryogenic CERN RF test facility

    SciTech Connect (OSTI)

    Pirotte, O.; Benda, V.; Brunner, O.; Inglese, V.; Maesen, P.; Vullierme, B.; Koettig, T.

    2014-01-29

    With the large number of superconducting radiofrequency (RF) cryomodules to be tested for the former LEP and the present LHC accelerator a RF test facility was erected early in the 1990s in the largest cryogenic test facility at CERN located at Point 18. This facility consisted of four vertical test stands for single cavities and originally one and then two horizontal test benches for RF cryomodules operating at 4.5 K in saturated helium. CERN is presently working on the upgrade of its accelerator infrastructure, which requires new superconducting cavities operating below 2 K in saturated superfluid helium. Consequently, the RF test facility has been renewed in order to allow efficient cavity and cryomodule tests in superfluid helium and to improve its thermal performances. The new RF test facility is described and its performances are presented.

  20. NREL, Clemson University Collaborate on Wind Energy Testing Facilities |

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

    Department of Energy NREL, Clemson University Collaborate on Wind Energy Testing Facilities NREL, Clemson University Collaborate on Wind Energy Testing Facilities September 16, 2015 - 6:55pm Addthis A photo of a large dynamometer in a warehouse. In May, two of our nation's most advanced wind research and test facilities joined forces to help the wind energy industry improve the performance of wind turbine drivetrains and better understand how the turbines can integrate effectively with the

  1. DARHT: Dual-Axis Radiographic Hydrodynamic Test Facility

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

    DARHT: Dual-Axis Radiographic Hydrodynamic Test Facility DARHT: Dual-Axis Radiographic Hydrodynamic Test Facility DARHT, supports a critical component of LANL's primary mission: to ensure the safety, security, and effectiveness of nuclear weapons in our nation's stockpile. Los Alamos scientists built DARHT, the world's most powerful x-ray machine, to analyze mockups of nuclear weapons. At the Los Alamos National Laboratory (LANL), the Dual-Axis Radiographic Hydrodynamic Test Facility, or DARHT,

  2. Advanced Test Reactor National Scientific User Facility: Addressing

    Office of Scientific and Technical Information (OSTI)

    advanced nuclear materials research (Conference) | SciTech Connect Advanced Test Reactor National Scientific User Facility: Addressing advanced nuclear materials research Citation Details In-Document Search Title: Advanced Test Reactor National Scientific User Facility: Addressing advanced nuclear materials research The Advanced Test Reactor National Scientific User Facility (ATR NSUF), based at the Idaho National Laboratory in the United States, is supporting Department of Energy and

  3. Near-facility environmental monitoring quality assurance project plan

    SciTech Connect (OSTI)

    McKinney, S.M.

    1997-11-24

    This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the preoperational and near facility environmental monitoring performed by Waste Management Federal Services, Inc., Northwest Operations and supersedes WHC-EP-0538-2. This plan applies to all sampling and monitoring activities performed by waste management Federal Services, Inc., Northwest Operations in implementing facility environmental monitoring at the Hanford Site.

  4. Cryogenic system for the Cryomodule Test Facility at Fermilab

    SciTech Connect (OSTI)

    White, Michael; Martinez, Alex; Bossert, Rick; Dalesandro, Andrew; Geynisman, Michael; Hansen, Benjamin; Klebaner, Arkadiy; Makara, Jerry; Pei, Liujin; Richardson, Dave; Soyars, William; Theilacker, Jay

    2014-01-29

    This paper provides an overview of the current progress and near-future plans for the cryogenic system at the new Cryomodule Test Facility (CMTF) at Fermilab, which includes the helium compressors, refrigerators, warm vacuum compressors, gas and liquid storage, and a distribution system. CMTF will house the Project X Injector Experiment (PXIE), which is the front end of the proposed Project X. PXIE includes one 162.5 MHz half wave resonator (HWR) cryomodule and one 325 MHz single spoke resonator (SSR) cryomodule. Both cryomodules contain superconducting radio-frequency (SRF) cavities and superconducting magnets operated at 2.0 K. CMTF will also support the Advanced Superconducting Test Accelerator (ASTA), which is located in the adjacent New Muon Lab (NML) building. A cryomodule test stand (CMTS1) located at CMTF will be used to test 1.3 GHz cryomodules before they are installed in the ASTA cryomodule string. A liquid helium pump and transfer line will be used to provide supplemental liquid helium to ASTA.

  5. Microsoft Word - News Release - Clemson Drivetrain Test Facility...

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

    Contributes to Clemson University's Wind Turbine Drivetrain Testing Facility and ... nuclear security and clean energy challenges. For more information, visit http:...

  6. The Fast Flux Test Facility shutdown program plan

    SciTech Connect (OSTI)

    Guttenberg, S.; Jones, D.H.; Midgett, J.C.; Nielsen, D.L.

    1995-01-01

    The Fast Flux Test Facility (FFTF) is a 400 MWt sodium-cooled research reactor owned by the US Department of Energy (DOE) and operated by the Westinghouse Hanford Company (WHC) on the Hanford Site in southeastern Washington State. The decision was made by the DOE in December, 1993, to initiate shutdown of the FFTF. This paper describes the FFTF Transition Project Plan (1) (formerly the FFTF Shutdown Program Plan) which provides the strategy, major elements, and project baseline for transitioning the FFTF to an industrially and radiologically safe shutdown condition. The Plan, and its resource loaded schedule, indicate this transition can be achieved in a period of six to seven years at a cost of approximately $359 million. The transition activities include reactor defueling, fuel offload to dry cask storage, sodium drain and reaction, management of sodium residuals, shutdown of auxiliary systems, and preparation of appropriate environmental and regulatory documentation. Completion of these activities will involve resolution of many challenging and unique issues associated with shutdown of a large sodium reactor facility. At the conclusion of these activities, the FFTF will be in a safe condition for turnover to the Hanford Site Environmental Restoration Contractor for a long term surveillance and maintenance phase and decommissioning.

  7. Fallon Test Ranges Geothermal Project | Open Energy Information

    Open Energy Info (EERE)

    Test Ranges Geothermal Project Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Development Project: Fallon Test Ranges Geothermal Project Project Location Information...

  8. Advanced Test Reactor National Scientific User Facility 2010 Annual Report

    SciTech Connect (OSTI)

    Mary Catherine Thelen; Todd R. Allen

    2011-05-01

    This is the 2010 ATR National Scientific User Facility Annual Report. This report provides an overview of the program for 2010, along with individual project reports from each of the university principal investigators. The report also describes the capabilities offered to university researchers here at INL and at the ATR NSUF partner facilities.

  9. New Wind Turbine Dynamometer Test Facility Dedicated at NREL - News

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

    Releases | NREL New Wind Turbine Dynamometer Test Facility Dedicated at NREL November 19, 2013 Today, the Energy Department (DOE) and its National Renewable Energy Laboratory (NREL) dedicated a new 5-megawatt (MW) Dynamometer Test Facility at NREL's National Wind Technology Center (NWTC). The $20 million facility enables NREL to work closely with industry engineers to enhance the drive trains and other electrical systems in the country's largest land based wind turbines. "Although wind

  10. EIS-0415: Deer Creek Station Energy Facility Project, South Dakota

    Broader source: Energy.gov [DOE]

    This EIS analyzes WAPA's decision to approve the interconnection request made by Basin Electric Power Cooperative (Basin Electric) with the USDA Rural Utilities Service (RUS) proposing to provide financial assistance, for the Deer Creek Station Project, a proposed 300-megawatt (MW) natural gas-fired generation facility.

  11. Sandia Energy National Solar Thermal Test Facility

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

    solarreserve-is-testing-prototype-heliostats-at-nsttffeed 0 Solar Regional Test Center in Vermont Achieves Milestone Installation http:energy.sandia.gov...

  12. An Injector Test Facility for the LCLS

    SciTech Connect (OSTI)

    Colby, E.,; /SLAC

    2007-03-14

    SLAC is in the privileged position of being the site for the world's first 4th generation light source as well as having a premier accelerator research staff and facilities. Operation of the world's first x-ray free electron laser (FEL) facility will require innovations in electron injectors to provide electron beams of unprecedented quality. Upgrades to provide ever shorter wavelength x-ray beams of increasing intensity will require significant advances in the state-of-the-art. The BESAC 20-Year Facilities Roadmap identifies the electron gun as ''the critical enabling technology to advance linac-based light sources'' and recognizes that the sources for next-generation light sources are ''the highest-leveraged technology'', and that ''BES should strongly support and coordinate research and development in this unique and critical technology''.[1] This white paper presents an R&D plan and a description of a facility for developing the knowledge and technology required to successfully achieve these upgrades, and to coordinate efforts on short-pulse source development for linac-based light sources.

  13. Mixed and Low-Level Treatment Facility Project

    SciTech Connect (OSTI)

    Not Available

    1992-04-01

    This appendix contains the mixed and low-level waste engineering design files (EDFS) documenting each low-level and mixed waste stream investigated during preengineering studies for Mixed and Low-Level Waste Treatment Facility Project. The EDFs provide background information on mixed and low-level waste generated at the Idaho National Engineering Laboratory. They identify, characterize, and provide treatment strategies for the waste streams. Mixed waste is waste containing both radioactive and hazardous components as defined by the Atomic Energy Act and the Resource Conservation and Recovery Act, respectively. Low-level waste is waste that contains radioactivity and is not classified as high-level waste, transuranic waste, spent nuclear fuel, or 11e(2) byproduct material as defined by DOE 5820.2A. Test specimens of fissionable material irradiated for research and development only, and not for the production of power or plutonium, may be classified as low-level waste, provided the concentration of transuranic is less than 100 nCi/g. This appendix is a tool that clarifies presentation format for the EDFS. The EDFs contain waste stream characterization data and potential treatment strategies that will facilitate system tradeoff studies and conceptual design development. A total of 43 mixed waste and 55 low-level waste EDFs are provided.

  14. Securing Operating Data From Passive Safety Tests at the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Wootan, David W.; Omberg, Ronald P.; Makenas, Bruce J.; Nielsen, Deborah L.; Nelson, Joseph V.; Polzin, David L.

    2011-06-01

    The Fast Flux Test Facility (FFTF) is the most recent Liquid Metal Reactor (LMR) to operate in the United States, from 1982 to 1992. The technologies employed in designing and constructing this reactor, along with information obtained from tests conducted during its operation, are currently being secured and archived by the Department of Energy’s Office of Nuclear Energy Fuel Cycle Research and Development Program. This report is one in a series documenting the overall project efforts to retrieve and preserve critical information related to advanced reactors. A previous report summarized the initial efforts to review, retrieve and preserve the most salient documents related to Passive Safety Testing (PST) in the FFTF. Efforts continue to locate, secure, and retrieve record copies of original plant data tapes for the series of passive safety tests conducted between 1986 and 1991.

  15. Securing Operating Data From Passive Safety Tests at the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Wootan, David W.; Omberg, Ronald P.; Makenas, Bruce J.; Nielsen, Deborah L.; Nelson, Joseph V.; Polzin, David L.

    2011-06-01

    The Fast Flux Test Facility (FFTF) is the most recent Liquid Metal Reactor (LMR) to operate in the United States, from 1982 to 1992. The technologies employed in designing and constructing this reactor, along with information obtained from tests conducted during its operation, are currently being secured and archived by the Department of Energy's Office of Nuclear Energy Fuel Cycle Research and Development Program. This report is one in a series documenting the overall project efforts to retrieve and preserve critical information related to advanced reactors. A previous report summarized the initial efforts to review, retrieve and preserve the most salient documents related to Passive Safety Testing (PST) in the FFTF. Efforts continue to locate, secure, and retrieve record copies of original plant data tapes for the series of passive safety tests conducted between 1986 and 1991.

  16. Status and Plans for an SRF Accelerator Test Facility at Fermilab

    SciTech Connect (OSTI)

    Church, M.; Leibfritz, J.; Nagaitsev, S.; /Fermilab

    2011-07-29

    A superconducting RF accelerator test facility is currently under construction at Fermilab. The accelerator will consist of an electron gun, 40 MeV injector, beam acceleration section consisting of 3 TTF-type or ILC-type cryomodules, and multiple downstream beam lines for testing diagnostics and performing beam experiments. With 3 cryomodules installed this facility will initially be capable of generating an 810 MeV electron beam with ILC beam intensity. The facility can accommodate up to 6 cryomodules for a total beam energy of 1.5 GeV. This facility will be used to test SRF cryomodules under high intensity beam conditions, RF power equipment, instrumentation, and LLRF and controls systems for future SRF accelerators such as the ILC and Project-X. This paper describes the current status and overall plans for this facility.

  17. Near Facility Environmental Monitoring Quality Assurance Project Plan

    SciTech Connect (OSTI)

    MCKINNEY, S.M.

    2000-05-01

    This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the preoperational and near-facility environmental monitoring directed by Waste Management Technical Services and supersedes HNF-EP-0538-4. This plan applies to all sampling and monitoring activities performed by Waste Management Technical Services in implementing near-facility environmental monitoring at the Hanford Site. This Quality Assurance Project Plan is required by U.S. Department of Energy Order 5400.1 (DOE 1990) as a part of the Environmental Monitoring Plan (DOE-RL 1997) and is used to define: Environmental measurement and sampling locations used to monitor environmental contaminants near active and inactive facilities and waste storage and disposal sites; Procedures and equipment needed to perform the measurement and sampling; Frequency and analyses required for each measurement and sampling location; Minimum detection level and accuracy; Quality assurance components; and Investigation levels. Near-facility environmental monitoring for the Hanford Site is conducted in accordance with the requirements of U.S. Department of Energy Orders 5400.1 (DOE 1990), 5400.5 (DOE 1993), 5484.1 (DOE 1990), and 435.1 (DOE 1999), and DOE/EH-O173T (DOE 1991). It is Waste Management Technical Services' objective to manage and conduct near-facility environmental monitoring activities at the Hanford Site in a cost-effective and environmentally responsible manner that is in compliance with the letter and spirit of these regulations and other environmental regulations, statutes, and standards.

  18. High Efficiency Particulate Air (HEPA) Filter Test Facility (FTF) |

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

    Department of Energy High Efficiency Particulate Air (HEPA) Filter Test Facility (FTF) High Efficiency Particulate Air (HEPA) Filter Test Facility (FTF) DOE-STD-3020-2015 Specification for HEPA Filters Used by DOE Contractors The purpose of this standard is to establish specifications and quality assurance (QA) requirements for the procurement, packaging, shipping and storage of high efficiency particulate air (HEPA) filters. DOE-STD-3025-2007 Quality Assurance Inspection and Testing of HEPA

  19. Kauai Test Facility two experiment rocket campaign. [Kauai Test Facility; Two Experiment Rocket Campaign

    SciTech Connect (OSTI)

    Not Available

    1991-01-01

    The Kauai Test Facility (KTF) is a Department of Energy (DOE) owned facility located at Barking Sands, on the west coast of the island of Kauai, Hawaii. The KTF has a rocket preparation and launching capability for both rail-launched and vertical-launched capability for both rail-launched and vertical-launched rockets. Launches primarily support high altitude scientific research and re-entry vehicle systems and carry experimental non-nuclear payloads. This environmental assessment (EA) has been prepared for the Two Experiment Rocket Campaign, during which the STRYPI/LACE (STRYPI is not an acronym -- its the name of the rocket; LACE is the acronym for Low Altitude Compensation Experiment) and the RAP-501 (Rocket Accelerated Penetration) will be flown in conjunction from the KTF in February 1991 to reduce costs. There have been numerous rocket campaigns at the KTF in prior years that have used the same motors to be used in the current two experiment rocket campaign. The main difference noted in this environmental documentation is that the two rockets have not previously been flown in conjunction. Previous National Environmental Policy Act (NEPA) approvals of launches using these motors were limited to different and separate campaigns with diverse sources of funding. 2 figs., 5 tabs.

  20. Mixed and Low-Level Waste Treatment Facility Project

    SciTech Connect (OSTI)

    Not Available

    1992-04-01

    Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report documents those studies so the project can continue with an evaluation of programmatic options, system tradeoff studies, and the conceptual design phase of the project. This report, appendix B, comprises the engineering design files for this project study. The engineering design files document each waste steam, its characteristics, and identified treatment strategies.

  1. Yeager Airport Hydrogen Vehicle Test Project

    SciTech Connect (OSTI)

    Davis, Williams

    2015-10-01

    The scope of this project was changed during the course of the project. Phase I of the project was designed to have the National Alternative Fuels Training Consortium (NAFTC), together with its partners, manage the Hydrogen Vehicle Test Project at the Yeager Airport in conjunction with the Central West Virginia Regional Airport Authority (CWVRAA) in coordination with the United States Department of Energy National Energy Technology Laboratory (U.S. DOE NETL). This program would allow testing and evaluation of the use of hydrogen vehicles in the state of West Virginia utilizing the hydrogen fueling station at Yeager Airport. The NAFTC and CWVRAA to raise awareness and foster a greater understanding of hydrogen fuel and hydrogen-powered vehicles through a targeted utilization and outreach and education effort. After initial implementation of the project, the project added, determine the source(s) of supply for hydrogen powered vehicles that could be used for the testing. After completion of this, testing was begun at Yeager Airport. During the course of the project, the station at Yeager Airport was closed and moved to Morgantown and the West Virginia University Research Corporation. The vehicles were then moved to Morgantown and a vehicle owned by the CWVRAA was purchased to complete the project at the new location. Because of a number of issues detailed in the report for DE-FE0002994 and in this report, this project did not get to evaluate the effectiveness of the vehicles as planned.

  2. Mixed and Low-Level Waste Treatment Facility project

    SciTech Connect (OSTI)

    Not Available

    1992-04-01

    Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report, Appendix A, Environmental Regulatory Planning Documentation, identifies the regulatory requirements that would be imposed on the operation or construction of a facility designed to process the INEL's waste streams. These requirements are contained in five reports that discuss the following topics: (1) an environmental compliance plan and schedule, (2) National Environmental Policy Act requirements, (3) preliminary siting requirements, (4) regulatory justification for the project, and (5) health and safety criteria.

  3. South Carolina Opens Nation's Largest Wind Drivetrain Testing Facility

    Broader source: Energy.gov [DOE]

    Today, U.S. Deputy Secretary of Energy Daniel Poneman joined with officials from Clemson University to dedicate the nation's largest and one of the world's most advanced wind energy testing facilities in North Charleston, S.C.

  4. EIS-0228: Dual Axis Radiographic Hydrodynamic Test (DARHT) Facility

    Broader source: Energy.gov [DOE]

    This EIS evaluates the potential environmental impact of a proposal to construct and operate the Dual Axis Radiographic Hydrodynamic Test (DARHT) facility at Los Alamos National Laboratory (LANL)...

  5. SWiFT Facility & Testing

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

    & Testing - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced Nuclear

  6. Sandia completes major overhaul of key nuclear weapons test facilities |

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration Home / Blog Sandia completes major overhaul of key nuclear weapons test facilities Tuesday, May 13, 2014 - 2:46pm Sandia National Laboratories recently completed the renovation of five large-scale test facilities that are crucial to ensuring the safety and reliability of the nation's nuclear weapons systems. The work supports Sandia's ongoing nuclear stockpile modernization work on the B61-12 and W88 Alt, assessments of current stockpile systems, and

  7. South Carolina Opens Nation's Largest Wind Drivetrain Testing Facility |

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

    Department of Energy 2:00am Addthis Today, U.S. Deputy Secretary of Energy Daniel Poneman joined with officials from Clemson University to dedicate the nation's largest and one of the world's most advanced wind energy testing facilities in North Charleston, S.C. Led by Clemson University's Restoration Institute, the facility will help test and validate new turbines, particularly for offshore wind-helping to speed deployment of next generation energy technology, reduce costs for

  8. SLAC National Accelerator Laboratory FACET & TEST BEAM FACILITIES PROPOSAL

    Office of Scientific and Technical Information (OSTI)

    (Technical Report) | SciTech Connect Technical Report: SLAC National Accelerator Laboratory FACET & TEST BEAM FACILITIES PROPOSAL Citation Details In-Document Search Title: SLAC National Accelerator Laboratory FACET & TEST BEAM FACILITIES PROPOSAL Authors: Merrill, Frank E. [1] ; Borozdin, Konstantin N. [1] ; Garnett, Robert W. [1] ; Mariam, Fesseha G. [1] ; Saunders, Alexander [1] ; Walstrom, Peter L. [1] ; Morris, Christopher [1] + Show Author Affiliations Los Alamos National

  9. Enhanced test facility for OTEC at Keahole Point

    SciTech Connect (OSTI)

    Hillis, D.L.; Stevens, H.C.; Panchal, C.B.

    1983-01-01

    Additional test facilities are being planned for Keahole Point, Hawaii, that would greatly increase the amounts of warm and cold water available for OTEC research and development. Present activities include the design of seawater systems and a pumping station, using the existing OTEC-1 cold-water pipe and pumps. Future options include the installation of available heat exchangers and ammonia-system equipment, the addition of a turbine generator, and facilities for open- and closed-cycle testing of components and systems.

  10. NREL, Clemson University Collaborate on Wind Energy Testing Facilities -

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

    News Releases | NREL NREL, Clemson University Collaborate on Wind Energy Testing Facilities June 8, 2015 Two of our nation's most advanced wind energy research and test facilities have joined forces to help the wind energy industry improve the performance of wind turbine drivetrains and better understand how the turbines can integrate more effectively with the electrical grid. Through a Cooperative Research and Development Agreement (CRADA), the Energy Department's National Renewable Energy

  11. WNR Group Leader Steve Wender LANSCE Neutron Testing Facility

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

    WNR Group Leader Steve Wender LANSCE Neutron Testing Facility 505.667.1344 wender@lanl.gov Proposal Process Contacts WNR User Office Administrator Tanya Herrera 505.667.6797 tanyah@lanl.gov LANSCE User Office Los Alamos Neutron Science Center 505.665.1010 lansce-user-office@lanl.gov For information on user facility agreements and payment terms for industrial users, contact: Technology Transfer Division 505.665.9090 Accelerated Neutron Testing of Semiconductors Los Alamos Neutron Science Center

  12. Accelerator Stewardship Test Facility Program - Elliptical Twin Cavity for

    Office of Scientific and Technical Information (OSTI)

    Accelerator Applications (Program Document) | SciTech Connect Accelerator Stewardship Test Facility Program - Elliptical Twin Cavity for Accelerator Applications Citation Details In-Document Search Title: Accelerator Stewardship Test Facility Program - Elliptical Twin Cavity for Accelerator Applications Funding is being requested pursuant to the proposals entitled Elliptical Twin Cavity for Accelerator Applications that was submitted and reviewed through the Portfolio Analysis and Management

  13. Safety requirements, facility user needs, and reactor concepts for a new Broad Application Test Reactor

    SciTech Connect (OSTI)

    Ryskamp, J.M.; Liebenthal, J.L.; Denison, A.B.; Fletcher, C.D.

    1992-07-01

    This report describes the EG&G Laboratory Directed Research and Development Program (LDRD) Broad Application Test Reactor (BATR) Project that was conducted in fiscal year 1991. The scope of this project was divided into three phases: a project process definition phase, a requirements development phase, and a preconceptual reactor design and evaluation phase. Multidisciplinary teams of experts conducted each phase. This report presents the need for a new test reactor, the project process definition, a set of current and projected regulatory compliance and safety requirements, a set of facility user needs for a broad range of projected testing missions, and descriptions of reactor concepts capable of meeting these requirements. This information can be applied to strategic planning to provide the Department of Energy with management options.

  14. Safety requirements, facility user needs, and reactor concepts for a new Broad Application Test Reactor

    SciTech Connect (OSTI)

    Ryskamp, J.M.; Liebenthal, J.L.; Denison, A.B.; Fletcher, C.D.

    1992-07-01

    This report describes the EG G Laboratory Directed Research and Development Program (LDRD) Broad Application Test Reactor (BATR) Project that was conducted in fiscal year 1991. The scope of this project was divided into three phases: a project process definition phase, a requirements development phase, and a preconceptual reactor design and evaluation phase. Multidisciplinary teams of experts conducted each phase. This report presents the need for a new test reactor, the project process definition, a set of current and projected regulatory compliance and safety requirements, a set of facility user needs for a broad range of projected testing missions, and descriptions of reactor concepts capable of meeting these requirements. This information can be applied to strategic planning to provide the Department of Energy with management options.

  15. Testing, Manufacturing, and Component Development Projects

    Broader source: Energy.gov [DOE]

    This report covers the Wind and Water Power Technologies Office's testing, manufacturing, and component development projects for utility-scale and distributed wind energy from fiscal years 2006 to 2014.

  16. Test facilities for evaluating nuclear thermal propulsion systems

    SciTech Connect (OSTI)

    Beck, D.F.; Allen, G.C.; Shipers, L.R.; Dobranich, D.; Ottinger, C.A.; Harmon, C.D.; Fan, W.C. ); Todosow, M. )

    1992-09-22

    Interagency panels evaluating nuclear thermal propulsion (NTP) development options have consistently recognized the need for constructing a major new ground test facility to support fuel element and engine testing. This paper summarizes the requirements, configuration, and baseline performance of some of the major subsystems designed to support a proposed ground test complex for evaluating nuclear thermal propulsion fuel elements and engines being developed for the Space Nuclear Thermal Propulsion (SNTP) program. Some preliminary results of evaluating this facility for use in testing other NTP concepts are also summarized.

  17. WIND TURBINE DRIVETRAIN TEST FACILITY DATA ACQUISITION SYSTEM

    SciTech Connect (OSTI)

    Mcintosh, J.

    2012-01-03

    The Wind Turbine Drivetrain Test Facility (WTDTF) is a state-of-the-art industrial facility used for testing wind turbine drivetrains and generators. Large power output wind turbines are primarily installed for off-shore wind power generation. The facility includes two test bays: one to accommodate turbine nacelles up to 7.5 MW and one for nacelles up to 15 MW. For each test bay, an independent data acquisition system (DAS) records signals from various sensors required for turbine testing. These signals include resistance temperature devices, current and voltage sensors, bridge/strain gauge transducers, charge amplifiers, and accelerometers. Each WTDTF DAS also interfaces with the drivetrain load applicator control system, electrical grid monitoring system and vibration analysis system.

  18. CENER/NREL Collaboration in Testing Facility and Code Development: Cooperative Research and Development Final Report, CRADA Number CRD-06-207

    SciTech Connect (OSTI)

    Moriarty, P.

    2014-11-01

    Under the funds-in CRADA agreement, NREL and CENER will collaborate in the areas of blade and drivetrain testing facility development and code development. The project shall include NREL assisting in the review and instruction necessary to assist in commissioning the new CENER blade test and drivetrain test facilities. In addition, training will be provided by allowing CENER testing staff to observe testing and operating procedures at the NREL blade test and drivetrain test facilities. CENER and NREL will exchange blade and drivetrain facility and equipment design and performance information. The project shall also include exchanging expertise in code development and data to validate numerous computational codes.

  19. Environmental Assessment -- Test Area North pool stabilization project update

    SciTech Connect (OSTI)

    1997-08-01

    The purpose of this Environmental Assessment (EA) is to update the ``Test Area North Pool Stabilization Project`` EA (DOE/EA-1050) and finding of no significant impact (FONSI) issued May 6, 1996. This update analyzes the environmental and health impacts of a drying process for the Three Mile Island (TMI) nuclear reactor core debris canisters now stored underwater in a facility on the Idaho National Engineering and Environmental Laboratory (INEEL). A drying process was analyzed in the predecision versions of the EA released in 1995 but that particular process was determined to be ineffective and dropped from the EA/FONSI issued May 6, 1996. A new drying process was subsequently developed and is analyzed in Section 2.1.2 of this document. As did the 1996 EA, this update analyzes the environmental and health impacts of removing various radioactive materials from underwater storage, dewatering these materials, constructing a new interim dry storage facility, and transporting and placing the materials into the new facility. Also, as did the 1996 EA, this EA analyzes the removal, treatment and disposal of water from the pool, and placement of the facility into a safe, standby condition. The entire action would take place within the boundaries of the INEEL. The materials are currently stored underwater in the Test Area North (TAN) building 607 pool, the new interim dry storage facility would be constructed at the Idaho Chemical Processing Plant (ICPP) which is about 25 miles south of TAN.

  20. Active test of separation facility at Rokkasho reprocessing plant

    SciTech Connect (OSTI)

    Iseki, Tadahiro; Inaba, Makoto; Takahashi, Naoki

    2007-07-01

    During the second and third steps of Active Test at Rokkasho Reprocessing Plant (RRP), the performances of the Separation Facility have been checked; (A) diluent washing efficiency, (B) plutonium stripping efficiency, (C) decontamination factor of fission products and (D) plutonium and uranium leakage into raffinate and spent solvent. Test results were equivalent to or better than expected. (authors)

  1. National RF Test Facility as a multipurpose development tool

    SciTech Connect (OSTI)

    McManamy, T.J.; Becraft, W.R.; Berry, L.A.; Blue, C.W.; Gardner, W.L.; Haselton, H.H.; Hoffman, D.J.; Loring, C.M. Jr.; Moeller, F.A.; Ponte, N.S.

    1983-01-01

    Additions and modifications to the National RF Test Facility design have been made that (1) focus its use for technology development for future large systems in the ion cyclotron range of frequencies (ICRF), (2) expand its applicability to technology development in the electron cyclotron range of frequencies (ECRF) at 60 GHz, (3) provide a facility for ELMO Bumpy Torus (EBT) 60-GHz ring physics studies, and (4) permit engineering studies of steady-state plasma systems, including superconducting magnet performance, vacuum vessel heat flux removal, and microwave protection. The facility will continue to function as a test bed for generic technology developments for ICRF and the lower hybrid range of frequencies (LHRF). The upgraded facility is also suitable for mirror halo physics experiments.

  2. Cryogenic systems for the Mirror Fusion Test Facility

    SciTech Connect (OSTI)

    Slack, D.S.; Nelson, R.L.; Chronis, W.C.

    1985-08-01

    This paper includes an in-depth discussion of the design, fabrication, and operation of the Mirror Fusion Test Facility (MFTF) cryogenic system located at Lawrence Livermore National Laboratory (LLNL). Each subsystem discussed to present a basic composite of the entire facility. The following subsystems are included: 500kW nitrogen reliquefier, subcoolers, and distribution system; 15kW helium refrigerator/liquefier and distribution system; helium recovery and storage system; rough vacuum and high vacuum systems.

  3. Sandia National Laboratories Algae Raceway Testing Facility Ribbon Cutting

    Broader source: Energy.gov [DOE]

    Sandia National Laboratories will be hosting a ribbon cutting on Feb. 4, 2016 at its Livermore Valley Open Campus to commemorate the opening of a new algae raceway testing facility. The new facility will allow researchers to better understand algal cultivation techniques, and is funded in part by the Bioenergy Technologies Office. Advanced Algal Systems Program Manager Alison Goss Eng and Technology Manager Daniel Fishman will be in attendance.

  4. Environmental Restoration Disposal Facility (Project W-296) Safety Assessment

    SciTech Connect (OSTI)

    Armstrong, D.L.

    1994-08-01

    This Safety Assessment is based on information derived from the Conceptual Design Report for the Environmental Restoration Disposal Facility (DOE/RL 1994) and ancillary documentation developed during the conceptual design phase of Project W-296. The Safety Assessment has been prepared to support the Solid Waste Burial Ground Interim Safety Basis document. The purpose of the Safety Assessment is to provide an evaluation of the design to determine if the process, as proposed, will comply with US Department of Energy (DOE) Limits for radioactive and hazardous material exposures and be acceptable from an overall health and safety standpoint. The evaluation considered affects on the worker, onsite personnel, the public, and the environment.

  5. Mission Need Statement: Idaho Spent Fuel Facility Project

    SciTech Connect (OSTI)

    Barbara Beller

    2007-09-01

    Approval is requested based on the information in this Mission Need Statement for The Department of Energy, Idaho Operations Office (DOE-ID) to develop a project in support of the mission established by the Office of Environmental Management to "complete the safe cleanup of the environmental legacy brought about from five decades of nuclear weapons development and government-sponsored nuclear energy research". DOE-ID requests approval to develop the Idaho Spent Fuel Facility Project that is required to implement the Department of Energy's decision for final disposition of spent nuclear fuel in the Geologic Repository at Yucca Mountain. The capability that is required to prepare Spent Nuclear Fuel for transportation and disposal outside the State of Idaho includes characterization, conditioning, packaging, onsite interim storage, and shipping cask loading to complete shipments by January 1,2035. These capabilities do not currently exist in Idaho.

  6. Summary of Testing of SuperLig 639 at the TFL Ion Exchange Facility

    SciTech Connect (OSTI)

    Steimke, J.L.

    2000-12-19

    A pilot scale facility was designed and built in the Thermal Fluids Laboratory at the Savannah River Technology Center to test ion exchange resins for removing technetium and cesium from simulated Hanford Low Activity Waste (LAW). The facility supports the design of the Hanford River Protection Project for BNFL, Inc. The pilot scale system mimics the full-length of the columns and the operational scenario of the planned ion exchange system. Purposes of the testing include confirmation of the design, evaluation of methods for process optimization and developing methods for waste volume minimization. This report documents the performance of the technetium removal resin.

  7. Cryogenic infrastructure for Fermilab's ILC vertical cavity test facility

    SciTech Connect (OSTI)

    Carcagno, R.; Ginsburg, C.; Huang, Y.; Norris, B.; Ozelis, J.; Peterson, T.; Poloubotko, V.; Rabehl, R.; Sylvester, C.; Wong, M.; /Fermilab

    2006-06-01

    Fermilab is building a Vertical Cavity Test Facility (VCTF) to provide for R&D and pre-production testing of bare 9-cell, 1.3-GHz superconducting RF (SRF) cavities for the International Linear Collider (ILC) program. This facility is located in the existing Industrial Building 1 (IB1) where the Magnet Test Facility (MTF) also resides. Helium and nitrogen cryogenics are shared between the VCTF and MTF including the existing 1500-W at 4.5-K helium refrigerator with vacuum pumping for super-fluid operation (125-W capacity at 2-K). The VCTF is being constructed in multiple phases. The first phase is scheduled for completion in mid 2007, and includes modifications to the IB1 cryogenic infrastructure to allow helium cooling to be directed to either the VCTF or MTF as scheduling demands require. At this stage, the VCTF consists of one Vertical Test Stand (VTS) cryostat for the testing of one cavity in a 2-K helium bath. Planning is underway to provide a total of three Vertical Test Stands at VCTF, each capable of accommodating two cavities. Cryogenic infrastructure improvements necessary to support these additional VCTF test stands include a dedicated ambient temperature vacuum pump, a new helium purification skid, and the addition of helium gas storage. This paper describes the system design and initial cryogenic operation results for the first VCTF phase, and outlines future cryogenic infrastructure upgrade plans for expanding to three Vertical Test Stands.

  8. 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.

  9. Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management

    SciTech Connect (OSTI)

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system.

  10. Project Impact Assessments: Building America FY14 Field Test...

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

    Project Impact Assessments: Building America FY14 Field Test Technical Support - 2014 BTO Peer Review Project Impact Assessments: Building America FY14 Field Test Technical Support ...

  11. Property:Did The Test Results Demonstrate Projected Performance...

    Open Energy Info (EERE)

    Did The Test Results Demonstrate Projected Performance? Jump to: navigation, search Property Name Did The Test Results Demonstrate Projected Performance? Property Type Text...

  12. Cryogenic vertical test facility for the SRF cavities at BNL

    SciTech Connect (OSTI)

    Than, R.; Liaw, CJ; Porqueddu, R.; Grau, M.; Tuozzolo, J.; Tallerico, T.; McIntyre, G.; Lederle, D.; Ben-Zvi, I.; Burrill, A.; Pate, D.

    2011-03-28

    A vertical test facility has been constructed to test SRF cavities and can be utilized for other applications. The liquid helium volume for the large vertical dewar is approximate 2.1m tall by 1m diameter with a clearance inner diameter of 0.95m after the inner cold magnetic shield installed. For radiation enclosure, the test dewar is located inside a concrete block structure. The structure is above ground, accessible from the top, and equipped with a retractable concrete roof. A second radiation concrete facility, with ground level access via a labyrinth, is also available for testing smaller cavities in 2 smaller dewars. The cryogenic transfer lines installation between the large vertical test dewar and the cryo plant's sub components is currently near completion. Controls and instrumentations wiring are also nearing completion. The Vertical Test Facility will allow onsite testing of SRF cavities with a maximum overall envelope of 0.9 m diameter and 2.1 m height in the large dewar and smaller SRF cavities and assemblies with a maximum overall envelope of 0.66 m diameter and 1.6 m height.

  13. Facility Configuration Study of the High Temperature Gas-Cooled Reactor Component Test Facility

    SciTech Connect (OSTI)

    S. L. Austad; L. E. Guillen; D. S. Ferguson; B. L. Blakely; D. M. Pace; D. Lopez; J. D. Zolynski; B. L. Cowley; V. J. Balls; E.A. Harvego, P.E.; C.W. McKnight, P.E.; R.S. Stewart; B.D. Christensen

    2008-04-01

    A test facility, referred to as the High Temperature Gas-Cooled Reactor Component Test Facility or CTF, will be sited at Idaho National Laboratory for the purposes of supporting development of high temperature gas thermal-hydraulic technologies (helium, helium-Nitrogen, CO2, etc.) as applied in heat transport and heat transfer applications in High Temperature Gas-Cooled Reactors. Such applications include, but are not limited to: primary coolant; secondary coolant; intermediate, secondary, and tertiary heat transfer; and demonstration of processes requiring high temperatures such as hydrogen production. The facility will initially support completion of the Next Generation Nuclear Plant. It will secondarily be open for use by the full range of suppliers, end-users, facilitators, government laboratories, and others in the domestic and international community supporting the development and application of High Temperature Gas-Cooled Reactor technology. This pre-conceptual facility configuration study, which forms the basis for a cost estimate to support CTF scoping and planning, accomplishes the following objectives: • Identifies pre-conceptual design requirements • Develops test loop equipment schematics and layout • Identifies space allocations for each of the facility functions, as required • Develops a pre-conceptual site layout including transportation, parking and support structures, and railway systems • Identifies pre-conceptual utility and support system needs • Establishes pre-conceptual electrical one-line drawings and schedule for development of power needs.

  14. Final Design Report for the RH LLW Disposal Facility (RDF) Project

    SciTech Connect (OSTI)

    Austad, Stephanie Lee

    2015-09-01

    The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.

  15. Final Design Report for the RH LLW Disposal Facility (RDF) Project

    SciTech Connect (OSTI)

    Austad, S. L.

    2015-05-01

    The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.

  16. Fermilab Test Beam Facility Annual Report. FY 2014

    SciTech Connect (OSTI)

    Brandt, A.

    2015-01-01

    Fermilab Test Beam Facility (FTBF) operations are summarized for FY 2014. It is one of a series of publications intended to gather information in one place. In this case, the information concerns the individual experiments that ran at FTBF. Each experiment section was prepared by the relevant authors, and was edited for inclusion in this summary.

  17. High temperature materials experience at the Central Receiver Test Facility

    SciTech Connect (OSTI)

    Holmes, J.T.

    1982-01-01

    During four years of operation at the Central Receiver Test Facility (CRTF) ceramics have performed well in cyclic solar flux densities of less than 30 W/cm/sup 2/. Above 100 W/cm/sup 2/, serious limitations exist. Important application considerations include: the geometry, cyclic and long time exposures, flux density gradients, thermal shock, weathering, and soiling.

  18. Use of the fast flux test facility for tritium production

    SciTech Connect (OSTI)

    Drell, S.; Hammer, D.; Cornwall, J.M.; Dyson, F.; Garwin, R.

    1996-10-25

    This report provides the results of a JASON review of the technical feasibility of using the Department of Energy`s (DOE`s) Fast Flux Test Facility (FFTF) to generate tritium needed for the enduring United States nuclear weapons stockpile.

  19. PROJECT MANGEMENT PLAN EXAMPLES Facility End State Decisions Examples

    Office of Environmental Management (EM)

    Facility End State Decisions Examples Example 3 3.0 POST DEACTIVATION END STATE VISION The Heavy Water Facility is scheduled to cease moderator operations and commence final shutdown of moderator processing and processing support systems. The Heavy Water Facility and supporting facilities will be declared excess. Deactivation will place the facilities into a passively safe, minimal cost, long term S&M mode. At the end of the deactivation period, the facilities will be categorized

  20. Fast Flux Test Facility Asbestos Location Tracking Program

    SciTech Connect (OSTI)

    REYNOLDS, J.A.

    1999-04-13

    Procedure Number HNF-PRO-408, revision 0, paragraph 1.0, ''Purpose,'' and paragraph 2.0, ''Requirements for Facility Management of Asbestos,'' relate building inspection and requirements for documentation of existing asbestos-containing building material (ACBM) per each building assessment. This documentation shall be available to all personnel (including contractor personnel) entering the facility at their request. Corrective action was required by 400 Area Integrated Annual Appraisal/Audit for Fiscal Year 1992 (IAA-92-0007) to provide this notification documentation. No formal method had been developed to communicate the location and nature of ACBM to maintenance personnel in the Fast Flux Test Facility (FFTF) 400 Area. The scope of this Data Package Document is to locate and evaluate any ACBM found at FFTF which constitutes a baseline. This includes all buildings within the protected area. These findings are compiled from earlier reports, numerous work packages and engineering evaluations of employee findings.

  1. Nondestructive Evaluation and Monitoring Projects NASA White...

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

    Nondestructive Evaluation and Monitoring Projects NASA White Sands Test Facility (WSTF) Nondestructive Evaluation and Monitoring Projects NASA White Sands Test Facility (WSTF) ...

  2. Integrated Disposal Facility FY 2012 Glass Testing Summary Report

    SciTech Connect (OSTI)

    Pierce, Eric M.; Kerisit, Sebastien N.; Krogstad, Eirik J.; Burton, Sarah D.; Bjornstad, Bruce N.; Freedman, Vicky L.; Cantrell, Kirk J.; Snyder, Michelle MV; Crum, Jarrod V.; Westsik, Joseph H.

    2013-03-29

    PNNL is conducting work to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility for Hanford immobilized low-activity waste (ILAW). Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program, PNNL is implementing a strategy, consisting of experimentation and modeling, to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. Key activities in FY12 include upgrading the STOMP/eSTOMP codes to do near-field modeling, geochemical modeling of PCT tests to determine the reaction network to be used in the STOMP codes, conducting PUF tests on selected glasses to simulate and accelerate glass weathering, developing a Monte Carlo simulation tool to predict the characteristics of the weathered glass reaction layer as a function of glass composition, and characterizing glasses and soil samples exhumed from an 8-year lysimeter test. The purpose of this report is to summarize the progress made in fiscal year (FY) 2012 and the first quarter of FY 2013 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of LAW glasses.

  3. Environmental assessment report: Nuclear Test Technology Complex. [Construction and operation of proposed facility

    SciTech Connect (OSTI)

    Tonnessen, K.; Tewes, H.A.

    1982-08-01

    The US Department of Energy (USDOE) is planning to construct and operate a structure, designated the Nuclear Test Technology Complex (NTTC), on a site located west of and adjacent to the Lawrence Livermore National Laboratory. The NTTC is designed to house 350 nuclear test program personnel, and will accommodate the needs of the entire staff of the continuing Nuclear Test Program (NTP). The project has three phases: land acquisition, facility construction and facility operation. The purpose of this environmental assessment report is to describe the activities associated with the three phases of the NTTC project and to evaluate potential environmental disruptions. The project site is located in a rural area of southeastern Alameda County, California, where the primary land use is agriculture; however, the County has zoned the area for industrial development. The environmental impacts of the project include surface disturbance, high noise levels, possible increases in site erosion, and decreased air quality. These impacts will occur primarily during the construction phase of the NTTC project and can be mitigated in part by measures proposed in this report.

  4. PPPL to launch major upgrade of key fusion energy test facility | Princeton

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

    Plasma Physics Lab to launch major upgrade of key fusion energy test facility NSTX project will produce most powerful spherical torus in the world By John Greenwald January 9, 2012 Tweet Widget Google Plus One Share on Facebook NSTX-U cross section. NSTX-U cross section. Gallery: (Photo by Elle Starkman, PPPL Office of Communications) (Photo by Elle Starkman, PPPL Office of Communications) (Photo by Elle Starkman, PPPL Office of Communications) (Photo by Elle Starkman, PPPL Office of

  5. Test program element II blanket and shield thermal-hydraulic and thermomechanical testing, experimental facility survey

    SciTech Connect (OSTI)

    Ware, A.G.; Longhurst, G.R.

    1981-12-01

    This report presents results of a survey conducted by EG and G Idaho to determine facilities available to conduct thermal-hydraulic and thermomechanical testing for the Department of Energy Office of Fusion Energy First Wall/Blanket/Shield Engineering Test Program. In response to EG and G queries, twelve organizations (in addition to EG and G and General Atomic) expressed interest in providing experimental facilities. A variety of methods of supplying heat is available.

  6. Assembly and installation of the large coil test facility test stand

    SciTech Connect (OSTI)

    Queen, C.C. Jr.

    1983-01-01

    The Large Coil Test Facility (LCTF) was built to test six tokamak-type superconducting coils, with three to be designed and built by US industrial teams and three provided by Japan, Switzerland, and Euratom under an international agreement. The facility is designed to test these coils in an environment which simulates that of a tokamak. The heart of this facility is the test stand, which is made up of four major assemblies: the Gravity Base Assembly, the Bucking Post Assembly, the Torque Ring Assembly, and the Pulse Coil Assembly. This paper provides a detailed review of the assembly and installation of the test stand components and the handling and installation of the first coil into the test stand.

  7. Recovery Act: Hydroelectric Facility Improvement Project - Replacement of Current Mechanical Seal System with Rope Packing System

    SciTech Connect (OSTI)

    Stephens, Jessica D.

    2013-05-29

    On January 27, 2010 the City of North Little Rock, Arkansas received notification of the awarding of a Department of Energy (DOE) grant totaling $450,000 in funding from the American Recovery and Reinvestment Act (ARRA) under the Project Title: Recovery Act: Hydroelectric Facility Improvement Project – Automated Intake Clearing Equipment and Materials Management. The purpose of the grant was for improvements to be made at the City’s hydroelectric generating facility located on the Arkansas River. Improvements were to be made through the installation of an intake maintenance device (IMD) and the purchase of a large capacity wood grinder. The wood grinder was purchased in order to receive the tree limbs, tree trunks, and other organic debris that collects at the intake of the plant during high flow. The wood grinder eliminates the periodic burning of the waste material that is cleared from the intake and reduces any additional air pollution to the area. The resulting organic mulch has been made available to the public at no charge. Design discussion and planning began immediately and the wood grinder was purchased in July of 2010 and immediately put to work mulching debris that was gathered regularly from the intake of the facility. The mulch is currently available to the public for free. A large majority of the design process was spent in discussion with the Corps of Engineers to obtain approval for drawings, documents, and permits that were required in order to make changes to the structure of the powerhouse. In April of 2011, the City’s Project Engineer, who had overseen the application, resigned and left the City’s employ. A new Systems Mechanical Engineer was hired and tasked with overseeing the project. The transfer of responsibility led to a re-examination of the original assumptions and research upon which the grant proposal was based. At that point, the project went under review and a trip was booked for July 2011 to visit facilities that currently had an IMD installed. This further study of facilities revealed that the implementation of the project as originally described, while proving the benefits described in the original grant application, would likely intensify sand intake. Increased sand intake would lead to an increase in required shutdowns for maintenance and more rapid depreciation of key equipment which would result in a loss of generation capacity. A better solution to the problem, one that continued to meet the criteria for the original grant and ARRA standards, was developed. A supporting day trip was planned to visit other facilities located on the Arkansas River to determine how they were coping with the same strong amounts of sand, silt, and debris. Upon returning from the trip to other Arkansas River facilities it was extremely clear what direction to go in order to most efficiently address the issue of generator capacity and efficiency. Of the plants visited on the Arkansas River, every one of them was running what is called a rope packing shaft sealing system as opposed to mechanical shaft seals, which the facility was running. Rope packing is a time proven sealing method that has been around for centuries. It has proved to perform very well in dirty water situations just like that of the Arkansas River. In April of 2012 a scope change proposal was submitted to the DOE for approval. In August of 2012 the City received word that the change of scope had been approved. Plans were immediately set in motion to begin the conversion from mechanical seals to a packing box at the facility. Contractors arrived on October 1st, 2012 and the project team began unwatering the unit for disassembly. The seal conversion was completed on February 29th, 2013 with start-up of the unit. Further testing and adjusting was done throughout the first two weeks of March.

  8. Sandia National Laboratories: Facilities

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

    Facilities State-Of-The-Art Supporting all elements of IMS projects Facilities Labs and Test Sites Integrated Military Systems maintains a number of state-of-the-art testing and fabrication facilities. Supporting all elements of IMS projects including design, prototyping, fabrication, development, testing, and assessments, these facilities enable customers to quickly realize their projects and get the information they need in a fast and effective way. Use the "left" and

  9. DOE-STD-3026-99; DOE Standard Filter Test Facility Quality Program...

    Energy Savers [EERE]

    Superseding DOE NE F 3-44 July 1986 DOE STANDARD FILTER TEST FACILITY QUALITY PROGRAM PLAN ... for HEPA filter testing performed at a DOE-accepted HEPA Filter Test Facility (FTF). ...

  10. Status of fuel, blanket, and absorber testing in the fast flux test facility

    SciTech Connect (OSTI)

    Baker, R.B.; Bard, F.E.; Leggett, R.D.; Pitner, A.L. )

    1992-01-01

    On December 2, 1980, the Fast Flux Test Facility (FFTF) reached its full design power of 400 MW for the first time. From the start, the FFTF provided a modern liquid-metal reactor (LMR) test facility recognized for excellence, innovation, and efficiency of operation. Its unique instrumentation and special test capabilities have allowed the facility to stay at the cutting edge of technology. Prototypical size and core environment allow the FFTF to demonstrate core components and directly support design optimization of LMRs. Since December 1980, the FFTF has irradiated > 64,000 mixed-oxide driver and test fuel pins, > 1,000 metal-fueled pins, > 100 carbide-fueled pins, and > 35 nitride-fueled pins (supporting the U.S. space reactor program). This paper reviews the status of one of the major activities at the FFTF for its first 12 yr of operation - DOE-sponsored testing and development of fuel, blanket, and absorber assemblies for commercial LMRs.

  11. Thermionic system evaluation test (TSET) facility construction: A United States and Russian effort

    SciTech Connect (OSTI)

    Wold, S.K.

    1992-01-01

    The Thermionic System Evaluation Test (TSET) is a ground test of an unfueled Russian TOPAZ-II in-core thermionic space reactor powered by electric heaters. The facility that will be used for testing of the TOPAZ-II systems is located at the New Mexico Engineering Research Institute (NMERI) complex in Albuquerque, NM. The reassembly of the Russian test equipment is the responsibility of International Scientific Products (ISP), a San Jose, CA, company and Inertek, a Russian corporation, with support provided by engineers and technicians from Phillips Laboratory (PL), Sandia National Laboratories (SNL), Los Alamos National Laboratory (LANL), and the University of New Mexico (UNM). This test is the first test to be performed under the New Mexico Strategic Alliance agreement. This alliance consist of the PL, SNL, LANL, and UNM. The testing is being funded by the Strategic Defense Initiative Organization (SDIO) with the PL responsible for project execution.

  12. Facility Software Quality Assurance for Capital Project Decisions RM

    Office of Environmental Management (EM)

    Facility Representative of the Year Award Facility Representative of the Year Award The Facility Representative Award Program is a special award designed to recognize superior or exemplary service by a Facility Representative over a period of one year. This special award program has been established in accordance with the requirements of Department of Energy (DOE) Order 331.1C, Employee Performance Management and Recognition Program. PDF icon FROTY_Guidance_14-11-13.pdf Responsible Contacts

  13. Large-Scale Industrial CCS Projects Selected for Continued Testing |

    Energy Savers [EERE]

    Large-Scale Federal Renewable Energy Projects Large-Scale Federal Renewable Energy Projects Renewable energy projects larger than 10 megawatts (MW), also known as utility-scale projects, are complex and typically require private-sector financing. The Federal Energy Management Program (FEMP) developed a guide to help federal agencies, and the developers and financiers that work with them, to successfully install these projects at federal facilities. FEMP's Large-Scale Renewable Energy Guide,

  14. Integrated Disposal Facility FY2011 Glass Testing Summary Report

    SciTech Connect (OSTI)

    Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Westsik, Joseph H.

    2011-09-29

    Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 x 10{sup 5} m{sup 3} of glass (Certa and Wells 2010). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 8.9 x 10{sup 14} Bq total activity) of long-lived radionuclides, principally {sup 99}Tc (t{sub 1/2} = 2.1 x 10{sup 5}), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2011 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses.

  15. Major Risk Factors Integrated Facility Disposition Project - Oak Ridge

    Office of Environmental Management (EM)

    D D e e p p a a r r t t m m e e n n t t o o f f E E n n e e r r g g y y O O f f f f i i c c e e o o f f E E n n v v i i r r o o n n m m e e n n t t a a l l M M a a n n a a g g e e m m e e n n t t ( ( E E M M ) ) E E n n g g i i n n e e e e r r i i n n g g a a n n d d T T e e c c h h n n o o l l o o g g y y External Technical Review (ETR) Report Major Risk Factors Integrated Facility Disposition Project (IFDP) Oak Ridge, TN AUGUST 1, 2008 Acknowledgement The External Technical Review of the

  16. Sandia National Laboratories/New Mexico existing environmental analyses bounding environmental test facilities.

    SciTech Connect (OSTI)

    May, Rodney A.; Bailey-White, Brenda E.; Cantwell, Amber

    2009-06-01

    This report identifies current environmental operating parameters for the various test and support facilities at SNL/NM. The intent of this report is solely to provide the limits which bound the facilities' operations. Understanding environmental limits is important to maximizing the capabilities and working within the existing constraints of each facility, and supports the decision-making process in meeting customer requests, cost and schedule planning, modifications to processes, future commitments, and use of resources. Working within environmental limits ensures that mission objectives will be met in a manner that protects human health and the environment. It should be noted that, in addition to adhering to the established limits, other approvals and permits may be required for specific projects.

  17. The Potential Role of a New Generation of Outdoor Building Test Facilities for Validation of Whole Building Simulation Tools

    Energy Savers [EERE]

    Program S. Selkowitz Lawrence Berkeley National Laboratory The Potential Role of a New Generation of Outdoor Building Test Facilities for Validation of Whole Building Simulation Tools Outline * Background and Context for Systems Testing * 30 years of Field Test Experience and Model Validation * Design Criteria for FLEXLAB * FLEXLAB Features and Status * Initial FLEXLAB test projects * FLEXLAB Calibration Status 2 Single component or isolated system EEM Current Design and Research Paradigm - Silo

  18. Pyroprocessing of fast flux test facility nuclear fuel

    SciTech Connect (OSTI)

    Westphal, B.R.; Wurth, L.A.; Fredrickson, G.L.; Galbreth, G.G.; Vaden, D.; Elliott, M.D.; Price, J.C.; Honeyfield, E.M.; Patterson, M.N.

    2013-07-01

    Used nuclear fuel from the Fast Flux Test Facility (FFTF) was recently transferred to the Idaho National Laboratory and processed by pyroprocessing in the Fuel Conditioning Facility. Approximately 213 kg of uranium from sodium-bonded metallic FFTF fuel was processed over a one year period with the equipment previously used for the processing of EBR-II used fuel. The peak burnup of the FFTF fuel ranged from 10 to 15 atom% for the 900+ chopped elements processed. Fifteen low-enriched uranium ingots were cast following the electrorefining and distillation operations to recover approximately 192 kg of uranium. A material balance on the primary fuel constituents, uranium and zirconium, during the FFTF campaign will be presented along with a brief description of operating parameters. Recoverable uranium during the pyroprocessing of FFTF nuclear fuel was greater than 95% while the purity of the final electro-refined uranium products exceeded 99%. (authors)

  19. Pyroprocessing of Fast Flux Test Facility Nuclear Fuel

    SciTech Connect (OSTI)

    B.R. Westphal; G.L. Fredrickson; G.G. Galbreth; D. Vaden; M.D. Elliott; J.C. Price; E.M. Honeyfield; M.N. Patterson; L. A. Wurth

    2013-10-01

    Used nuclear fuel from the Fast Flux Test Facility (FFTF) was recently transferred to the Idaho National Laboratory and processed by pyroprocessing in the Fuel Conditioning Facility. Approximately 213 kg of uranium from sodium-bonded metallic FFTF fuel was processed over a one year period with the equipment previously used for the processing of EBR-II used fuel. The peak burnup of the FFTF fuel ranged from 10 to 15 atom% for the 900+ chopped elements processed. Fifteen low-enriched uranium ingots were cast following the electrorefining and distillation operations to recover approximately 192 kg of uranium. A material balance on the primary fuel constituents, uranium and zirconium, during the FFTF campaign will be presented along with a brief description of operating parameters. Recoverable uranium during the pyroprocessing of FFTF nuclear fuel was greater than 95% while the purity of the final electrorefined uranium products exceeded 99%.

  20. The materials test station: a fast spectrum irradiation facility

    SciTech Connect (OSTI)

    Pitcher, Eric J.

    2007-07-01

    The Materials Test Station is a fast-neutron spectrum irradiation facility under design at the Los Alamos National Laboratory in support of the United States Department of Energy's Global Nuclear Energy Partnership. The facility will be capable of rodlets-scale irradiations of candidate fuel forms being developed to power the next generation of fast reactors. Driven by a powerful proton beam, the fuel irradiation region exhibits a neutron spectrum similar to that seen in a fast reactor, with a peak neutron flux of 1.6 x 10{sup 15} n.cm{sup -2}.s{sup -1}. Site preparation and construction are estimated to take four years, with a cost range of $60 M to $90 M. (author)

  1. Sicangu Lakota Oyate, Hihan Sapa Wapaha, Tate Woilagyapi Project - 30 MW Wind Energy Facility

    Energy Savers [EERE]

    Sicangu Lakota Oyate (Rosebud Sioux Tribe) Hihan Sapa Wapaha Tate Woilagyapi Project (Owl Feather War Bonnet Wind Project) 30 MW Wind Energy Facility Phil Two Eagle, Director Ken Haukaas, Project Manager Resource Development Office Dale Osborn, President Distributed Generation Systems, Inc. (DISGEN) www.disgenonline.com Sicangu Lakota Oyate (Rosebud Sioux Tribe) Hihan Sapa Wapaha Tate Woilagyapi Project (Owl Feather War Bonnet Wind Project) Project Objectives 1. Complete all the development

  2. Five years operating experience at the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Baumhardt, R. J.; Bechtold, R. A.

    1987-04-01

    The Fast Flux Test Facility (FFTF) is a 400 Mw(t), loop-type, sodium-cooled, fast neutron reactor. It is operated by the Westinghouse Hanford Company for the United States Department of Energy at Richland, Washington. The FFTF is a multipurpose test reactor used to irradiate fuels and materials for programs such as Liquid Metal Reactor (LMR) research, fusion research, space power systems, isotope production and international research. FFTF is also used for testing concepts to be used in Advanced Reactors which will be designed to maximize passive safety features and not require complex shutdown systems to assure safe shutdown and heat removal. The FFTF also provides experience in the operation and maintenance of a reactor having prototypic components and systems typical of large LMR (LMFBR) power plants. The 5 year operational performance of the FFTF reactor is discussed in this report. 6 refs., 10 figs., 2 tabs.

  3. Oxy-Combustion Burner and Integrated Pollutant Removal Research and Development Test Facility

    SciTech Connect (OSTI)

    Mark Schoenfield; Manny Menendez; Thomas Ochs; Rigel Woodside; Danylo Oryshchyn

    2012-09-30

    A high flame temperature oxy-combustion test facility consisting of a 5 MWe equivalent test boiler facility and 20 KWe equivalent IPR® was constructed at the Hammond, Indiana manufacturing site. The test facility was operated natural gas and coal fuels and parametric studies were performed to determine the optimal performance conditions and generated the necessary technical data required to demonstrate the technologies are viable for technical and economic scale-up. Flame temperatures between 4930-6120F were achieved with high flame temperature oxy-natural gas combustion depending on whether additional recirculated flue gases are added to balance the heat transfer. For high flame temperature oxy-coal combustion, flame temperatures in excess of 4500F were achieved and demonstrated to be consistent with computational fluid dynamic modeling of the burner system. The project demonstrated feasibility and effectiveness of the Jupiter Oxygen high flame temperature oxy-combustion process with Integrated Pollutant Removal process for CCS and CCUS. With these technologies total parasitic power requirements for both oxygen production and carbon capture currently are in the range of 20% of the gross power output. The Jupiter Oxygen high flame temperature oxy-combustion process has been demonstrated at a Technology Readiness Level of 6 and is ready for commencement of a demonstration project.

  4. Field Lysimeter Test Facility status report IV: FY 1993

    SciTech Connect (OSTI)

    Gee, G.W.; Felmy, D.G.; Ritter, J.C.; Campbell, M.D.; Downs, J.L.; Fayer, M.J.; Kirkham, R.R.; Link, S.O.

    1993-10-01

    At the U.S. Department of Energy`s Hanford Site near Richland, Washington, a unique facility, the Field Lysimeter Test Facility (FLTF) is used to measure drainage from and water storage in soil covers. Drainage has ranged from near zero amounts to more than 50% of the applied water, with the amount depending on vegetative cover and soil type. Drainage occurred from lysimeters with coarse soils and gravel covers, but did not occur from capillary barrier-type lysimeters (1.5 m silt loam soil over coarse sands and gravels) except under the most extreme condition tested. For capillary barriers that were irrigated and kept vegetation-free (bare surface), no drainage occurred in 5 of the past 6 years. However, this past year (1992--1993) a record snowfall of 1,425 mm occurred and water storage in the irrigated, bare-surfaced capillary barriers exceeded 500 mm resulting in drainage of more than 30 mm from these barriers. In contrast, capillary barriers, covered with native vegetation (i.e., shrubs and grasses) did not drain under any climatic condition (with or without irrigation). In FY 1994, the FLTF treatments will be increased from 11 to 17 with the addition of materials that will simulate portions of a prototype barrier planned for construction in 1994 at the Hanford Site. The 17 FLTF treatments are designed to test the expected range of surface soil, vegetation, and climatic conditions encountered at the Hanford Site and will assist in evaluating final surface barrier designs for a waste disposal facility.

  5. Vehicle Testing and Integration Facility; NREL (National Renewable Energy Laboratory)

    SciTech Connect (OSTI)

    2015-03-02

    Engineers at the National Renewable Energy Laboratory’s (NREL’s) Vehicle Testing and Integration Facility (VTIF) are developing strategies to address two separate but equally crucial areas of research: meeting the demands of electric vehicle (EV) grid integration and minimizing fuel consumption related to vehicle climate control. Dedicated to renewable and energy-efficient solutions, the VTIF showcases technologies and systems designed to increase the viability of sustainably powered vehicles. NREL researchers instrument every class of on-road vehicle, conduct hardware and software validation for EV components and accessories, and develop analysis tools and technology for the Department of Energy, other government agencies, and industry partners.

  6. Dual Axis Radiographic Hydrodynamic Test Facility | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration Dual Axis Radiographic Hydrodynamic Test Facility An integral part of the national hydrotest program, the DARHT is the world's most powerful x-ray machine. DARHT consists of two electron accelerators oriented at right angles to one another. Each accelerator creates a powerful electron beam that is focused onto a metal target which converts the kinetic energy of the electron beam into high energy x or gamma-rays. The x-ray dose from one DARHT accelerator is the

  7. Polymer Exposure and Testing Facilities at the Savannah River Site

    Office of Environmental Management (EM)

    Polymer Exposure and Testing Facilities at the Savannah River Site Elise B. Fox, Ph.D. Tritium Focus Group April 22, 2014 SRNL-MS-2014-00050 Outline * How we expose our materials * Available characterization methods * Previous and current work 2 Sample Exposure * Design rating for 500 psig and 260°C * Typically loaded with six samples or the same material - ½" * 2" * Load with 1 atm T * Partial pressures have also been loaded * Gas composition confirmed by GC at loading * Record

  8. Maintenance implementation plan for the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Boyd, J.A.

    1997-01-30

    This plan implements the U.S. Department of Energy (DOE) 4330.4B, Maintenance Management Program (1994), at the Fast Flux Test Facility (FFTF). The FFTF is a research and test reactor located near Richland, Washington, and is operated under contract for the DOE by the B&W Hanford Company (BWHC). The intent of this Maintenance Implementation Plan (MIP) is to describe the manner in which the activities of the maintenance function are executed and controlled at the FFTF and how this compares to the requirements of DOE 4330.4B. The MIP ii a living document that is updated through a Facility Maintenance Self- Assessment Program. During the continuing self-assessment program, any discrepancies found are resolved to meet DOE 4330.4B requirements and existing practices. The philosophy of maintenance management at the FFTF is also describe within this MIP. This MIP has been developed based on information obtained from various sources including the following: * A continuing self-assessment against the requirements of the Conduct of Maintenance Order * In-depth reviews conducted by the members of the task team that assembled this MIP * Inputs from routine audits and appraisals conducted at the facility The information from these sources is used to identify those areas in which improvements could be made in the manner in which the facility conducts maintenance activities. The action items identified in Rev. 1 of the MIP have been completed. The MIP is arranged in six sections. Section I is this Executive Summary. Section 2 describes the facility and its 0683 history. Section 3 describes the philosophy of the graded approach and how it is applied at FFTF. Section 3 also discusses the strategy and the basis for the prioritizing resources. Section 4 contains the detailed discussion of `the elements of DOE 4330.4B and their state of implementation. Section 5 is for waivers and requested deviations from the requirements of the order. Section 6 contains a copy of the Maintenance Self-Assessment Schedule for the FFTF. In January 1997, the Secretary of Energy declared that DOE-HQ planned to place the FFTF in a hot standby condition.

  9. Suppression Pool Mixing and Condensation Tests in PUMA Facility

    SciTech Connect (OSTI)

    Ling Cheng; Kyoung Suk Woo; Mamoru Ishii; Jaehyok Lim; Han, James

    2006-07-01

    Condensation of steam with non-condensable in the form of jet flow or bubbly flow inside the suppression pool is an important phenomenon on determining the containment pressure of a passively safe boiling water reactor. 32 cases of pool mixing and condensation test have been performed in Purdue University Multi-Dimensional Integral Test Assembly (PUMA) facility under the sponsor of the U.S. Nuclear Regulatory Commission to investigate thermal stratification and pool mixing inside the suppression pool during the reactor blowdown period. The test boundary conditions, such as the steam flow rate, the noncondensable gas flow rate, the initial water temperature, the pool initial pressure and the vent opening submergence depth, which covers a wide range of prototype (SBWR-600) conditions during Loss of Coolant Accident (LOCA) were obtained from the RELAP5 calculation. The test results show that steam is quickly condensed at the exit of the vent opening. For pure steam injection or low noncondensable injection cases, only the portion above the vent opening in the suppression pool is heated up by buoyant plumes. The water below the vent opening can be heated up slowly through conduction. The test results also show that the degree of thermal stratification in suppression pool is affected by the vent opening submergence depth, the pool initial pressure and the steam injection rate. And it is slightly affected by the initial water temperature. From these tests it is concluded that the pool mixing is strongly affected by the noncondensable gas flow rate. (authors)

  10. Preserving physics knowledge at the fast flux test facility

    SciTech Connect (OSTI)

    Wootan, D.; Omberg, R.; Makenas, B. J.; Polzin, D. L.

    2012-07-01

    One of the goals of the Dept. of Energy's Office of Nuclear Energy, initiated under the Fuel Cycle Research and Development Program (FCRD) and continued under the Advanced Reactor Concepts Program (ARC) is to preserve the knowledge that has been gained in the United States on Liquid Metal Reactors (LMRs) that could support the development of an environmentally and economically sound nuclear fuel cycle. The Fast Flux Test Facility (FFTF) is the most recent LMR to operate in the United States, from 1982 to 1992, and was designed as a fully instrumented test reactor with on-line, real time test control and performance monitoring of components and tests installed in the reactor. The 10 years of operation of the FFTF provided a very useful framework for testing the advances in LMR safety technology based on passive safety features that may be of increased importance to new designs after the events at Fukushima. Knowledge preservation at the FFTF is focused on the areas of design, construction, and startup of the reactor, as well as on preserving information obtained from 10 years of successful operating history and extensive irradiation testing of fuels and materials. In order to ensure protection of information at risk, the program to date has sequestered reports, files, tapes, and drawings to allow for secure retrieval. A disciplined and orderly approach has been developed to respond to client's requests for documents and data in order to minimize the search effort and ensure that future requests for this information can be readily accommodated. (authors)

  11. Summary - Major Risk Factors Integrated Facility Disposition Project (IFDP) Oak Ridge, TN

    Office of Environmental Management (EM)

    & ORNL, Oak Ridge, TN EM Project: Integrated Facility Disposition Project (IFDP) ETR Report Date: August 2008 ETR-15 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Major Risk Factors Integrated Facility Disposition Project (IFDP) Oak Ridge, TN Why DOE-EM Did This Review Approximately two million pounds of mercury are unaccounted for at Y-12 and mercury contamination has been detected in both soils and groundwater. The IFDP will

  12. The Radioactive Liquid Waste Treatment Facility Replacement Project at Los Alamos National Laboratory

    Energy Savers [EERE]

    Radioactive Liquid Waste Treatment Facility Replacement Project at Los Alamos National Laboratory OAS-L-13-15 September 2013 Department of Energy Washington, DC 20585 September 26, 2013 MEMORANDUM FOR THE ASSOCIATE ADMINISTRATOR FOR ACQUISITION AND PROJECT MANAGEMENT MANAGER LOS ALAMOS FIELD OFFICE FROM: David Sedillo Western Audits Division Office of Inspector General SUBJECT: INFORMATION: Audit Report on "The Radioactive Liquid Waste Treatment Facility Replacement Project at Los Alamos

  13. DOE to Build Hydrogen Fuel Test Facility at West Virginia Airport...

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

    to Build Hydrogen Fuel Test Facility at West Virginia Airport DOE to Build Hydrogen Fuel Test Facility at West Virginia Airport March 25, 2009 - 1:00pm Addthis Washington, DC - The ...

  14. Large Wind Turbine Blade Test Facilities to be in Mass., Texas...

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

    Large Wind Turbine Blade Test Facilities to be in Mass., Texas Access to waterways key; ... build and operate new facilities to test the next generation of giant wind turbine blades. ...

  15. Plans for an ERL Test Facility at CERN (Conference) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    Conference: Plans for an ERL Test Facility at CERN Citation Details In-Document Search Title: Plans for an ERL Test Facility at CERN You are accessing a document from the ...

  16. Recovery Act-Funded 90-m Blade Test Facility Commissioned May...

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

    Recovery Act-Funded 90-m Blade Test Facility Commissioned May 18, 2011 Recovery Act-Funded 90-m Blade Test Facility Commissioned May 18, 2011 May 20, 2011 - 3:06pm Addthis This is ...

  17. PEROXIDE DESTRUCTION TESTING FOR THE 200 AREA EFFLUENT TREATMENT FACILITY

    SciTech Connect (OSTI)

    HALGREN DL

    2010-03-12

    The hydrogen peroxide decomposer columns at the 200 Area Effluent Treatment Facility (ETF) have been taken out of service due to ongoing problems with particulate fines and poor destruction performance from the granular activated carbon (GAC) used in the columns. An alternative search was initiated and led to bench scale testing and then pilot scale testing. Based on the bench scale testing three manganese dioxide based catalysts were evaluated in the peroxide destruction pilot column installed at the 300 Area Treated Effluent Disposal Facility. The ten inch diameter, nine foot tall, clear polyvinyl chloride (PVC) column allowed for the same six foot catalyst bed depth as is in the existing ETF system. The flow rate to the column was controlled to evaluate the performance at the same superficial velocity (gpm/ft{sup 2}) as the full scale design flow and normal process flow. Each catalyst was evaluated on peroxide destruction performance and particulate fines capacity and carryover. Peroxide destruction was measured by hydrogen peroxide concentration analysis of samples taken before and after the column. The presence of fines in the column headspace and the discharge from carryover was generally assessed by visual observation. All three catalysts met the peroxide destruction criteria by achieving hydrogen peroxide discharge concentrations of less than 0.5 mg/L at the design flow with inlet peroxide concentrations greater than 100 mg/L. The Sud-Chemie T-2525 catalyst was markedly better in the minimization of fines and particle carryover. It is anticipated the T-2525 can be installed as a direct replacement for the GAC in the peroxide decomposer columns. Based on the results of the peroxide method development work the recommendation is to purchase the T-2525 catalyst and initially load one of the ETF decomposer columns for full scale testing.

  18. Knowledge Preservation at the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Wootan, David W.; Omberg, Ronald P.

    2011-12-30

    One of the goals of the Department of Energy's Office of Nuclear Energy Fuel Cycle Research and Development Program (FCRD) is to preserve the knowledge that has been gained in the United States on Liquid Metal Reactors (LMRs) that could support the development of an environmentally and economically sound nuclear fuel cycle. The Fast Flux Test Facility (FFTF) is the most recent LMR to operate in the United States, from 1982 to 1992, and was designed as a fully instrumented test reactor with on-line, real time test control and performance monitoring of components and tests installed in the reactor. Knowledge preservation at the FFTF is focused on the areas of design, construction, and startup of the reactor, as well as on preserving information obtained from 10 years of successful operating history and extensive irradiation testing of fuels and materials. In order to ensure protection of information at risk, the program to date has sequestered reports, files, tapes, and drawings to allow for secure retrieval. A disciplined and orderly approach has been developed to respond to client's requests for documents and data in order to minimize the search effort and ensure that future requests for this information can be readily accommodated.

  19. Closure of the Fast Flux Test Facility: current status and future plans

    SciTech Connect (OSTI)

    Lesperance, C. P.; Doebler, S. V.; Burke, T. M.

    2007-07-01

    The Fast Flux Test Facility (FFTF) was a 400 MWt sodium-cooled fast reactor situated on the U.S. Department of Energy's (DOE) Hanford Site in the southeastern portion of Washington State. DOE issued the final order to shut down the facility in 2001, when it was concluded that there was no longer a need for FFTF. Deactivation activities are in progress to remove or stabilize major hazards and deactivate systems to achieve end points documented in the project baseline. The reactor has been de-fueled, and approximately 97% of the fuel has been removed from the facility. Approximately 97% of the sodium has been drained from the plant's systems and placed into an on-site Sodium Storage Facility. The residual sodium will be kept frozen under a blanket of inert gas until it is removed later as part of the facility's decontamination and decommissioning (D and D). Plant systems have been shut down and placed in a low-risk state to minimize requirements for surveillance and maintenance. D and D work cannot begin until an Environmental Impact Statement has been prepared to evaluate various end state options and to provide a basis for selecting one of the options. The Environmental Impact Statement is expected to be issued in 2009. (authors)

  20. CLOSURE OF THE FAST FLUX TEST FACILITY (FFTF) CURRENT STATUS & FUTURE PLANS

    SciTech Connect (OSTI)

    LESPERANCE, C.P.

    2007-05-23

    The Fast Flux Test Facility (FFTF) was a 400 MWt sodium-cooled fast reactor situated on the U.S. Department of Energy's (DOE) Hanford Site in the southeastern portion of Washington State. DOE issued the final order to shut down the facility in 2001, when it was concluded that there was no longer a need for FFTF. Deactivation activities are in progress to remove or stabilize major hazards and deactivate systems to achieve end points documented in the project baseline. The reactor has been defueled, and approximately 97% of the fuel has been removed from the facility. Approximately 97% of the sodium has been drained from the plant's systems and placed into an on-site Sodium Storage Facility. The residual sodium will be kept frozen under a blanket of inert gas until it is removed later as part of the facility's decontamination and decommissioning (D&D). Plant systems have been shut down and placed in a low-risk state to minimize requirements for surveillance and maintenance. D&D work cannot begin until an Environmental Impact Statement has been prepared to evaluate various end state options and to provide a basis for selecting one of the options. The Environmental Impact Statement is expected to be issued in 2009.

  1. Concept, implementation and commissioning of the automation system for the accelerator module test facility AMTF

    SciTech Connect (OSTI)

    Bckmann, Torsten A.; Korth, Olaf; Clausen, Matthias; Schoeneburg, Bernd

    2014-01-29

    The European XFEL project launched on June 5, 2007 will require about 103 accelerator modules as a main part of the XFEL linear accelerator. All superconducting components constituting the accelerator module like cavities and magnets have to be tested before the assembly. For the tests of the individual cavities and the complete modules an XFEL Accelerator Module Test Facility (AMTF) has been erected at DESY. The process control system EPICS (Experimental Physics and Industrial Control System) is used to control and operate the cryogenic plant and all its subcomponents. A complementary component of EPICS is the Open Source software suit CSS (Control System Studio). CSS is an integrated engineering, maintenance and operating tool for EPICS. CSS enables local and remote operating and monitoring of the complete system and thus represents the human machine interface. More than 250 PROFIBUS nodes work at the accelerator module test facility. DESY installed an extensive diagnostic and condition monitoring system. With these diagnostic tools it is possible to examine the correct installation and configuration of all PROFIBUS nodes in real time. The condition monitoring system based on FDT/DTM technology shows the state of the PROFIBUS devices at a glance. This information can be used for preventive maintenance which is mandatory for continuous operation of the AMTF facility. The poster will describe all steps form engineering to implementation and commissioning.

  2. Integrated Disposal Facility FY2010 Glass Testing Summary Report

    SciTech Connect (OSTI)

    Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Serne, R Jeffrey; Mattigod, Shas V.

    2010-09-30

    Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 105 m3 of glass (Puigh 1999). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 0.89 1018 Bq total activity) of long-lived radionuclides, principally 99Tc (t1/2 = 2.1 105), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessement (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2010 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses. The emphasis in FY2010 was the completing an evaluation of the most sensitive kinetic rate law parameters used to predict glass weathering, documented in Bacon and Pierce (2010), and transitioning from the use of the Subsurface Transport Over Reactive Multi-phases to Subsurface Transport Over Multiple Phases computer code for near-field calculations. The FY2010 activities also consisted of developing a Monte Carlo and Geochemical Modeling framework that links glass composition to alteration phase formation by 1) determining the structure of unreacted and reacted glasses for use as input information into Monte Carlo calculations, 2) compiling the solution data and alteration phases identified from accelerated weathering tests conducted with ILAW glass by PNNL and Viteous State Laboratory/Catholic University of America as well as other literature sources for use in geochemical modeling calculations, and 3) conducting several initial calculations on glasses that contain the four major components of ILAW-Al2O3, B2O3, Na2O, and SiO2.

  3. Independent Oversight Assessment, Salt Waste Processing Facility Project -

    Office of Environmental Management (EM)

    2012 | Department of Energy Portsmouth/Paducah Project Office - May 2012 Independent Oversight Assessment, Portsmouth/Paducah Project Office - May 2012 May 2012 Assessment of the Portsmouth/Paducah Project Office Conduct of Operations Oversight of the Depleted Uranium Hexafluoride Conversion Plants This report provides the results of an independent assessment of the Department of Energy's (DOE) Portsmouth/Paducah Project Office oversight of conduct of operations at DOE's depleted uranium

  4. Major Risk Factors Integrated Facility Disposition Project - Oak Ridge |

    Energy Savers [EERE]

    Biomass Program Major DOE Biofuels Project Locations in the United States PDF icon Major DOE Biofuels Project Locations More Documents & Publications Major DOE Biofuels Project Locations Major DOE Biofuels Project Locations Algal Biofuel Technologies

    Slide 1 The Current State of Technology for Cellulosic Ethanol

    Algal Biofuel Technologies Slide 1

    101 Major Program Offices Doing Business with... Energy Efficiency and Renewable Energy Office of Environmental Management

  5. Status Review of Wildlife Mitigation, Columbia Basin Hydroelectric Projects, Columbia River Mainstem Facilities, 1984 Final Report.

    SciTech Connect (OSTI)

    Howerton, Jack; Hwang, Diana

    1984-11-01

    This report reviews the status of past, present, and proposed future wildlife planning and mitigation programs at existing hydroelectric projects in the Columbia River Basin. The project evaluations will form the basis for determining any needed remedial measures or additional project analysis. Each hydropower facility report is abstracted separately for inclusion in the Energy Data Base.

  6. Thermal vacuum life test facility for radioisotope thermoelectric generators

    SciTech Connect (OSTI)

    Deaton, R.L.; Goebel, C.J.; Amos, W.R.

    1990-01-01

    In the late 1970's, the Department of Energy (DOE) assigned Monsanto Research Corporation, Mound Facility, now operated by EG G Mound Applied Technologies, the responsibility for assembling and testing General Purpose Heat Source (GPHS) radioisotope thermoelectric generators (RTGs). Assembled and tested were five RTGs, which included four flight units and one non-flight qualification unit. Figure 1 shows the RTG, which was designed by General Electric AstroSpace Division (GE/ASD) to produce 285 W of electrical power. A detailed description of the processes for RTG assembly and testing is presented by Amos and Goebel (1989). The RTG performance data are described by Bennett, et al. (1986). The flight units will provide electrical power for the National Aeronautics and Space Administration's (NASA) Galileo mission to Jupiter (two RTGs) and the joint NASA/European Space Agency (ESA) Ulysses mission to study the polar regions of the sun (one RTG). The remaining flight unit will serve as the spare for both missions, and a non-flight qualification unit was assembled and tested to ensure that performance criteria were adequately met. 4 refs., 3 figs.

  7. Project Title: Nuclear Astrophysics Data from Radioactive Beam Facilities

    SciTech Connect (OSTI)

    Alan A. Chen

    2008-03-27

    The scientific aims of this project have been the evaluation and dissemination of key nuclear reactions in nuclear astrophysics, with a focus on ones to be studied at new radioactive beam facilities worldwide. These aims were maintained during the entire funding period from 2003 - 2006. In the following, a summary of the reactions evaluated during this period is provided. Year 1 (2003-04): {sup 21}Na(p,{gamma}){sup 22}Mg and {sup 18}Ne({alpha},p){sup 21}Na - The importance of the {sup 21}Na(p,{gamma}){sup 22}Mg and the {sup 18}Ne({alpha},p){sup 21}Na reactions in models of exploding stars has been well documented: the first is connected to the production of the radioisotope {sup 22}Na in nova nucleosynthesis, while the second is a key bridge between the Hot-CNO cycles and the rp-process in X-ray bursts. By the end of Summer 2004, our group had updated these reaction rates to include all published data up to September 2004, and cast the reaction rates into standard analytical and tabular formats with the assistance of Oak Ridge National Laboratory's computational infrastructure for reaction rates. Since September 2004, ongoing experiments on these two reactions have been completed, with our group's participation in both: {sup 21}Na(p,{gamma}){sup 22}Mg at the TRIUMF-ISAC laboratory (DRAGON collaboration), and 18Ne({alpha},p){sup 21}Na at Argonne National Laboratory (collaboration with Ernst Rehm, Argonne). The data from the former was subsequently published and included in our evaluation. Publication from the latter still awaits independent confirmation of the experimental results. Year 2 (2004-05): The 25Al(p,{gamma}){sup 26}Si and {sup 13}N(p,{gamma})14O reactions - For Year 2, we worked on evaluations of the {sup 25}Al(p,{gamma}){sup 26}Si and {sup 13}N(p,{gamma}){sup 14}O reactions, in accordance with our proposed deliverables and following similar standard procedures to those used in Year 1. The {sup 25}Al(p,{gamma}){sup 26}Si reaction is a key uncertainty in the understanding the origin of galactic {sup 26}Al, a target radioisotope for gamma ray astronomy; the {sup 13}N(p,{gamma}){sup 14}O reaction in turn is the trigger reaction for the transition into the Hot-CNO cycles in novae and X-ray bursts. A graduate student of mine, who has been supported part-time by this grant, completed the evaluation of the {sup 25}Al(p,{gamma}){sup 26}Si reaction as part of his plans to measure this reaction at TRIUMF for his Ph.D. thesis project. I also hired a part-time undergraduate student for the 2004-05 academic year to assist with the evaluations, including that of the {sup 13}N(p,{gamma}){sup 14}O reaction. Year 3 (2005-06): The {sup 40}Ca({alpha},{gamma}){sup 44}Ti and {sup 26}Al(p,{gamma}){sup 27}Si reactions - This year's progress was closely coupled to new results coming from our collaboration on the DRAGON spectrometer team at TRIUMF. The {sup 40}Ca({alpha},{gamma}){sup 44}Ti and {sup 26}Al(p,{gamma}){sup 27}Si reactions were both measured, and significant modifications to their respective reaction rates were required. Both are required input toward predicting the respective amounts of Titanium-44 and Aluminum-26 produced in our galaxy, in supernovae, massive stars, and nova explosions. The {sup 26}Al(p,{gamma}){sup 27}Si reaction rate was successfully completed. The {sup 40}Ca({alpha},{gamma}){sup 44}Ti reaction in particular served as the Ph.D. thesis for Christian Ouellet, and therefore the evaluation of this rate fell naturally within his thesis project. Christian successfully defended his thesis in 2007 and is now working for me on the McMaster DOE-funded Nuclear Data Project. In light of the recent data from his thesis, Christian is now putting the final touches on this evaluation, and will disseminate it through the Oak Ridge National Laboratory reaction rate database.

  8. Knowledge Management at the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Wootan, David W.; Omberg, Ronald P.

    2013-06-01

    One of the goals of the Department of Energy’s Office of Nuclear Energy, initiated under the Fuel Cycle Research and Development Program (FCRD) and continued under the Advanced Reactor Concepts Program (ARC) is to preserve the knowledge that has been gained in the United States on Liquid Metal Reactors (LMRs) that could support the development of an environmentally and economically sound nuclear fuel cycle. The Fast Flux Test Facility (FFTF) is the most recent LMR to operate in the United States, from 1982 to 1992, and was designed as a fully instrumented test reactor with on-line, real time test control and performance monitoring of components and tests installed in the reactor. The 10 years of operation of the FFTF provided a very useful framework for testing the advances in LMR safety technology based on passive safety features that may be of increased importance to new designs after the events at Fukushima. Knowledge preservation at the FFTF is focused on the areas of design, construction, and startup of the reactor, as well as on preserving information obtained from 10 years of successful operating history and extensive irradiation testing of fuels and materials. In order to ensure protection of information at risk, the program to date has sequestered reports, files, tapes, and drawings to allow for secure retrieval. The FFTF knowledge management program includes a disciplined and orderly approach to respond to client’s requests for documents and data in order to minimize the search effort and ensure that future requests for this information can be readily accommodated.

  9. Preserving Physics Knowledge at the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Wootan, David W.; Omberg, Ronald P.; Makenas, Bruce J.; Nielsen, Deborah L.; Nelson, Joseph V.; Polzin, David L.

    2011-11-01

    One of the goals of the Department of Energy’s Office of Nuclear Energy, initiated under the Fuel Cycle Research and Development Program (FCRD) and continued under the Advanced Reactor Concepts Program (ARC) is to preserve the knowledge that has been gained in the United States on Liquid Metal Reactors (LMRs) that could support the development of an environmentally and economically sound nuclear fuel cycle. The Fast Flux Test Facility (FFTF) is the most recent LMR to operate in the United States, from 1982 to 1992, and was designed as a fully instrumented test reactor with on-line, real time test control and performance monitoring of components and tests installed in the reactor. The 10 years of operation of the FFTF provided a very useful framework for testing the advances in LMR safety technology based on passive safety features that may be of increased importance to new designs after the events at Fukushima. Knowledge preservation at the FFTF is focused on the areas of design, construction, and startup of the reactor, as well as on preserving information obtained from 10 years of successful operating history and extensive irradiation testing of fuels and materials. In order to ensure protection of information at risk, the program to date has sequestered reports, files, tapes, and drawings to allow for secure retrieval. A disciplined and orderly approach has been developed to respond to client’s requests for documents and data in order to minimize the search effort and ensure that future requests for this information can be readily accommodated.

  10. Scaling Studies for High Temperature Test Facility and Modular High Temperature Gas-Cooled Reactor

    SciTech Connect (OSTI)

    Richard R. Schult; Paul D. Bayless; Richard W. Johnson; James R. Wolf; Brian Woods

    2012-02-01

    The Oregon State University (OSU) High Temperature Test Facility (HTTF) is an integral experimental facility that will be constructed on the OSU campus in Corvallis, Oregon. The HTTF project was initiated, by the U.S. Nuclear Regulatory Commission (NRC), on September 5, 2008 as Task 4 of the 5-year High Temperature Gas Reactor Cooperative Agreement via NRC Contract 04-08-138. Until August, 2010, when a DOE contract was initiated to fund additional capabilities for the HTTF project, all of the funding support for the HTTF was provided by the NRC via their cooperative agreement. The U.S. Department of Energy (DOE) began their involvement with the HTTF project in late 2009 via the Next Generation Nuclear Plant (NGNP) project. Because the NRC's interests in HTTF experiments were only centered on the depressurized conduction cooldown (DCC) scenario, NGNP involvement focused on expanding the experimental envelope of the HTTF to include steady-state operations and also the pressurized conduction cooldown (PCC).

  11. FFTF (Fast Flux Test Facility) reactor shutdown system reliability reevaluation

    SciTech Connect (OSTI)

    Pierce, B.F.

    1986-07-01

    The reliability analysis of the Fast Flux Test Facility reactor shutdown system was reevaluated. Failure information based on five years of plant operating experience was used to verify original reliability numbers or to establish new ones. Also, system modifications made subsequent to performance of the original analysis were incorporated into the reevaluation. Reliability calculations and sensitivity analyses were performed using a commercially available spreadsheet on a personal computer. The spreadsheet was configured so that future failures could be tracked and compared with expected failures. A number of recommendations resulted from the reevaluation including both increased and decreased surveillance intervals. All recommendations were based on meeting or exceeding existing reliability goals. Considerable cost savings will be incurred upon implementation of the recommendations.

  12. Emittance Measurements of the SSRL Gun Test Facility

    SciTech Connect (OSTI)

    Hernandez, Michael; Clendenin, James; Fisher, Alan; Miller, Roger; Palmer, Dennis; Park, Sam; Schmerge, John; Weaver, Jim; Wiedemann, Helmut; Winick, Herman; Yeremian, Dian; Meyerhofer, David; Reis, David; /Rochester U.

    2011-09-01

    A photocathode RF gun test stand is under construction in the injector vault of the Stanford Synchrotron Radiation Laboratory at SLAC. The goal of this facility is to produce an electron beam with a normalized emittance of 1-3[mm-mr], a longitudinal bunch duration of the order of 10[ps] FWHM and approximately 1[nC] of charge per bunch. The beam will be generated from a laser driven copper photocathode RF gun developed in collaboration with BNL, LBL and UCLA. The 3-5[MeV] beam from the gun will be accelerated using a SLAC three meter S-band accelerator section. The emittance of the electron beam will be measured through the use of quadrupole scans with phosphor screens and also a wire scanner. The details of the experimental setup will be discussed, and first measurements will be presented and compared with results from PARMELA simulations.

  13. SHEAR STRENGTH MEASURING EQUIPMENT EVALUATION AT THE COLD TEST FACILITY

    SciTech Connect (OSTI)

    MEACHAM JE

    2009-09-09

    Retrievals under current criteria require that approximately 2,000,000 gallons of double-shell tank (DST) waste storage space not be used to prevent creating new tanks that might be susceptible to buoyant displacement gas release events (BDGRE). New criteria are being evaluated, based on actual sludge properties, to potentially show that sludge wastes do not exhibit the same BDGRE risk. Implementation of the new criteria requires measurement of in situ waste shear strength. Cone penetrometers were judged the best equipment for measuring in situ shear strength and an A.P. van den berg Hyson 100 kN Light Weight Cone Penetrometer (CPT) was selected for evaluation. The CPT was procured and then evaluated at the Hanford Site Cold Test Facility. Evaluation demonstrated that the equipment with minor modification was suitable for use in Tank Farms.

  14. Power Systems Development Facility Gasification Test Campaign TC25

    SciTech Connect (OSTI)

    Southern Company Services

    2008-12-01

    In support of technology development to utilize coal for efficient, affordable, and environmentally clean power generation, the Power Systems Development Facility (PSDF), located in Wilsonville, Alabama, routinely demonstrates gasification technologies using various types of coals. The PSDF is an engineering scale demonstration of key features of advanced coal-fired power systems, including a KBR Transport Gasifier, a hot gas particulate control device, advanced syngas cleanup systems, and high-pressure solids handling systems. This report summarizes the results of TC25, the second test campaign using a high moisture lignite coal from the Red Hills mine in Mississippi as the feedstock in the modified Transport Gasifier configuration. TC25 was conducted from July 4, 2008, through August 12, 2008. During TC25, the PSDF gasification process operated for 742 hours in air-blown gasification mode. Operation with the Mississippi lignite was significantly improved in TC25 compared to the previous test (TC22) with this fuel due to the addition of a fluid bed coal dryer. The new dryer was installed to dry coals with very high moisture contents for reliable coal feeding. The TC25 test campaign demonstrated steady operation with high carbon conversion and optimized performance of the coal handling and gasifier systems. Operation during TC25 provided the opportunity for further testing of instrumentation enhancements, hot gas filter materials, and advanced syngas cleanup technologies. The PSDF site was also made available for testing of the National Energy Technology Laboratory's fuel cell module and Media Process Technology's hydrogen selective membrane with syngas from the Transport Gasifier.

  15. FEMP Helps Federal Facilities Develop Large-Scale Renewable Energy Projects

    Broader source: Energy.gov [DOE]

    FEMP developed a guide to help federal agencies, as well as the developers and financiers that work with them, to successfully install large-scale renewable energy projects at federal facilities.

  16. Community- and Facility-Scale Tribal Renewable Energy Project Development and Finance Workshop Agenda

    Broader source: Energy.gov [DOE]

    Downoad the agenda for the Office of Indian Energy's Community- and Facility-Scale Tribal Renewable Energy Project Development and Finance Workshop, which will be held September 18-20 at the...

  17. Community- and Facility-Scale Tribal Renewable Energy Project Workshop to be Held in September

    Broader source: Energy.gov [DOE]

    Tribal leaders and staff are invited to attend this interactive workshop that will walk through the five steps of developing and financing community- and facility-scale projects on tribal lands.

  18. Aug. 27 Webinar Will Focus on Financing Facility- and Community-Scale Tribal Renewable Energy Projects

    Broader source: Energy.gov [DOE]

    The Aug. 27 Tribal Renewable Energy Series webinar will explore various forms of financing for smaller facility- and community-scale renewable energy projects, including their relative advantages and disadvantages to tribal communities.

  19. Test Results From The Idaho National Laboratory 15kW High Temperature Electrolysis Test Facility

    SciTech Connect (OSTI)

    Carl M. Stoots; Keith G. Condie; James E. O'Brien; J. Stephen Herring; Joseph J. Hartvigsen

    2009-07-01

    A 15kW high temperature electrolysis test facility has been developed at the Idaho National Laboratory under the United States Department of Energy Nuclear Hydrogen Initiative. This facility is intended to study the technology readiness of using high temperature solid oxide cells for large scale nuclear powered hydrogen production. It is designed to address larger-scale issues such as thermal management (feed-stock heating, high temperature gas handling, heat recuperation), multiple-stack hot zone design, multiple-stack electrical configurations, etc. Heat recuperation and hydrogen recycle are incorporated into the design. The facility was operated for 1080 hours and successfully demonstrated the largest scale high temperature solid-oxide-based production of hydrogen to date.

  20. Design of a horizontal test cryostat for superconducting RF cavities for the FREIA facility at Uppsala University

    SciTech Connect (OSTI)

    Chevalier, N. R.; Thermeau, J.-P.; Bujard, P.; Junquera, T. [Accelerators and Cryogenic Systems (ACS), 86 rue de Paris, 91400 Orsay (France); Hermansson, L.; Kern, R. Santiago; Ruber, R. [Uppsala University, Department of Physics and Astronomy, 75120 Uppsala (Sweden)

    2014-01-29

    Uppsala University is constructing a large scale facility, called FREIA (Facility for Research Instrumentation and Accelerator Development). FREIA includes a helium liquefier and an accelerator test facility and has the capacity to test superconducting radio-frequency (RF) cavities with the same RF system and RF power level as in an accelerator. A central element of FREIA is a horizontal test cryostat connected in closed loop to a helium liquefier. This cryostat can house two fully equipped (tuners, piezo, power coupler, helium tank) superconducting cavities to perform full RF high power tests and operate at temperatures between 1.8 K and 4.2 K. The cryostat is designed to accommodate a large array of superconducting cavities and magnets, among which the European Spallation Source (ESS) type spoke and high-? elliptical cavities as well as TESLA/ILC type elliptical cavities. The present status of the project and the design of the cryostat are reported.

  1. Advanced Test Reactor - A National Scientific User Facility

    SciTech Connect (OSTI)

    Clifford J. Stanley

    2008-05-01

    The ATR is a pressurized, light-water moderated and cooled, beryllium-reflected nuclear research reactor with a maximum operating power of 250 MWth. The unique serpentine configuration of the fuel elements creates five main reactor power lobes (regions) and nine flux traps. In addition to these nine flux traps there are 68 additional irradiation positions in the reactor core reflector tank. There are also 34 low-flux irradiation positions in the irradiation tanks outside the core reflector tank. The ATR is designed to provide a test environment for the evaluation of the effects of intense radiation (neutron and gamma). Due to the unique serpentine core design each of the five lobes can be operated at different powers and controlled independently. Options exist for the individual test trains and assemblies to be either cooled by the ATR coolant (i.e., exposed to ATR coolant flow rates, pressures, temperatures, and neutron flux) or to be installed in their own independent test loops where such parameters as temperature, pressure, flow rate, neutron flux, and energy can be controlled per experimenter specifications. The full-power maximum thermal neutron flux is ~1.0 x1015 n/cm2-sec with a maximum fast flux of ~5.0 x1014 n/cm2-sec. The Advanced Test Reactor, now a National Scientific User Facility, is a versatile tool in which a variety of nuclear reactor, nuclear physics, reactor fuel, and structural material irradiation experiments can be conducted. The cumulative effects of years of irradiation in a normal power reactor can be duplicated in a few weeks or months in the ATR due to its unique design, power density, and operating flexibility.

  2. Power Systems Development Facility Gasification Test Campaign TC24

    SciTech Connect (OSTI)

    Southern Company Services

    2008-03-30

    In support of technology development to utilize coal for efficient, affordable, and environmentally clean power generation, the Power Systems Development Facility (PSDF), located in Wilsonville, Alabama, routinely demonstrates gasification technologies using various types of coals. The PSDF is an engineering scale demonstration of key features of advanced coal-fired power systems, including a KBR Transport Gasifier, a hot gas particulate control device, advanced syngas cleanup systems, and high-pressure solids handling systems. This report summarizes the results of TC24, the first test campaign using a bituminous coal as the feedstock in the modified Transport Gasifier configuration. TC24 was conducted from February 16, 2008, through March 19, 2008. The PSDF gasification process operated for about 230 hours in air-blown gasification mode with about 225 tons of Utah bituminous coal feed. Operational challenges in gasifier operation were related to particle agglomeration, a large percentage of oversize coal particles, low overall gasifier solids collection efficiency, and refractory degradation in the gasifier solids collection unit. The carbon conversion and syngas heating values varied widely, with low values obtained during periods of low gasifier operating temperature. Despite the operating difficulties, several periods of steady state operation were achieved, which provided useful data for future testing. TC24 operation afforded the opportunity for testing of various types of technologies, including dry coal feeding with a developmental feeder, the Pressure Decoupled Advanced Coal (PDAC) feeder; evaluating a new hot gas filter element media configuration; and enhancing syngas cleanup with water-gas shift catalysts. During TC24, the PSDF site was also made available for testing of the National Energy Technology Laboratory's fuel cell module and Media Process Technology's hydrogen selective membrane.

  3. Fast flux test facility radioisotope production and medical applications

    SciTech Connect (OSTI)

    Schenter, R.E.; Smith, S.G.; Tenforde, T.S.

    1997-12-01

    The Fast Flux Test Facility (FFTF) is a 400-MW, sodium-cooled reactor that operated successfully from 1982 to 1992, conducting work in support of the liquid-metal reactor industry by developing and testing fuel assemblies, control rods, and other core reactor components. Upon termination of this program, the primary mission of FFTF ended, and it was placed in a standby mode in 1993. However, in January 1997 the U.S. Secretary of Energy requested that FFTF be evaluated for a future mission that would consist of a primary goal of producing tritium for nuclear defense applications and a secondary goal of supplying medical isotopes for research and clinical applications. Production by FFTF of tritium for U.S. nuclear weapons would augment the dual-track strategy now under consideration for providing a long-term tritium supply in the United States (consisting of a light water reactor option and an accelerator option). A decision by the Secretary of Energy on proceeding with steps leading toward the possible reactivation of FFTF will be made before the end of 1998.

  4. Parametric Thermal Models of the Transient Reactor Test Facility (TREAT)

    SciTech Connect (OSTI)

    Bradley K. Heath

    2014-03-01

    This work supports the restart of transient testing in the United States using the Department of Energy’s Transient Reactor Test Facility at the Idaho National Laboratory. It also supports the Global Threat Reduction Initiative by reducing proliferation risk of high enriched uranium fuel. The work involves the creation of a nuclear fuel assembly model using the fuel performance code known as BISON. The model simulates the thermal behavior of a nuclear fuel assembly during steady state and transient operational modes. Additional models of the same geometry but differing material properties are created to perform parametric studies. The results show that fuel and cladding thermal conductivity have the greatest effect on fuel temperature under the steady state operational mode. Fuel density and fuel specific heat have the greatest effect for transient operational model. When considering a new fuel type it is recommended to use materials that decrease the specific heat of the fuel and the thermal conductivity of the fuel’s cladding in order to deal with higher density fuels that accompany the LEU conversion process. Data on the latest operating conditions of TREAT need to be attained in order to validate BISON’s results. BISON’s models for TREAT (material models, boundary convection models) are modest and need additional work to ensure accuracy and confidence in results.

  5. Fast Flux Test Facility (FFTF) Briefing Book 1 Summary

    SciTech Connect (OSTI)

    WJ Apley

    1997-12-01

    This report documents the results of evaluations preformed during 1997 to determine what, if an, future role the Fast Flux Test Facility (FFTF) might have in support of the Department of Energy’s tritium productions strategy. An evaluation was also conducted to assess the potential for the FFTF to produce medical isotopes. No safety, environmental, or technical issues associated with producing 1.5 kilograms of tritium per year in the FFTF have been identified that would change the previous evaluations by the Department of Energy, the JASON panel, or Putnam, Hayes & Bartlett. The FFTF can be refitted and restated by July 2002 for a total expenditure of $371 million, with an additional $64 million of startup expense necessary to incorporate the production of medical isotopes. Therapeutic and diagnostic applications of reactor-generated medical isotopes will increase dramatically over the next decade. Essential medical isotopes can be produced in the FFTF simultaneously with tritium production, and while a stand-alone medical isotope mission for the facility cannot be economically justified given current marker conditions, conservative estimates based on a report by Frost &Sullivan indicate that 60% of the annual operational costs (reactor and fuel supply) could be offset by revenues from medical isotope production within 10 yeas of restart. The recommendation of the report is for the Department of Energy to continue to maintain the FFTF in standby and proceed with preparation of appropriate Nations Environmental Policy Act documentation in full consultation with the public to consider the FFTF as an interim tritium production option (1.5 kilograms/year) with a secondary mission of producing medical isotopes.

  6. Idaho Cleanup Project completes work at Test Area North complex at DOE�s

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

    Idaho site Idaho Cleanup Project completes work at Test Area North complex at DOE�s Idaho site Loss-Of-Fluid Test Reactor Facility (before) Idaho Cleanup Project workers have completed all the original contract work scope at the U.S. Department of Energy�s Idaho Site�s Test Area North (TAN) complex. The work involved close cooperation among the Department of Energy, the Environmental Protection Agency and the Idaho Department of Environmental Quality, with public input incorporated

  7. EIS-0017: Fusion Materials Irradiation Testing Facility, Hanford Reservation, Richland, Washington

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy developed this statement to evaluate the environmental impacts associated with proposed construction and operation of an irradiation test facility, the Deuterium-Lithium High Flux Neutron Source Facility, at the Hanford Reservation.

  8. Feasibility of MHD submarine propulsion. Phase II, MHD propulsion: Testing in a two Tesla test facility

    SciTech Connect (OSTI)

    Doss, E.D.; Sikes, W.C.

    1992-09-01

    This report describes the work performed during Phase 1 and Phase 2 of the collaborative research program established between Argonne National Laboratory (ANL) and Newport News Shipbuilding and Dry Dock Company (NNS). Phase I of the program focused on the development of computer models for Magnetohydrodynamic (MHD) propulsion. Phase 2 focused on the experimental validation of the thruster performance models and the identification, through testing, of any phenomena which may impact the attractiveness of this propulsion system for shipboard applications. The report discusses in detail the work performed in Phase 2 of the program. In Phase 2, a two Tesla test facility was designed, built, and operated. The facility test loop, its components, and their design are presented. The test matrix and its rationale are discussed. Representative experimental results of the test program are presented, and are compared to computer model predictions. In general, the results of the tests and their comparison with the predictions indicate that thephenomena affecting the performance of MHD seawater thrusters are well understood and can be accurately predicted with the developed thruster computer models.

  9. Advanced conceptual design report solid waste retrieval facility, phase I, project W-113

    SciTech Connect (OSTI)

    Smith, K.E.

    1994-03-21

    Project W-113 will provide the equipment and facilities necessary to retrieve suspect transuranic (TRU) waste from Trench 04 of the 218W-4C burial ground. As part of the retrieval process, waste drums will be assayed, overpacked, vented, head-gas sampled, and x-rayed prior to shipment to the Phase V storage facility in preparation for receipt at the Waste Receiving and Processing Facility (WRAP). Advanced Conceptual Design (ACD) studies focused on project items warranting further definition prior to Title I design and areas where the potential for cost savings existed. This ACD Report documents the studies performed during FY93 to optimize the equipment and facilities provided in relation to other SWOC facilities and to provide additional design information for Definitive Design.

  10. Advanced Test Reactor Design Basis Reconstitution Project Issue Resolution Process

    SciTech Connect (OSTI)

    Steven D. Winter; Gregg L. Sharp; William E. Kohn; Richard T. McCracken

    2007-05-01

    The Advanced Test Reactor (ATR) Design Basis Reconstitution Program (DBRP) is a structured assessment and reconstitution of the design basis for the ATR. The DBRP is designed to establish and document the ties between the Document Safety Analysis (DSA), design basis, and actual system configurations. Where the DBRP assessment team cannot establish a link between these three major elements, a gap is identified. Resolutions to identified gaps represent configuration management and design basis recovery actions. The proposed paper discusses the process being applied to define, evaluate, report, and address gaps that are identified through the ATR DBRP. Design basis verification may be performed or required for a nuclear facility safety basis on various levels. The process is applicable to large-scale design basis reconstitution efforts, such as the ATR DBRP, or may be scaled for application on smaller projects. The concepts are applicable to long-term maintenance of a nuclear facility safety basis and recovery of degraded safety basis components. The ATR DBRP assessment team has observed numerous examples where a clear and accurate link between the DSA, design basis, and actual system configuration was not immediately identifiable in supporting documentation. As a result, a systematic approach to effectively document, prioritize, and evaluate each observation is required. The DBRP issue resolution process provides direction for consistent identification, documentation, categorization, and evaluation, and where applicable, entry into the determination process for a potential inadequacy in the safety analysis (PISA). The issue resolution process is a key element for execution of the DBRP. Application of the process facilitates collection, assessment, and reporting of issues identified by the DBRP team. Application of the process results in an organized database of safety basis gaps and prioritized corrective action planning and resolution. The DBRP team follows the ATR DBRP issue resolution process which provides a method for the team to promptly sort and prioritize questions and issues between those that can be addressed as a normal part of the reconstitution project and those that are to be handle as PISAs. Presentation of the DBRP issue resolution process provides an example for similar activities that may be required at other facilities within the Department of Energy complex.

  11. MHK Projects/Leancon Real Sea Test | Open Energy Information

    Open Energy Info (EERE)

    Leancon Real Sea Test < MHK Projects Jump to: navigation, search << Return to the MHK database homepage Loading map... "minzoom":false,"mappingservice":"googlemaps3","type":"ROADM...

  12. Property:Hydrodynamic Testing Facility Type | Open Energy Information

    Open Energy Info (EERE)

    Flume + Flume + Alden Tow Tank + Tow Tank + Alden Wave Basin + Wave Basin + B Breakwater Research Facility + Wave Basin + Bucknell Hydraulic Flume + Flume + C Carderock 2-ft...

  13. Desiccant contamination research: Report on the desiccant contamination test facility

    SciTech Connect (OSTI)

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

    1991-07-01

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

  14. Power Systems Development Facility Gasification Test Campaign TC22

    SciTech Connect (OSTI)

    Southern Company Services

    2008-11-01

    In support of technology development to utilize coal for efficient, affordable, and environmentally clean power generation, the Power Systems Development Facility (PSDF), located in Wilsonville, Alabama, routinely demonstrates gasification technologies using various types of coals. The PSDF is an engineering scale demonstration of key features of advanced coal-fired power systems, including a KBR Transport Gasifier, a hot gas particulate control device, advanced syngas cleanup systems, and high-pressure solids handling systems. This report summarizes the results of TC22, the first test campaign using a high moisture lignite from Mississippi as the feedstock in the modified Transport Gasifier configuration. TC22 was conducted from March 24 to April 17, 2007. The gasification process was operated for 543 hours, increasing the total gasification operation at the PSDF to over 10,000 hours. The PSDF gasification process was operated in air-blown mode with a total of about 1,080 tons of coal. Coal feeder operation was challenging due to the high as-received moisture content of the lignite, but adjustments to the feeder operating parameters reduced the frequency of coal feeder trips. Gasifier operation was stable, and carbon conversions as high as 98.9 percent were demonstrated. Operation of the PCD and other support equipment such as the recycle gas compressor and ash removal systems operated reliably.

  15. Nuclear Facility Risk Reduction project moves forward at Y-12...

    National Nuclear Security Administration (NNSA)

    ... application of nuclear science. NNSA maintains and enhances the safety, security, reliability and performance of the U.S. nuclear weapons stockpile without nuclear testing; works ...

  16. FEDERAL FACILITY COMPLIANCE AGREEMENT (FFCA) STACK ISOLATION PROJECT FUNCTIONS & REQUIREMENTS

    SciTech Connect (OSTI)

    TRANBARGER, R.K.

    2003-12-16

    This document delineates the functions and requirements for the FFCA Stack Isolation Project for the 244-A, 244-BX, 244-5, and 244-TX DCRTs. The isolation of each ventilation system and stack includes the electrical, instrumentation, and mechanical isolation of the ventilation system and the installation of primary and annulus breather filters to provide passive ventilation to meet the FFCA requirements.

  17. RF Test Results from Cryomodule 1 at the Fermilab SRF Beam Test Facility

    SciTech Connect (OSTI)

    Harms, E.; Carlson, K.; Chase, B.; Cullerton, E.; Hocker, A.; Jensen, C.; Joireman, P.; Klebaner, A.; Kubicki, T.; Kucera, M.; Legan, A.; /Fermilab /DESY

    2011-07-26

    Powered operation of Cryomodule 1 (CM-1) at the Fermilab SRF Beam Test Facility began in late 2010. Since then a series of tests first on the eight individual cavities and then the full cryomodule have been performed. We report on the results of these tests and lessons learned which will have an impact on future module testing at Fermilab. Since November 2010 Cryomodule 1 has been operating at 2 Kelvin. After evaluating each of the eight cavities while individually powered, the entire module has recently been powered and peak operation determined as shown in Figure 4. Several more weeks of measurements are planned before the module is warmed up, removed and replaced with Cryomodule 2 now under assembly at Fermilab.

  18. Central Japan Synchrotron Radiation Research Facility Project-(II)

    SciTech Connect (OSTI)

    Yamamoto, N.; Takashima, Y.; Hosaka, M.; Takami, K.; Morimoto, H.; Ito, T.; Sakurai, I.; Hara, H.; Okamoto, W.; Watanabe, N.; Takeda, Y.; Katoh, M.; Hori, Y.; Sasaki, S.

    2010-06-23

    A synchrotron radiation facility that is used not only for basic research, but also for engineering and industrial research and development has been proposed to be constructed in the Central area of Japan. The key equipment of this facility is a compact electron storage ring that is able to supply hard X-rays. The circumference of the storage ring is 72 m with the energy of 1.2 GeV, the beam current of 300 mA, and the natural emittance of about 53 nm-rad. The configuration of the storage ring is based on four triple bend cells, and four of the twelve bending magnets are 5 T superconducting ones. The bending angle and critical energy are 12 degree and 4.8 keV, respectively. For the top-up operation, the electron beam will be injected from a booster synchrotron with the full energy. Currently, six beamlines are planned for the first phase starting from 2012.

  19. Project Closeout Report Francium trapping facility at Triumf

    SciTech Connect (OSTI)

    Orozco, Luis A

    2014-09-30

    This is a report of the construction of a Francium Trapping Facility (FTF) at the Isotope Separator and Accelerator (ISAC) of TRIUMF in Vancouver, Canada, where the Francium Parity Non Conservation (FrPNC) international collaboration has its home. This facility will be used to study fundamental symmetries with high-resolution atomic spectroscopy. The primary scientific objective of the program is a measurement of the anapole moment of francium in a chain of isotopes by observing the parity violation induced by the weak interaction. The anapole moment of francium and associated signal are expected to be ten times larger than in cesium, the only element in which an anapole moment has been observed. The measurement will provide crucial information for better understanding weak hadronic interactions in the context of Quantum Chromodynamics (QCD). The methodology combines nuclear and particle physics techniques for the production of francium with precision measurements based on laser cooling and trapping and microwave spectroscopy. The program builds on an initial series of atomic spectroscopy measurements of the nuclear structure of francium, based on isotope shifts and hyperfine anomalies, before conducting the anapole moment measurements, these measurements performed during commissioning runs help understand the atomic and nuclear structure of Fr.

  20. Advanced Wind Energy Projects Test Facility Moving to Texas Tech...

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

    ... Technology Center, offers the collaboration a 35-year history in wind science research. ... by selling the energy produced will go toward scholarships and research grants for ...

  1. Calendar Year 2004 annual site environmental report : Tonopah Test Range, Nevada & Kauai Test Facility, Hawaii.

    SciTech Connect (OSTI)

    Montoya, Amber L.; Wagner, Katrina; Goering, Teresa Lynn; Koss, Susan I.; Salinas, Stephanie A.

    2005-09-01

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, manages TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2004. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 450.1, Environmental Protection Program (DOE 2005) and DOE Order 231.1A, Environment, Safety, and Health Reporting (DOE 2004b).

  2. RELAP5 Prediction of Transient Tests in the RD-14 Test Facility

    SciTech Connect (OSTI)

    Lee, Sukho; Kim, Manwoong; Kim, Hho-Jung; Lee, John C.

    2005-09-15

    Although the RELAP5 computer code has been developed for best-estimate transient simulation of a pressurized water reactor and its associated systems, it could not assess the thermal-hydraulic behavior of a Canada deuterium uranium (CANDU) reactor adequately. However, some studies have been initiated to explore the applicability for simulating a large-break loss-of-coolant accident in CANDU reactors. In the present study, the small-reactor inlet header break test and the steam generator secondary-side depressurization test conducted in the RD-14 test facility were simulated with the RELAP5/MOD3.2.2 code to examine its extended capability for all the postulated transients and accidents in CANDU reactors. The results were compared with experimental data and those of the CATHENA code performed by Atomic Energy of Canada Limited.In the RELAP5 analyses, the heated sections in the facility were simulated as a multichannel with five pipe models, which have identical flow areas and hydraulic elevations, as well as a single-pipe model.The results of the small-reactor inlet header break and the steam generator secondary-side depressurization simulations predicted experimental data reasonably well. However, some discrepancies in the depressurization of the primary heat transport system after the header break and consequent time delay of the major phenomena were observed in the simulation of the small-reactor inlet header break test.

  3. Mixed and low-level waste treatment facility project

    SciTech Connect (OSTI)

    Not Available

    1992-04-01

    The technology information provided in this report is only the first step toward the identification and selection of process systems that may be recommended for a proposed mixed and low-level waste treatment facility. More specific information on each technology will be required to conduct the system and equipment tradeoff studies that will follow these preengineering studies. For example, capacity, maintainability, reliability, cost, applicability to specific waste streams, and technology availability must be further defined. This report does not currently contain all needed information; however, all major technologies considered to be potentially applicable to the treatment of mixed and low-level waste are identified and described herein. Future reports will seek to improve the depth of information on technologies.

  4. Burnup Predictions for Metal Fuel Tests in the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Wootan, David W.; Nelson, Joseph V.

    2012-06-01

    The Fast Flux Test Facility (FFTF) is the most recent Liquid Metal Reactor (LMR) to be designed, constructed, and operated by the U.S. Department of Energy (DOE). The FFTF operated successfully from initial startup in 1980 through the end of the last operating cycle in March, 1992. A variety of fuel tests were irradiated in FFTF to provide performance data over a range of conditions. The MFF-3 and MFF-5 tests were U10Zr metal fuel tests with HT9 cladding. The MFF-3 and MFF-5 tests were both aggressive irradiation tests of U10Zr metal fuel pins with HT9 cladding that were prototypic of full scale LMR designs. MFF-3 was irradiated for 726 Effective Full Power Days (EFPD), starting from Cycle 10C1 (from November 1988 through March 1992), and MFF-5 was irradiated for 503 EFPD starting from Cycle 11B1 (from January 1990 through March 1992). A group of fuel pins from these two tests are undergoing post irradiation examination at the Idaho National Laboratory (INL) for the Fuel Cycle Research and Development Program (FCRD). The generation of a data package of key information on the irradiation environment and current pin detailed compositions for these tests is described. This information will be used in interpreting the results of these examinations.

  5. Voluntary Protection Program Onsite Review, Fluor Hanford Fast Flux Test Facility Recertification- October 2007

    Broader source: Energy.gov [DOE]

    Evaluation to determine whether Fluor Hanford Fast Flux Test Facility is continuing to perform at a level deserving DOE-VPP Star recognition.

  6. Algae Raceway Testing Facility Brings Algal Biofuels One Step Closer to Reality

    Broader source: Energy.gov [DOE]

    A new algae raceway testing facility opened earlier this month at Sandia National Laboratories in Livermore, California, that could help bring algal biofuels one step closer to commercialization....

  7. Testing standards for physical security systems at Category 1 fuel cycle facilities

    SciTech Connect (OSTI)

    Dwyer, P.A.

    1991-10-01

    This NUREG is a compilation of physical security testing standards for use at fuel cycle facilities using or possessing formula quantities of strategic special nuclear material.

  8. Interface Control Document for the Interface between the Central Solenoid Insert Coil and the Test Facility

    SciTech Connect (OSTI)

    Smirnov, Alexandre; Martovetsky, Nicolai N; Nunoya, Yoshihiko

    2011-06-01

    This document provides the interface definition and interface control between the Central Solenoid Insert Coil and the Central Solenoid Model Coil Test Facility in Japan.

  9. EERE Success Story-New Wind Test Facilities Open in Colorado and South

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

    Carolina | Department of Energy Wind Test Facilities Open in Colorado and South Carolina EERE Success Story-New Wind Test Facilities Open in Colorado and South Carolina January 1, 2014 - 12:00am Addthis Two of the world's largest state-of-the-art drivetrain test facilities are now open for business: the Wind Turbine Drivetrain Testing Facility at the Clemson University Restoration Institute in South Carolina and the 5-megawatt (MW) dynamometer at the U.S. Department of Energy's (DOE)

  10. Seismic requirements for design of nuclear power plants and nuclear test facilities

    SciTech Connect (OSTI)

    Not Available

    1985-02-01

    This standard establishes engineering requirements for the design of nuclear power plants and nuclear test facilities to accommodate vibratory effects of earthquakes.

  11. PROJECT PROFILE: Regional Test Center Operations

    Broader source: Energy.gov [DOE]

    The Regional Test Center (RTC) program aims to support technical innovation in the U.S. solar sector by validating the performance of new PV products in multiple climates. The RTCs are the premier sites for climatically distinct testing of new PV module products from U.S. manufacturers. Tests conducted directly address U.S. manufacturing needs for improved bankability and reduced market barriers for novel technologies.

  12. Project Impact Assessments: Building America FY14 Field Test Technical

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

    Support - 2014 BTO Peer Review | Department of Energy Project Impact Assessments: Building America FY14 Field Test Technical Support - 2014 BTO Peer Review Project Impact Assessments: Building America FY14 Field Test Technical Support - 2014 BTO Peer Review Presenter: Lieko Earle, National Renewable Energy Laboratory The goal of this project is for the National Renewable Energy Laboratory to provide extensive, hands-on technical support to Building America teams in the areas of experiment

  13. Novel Muon Beam Facilities for Project X at Fermilab

    SciTech Connect (OSTI)

    Neuffer, D.V.; Ankenbrandt, C.M.; Abrams, R.; Roberts, T.J.; Yoshikawa, C.Y.; /MUONS Inc., Batavia

    2012-05-01

    Innovative muon beam concepts for intensity-frontier experiments such as muon-to-electron conversion are described. Elaborating upon a previous single-beam idea, we have developed a design concept for a system to generate four high quality, low-energy muon beams (two of each sign) from a single beam of protons. As a first step, the production of pions by 1 and 3 GeV protons from the proposed Project X linac at Fermilab is being simulated and compared with the 8-GeV results from the previous study.

  14. NREL: MIDC/Vehicle Testing and Integration Facility RSR (39.74 N, 105.18 W,

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

    1793 m, GMT-7) NREL Vehicle Testing and Integration Facility (RSR)

  15. Action Memorandum for the Engineering Test Reactor under the Idaho Cleanup Project

    SciTech Connect (OSTI)

    A. B. Culp

    2007-01-26

    This Action Memorandum documents the selected alternative for decommissioning of the Engineering Test Reactor at the Idaho National Laboratory under the Idaho Cleanup Project. Since the missions of the Engineering Test Reactor Complex have been completed, an engineering evaluation/cost analysis that evaluated alternatives to accomplish the decommissioning of the Engineering Test Reactor Complex was prepared adn released for public comment. The scope of this Action Memorandum is to encompass the final end state of the Complex and disposal of the Engineering Test Reactor vessol. The selected removal action includes removing and disposing of the vessel at the Idaho CERCLA Disposal Facility and demolishing the reactor building to ground surface.

  16. Development and Commissioning of a Small/Mid-Size Wind Turbine Test Facility: Preprint

    SciTech Connect (OSTI)

    Valyou, D.; Arsenault, T.; Janoyan, K.; Marzocca, P.; Post, N.; Grappasonni, G.; Arras, M.; Coppotelli, G.; Cardenas, D.; Elizalde, H.; Probst, O.

    2015-01-01

    This paper describes the development and commissioning tests of the new Clarkson University/Center for Evaluation of Clean Energy Technology Blade Test Facility. The facility is a result of the collaboration between the New York State Energy Research and Development Authority and Intertek, and is supported by national and international partners. This paper discusses important aspects associated with blade testing and includes results associated with modal, static, and fatigue testing performed on the Sandia National Laboratories' Blade Systems Design Studies blade. An overview of the test capabilities of the Blade Test Facility are also provided.

  17. Deuteron injector for Peking University Neutron Imaging Facility project

    SciTech Connect (OSTI)

    Ren, H. T.; Chen, J. E.; Peng, S. X.; Lu, P. N.; Zhou, Q. F.; Yuan, Z. X.; Zhao, J.; Zhang, M.; Song, Z. Z.; Yu, J. X.; Guo, Z. Y.

    2012-02-15

    The deuteron injector developed for the PKUNIFTY (Peking University Neutron Imaging Facility) has been installed and commissioned at Peking University (PKU). The injector system must transfer 50 keV 50 mA of D{sup +} ion beam to the entrance of the 2 MeV radio frequency quadrupole (RFQ) with 10% duty factor (1 ms, 100 Hz). A compact 2.45 GHz permanent magnet electron cyclotron resonance (PMECR) ion source and a 1.36 m long low energy beam transport (LEBT) line using two solenoids was developed as the deuteron injector. A {phi}5 mm four-quadrant diaphragm was used to simulate the entrance of RFQ electrodes. The beam parameters are measured after this core with an emittance measurement unit (EMU) and a bending magnet for ion fraction analysis at the end of injector. During the commissioning, 77 mA of total deuteron beam was extracted from PMECR and 56 mA of pure D{sup +} beam that passed through the {phi}5 mm four-quadrant diaphragm was obtained at the position of RFQ entrance with the measured normalized rms emittance 0.12-0.16{pi} mm mrad. Ion species analysis results show that the deuteron fraction is as high as 99.5%. All of the parameters satisfy PKUNIFTY's requirements. In this paper, we will describe the deuteron injector design and report the commissioning results as well as the initial operation.

  18. SEISMIC DESIGN REQUIREMENTS SELECTION METHODOLOGY FOR THE SLUDGE TREATMENT & M-91 SOLID WASTE PROCESSING FACILITIES PROJECTS

    SciTech Connect (OSTI)

    RYAN GW

    2008-04-25

    In complying with direction from the U.S. Department of Energy (DOE), Richland Operations Office (RL) (07-KBC-0055, 'Direction Associated with Implementation of DOE-STD-1189 for the Sludge Treatment Project,' and 08-SED-0063, 'RL Action on the Safety Design Strategy (SDS) for Obtaining Additional Solid Waste Processing Capabilities (M-91 Project) and Use of Draft DOE-STD-I 189-YR'), it has been determined that the seismic design requirements currently in the Project Hanford Management Contract (PHMC) will be modified by DOE-STD-1189, Integration of Safety into the Design Process (March 2007 draft), for these two key PHMC projects. Seismic design requirements for other PHMC facilities and projects will remain unchanged. Considering the current early Critical Decision (CD) phases of both the Sludge Treatment Project (STP) and the Solid Waste Processing Facilities (M-91) Project and a strong intent to avoid potentially costly re-work of both engineering and nuclear safety analyses, this document describes how Fluor Hanford, Inc. (FH) will maintain compliance with the PHMC by considering both the current seismic standards referenced by DOE 0 420.1 B, Facility Safety, and draft DOE-STD-1189 (i.e., ASCE/SEI 43-05, Seismic Design Criteria for Structures, Systems, and Components in Nuclear Facilities, and ANSI!ANS 2.26-2004, Categorization of Nuclear Facility Structures, Systems and Components for Seismic Design, as modified by draft DOE-STD-1189) to choose the criteria that will result in the most conservative seismic design categorization and engineering design. Following the process described in this document will result in a conservative seismic design categorization and design products. This approach is expected to resolve discrepancies between the existing and new requirements and reduce the risk that project designs and analyses will require revision when the draft DOE-STD-1189 is finalized.

  19. Manhattan Project buildings and facilities at the Hanford Site: A construction history

    SciTech Connect (OSTI)

    Gerber, M.S.

    1993-09-01

    This document thoroughly examines the role that the Hanford Engineer Works played in the Manhattan project. The historical aspects of the buildings and facilities are characterized. An in depth look at the facilities, including their functions, methods of fabrication and appearance is given for the 100 AREAS, 200 AREAS, 300 AREAS, 500, 800 and 900 AREAS, 600 AREA, 700 AREA, 1100 AREA and temporary construction structures.

  20. Project W320 52-inch diameter equipment container load test: Test report

    SciTech Connect (OSTI)

    Bellomy, J.R.

    1995-02-22

    This test report summarizes testing activities and documents the results of the load tests performed on-site and off-site to structural qualify the 52-inch equipment containers designed and fabricated under Project W-320.

  1. EA-1616: National Carbon Research Center Project at Southern Company Services' Power Systems Development Facility near Wilsonville, Alabama

    Broader source: Energy.gov [DOE]

    This EA evaluates and updates the potential environmental impacts of DOE’s proposed continued operations of the NCCC Project at the PSDF plant. The NCCC is designed to test and evaluate carbon dioxide (CO2) control technologies for power generation facilities, including CO2 capture solvents and sorbents, mass-transfer devices, lower cost water-gas shift reactors, and scaled-up membrane technologies. Additionally, the NCCC evaluates methods to integrate CO2 capture technologies with other coal-based power plant systems by testing both pre-combustion and post-combustion technologies. The NCCC provides the capability to test these systems under a wide range of fuels, including bituminous and sub-bituminous coals, lignites and biomass/coal mixtures. The goal of the NCCC project is to accelerate the development, optimization, and commercialization of viable CO2 control technologies.

  2. Integrated Performance Testing for Nonproliferation Support Project

    SciTech Connect (OSTI)

    Johns, Russell; Bultz, Garl Alan; Byers, Kenneth R.; Yaegle, William

    2013-08-20

    The objective of this workshop is to provide participants with training in testing techniques and methodologies for assessment of the performance of: Physical Protection system elements; Material Control and Accounting (MC&A) system elements.

  3. Project Hanford management contract quality assurance program implementation plan for nuclear facilities

    SciTech Connect (OSTI)

    Bibb, E.K.

    1997-10-15

    During transition from the Westinghouse Hanford Company (WHC) Management and Operations (M and O) contract to the Fluor Daniel Hanford (FDH) Management and Integration (M and I) contract, existing WHC policies, procedures, and manuals were reviewed to determine which to adopt on an interim basis. Both WHC-SP-1131,Hanford Quality Assurance Program and Implementation Plan, and WHC-CM-4-2, Quality Assurance Manual, were adopted; however, it was recognized that revisions were required to address the functions and responsibilities of the Project Hanford Management Contract (PHMC). This Quality Assurance Program Implementation Plan for Nuclear Facilities (HNF-SP-1228) supersedes the implementation portion of WHC-SP-1 13 1, Rev. 1. The revised Quality Assurance (QA) Program is documented in the Project Hanford Quality Assurance Program Description (QAPD), HNF-MP-599. That document replaces the QA Program in WHC-SP-1131, Rev. 1. The scope of this document is limited to documenting the nuclear facilities managed by FDH and its Major Subcontractors (MSCS) and the status of the implementation of 10 CFR 830.120, Quality Assurance Requirements, at those facilities. Since the QA Program for the nuclear facilities is now documented in the QAPD, future updates of the information provided in this plan will be by letter. The layout of this plan is similar to that of WHC-SP-1 13 1, Rev. 1. Sections 2.0 and 3.0 provide an overview of the Project Hanford QA Program. A list of Project Hanford nuclear facilities is provided in Section 4.0. Section 5.0 provides the status of facility compliance to 10 CFR 830.120. Sections 6.0, 7.0, and 8.0 provide requested exemptions, status of open items, and references, respectively. The four appendices correspond to the four projects that comprise Project Hanford.

  4. Description of the OSU APEX test facility to assess AP600 passive safety

    SciTech Connect (OSTI)

    Hochreiter, L.E.; Lau, L.K.; Reyes, J.N. Jr.; Groome, J.T.

    1995-12-31

    The objective of this paper is to describe the Advanced Plant Experiment (APEX) test facility, which is a new integral system test facility located at Oregon State University (OSU) specifically scaled, designed, and built to simulate all of the important geometrical details of the Westinghouse AP600. The APEX facility has been designed and constructed to develop a database that can be used to validate the thermal hydraulic safety analysis codes that will be used in the AP600 design certification process. The test facility has been specifically designed and scaled to model small break loss-of-coolant and long-term cooling transients, which utilize the AP600 passive safety systems.

  5. EERE Success Story-DOE-Funded Project is First Permanent Facility to

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

    Co-produce Electricity from Geothermal Resources at an Oil and Gas Well | Department of Energy DOE-Funded Project is First Permanent Facility to Co-produce Electricity from Geothermal Resources at an Oil and Gas Well EERE Success Story-DOE-Funded Project is First Permanent Facility to Co-produce Electricity from Geothermal Resources at an Oil and Gas Well May 12, 2016 - 11:03am Addthis Source: Kirby Baier of Continental Resources Source: Kirby Baier of Continental Resources The U.S.

  6. Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

    SciTech Connect (OSTI)

    IRWIN, J.J.

    2000-11-18

    The mission of the Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying Facility (CVDF) is to achieve the earliest possible removal of free water from Multi-Canister Overpacks (MCOs). The MCOs contain metallic uranium SNF that have been removed from the 100K Area fuel storage water basins (i.e., the K East and K West Basins) at the US. Department of Energy Hanford Site in Southeastern Washington state. Removal of free water is necessary to halt water-induced corrosion of exposed uranium surfaces and to allow the MCOs and their SNF payloads to be safely transported to the Hanford Site 200 East Area and stored within the SNF Project Canister Storage Building (CSB). The CVDF is located within a few hundred yards of the basins, southwest of the 165KW Power Control Building and the 105KW Reactor Building. The site area required for the facility and vehicle circulation is approximately 2 acres. Access and egress is provided by the main entrance to the 100K inner area using existing roadways. The CVDF will remove free. water from the MCOs to reduce the potential for continued fuel-water corrosion reactions. The cold vacuum drying process involves the draining of bulk water from the MCO and subsequent vacuum drying. The MCO will be evacuated to a pressure of 8 torr or less and backfilled with an inert gas (helium). The MCO will be sealed, leak tested, and then transported to the CSB within a sealed shipping cask. (The MCO remains within the same shipping Cask from the time it enters the basin to receive its SNF payload until it is removed from the Cask by the CSB MCO handling machine.) The CVDF subproject acquired the required process systems, supporting equipment, and facilities. The cold vacuum drying operations result in an MCO containing dried fuel that is prepared for shipment to the CSB by the Cask transportation system. The CVDF subproject also provides equipment to dispose of solid wastes generated by the cold vacuum drying process and transfer process water removed from the MCO back to the K Basins.

  7. Test Facility Pilot Program | U.S. DOE Office of Science (SC)

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

    Test Facility Pilot Program High Energy Physics (HEP) HEP Home About Research Science Drivers of Particle Physics Energy Frontier Intensity Frontier Cosmic Frontier Theoretical and Computational Physics Advanced Technology R&D Accelerator Stewardship Background Awards Information for Investigators Test Facility Pilot Program Workshop Reports Facilities Science Highlights Benefits of HEP Funding Opportunities Advisory Committees Community Resources Contact Information High Energy Physics U.S.

  8. Recovery Act-Funded 90-m Blade Test Facility Commissioned May 18, 2011

    Broader source: Energy.gov [DOE]

    The Wind Technology Testing Center (WTTC) in Boston, Massachusetts, now offers a full suite of certification tests for turbine blades up to 90 m in length as the state-of-the-art facility opened May 18, 2011.

  9. Recovery Act-Funded 90-m Blade Test Facility Commissioned May...

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

    suite of certification tests for turbine blades up to 90 m in length as the state-of-the-art facility opened May 18, 2011. The center is the first commercial large blade test...

  10. New Battery Testing Facility Could Boost Future of Electric Vehicles

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

    Heat transfer and fluid flow experiments have been used to design battery packs. The laboratory's computer-aided design expertise can project the thermal performance of modules and ...

  11. Design Report for the Scale Air-Cooled RCCS Tests in the Natural convection Shutdown heat removal Test Facility (NSTF)

    SciTech Connect (OSTI)

    Lisowski, D. D.; Farmer, M. T.; Lomperski, S.; Kilsdonk, D. J.; Bremer, N.; Aeschlimann, R. W.

    2014-06-01

    The Natural convection Shutdown heat removal Test Facility (NSTF) is a large scale thermal hydraulics test facility that has been built at Argonne National Laboratory (ANL). The facility was constructed in order to carry out highly instrumented experiments that can be used to validate the performance of passive safety systems for advanced reactor designs. The facility has principally been designed for testing of Reactor Cavity Cooling System (RCCS) concepts that rely on natural convection cooling for either air or water-based systems. Standing 25-m in height, the facility is able to supply up to 220 kW at 21 kW/m2 to accurately simulate the heat fluxes at the walls of a reactor pressure vessel. A suite of nearly 400 data acquisition channels, including a sophisticated fiber optic system for high density temperature measurements, guides test operations and provides data to support scaling analysis and modeling efforts. Measurements of system mass flow rate, air and surface temperatures, heat flux, humidity, and pressure differentials, among others; are part of this total generated data set. The following report provides an introduction to the top level-objectives of the program related to passively safe decay heat removal, a detailed description of the engineering specifications, design features, and dimensions of the test facility at Argonne. Specifications of the sensors and their placement on the test facility will be provided, along with a complete channel listing of the data acquisition system.

  12. Safety Design Strategy for the Advanced Test Reactor Emergency Firewater Injection System Replacement Project

    SciTech Connect (OSTI)

    Noel Duckwitz

    2011-06-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

  13. Safety Design Strategy for the Advanced Test Reactor Primary Coolant Pump and Motor Replacement Project

    SciTech Connect (OSTI)

    Noel Duckwitz

    2011-06-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

  14. Safety Design Strategy for the Advanced Test Reactor Diesel Bus (E-3) and Switchgear Replacement Project

    SciTech Connect (OSTI)

    Noel Duckwitz

    2011-06-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

  15. Design review plan for Multi-Function Waste Tank Facility (Project W-236A)

    SciTech Connect (OSTI)

    Renfro, G.G.

    1994-12-20

    This plan describes how the Multi-Function Waste Tank Facility (MWTF) Project conducts reviews of design media; describes actions required by Project participants; and provides the methodology to ensure that the design is complete, meets the technical baseline of the Project, is operable and maintainable, and is constructable. Project W-236A is an integrated project wherein the relationship between the operating contractor and architect-engineer is somewhat different than that of a conventional project. Working together, Westinghouse Hanford Company (WHC) and ICF Karser Hanford (ICF KH) have developed a relationship whereby ICF KH performs extensive design reviews and design verification. WHC actively participates in over-the-shoulder reviews during design development, performs a final review of the completed design, and conducts a formal design review of the Safety Class I, ASME boiler and Pressure Vessel Code items in accordance with WHC-CM-6-1, Standard Engineering Practices.

  16. Energy Department Announces $5 Million to Develop Clean Energy Projects at Federal Facilities

    Broader source: Energy.gov [DOE]

    The Energy Department today announced $5 million in funding for nine projects that will advance the development of combined heat and power (CHP) and renewable energy technologies at facilities across the federal government and help meet energy efficiency, renewable energy, and greenhouse gas reduction goals.

  17. Evolution of Safeguards over Time: Past, Present, and Projected Facilities, Material, and Budget

    SciTech Connect (OSTI)

    Kollar, Lenka; Mathews, Caroline E.

    2009-07-01

    This study examines the past trends and evolution of safeguards over time and projects growth through 2030. The report documents the amount of nuclear material and facilities under safeguards from 1970 until present, along with the corresponding budget. Estimates for the future amount of facilities and material under safeguards are made according to non-nuclear-weapons states’ (NNWS) plans to build more nuclear capacity and sustain current nuclear infrastructure. Since nuclear energy is seen as a clean and economic option for base load electric power, many countries are seeking to either expand their current nuclear infrastructure, or introduce nuclear power. In order to feed new nuclear power plants and sustain existing ones, more nuclear facilities will need to be built, and thus more nuclear material will be introduced into the safeguards system. The projections in this study conclude that a zero real growth scenario for the IAEA safeguards budget will result in large resource gaps in the near future.

  18. Facilities

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

    Energy Future MissionFacilities FacilitiesTara Camacho-Lopez2016-04-06T18:06:13+00:00 National Solar Thermal ... experimental engineering data for the design, ...

  19. Large-Scale Renewable Energy Guide: Developing Renewable Energy Projects Larger Than 10 MWs at Federal Facilities

    Broader source: Energy.gov [DOE]

    The Large-Scale Renewable Energy Guide: Developing Renewable Energy Projects Larger Than 10 MWs at Federal Facilities provides best practices and other helpful guidance for federal agencies developing large-scale renewable energy projects.

  20. Benchmarking the Remote-Handled Waste Facility at the West Valley Demonstration Project

    SciTech Connect (OSTI)

    O. P. Mendiratta; D. K. Ploetz

    2000-02-29

    ABSTRACT Facility decontamination activities at the West Valley Demonstration Project (WVDP), the site of a former commercial nuclear spent fuel reprocessing facility near Buffalo, New York, have resulted in the removal of radioactive waste. Due to high dose and/or high contamination levels of this waste, it needs to be handled remotely for processing and repackaging into transport/disposal-ready containers. An initial conceptual design for a Remote-Handled Waste Facility (RHWF), completed in June 1998, was estimated to cost $55 million and take 11 years to process the waste. Benchmarking the RHWF with other facilities around the world, completed in November 1998, identified unique facility design features and innovative waste pro-cessing methods. Incorporation of the benchmarking effort has led to a smaller yet fully functional, $31 million facility. To distinguish it from the June 1998 version, the revised design is called the Rescoped Remote-Handled Waste Facility (RRHWF) in this topical report. The conceptual design for the RRHWF was completed in June 1999. A design-build contract was approved by the Department of Energy in September 1999.

  1. New Zero Net-Energy Facility: A Test Bed for Home Efficiency | Department

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

    of Energy Zero Net-Energy Facility: A Test Bed for Home Efficiency New Zero Net-Energy Facility: A Test Bed for Home Efficiency September 17, 2012 - 2:34pm Addthis Deputy Assistant Secretary for Energy Efficiency Kathleen Hogan joined representatives from the National Institute of Standards and Technology (NIST) and state and local elected officials to celebrate the opening of the new zero net-energy residential test laboratory. | Photo courtesy of NIST. Deputy Assistant Secretary for Energy

  2. Advanced Test Reactor National Scientific User Facility (ATR NSUF) Monthly Report October 2014

    SciTech Connect (OSTI)

    Dan Ogden

    2014-10-01

    Advanced Test Reactor National Scientific User Facility (ATR NSUF) Monthly Report October 2014 Highlights Rory Kennedy, Dan Ogden and Brenden Heidrich traveled to Germantown October 6-7, for a review of the Infrastructure Management mission with Shane Johnson, Mike Worley, Bradley Williams and Alison Hahn from NE-4 and Mary McCune from NE-3. Heidrich briefed the group on the project progress from July to October 2014 as well as the planned path forward for FY15. Jim Cole gave two invited university seminars at Ohio State University and University of Florida, providing an overview of NSUF including available capabilities and the process for accessing facilities through the peer reviewed proposal process. Jim Cole and Rory Kennedy co-chaired the NuMat meeting with Todd Allen. The meeting, sponsored by Elsevier publishing, was held in Clearwater, Florida, and is considered one of the premier nuclear fuels and materials conferences. Over 340 delegates attended with 160 oral and over 200 posters presented over 4 days. Thirty-one pre-applications were submitted for NSUF access through the NE-4 Combined Innovative Nuclear Research Funding Opportunity Announcement. Fourteen proposals were received for the NSUF Rapid Turnaround Experiment Summer 2014 call. Proposal evaluations are underway. John Jackson and Rory Kennedy attended the Nuclear Fuels Industry Research meeting. Jackson presented an overview of ongoing NSUF industry research.

  3. Project Manager, Nevada Test Site | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Project Manager, Nevada Test Site Susan Livenick, NTS Project Manager Susan Livenick August 2009 U.S. Department of Energy's Management Award On August 12, Susan Livenick, a Project Manager at the Nevada Test Site received the 2009 U.S. Department of Energy's Management Award at a special awards ceremony in Providence, R.I. The awards honor outstanding achievements in energy and water management. Susan oversaw Bldg. B3's abatement and renovation from 2005-2008, making B3 the

  4. Transition plan: Project C-018H, 200-E Area Effluent Treatment Facility

    SciTech Connect (OSTI)

    Connor, M.D.

    1994-09-29

    The purpose of this transition plan is to ensure an orderly transfer of project information to operations to satisfy Westinghouse Hanford Company (WHC) operational requirements and objectives, and ensure safe and efficient operation of Project C-018H, the 200-E Area Effluent Treatment Facility (ETF). This plan identifies the deliverables for Project C-018H upon completion of construction and turnover to WHC for operations, and includes acceptance criteria to objectively assess the adequacy of the contract deliverables in relation to present requirements. The scope of this plan includes a general discussion of the need for complete and accurate design basis documentation and design documents as project deliverables. This plan also proposes that a configuration management plan be prepared to protect and control the transferred design documents and reconstitute the design basis and design requirements, in the event that the deliverables and project documentation received from the contractor are less than adequate at turnover.

  5. Recovery of Information from the Fast Flux Test Facility for the Advanced Fuel Cycle Initiative

    SciTech Connect (OSTI)

    Nielsen, Deborah L.; Makenas, Bruce J.; Wootan, David W.; Butner, R. Scott; Omberg, Ronald P.

    2009-09-30

    The Fast Flux Test Facility is the most recent Liquid Metal Reactor to operate in the United States. Information from the design, construction, and operation of this reactor was at risk as the facilities associated with the reactor are being shut down. The Advanced Fuel Cycle Initiative is a program managed by the Office of Nuclear Energy of the U.S. Department of Energy with a mission to develop new fuel cycle technologies to support both current and advanced reactors. Securing and preserving the knowledge gained from operation and testing in the Fast Flux Test Facility is an important part of the Knowledge Preservation activity in this program.

  6. A Cryogenic RF Material Testing Facility at SLAC

    SciTech Connect (OSTI)

    Guo, Jiquan; Martin, David; Tantawi, Sami; Yoneda, Charles; /SLAC

    2012-06-22

    The authors have developed an X-band SRF testing system using a high-Q copper cavity with an interchangeable flat bottom for the testing of different materials. By measuring the Q of the cavity, the system is capable to characterize the quenching magnetic field of the superconducting samples at different power level and temperature, as well as the surface resistivity. This paper presents the most recent development of the system and testing results.

  7. 2014 WIND POWER PROGRAM PEER REVIEW-TEST FACILITIES

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

    ... the distribution and transmission infrastructure is ... extreme conditions - Data to test design margins and validate ... mast top (in situ) * Microwave radiometer for T, q * ...

  8. Testing Promising Technologies: A Role for Federal Facilities

    Broader source: Energy.gov [DOE]

    Presentation covers the testing of promising technologies and is given at the Spring 2011 Federal Utility Partnership Working Group (FUPWG) meeting.

  9. New Test Facilities Opening this Fall | Department of Energy

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

    for testing the larger multimegawatt wind turbines currently being developed by both U.S. ... engineers with a better understanding of how wind turbines react to grid disturbances. ...

  10. High Burnup Dry Storage Cask Research and Development Project, Final Test Plan

    SciTech Connect (OSTI)

    2014-02-27

    EPRI is leading a project team to develop and implement the first five years of a Test Plan to collect data from a SNF dry storage system containing high burnup fuel.12 The Test Plan defined in this document outlines the data to be collected, and the storage system design, procedures, and licensing necessary to implement the Test Plan.13 The main goals of the proposed test are to provide confirmatory data14 for models, future SNF dry storage cask design, and to support license renewals and new licenses for ISFSIs. To provide data that is most relevant to high burnup fuel in dry storage, the design of the test storage system must mimic real conditions that high burnup SNF experiences during all stages of dry storage: loading, cask drying, inert gas backfilling, and transfer to the ISFSI for multi-year storage.15 Along with other optional modeling, SETs, and SSTs, the data collected in this Test Plan can be used to evaluate the integrity of dry storage systems and the high burnup fuel contained therein over many decades. It should be noted that the Test Plan described in this document discusses essential activities that go beyond the first five years of Test Plan implementation.16 The first five years of the Test Plan include activities up through loading the cask, initiating the data collection, and beginning the long-term storage period at the ISFSI. The Test Plan encompasses the overall project that includes activities that may not be completed until 15 or more years from now, including continued data collection, shipment of the Research Project Cask to a Fuel Examination Facility, opening the cask at the Fuel Examination Facility, and examining the high burnup fuel after the initial storage period.

  11. Underground Test Area Subproject Project Management Plan, Revision 1

    SciTech Connect (OSTI)

    1998-06-03

    This Project Management Plan (PMP) describes the manner in which the US Department of Energy Nevada Operations Office (DOE/NV) will manage the Underground Test Area (UGTA) Subproject at the Nevada Test Site (NTS). It provides the basic guidance for implementation and the organizational structure for meeting the UGTA objectives.

  12. Early test facilities and analytic methods for radiation shielding: Proceedings

    SciTech Connect (OSTI)

    Ingersoll, D.T. ); Ingersoll, J.K. )

    1992-11-01

    This report represents a compilation of eight papers presented at the 1992 American Nuclear Society/European Nuclear Society International Meeting. The meeting is of special significance since it commemorates the fiftieth anniversary of the first controlled nuclear chain reaction. The papers contained in this report were presented in a special session organized by the Radiation Protection and Shielding Division in keeping with the historical theme of the meeting. The paper titles are good indicators of their content and are: (1) The origin of radiation shielding research: The Oak Ridge experience, (2) Shielding research at the hanford site, (3) Aircraft shielding experiments at General Dynamics Fort Worth, 1950-1962, (4) Where have the neutrons gone , a history of the tower shielding facility, (5) History and evolution of buildup factors, (6) Early shielding research at Bettis atomic power laboratory, (7) UK reactor shielding: then and now, (8) A very personal view of the development of radiation shielding theory.

  13. South Carolina Opens Nation’s Largest Wind Drivetrain Testing Facility

    Broader source: Energy.gov [DOE]

    Today, U.S. Deputy Secretary of Energy Daniel Poneman joined with officials from Clemson University to dedicate the nation's largest and one of the world's most advanced wind energy testing facilities in North Charleston, S.C.

  14. EA-0993: Shutdown of the Fast Flux Testing Facility, Richland, Washington

    Office of Energy Efficiency and Renewable Energy (EERE)

    This EA evaluates the environmental impacts of the U.S. Department of Energy's Hanford Site's proposal to place the Fast Flux Test Facility (FFTF) in a radiologically and industrially safe shutdown...

  15. Report of Survey of the Los Alamos Tritium Systems Test Assembly Facility

    Broader source: Energy.gov [DOE]

    The purpose of this document is to report the results of a survey conducted at the Los Alamos Tritium Systems Test Assembly (TSTA Facility). The survey was conducted during the week of 3/20/00.

  16. Summary description of the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Cabell, C.P.

    1980-12-01

    This document has been compiled and issued to provide an illustrated engineering summary description of the FFTF. The document is limited to a description of the plant and its functions, and does not cover the extensive associated programs that have been carried out in the fields of design, design analysis, safety analysis, fuels development, equipment development and testing, quality assurance, equipment fabrication, plant construction, acceptance testing, operations planning and training, and the like.

  17. Coal-fired MHD test progress at the component development and integration facility

    SciTech Connect (OSTI)

    Hart, A.T.; Lofftus, D.

    1994-12-31

    The Component and Development and Integration Facility (CDIF) is a Department of Energy test facility operated by MSE, Inc. MSE personnel were responsible for the integration of topping cycle components for the national coal-fired magnetohydrodynamics development program. Initial facility checkout and baseline data generation testing at the CDIF used a 50-megawatt (MW{sub t}), oil-fired combustor (with ash injection to simulate coal slag carryover) coupled to the 1A{sub 1} supersonic channel. In the fall of 1984, a 50-MW{sub t}, pressurized, slag rejecting coal-fired combustor replaced the oil-fired combustor in the test train. In the spring of 1989, a coal-fired precombustor was added to the workhorse test hardware. In the spring of 1992, workhorse hardware was replaced with the prototypic coal-fired test train. Testing during the last year emphasized prototypic hardware testing targeted at longer duration testing, some intermediate checkout testing, and more reliable operation. These phases of testing and the associated facility modifications are discussed. Progress of the proof-of-concept testing, through the time of testing shutdown, is addressed.

  18. Baseline tests for arc melter vitrification of INEL buried wastes. Volume 1: Facility description and summary data report

    SciTech Connect (OSTI)

    Oden, L.L.; O`Connor, W.K.; Turner, P.C.; Soelberg, N.R.; Anderson, G.L.

    1993-11-19

    This report presents field results and raw data from the Buried Waste Integrated Demonstration (BWID) Arc Melter Vitrification Project Phase 1 baseline test series conducted by the Idaho National Engineering Laboratory (INEL) in cooperation with the U.S. Bureau of Mines (USBM). The baseline test series was conducted using the electric arc melter facility at the USBM Albany Research Center in Albany, Oregon. Five different surrogate waste feed mixtures were tested that simulated thermally-oxidized, buried, TRU-contaminated, mixed wastes and soils present at the INEL. The USBM Arc Furnace Integrated Waste Processing Test Facility includes a continuous feed system, the arc melting furnace, an offgas control system, and utilities. The melter is a sealed, 3-phase alternating current (ac) furnace approximately 2 m high and 1.3 m wide. The furnace has a capacity of 1 metric ton of steel and can process as much as 1,500 lb/h of soil-type waste materials. The surrogate feed materials included five mixtures designed to simulate incinerated TRU-contaminated buried waste materials mixed with INEL soil. Process samples, melter system operations data and offgas composition data were obtained during the baseline tests to evaluate the melter performance and meet test objectives. Samples and data gathered during this program included (a) automatically and manually logged melter systems operations data, (b) process samples of slag, metal and fume solids, and (c) offgas composition, temperature, velocity, flowrate, moisture content, particulate loading and metals content. This report consists of 2 volumes: Volume I summarizes the baseline test operations. It includes an executive summary, system and facility description, review of the surrogate waste mixtures, and a description of the baseline test activities, measurements, and sample collection. Volume II contains the raw test data and sample analyses from samples collected during the baseline tests.

  19. A Test Facility for MEIC ERL Circulator Ring Based Electron Cooler Design

    SciTech Connect (OSTI)

    Zhang, Yuhong; Derbenev, Yaroslav S.; Douglas, David R.; Hutton, Andrew M.; Krafft, Geoffrey A.; Nissen, Edward W.

    2013-05-01

    An electron cooling facility which is capable to deliver a beam with energy up to 55 MeV and average current up to 1.5 A at a high bunch repetition rate up to 750 MHz is required for MEIC. The present cooler design concept is based on a magnetized photo-cathode SRF gun, an SRF ERL and a compact circulator ring. In this paper, we present a proposal of a test facility utilizing the JLab FEL ERL for a technology demonstration of this cooler design concept. Beam studies will be performed and supporting technologies will also be developed in this test facility.

  20. REPORT OF SURVEY OF THE LOS ALAMOS TRITIUM SYSTEMS TEST ASSEMBLY FACILITY

    Office of Environmental Management (EM)

    REPORT OF SURVEY OF THE LOS ALAMOS TRITIUM SYSTEMS TEST ASSEMBLY FACILITY U.S. Department of Energy Office of Environmental Management & Office of Science Report of Survey of the Los Alamos Tritium Systems Test Assembly Facility Rev. E (Final) October 3, 2000 Contents 1. Introduction 1.1 Purpose 1.2 Facility Description 1.3 Organization Representatives 1.4 Survey Participants 2. Summary, Conclusions & Recommendations 2.1 Comparison With LCAM Requirements 2.2 Transfer Considerations 2.3

  1. The mixed waste management facility. Project baseline revision 1.2

    SciTech Connect (OSTI)

    Streit, R.D.; Throop, A.L.

    1995-04-01

    Revision 1.2 to the Project Baseline (PB) for the Mixed Waste Management Facility (MWMF) is in response to DOE directives and verbal guidance to (1) Collocate the Decontamination and Waste Treatment Facility (DWTF) and MWMF into a single complex, integrate certain and overlapping functions as a cost-saving measure; (2) Meet certain fiscal year (FY) new-BA funding objectives ($15.3M in FY95) with lower and roughly balanced funding for out years; (3) Reduce Total Project Cost (TPC) for the MWMF Project; (4) Include costs for all appropriate permitting activities in the project TPC. This baseline revision also incorporates revisions in the technical baseline design for Molten Salt Oxidation (MSO) and Mediated Electrochemical Oxidation (MEO). Changes in the WBS dictionary that are necessary as a result of this rebaseline, as well as minor title changes, at WBS Level 3 or above (DOE control level) are approved as a separate document. For completeness, the WBS dictionary that reflects these changes is contained in Appendix B. The PB, with revisions as described in this document, were also the basis for the FY97 Validation Process, presented to DOE and their reviewers on March 21-22, 1995. Appendix C lists information related to prior revisions to the PB. Several key changes relate to the integration of functions and sharing of facilities between the portion of the DWTF that will house the MWMF and those portions that are used by the Hazardous Waste Management (HWM) Division at LLNL. This collocation has been directed by DOE as a cost-saving measure and has been implemented in a manner that maintains separate operational elements from a safety and permitting viewpoint. Appendix D provides background information on the decision and implications of collocating the two facilities.

  2. Active Test of Purification Facility at Rokkasho Reprocessing Plant

    SciTech Connect (OSTI)

    Iseki, Tadahiro; Tsujimura, Akino; Nitta, Takeshi; Matsuda, Takashi

    2007-07-01

    During the second and third steps of Active Test of the Plutonium Purification unit, the extraction and reextraction performances of pulsed columns and mixer-settlers have been checked. Plutonium losses into wastes have been also checked. As a result, it was confirmed that the expected performances had been achieved. (authors)

  3. 340 Facility Secondary Containment and Leak Detection Project W-302 Functional Design Criteria

    SciTech Connect (OSTI)

    Stordeur, R.T.

    1995-03-01

    This functional design criteria for the upgrade to the 340 radioactive liquid waste storage facility (Project W-302) specifically addresses the secondary containment issues at the current vault facility of the 340 Complex. This vault serves as the terminus for the Radioactive Liquid Waste System (RLWS). Project W-302 is necessary in order to bring this portion of the Complex into full regulatory compliance. The project title, ``340 Facility Secondary Containment and Leak Detection``, illustrates preliminary thoughts of taking corrective action directly upon the existing vault (such as removing the tanks, lining the vault, and replacing tanks). However, based on the conclusion of the engineering study, ``Engineering Study of the 300 Area Process Wastewater Handling System``, WHC-SD-WM-ER-277 (as well as numerous follow-up meetings with cognizant staff), this FDC prescribes a complete replacement of the current tank/vault system. This offers a greater array of tanks, and provides greater operating flexibility and ease of maintenance. This approach also minimizes disruption to RLWS services during ``tie-in``, as compared to the alternative of trying to renovate the old vault. The proposed site is within the current Complex area, and maintains the receipt of RLWS solutions through gravity flow.

  4. Developing Renewable Energy Projects Larger Than 10 MWs at Federal Facilities

    SciTech Connect (OSTI)

    2013-03-01

    To accomplish Federal goals for renewable energy, sustainability, and energy security, large-scale renewable energy projects must be developed and constructed on Federal sites at a significant scale with significant private investment. For the purposes of this Guide, large-scale Federal renewable energy projects are defined as renewable energy facilities larger than 10 megawatts (MW) that are sited on Federal property and lands and typically financed and owned by third parties.1 The U.S. Department of Energy’s Federal Energy Management Program (FEMP) helps Federal agencies meet these goals and assists agency personnel navigate the complexities of developing such projects and attract the necessary private capital to complete them. This Guide is intended to provide a general resource that will begin to develop the Federal employee’s awareness and understanding of the project developer’s operating environment and the private sector’s awareness and understanding of the Federal environment. Because the vast majority of the investment that is required to meet the goals for large-scale renewable energy projects will come from the private sector, this Guide has been organized to match Federal processes with typical phases of commercial project development. FEMP collaborated with the National Renewable Energy Laboratory (NREL) and professional project developers on this Guide to ensure that Federal projects have key elements recognizable to private sector developers and investors. The main purpose of this Guide is to provide a project development framework to allow the Federal Government, private developers, and investors to work in a coordinated fashion on large-scale renewable energy projects. The framework includes key elements that describe a successful, financially attractive large-scale renewable energy project. This framework begins the translation between the Federal and private sector operating environments. When viewing the overall

  5. ESTB: A New Beam Test Facility at SLAC

    SciTech Connect (OSTI)

    Pivi, M.; Fieguth, T.; Hast, C.; Iverson, R.; Jaros, J.; Jobe, K.; Keller, L.; Walz, D.; Weathersby, S.; Woods, M.; /SLAC

    2011-04-05

    End Station A Test Beam (ESTB) is a beam line at SLAC using a small fraction of the bunches of the 13.6 GeV electron beam from the Linac Coherent Light Source (LCLS), restoring test beam capabilities in the large End Station A (ESA) experimental hall. ESTB will provide one of a kind test beam essential for developing accelerator instrumentation and accelerator R&D, performing particle and particle astrophysics detector research, linear collider machine and detector interface (MDI) R&D studies, development of radiation-hard detectors, and material damage studies with several distinctive features. In the past, 18 institutions participated in the ESA program at SLAC. In stage I, 4 new kicker magnets will be added to divert 5 Hz of the LCLS beam to the A-line. A new beam dump will be installed and a new Personnel Protection System (PPS) is being built in ESA. In stage II, a secondary hadron target will be installed, able to produce pions up to about 12 GeV/c at 1 particle/pulse.

  6. Final Turbine and Test Facility Design Report Alden/NREC Fish Friendly Turbine

    Broader source: Energy.gov [DOE]

    The final report provides an overview of the Alden/NREC Fish Friendly turbine design phase, turbine test plan, preliminary test results, costs, schedule, and a hypothetical application at a real world project.

  7. Prototypical Rod Consolidation Demonstration Project. Phase 3, Final report: Volume 1, Cold checkout test report, Book 1

    SciTech Connect (OSTI)

    Not Available

    1993-05-01

    The objective of Phase 3 of the Prototypical Rod consolidation Demonstration Project (PRCDP) was to procure, fabricate, assemble, and test the Prototypical Rod consolidation System as described in the NUS Phase 2 Final Design Report. This effort required providing the materials, components, and fabricated parts which makes up all of the system equipment. In addition, it included the assembly, installation, and setup of this equipment at the Cold Test Facility. During the Phase 3 effort the system was tested on a component, subsystem, and system level. This volume 1, discusses the PRCDP Phase 3 Test Program that was conducted by the HALLIBURTON NUS Environmental Corporation under contract AC07-86ID12651 with the United States Department of Energy. This document, Volume 1, Book 1 discusses the following topics: the background of the project; test program description; summary of tests and test results; problem evaluation; functional requirements confirmation; recommendations; and completed test documentation for tests performed in Phase 3.

  8. Ultra-accelerated natural sunlight exposure testing facilities

    DOE Patents [OSTI]

    Lewandowski, Allan A.; Jorgensen, Gary J.

    2003-08-12

    A multi-faceted concentrator apparatus for providing ultra-accelerated natural sunlight exposure testing for sample materials under controlled weathering conditions comprising: facets that receive incident natural sunlight, transmits VIS/NIR and reflects UV/VIS to deliver a uniform flux of UV/VIS onto a sample exposure plane located near a center of a facet array in chamber means that provide concurrent levels of temperature and/or relative humidity at high levels of up to 100.times. of natural sunlight that allow sample materials to be subjected to accelerated irradiance exposure factors for a significant period of time of about 3 to 10 days to provide a corresponding time of about at least a years worth representative weathering of sample materials.

  9. Ultra-Accelerated Natural Sunlight Exposure Testing Facilities

    DOE Patents [OSTI]

    Lewandowski, Allan A.; Jorgensen, Gary J.

    2004-11-23

    A multi-faceted concentrator apparatus for providing ultra-accelerated natural sunlight exposure testing for sample materials under controlled weathering conditions comprising: facets that receive incident natural sunlight, transmits VIS/NIR and reflects UV/VIS onto a secondary reflector that delivers a uniform flux of UV/VIS onto a sample exposure plane located near a center of a facet array in a chamber that provide concurrent levels of temperature and/or relative humidity at high levels of up to 100.times. of natural sunlight that allow sample materials to be subjected to accelerated irradiance exposure factors for a significant period of time of about 3 to 10 days to provide a corresponding time of about at least a years worth representative weathering of sample materials.

  10. Regional Test Centers Project Expands U.S. Small Wind Certification...

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

    Regional Test Centers Project Expands U.S. Small Wind Certification Testing Capability ... partners to establish small wind Regional Test Centers (RTCs) to conduct tests on small ...

  11. Coal-fired MHD test progress at the Component Development and Integration Facility

    SciTech Connect (OSTI)

    Hart, A.T.; Filius, K.D.; Micheletti, D.A.; Cashell, P.V.

    1993-12-31

    The Component Development and Integration Facility (CDIF) is a Department of Energy test facility operated by MSE, Inc. MSE personnel are responsible for integrated testing of topping cycle components for the national coal-fired magnetohydrodynamics (MHD) development program. Initial facility checkout and baseline data generation testing at the CDIF used a 50-MW{sub t}, oil-fired combustor (with ash injection to simulate coal slag carryover) coupled to the 1A{sub 1} supersonic workhorse channel. In the fall of 1984, a 50-MW{sub t}, pressurized, slag rejecting coal-fired workhorse combustor replaced the oil-fired combustor in the test train. In the spring of 1989, a coal-fired precombustor was added to the test hardware, and current controls were installed in the spring of 1990. In the fall of 1990, the slag rejector was installed. In the spring of 1992, a 50-MW{sub t} pressurized, slag rejecting coal-fired prototypical combustor replaced the workhorse combustor in the test train. A 1A{sub 4} supersonic prototypical channel replaced the 1A{sub 1} workhorse channel in the fall of 1993. This prototypical hardware is slated to be used for the proof-of-concept (POC) testing. Improved facility systems targeting longer duration testing and more reliable operation will be discussed, including the air emissions control and monitoring hardware, oxygen and nitrogen expansion, coal and seed system upgrades, A-Bay modifications, and new solid suspension injection equipment.

  12. Preliminary Analysis of the Transient Reactor Test Facility (TREAT) with PROTEUS

    SciTech Connect (OSTI)

    Connaway, H. M.; Lee, C. H.

    2015-11-30

    The neutron transport code PROTEUS has been used to perform preliminary simulations of the Transient Reactor Test Facility (TREAT). TREAT is an experimental reactor designed for the testing of nuclear fuels and other materials under transient conditions. It operated from 1959 to 1994, when it was placed on non-operational standby. The restart of TREAT to support the U.S. Department of Energy’s resumption of transient testing is currently underway. Both single assembly and assembly-homogenized full core models have been evaluated. Simulations were performed using a historic set of WIMS-ANL-generated cross-sections as well as a new set of Serpent-generated cross-sections. To support this work, further analyses were also performed using additional codes in order to investigate particular aspects of TREAT modeling. DIF3D and the Monte-Carlo codes MCNP and Serpent were utilized in these studies. MCNP and Serpent were used to evaluate the effect of geometry homogenization on the simulation results and to support code-to-code comparisons. New meshes for the PROTEUS simulations were created using the CUBIT toolkit, with additional meshes generated via conversion of selected DIF3D models to support code-to-code verifications. All current analyses have focused on code-to-code verifications, with additional verification and validation studies planned. The analysis of TREAT with PROTEUS-SN is an ongoing project. This report documents the studies that have been performed thus far, and highlights key challenges to address in future work.

  13. A free-piston Stirling engine/linear alternator controls and load interaction test facility

    SciTech Connect (OSTI)

    Rauch, J.S.; Kankam, M.D.; Santiago, W.; Madi, F.J.

    1992-08-01

    A test facility at LeRC was assembled for evaluating free-piston Stirling engine/linear alternator control options, and interaction with various electrical loads. This facility is based on a 'SPIKE' engine/alternator. The engine/alternator, a multi-purpose load system, a digital computer based load and facility control, and a data acquisition system with both steady-periodic and transient capability are described. Preliminary steady-periodic results are included for several operating modes of a digital AC parasitic load control. Preliminary results on the transient response to switching a resistive AC user load are discussed.

  14. Preliminary design for hot dirty-gas control-valve test facility. Final report

    SciTech Connect (OSTI)

    Not Available

    1980-01-01

    This report presents the results of a preliminary design and cost estimating effort for a facility for the testing of control valves in Hot Dirty Gas (HDGCV) service. This design was performed by Mittelhauser Corporation for the United States Department of Energy's Morgantown Energy Technology Center (METC). The objective of this effort was to provide METC with a feasible preliminary design for a test facility which could be used to evaluate valve designs under simulated service conditions and provide a technology data base for DOE and industry. In addition to the actual preliminary design of the test facility, final design/construction/operating schedules and a facility cost estimate were prepared to provide METC sufficient information with which to evaluate this design. The bases, assumptions, and limitations of this study effort are given. The tasks carried out were as follows: METC Facility Review, Environmental Control Study, Gas Generation Study, Metallurgy Review, Safety Review, Facility Process Design, Facility Conceptual Layout, Instrumentation Design, Cost Estimates, and Schedules. The report provides information regarding the methods of approach used in the various tasks involved in the completion of this study. Section 5.0 of this report presents the results of the study effort. The results obtained from the above-defined tasks are described briefly. The turnkey cost of the test facility is estimated to be $9,774,700 in fourth quarter 1979 dollars, and the annual operating cost is estimated to be $960,000 plus utilities costs which are not included because unit costs per utility were not available from METC.

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

    SciTech Connect (OSTI)

    Michael R. Kruzic

    2008-06-01

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

  16. Piping system response during high-level simulated seismic tests at the Heissdampfreaktor Facility: (SHAM Test Facility)

    SciTech Connect (OSTI)

    Steele, R. Jr.; Nitzel, M.E.

    1992-07-01

    The SHAM seismic research program studied the effects of increasing levels of seismic excitation on a full-scale, in situ nuclear piping system containing a naturally aged United States (US) 8-in. motor-operated gate valve. The program was conducted by Kernforschungszentrum Karlsruhe at the Heissdampfreaktor near Frankfurt, Germany. Participants included the United States, Germany, and England. Fifty-one experiments were conducted, with the piping supported by six different piping support systems, including a typical stiff US piping support system of snubbers and rigid struts. This report specifically addresses the tests conducted with the US system. The piping system withstood large displacements caused by overload snubber failures and local piping strains. Although some limit switch chatter was observed, the motor operator and valve functioned smoothly throughout the tests. The results indicate that sufficient safety margins exist when commonly accepted design methods are applied and that piping systems will likely maintain their pressure boundary in the presence of severe loading and the loss of multiple supports.

  17. EA-0930: Facility Operations at the U.S. DOE Grand Junction Projects Office, Grand Junction, Colorado

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of the proposal to expand and upgrade the U.S. Department of Energy's Grand Junction Projects Office facilities and operations in Grand Junction, Colorado.

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

    SciTech Connect (OSTI)

    Michael Kruzic

    2007-09-01

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

  19. Evaluation of the effects of underground water usage and spillage in the Exploratory Studies Facility; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Dunn, E.; Sobolik, S.R.

    1993-12-01

    The Yucca Mountain Site Characterization Project is studying Yucca Mountain in southwestern Nevada as a potential site for a high-level radioactive waste repository. Analyses reported herein were performed to support the design of site characterization activities so that these activities will have a minimal impact on the ability of the site to isolate waste and a minimal impact on underground tests performed as part of the characterization process. These analyses examine the effect of water to be used in the underground construction and testing activities for the Exploratory Studies Facility on in situ conditions. Underground activities and events where water will be used include construction, expected but unplanned spills, and fire protection. The models used predict that, if the current requirements in the Exploratory Studies Facility Design Requirements are observed, water that is imbibed into the tunnel wall rock in the Topopah Springs welded tuff can be removed over the preclosure time period by routine or corrective ventilation, and also that water imbibed into the Paintbrush Tuff nonwelded tuff will not reach the potential waste storage area.

  20. Infrastructure Development of Single Cell Testing Capability at A0 Facility

    SciTech Connect (OSTI)

    Dhanaraj, Nandhini; Padilla, R.; Reid, J.; Khabiboulline, T.; Ge, M.; Mukherjee, A.; Rakhnov, I.; Ginsburg, C.; Wu, G.; Harms, E.; Carter, H.; /Fermilab

    2009-09-01

    The objective of this technical note is to document the details of the infrastructure development process that was realized at the A0 photo injector facility to establish RF cold testing capability for 1.3 GHz superconducting niobium single cell cavities. The activity began the last quarter of CY 2006 and ended the first quarter of CY 2009. The whole process involved addressing various aspects such as design of vertical insert and lifting fixture, modification of existing RF test station and design of new couplers, development of a Temperature Mapping (T-Map) system, radiation considerations for the test location (north cave), update of existing High Pressure Rinse (HPR) system, preparation of necessary safety documents and eventually obtaining an Operational Readiness Clearance (ORC). Figure 1 illustrates the various components of the development process. In the past, the north cave test station at A0 has supported the cold testing 3.9 GHz nine cell and single cell cavities, thus some of the components were available for use and some needed modification. The test dewar had the capacity to accommodate 1.3 GHz single cells although a new vertical insert that could handle both cavity types (1.3 and 3.9 GHz) had to be designed. The existing cryogenic system with an average capacity of {approx} 0.5 g/sec was deemed sufficient. The RF system was updated with broadband components and an additional amplifier with higher power capacity to handle higher gradients usually achieved in 1.3 GHz cavities. The initial testing phase was arbitrated to proceed with fixed power coupling. A new temperature mapping system was developed to provide the diagnostic tool for hot spot studies, quench characterization and field emission studies. The defining feature of this system was the use of diode sensors instead of the traditional carbon resistors as sensing elements. The unidirectional current carrying capacity (forward bias) of the diodes provided for the ease of multiplexing of the system, thus substantially reducing the number of cables required to power the sensors. The high gradient capacity of the 1.3 GHz cavities required a revision of the radiation shielding and interlocks. The cave was updated as per the recommendations of the radiation safety committee. The high pressure rinse system was updated with new adapters to assist the rinsing 1.3 GHz single cell cavities. Finally, a proposal for cold testing 1.3 GHz single cell cavities at A0 north cave was made to the small experiments approval committee, radiation safety committee and the Tevatron cryogenic safety sub-committee for an operational readiness clearance and the same was approved. The project was classified under research and development of single cell cavities (project 18) and was allocated a budget of $200,000 in FY 2007.

  1. BENCHMARK EVALUATION OF THE INITIAL ISOTHERMAL PHYSICS MEASUREMENTS AT THE FAST FLUX TEST FACILITY

    SciTech Connect (OSTI)

    John Darrell Bess

    2010-05-01

    The benchmark evaluation of the initial isothermal physics tests performed at the Fast Flux Test Facility, in support of Fuel Cycle Research and Development and Generation-IV activities at the Idaho National Laboratory, has been completed. The evaluation was performed using MCNP5 with ENDF/B-VII.0 nuclear data libraries and according to guidelines provided for inclusion in the International Reactor Physics Experiment Evaluation Project Handbook. Results provided include evaluation of the initial fully-loaded core critical, two neutron spectra measurements near the axial core center, 32 reactivity effects measurements (21 control rod worths, two control rod bank worths, six differential control rod worths, two shutdown margins, and one excess reactivity), isothermal temperature coefficient, and low-energy electron and gamma spectra measurements at the core center. All measurements were performed at 400 ºF. There was good agreement between the calculated and benchmark values for the fully-loaded core critical eigenvalue, reactivity effects measurements, and isothermal temperature coefficient. General agreement between benchmark experiment measurements and calculated spectra for neutrons and low-energy gammas at the core midplane exists, but calculations of the neutron spectra below the core and the low-energy gamma spectra at core midplane did not agree well. Homogenization of core components may have had a significant impact upon computational assessment of these effects. Future work includes development of a fully-heterogeneous model for comprehensive evaluation. The reactor physics measurement data can be used in nuclear data adjustment and validation of computational methods for advanced fuel cycle and nuclear reactor systems using Liquid Metal Fast Reactor technology.

  2. Structural testing of corrugated asbestos-cement roof panels at the Hanford Facilities, Richland, Washington

    SciTech Connect (OSTI)

    Moustafa, S.E.; Rodehaver, S.M.; Frier, W.A.

    1993-10-01

    This report describes a roof testing program that was carried out at the 105KE/KW Spent Fuel Storage Basins and their surrounding facilities at the Hanford Site in Richland, Washington. The roof panels were constructed in the mid 1950`s of corrugated asbestos-cement (A/C), which showed common signs of aging. Based on the construction specifications, the panels capacity to meet current design standards was questioned. Both laboratory and in-situ load testing of the corrugated A/C panels was conducted. The objective of the complete test program was to determine the structural integrity of the existing A/C roof panels installed in the 105KE and 105KW facilities. The data from these tests indicated that the roofs are capable of resisting the design loads and are considered safe. A second phase test to address the roof resistance to personnel and roof removal/roofing system installation equipment was recommended and is underway.

  3. Results from the NRC AP600 testing program at the Oregon State University APEX facility

    SciTech Connect (OSTI)

    Reyes, J.N. Jr.; Bessette, D.E.; DiMarzo, M.

    1996-03-01

    The Department of Nuclear Engineering at Oregon State University (OSU) is performing a series of confirmatory tests for the U.S. Nuclear Regulatory Commission. These tests are being conducted in the Advanced Plant Experiment (APEX) facility which is a 1/4 length scale and 1/192 volume scale integral system simulation of the Westinghouse Advanced Passive 600 MWe (AP600) plant. The purpose of the testing program is to examine AP600 passive safety system performance, particularly during long term cooling. Thus far, OSU has successfully performed ten integral system tests for the NRC. This paper presents a description of the APEX facility and summarizes the important results of the NRC test program at OSU.

  4. Geotechnical characterization of the North Ramp of the Exploratory Studies Facility: Yucca Mountain Site Characterization Project. Volume 1, Data summary

    SciTech Connect (OSTI)

    Brechtel, C.E.; Lin, Ming; Martin, E.; Kessel, D.S.

    1995-05-01

    This report presents the results of geological and geotechnical characterization of the Miocene volcanic tuff rocks of the Timber Mountain and Paintbrush groups that the tunnel boring machine will encounter during excavation of the Exploratory Studies Facility (ESF) North Ramp. The is being constructed by the DOE as part of the Yucca Mountain Project site characterization activities. The purpose of these activities is to evaluate the feasibility of locating a potential high-level nuclear waste repository on lands adjacent to the Nevada Test Site, Nye County, Nevada. This report was prepared as part of the Soil and Rock Properties Studies in accordance with the 8.3.1.14.2 Study Plan. This report is volume 1 of the data summary.

  5. Test and evaluation plan for Project W-314 tank farm restoration and safe operations

    SciTech Connect (OSTI)

    Hays, W.H.

    1998-06-25

    The ``Tank Farm Restoration and Safe Operations`` (TFRSO), Project W-314 will restore and/or upgrade existing Hanford Tank Farm facilities and systems to ensure that the Tank Farm infrastructure will be able to support near term TWRS Privatization`s waste feed delivery and disposal system and continue safe management of tank waste. The capital improvements provided by this project will increase the margin of safety for Tank Farms operations, and will aid in aligning affected Tank Farm systems with compliance requirements from applicable state, Federal, and local regulations. Secondary benefits will be realized subsequent to project completion in the form of reduced equipment down-time, reduced health and safety risks to workers, reduced operating and maintenance costs, and minimization of radioactive and/or hazardous material releases to the environment. The original regulatory (e.g., Executive Orders, WACS, CFRS, permit requirements, required engineering standards, etc.) and institutional (e.g., DOE Orders, Hanford procedures, etc.) requirements for Project W-314 were extracted from the TWRS S/RIDs during the development of the Functions and Requirements (F and Rs). The entire family of requirements were then validated for TWRS and Project W-314. This information was contained in the RDD-100 database and used to establish the original CDR. The Project Hanford Management Contract (PHMC) team recognizes that safety, quality, and cost effectiveness in the Test and Evaluation (T and E) program is achieved through a planned systematic approach to T and E activities. It is to this end that the Test and Evaluation Plan (TEP) is created. The TEP for the TFRSO Project, was developed based on the guidance in HNF-IP-0842, and the Good Practice Guide GPG-FM-005, ``Test and Evaluation,`` which is derived from DOE Order 430.1, ``Life Cycle Asset Management.`` It describes the Test and Evaluation program for the TFRSO project starting with the definitive design phase and ending with operational testing and turn-over of the upgraded systems to Tank Farm Operations. The TEP will be updated as required to reflect the appropriate test acceptance and startup requirements to support design, construction, turnover and initial operations.

  6. Listing of Defense Nuclear Facilities

    Energy Savers [EERE]

    Listing of Defense Nuclear Facilities The facilities listed below are considered DOE defense nuclear facilities for purposes of Section 3161. Kansas City Plant Pinellas Plant Mound Facility Fernald Environmental Management Project Site Pantex Plant Rocky Flats Environmental Technology Site, including the Oxnard Facility Savannah River Site Los Alamos National Laboratory Sandia National Laboratory Lawrence Livermore National Laboratory Oak Ridge National Laboratory Nevada Test Site 1 Y-12 Plant

  7. CERTS Microgrid Laboratory Test Bed - PIER Final Project Report

    SciTech Connect (OSTI)

    Eto, Joseph H.; Eto, Joseph H.; Lasseter, Robert; Schenkman, Ben; Klapp, Dave; Linton, Ed; Hurtado, Hector; Roy, Jean; Lewis, Nancy Jo; Stevens, John; Volkommer, Harry

    2008-07-25

    The objective of the CERTS Microgrid Laboratory Test Bed project was to enhance the ease of integrating small energy sources into a microgrid. The project accomplished this objective by developing and demonstrating three advanced techniques, collectively referred to as the CERTS Microgrid concept, that significantly reduce the level of custom field engineering needed to operate microgrids consisting of small generating sources. The techniques comprising the CERTS Microgrid concept are: 1) a method for effecting automatic and seamless transitions between grid-connected and islanded modes of operation; 2) an approach to electrical protection within the microgrid that does not depend on high fault currents; and 3) a method for microgrid control that achieves voltage and frequency stability under islanded conditions without requiring high-speed communications. The techniques were demonstrated at a full-scale test bed built near Columbus, Ohio and operated by American Electric Power. The testing fully confirmed earlier research that had been conducted initially through analytical simulations, then through laboratory emulations, and finally through factory acceptance testing of individual microgrid components. The islanding and resychronization method met all Institute of Electrical and Electronics Engineers 1547 and power quality requirements. The electrical protections system was able to distinguish between normal and faulted operation. The controls were found to be robust and under all conditions, including difficult motor starts. The results from these test are expected to lead to additional testing of enhancements to the basic techniques at the test bed to improve the business case for microgrid technologies, as well to field demonstrations involving microgrids that involve one or mroe of the CERTS Microgrid concepts.

  8. Central and Eastern United States (CEUS) Seismic Source Characterization (SSC) for Nuclear Facilities Project

    SciTech Connect (OSTI)

    Kevin J. Coppersmith; Lawrence A. Salomone; Chris W. Fuller; Laura L. Glaser; Kathryn L. Hanson; Ross D. Hartleb; William R. Lettis; Scott C. Lindvall; Stephen M. McDuffie; Robin K. McGuire; Gerry L. Stirewalt; Gabriel R. Toro; Robert R. Youngs; David L. Slayter; Serkan B. Bozkurt; Randolph J. Cumbest; Valentina Montaldo Falero; Roseanne C. Perman' Allison M. Shumway; Frank H. Syms; Martitia P. Tuttle

    2012-01-31

    This report describes a new seismic source characterization (SSC) model for the Central and Eastern United States (CEUS). It will replace the Seismic Hazard Methodology for the Central and Eastern United States, EPRI Report NP-4726 (July 1986) and the Seismic Hazard Characterization of 69 Nuclear Plant Sites East of the Rocky Mountains, Lawrence Livermore National Laboratory Model, (Bernreuter et al., 1989). The objective of the CEUS SSC Project is to develop a new seismic source model for the CEUS using a Senior Seismic Hazard Analysis Committee (SSHAC) Level 3 assessment process. The goal of the SSHAC process is to represent the center, body, and range of technically defensible interpretations of the available data, models, and methods. Input to a probabilistic seismic hazard analysis (PSHA) consists of both seismic source characterization and ground motion characterization. These two components are used to calculate probabilistic hazard results (or seismic hazard curves) at a particular site. This report provides a new seismic source model. Results and Findings The product of this report is a regional CEUS SSC model. This model includes consideration of an updated database, full assessment and incorporation of uncertainties, and the range of diverse technical interpretations from the larger technical community. The SSC model will be widely applicable to the entire CEUS, so this project uses a ground motion model that includes generic variations to allow for a range of representative site conditions (deep soil, shallow soil, hard rock). Hazard and sensitivity calculations were conducted at seven test sites representative of different CEUS hazard environments. Challenges and Objectives The regional CEUS SSC model will be of value to readers who are involved in PSHA work, and who wish to use an updated SSC model. This model is based on a comprehensive and traceable process, in accordance with SSHAC guidelines in NUREG/CR-6372, Recommendations for Probabilistic Seismic Hazard Analysis: Guidance on Uncertainty and Use of Experts. The model will be used to assess the present-day composite distribution for seismic sources along with their characterization in the CEUS and uncertainty. In addition, this model is in a form suitable for use in PSHA evaluations for regulatory activities, such as Early Site Permit (ESPs) and Combined Operating License Applications (COLAs). Applications, Values, and Use Development of a regional CEUS seismic source model will provide value to those who (1) have submitted an ESP or COLA for Nuclear Regulatory Commission (NRC) review before 2011; (2) will submit an ESP or COLA for NRC review after 2011; (3) must respond to safety issues resulting from NRC Generic Issue 199 (GI-199) for existing plants and (4) will prepare PSHAs to meet design and periodic review requirements for current and future nuclear facilities. This work replaces a previous study performed approximately 25 years ago. Since that study was completed, substantial work has been done to improve the understanding of seismic sources and their characterization in the CEUS. Thus, a new regional SSC model provides a consistent, stable basis for computing PSHA for a future time span. Use of a new SSC model reduces the risk of delays in new plant licensing due to more conservative interpretations in the existing and future literature. Perspective The purpose of this study, jointly sponsored by EPRI, the U.S. Department of Energy (DOE), and the NRC was to develop a new CEUS SSC model. The team assembled to accomplish this purpose was composed of distinguished subject matter experts from industry, government, and academia. The resulting model is unique, and because this project has solicited input from the present-day larger technical community, it is not likely that there will be a need for significant revision for a number of years. See also Sponsors Perspective for more details. The goal of this project was to implement the CEUS SSC work plan for developing a regional CEUS SSC model. The work plan, formulated by the project manager and a technical integration team, consists of a series of tasks designed to meet the project objectives. This report was reviewed by a participatory peer review panel (PPRP), sponsor reviewers, the NRC, the U.S. Geological Survey, and other stakeholders. Comments from the PPRP and other reviewers were considered when preparing the report. The SSC model was completed at the end of 2011.

  9. Work plan for the High Ranking Facilities Deactivation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    1996-03-01

    The High Ranking Facilities Deactivation Project (HRFDP), commissioned by the US Department of Energy Nuclear Materials and Facility Stabilization Program, is to place four primary high-risk surplus facilities with 28 associated ancillary facilities at Oak Ridge National Laboratory in a safe, stable, and environmentally sound condition as rapidly and economically as possible. The facilities will be deactivated and left in a condition suitable for an extended period of minimized surveillance and maintenance (S and M) prior to decontaminating and decommissioning (D and D). These four facilities include two reactor facilities containing spent fuel. One of these reactor facilities also contains 55 tons of sodium with approximately 34 tons containing activated sodium-22, 2.5 tons of lithium hydride, approximately 100 tons of potentially contaminated lead, and several other hazardous materials as well as bulk quantities of contaminated scrap metals. The other two facilities to be transferred include a facility with a bank of hot cells containing high levels of transferable contamination and also a facility containing significant quantities of uranyl nitrate and quantities of transferable contamination. This work plan documents the objectives, technical requirements, and detailed work plans--including preliminary schedules, milestones, and conceptual FY 1996 cost estimates--for the Oak Ridge National Laboratory (ORNL). This plan has been developed by the Environmental Restoration (ER) Program of Lockheed Martin Energy Systems (Energy Systems) for the US Department of Energy (DOE) Oak Ridge Operations Office (ORO).

  10. Final Test and Evaluation Results from the Solar Two Project

    SciTech Connect (OSTI)

    BRADSHAW, ROBERT W.; DAWSON, DANIEL B.; DE LA ROSA, WILFREDO; GILBERT, ROCKWELL; GOODS, STEVEN H.; HALE, MARY JANE; JACOBS, PETER; JONES, SCOTT A.; KOLB, GREGORY J.; PACHECO, JAMES E.; PRAIRIE, MICHAEL R.; REILLY, HUGH E.; SHOWALTER, STEVEN K.; VANT-HULL, LORIN L.

    2002-01-01

    Solar Two was a collaborative, cost-shared project between 11 U. S. industry and utility partners and the U. S. Department of Energy to validate molten-salt power tower technology. The Solar Two plant, located east of Barstow, CA, comprised 1926 heliostats, a receiver, a thermal storage system, a steam generation system, and steam-turbine power block. Molten nitrate salt was used as the heat transfer fluid and storage media. The steam generator powered a 10-MWe (megawatt electric), conventional Rankine cycle turbine. Solar Two operated from June 1996 to April 1999. The major objective of the test and evaluation phase of the project was to validate the technical characteristics of a molten salt power tower. This report describes the significant results from the test and evaluation activities, the operating experience of each major system, and overall plant performance. Tests were conducted to measure the power output (MW) of the each major system, the efficiencies of the heliostat, receiver, thermal storage, and electric power generation systems and the daily energy collected, daily thermal-to-electric conversion, and daily parasitic energy consumption. Also included are detailed test and evaluation reports.

  11. 105-K Basin Material Design Basis Feed Description for Spent Nuclear Fuel (SNF) Project Facilities VOL 1 Fuel

    SciTech Connect (OSTI)

    PACKER, M.J.

    1999-11-04

    Metallic uranium Spent Nuclear Fuel (SNF) is currently stored within two water filled pools, 105-KE Basin (KE Basin) and 105-KW Basin (KW Basin), at the United States Department of Energy (U.S. DOE) Hanford Site, in southeastern Washington State. The Spent Nuclear Fuel Project (SNF Project) is responsible to DOE for operation of these fuel storage pools and for the 2100 metric tons of SNF materials that they contain. The SNF Project mission includes safe removal and transportation of all SNF from these storage basins to a new storage facility in the 200 East Area. To accomplish this mission, the SNF Project modifies the existing KE Basin and KW Basin facilities and constructs two new facilities: the 100 K Area Cold Vacuum Drying Facility (CVDF), which drains and dries the SNF; and the 200 East Area Canister Storage Building (CSB), which stores the SNF. The purpose of this document is to describe the design basis feed compositions for materials stored or processed by SNF Project facilities and activities. This document is not intended to replace the Hanford Spent Fuel Inventory Baseline (WHC 1994b), but only to supplement it by providing more detail on the chemical and radiological inventories in the fuel (this volume) and sludge. A variety of feed definitions is required to support evaluation of specific facility and process considerations during the development of these new facilities. Six separate feed types have been identified for development of new storage or processing facilities. The approach for using each feed during design evaluations is to calculate the proposed facility flowsheet assuming each feed. The process flowsheet would then provide a basis for material compositions and quantities which are used in follow-on calculations.

  12. Facility Closure Report for T-Tunnel (U12t), Area 12, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2008-08-01

    This Facility Closure Report (FCR) has been prepared to document the actions taken to permanently close the remaining accessible areas of U12t-Tunnel (T-Tunnel) in Area 12 of the Nevada Test Site (NTS). The closure of T-Tunnel was a prerequisite to transfer facility ownership from the Defense Threat Reduction Agency (DTRA) to the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Closure of the facility was accomplished with the cooperation and concurrence of both NNSA/NSO and the Nevada Division of Environmental Protection (NDEP). The purpose of this FCR is to document that the closure of T-Tunnel complied with the closure requirements specified in the Facility Closure Plan for N- and T-Tunnels Area 12, Nevada Test Site (Appendix D) and that the facility is ready for transfer to NNSA/NSO. The Facility Closure Plan (FCP) is provided in Appendix D. T-Tunnel is located approximately 42 miles north of Mercury in Area 12 of the NTS (Figure 1). Between 1970 and 1987, T-Tunnel was used for six Nuclear Weapons Effects Tests (NWETs). The tunnel was excavated horizontally into the volcanic tuffs of Rainier Mesa. The T-Tunnel complex consists of a main access drift with two NWET containment structures, a Gas Seal Plug (GSP), and a Gas Seal Door (GSD) (Figure 2). The T-Tunnel complex was mothballed in 1993 to preserve the tunnel for resumption of testing, should it happen in the future, to stop the discharge of tunnel effluent, and to prevent unauthorized access. This was accomplished by sealing the main drift GSD.

  13. FAST FLUX TEST FACILITY (FFTF) A HISTORY OF SAFETY & OPERATIONAL EXCELLENCE

    SciTech Connect (OSTI)

    NIELSEN, D L

    2004-02-26

    The Fast Flux Test Facility (FFTF) is a 400-megawatt (thermal) sodium-cooled, high temperature, fast neutron flux, loop-type test reactor. The facility was constructed to support development and testing of fuels, materials and equipment for the Liquid Metal Fast Breeder Reactor program. FFTF began operation in 1980 and over the next 10 years demonstrated its versatility to perform experiments and missions far beyond the original intent of its designers. The reactor had several distinctive features including its size, flux, core design, extensive instrumentation, and test features that enabled it to simultaneously carry out a significant array of missions while demonstrating its features that contributed to a high level of plant safety and availability. FFTF is currently being deactivated for final closure.

  14. Design of a test facility for gas-fired desiccant-based air conditioning systems

    SciTech Connect (OSTI)

    Jalalzadeh-Azar, A.A.; Steele, W.G.; Hodge, B.K.

    1996-12-31

    The design of a facility for testing desiccant-based air conditioning systems is presented. The determination of the performance parameters of desiccant systems is discussed including moisture removal capacity, latent and total cooling capacities, and efficiency indexes. The appropriate procedures and key measurements for determining these parameters are identified using uncertainty analysis.

  15. NREL Vehicle Testing and Integration Facility (VTIF): Rotating Shadowband Radiometer (RSR); Golden, Colorado (Data)

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

    Lustbader, J.; Andreas, A.

    This measurement station at NREL's Vehicle Testing and Integration Facility (VTIF) monitors global horizontal, direct normal, and diffuse horizontal irradiance to define the amount of solar energy that hits this particular location. The solar measurement instrumentation is also accompanied by meteorological monitoring equipment.

  16. NREL Vehicle Testing and Integration Facility (VTIF): Rotating Shadowband Radiometer (RSR); Golden, Colorado (Data)

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

    Lustbader, J.; Andreas, A.

    2012-04-01

    This measurement station at NREL's Vehicle Testing and Integration Facility (VTIF) monitors global horizontal, direct normal, and diffuse horizontal irradiance to define the amount of solar energy that hits this particular location. The solar measurement instrumentation is also accompanied by meteorological monitoring equipment.

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

    Office of Energy Efficiency and Renewable Energy (EERE)

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

  18. Scoping assessment on medical isotope production at the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Scott, S.W.

    1997-08-29

    The Scoping Assessment addresses the need for medical isotope production and the capability of the Fast Flux Test Facility to provide such isotopes. Included in the discussion are types of isotopes used in radiopharmaceuticals, which types of cancers are targets, and in what way isotopes provide treatment and/or pain relief for patients.

  19. DOE’s New Large Blade Test Facility in Massachusetts Completes First Commercial Blade Tests

    Office of Energy Efficiency and Renewable Energy (EERE)

    Since opening its doors for business in May, the Wind Technology Testing Center (WTTC), in Boston, Massachusetts, has come up to full speed testing the long wind turbine blades produced for today's larger wind turbines.

  20. Results of Active Test of Uranium-Plutonium Co-denitration Facility at Rokkasho Reprocessing Plant

    SciTech Connect (OSTI)

    Numao, Teruhiko; Nakayashiki, Hiroshi; Arai, Nobuyuki; Miura, Susumu; Takahashi, Yoshiharu; Nakamura, Hironobu; Tanaka, Izumi

    2007-07-01

    In the U-Pu co-denitration facility at Rokkasho Reprocessing Plant (RRP), Active Test which composes of 5 steps was performed by using uranium-plutonium nitrate solution that was extracted from spent fuels. During Active Test, two kinds of tests were performed in parallel. One was denitration performance test in denitration ovens, and expected results were successfully obtained. The other was validation and calibration of non-destructive assay (NDA) systems, and expected performances were obtained and their effectiveness as material accountancy and safeguards system was validated. (authors)

  1. Kauai Test Facility, Hawaii Sandia Report SAND2014-16456R Unlimited Release

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

    annual site environmental report for sandia national laboratories, Tonopah Test range, Nevada & Kauai Test Facility, Hawaii Sandia Report SAND2014-16456R Unlimited Release Printed September 2014 Prepared by Sandia National Laboratories Albuquerque, New Mexico 87185 Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security

  2. HANFORD CONTAINERIZED CAST STONE FACILITY TASK 1 PROCESS TESTING & DEVELOPMENT FINAL TEST REPORT

    SciTech Connect (OSTI)

    LOCKREM, L L

    2005-07-13

    Laboratory testing and technical evaluation activities on Containerized Cast Stone (CCS) were conducted under the Scope of Work (SOW) contained in CH2M HILL Hanford Group, Inc. (CHG) Contract No. 18548 (CHG 2003a). This report presents the results of testing and demonstration activities discussed in SOW Section 3.1, Task I--''Process Development Testing'', and described in greater detail in the ''Containerized Grout--Phase I Testing and Demonstration Plan'' (CHG, 2003b). CHG (2003b) divided the CCS testing and evaluation activities into six categories, as follows: (1) A short set of tests with simulant to select a preferred dry reagent formulation (DRF), determine allowable liquid addition levels, and confirm the Part 2 test matrix. (2) Waste form performance testing on cast stone made from the preferred DRF and a backup DRF, as selected in Part I, and using low activity waste (LAW) simulant. (3) Waste form performance testing on cast stone made from the preferred DRF using radioactive LAW. (4) Waste form validation testing on a selected nominal cast stone formulation using the preferred DRF and LAW simulant. (5) Engineering evaluations of explosive/toxic gas evolution, including hydrogen, from the cast stone product. (6) Technetium ''getter'' testing with cast stone made with LAW simulant and with radioactive LAW. In addition, nitrate leaching observations were drawn from nitrate leachability data obtained in the course of the Parts 2 and 3 waste form performance testing. The nitrate leachability index results are presented along with other data from the applicable activity categories.

  3. Technical Approach and Plan for Transitioning Spent Nuclear Fuel (SNF) Project Facilities to the Environmental Restoration Program

    SciTech Connect (OSTI)

    SKELLY, W.A.

    1999-10-06

    This document describes the approach and process in which the 100-K Area Facilities are to be deactivated and transitioned over to the Environmental Restoration Program after spent nuclear fuel has been removed from the K Basins. It describes the Transition Project's scope and objectives, work breakdown structure, activity planning, estimated cost, and schedule. This report will be utilized as a planning document for project management and control and to communicate details of project content and integration.

  4. Final project report: High energy rotor development, test and evaluation

    SciTech Connect (OSTI)

    1996-09-01

    Under the auspices of the {open_quotes}Government/Industry Wind Technology Applications Project{close_quotes} [{open_quotes}Letter of Interest{close_quotes} (LOI) Number RC-1-11101], Flo Wind Corp. has successfully developed, tested, and delivered a high-energy rotor upgrade candidate for their 19-meter Vertical Axis Wind Turbine. The project included the demonstration of the innovative extended height-to-diameter ratio concept, the development of a continuous span single-piece composite blade, the demonstration of a continuous blade manufacturing technique, the utilization of the Sandia National Laboratories developed SNLA 2150 natural laminar flow airfoil and the reuse of existing wind turbine and wind power plant infrastructure.

  5. Diagnostic development and support of MHD test facilities. Final progress report, March 1980--March 1994

    SciTech Connect (OSTI)

    Not Available

    1995-02-01

    The Diagnostic Instrumentation and Analysis Laboratory (DIAL) at Mississippi State University (MSU), under U.S. Department of Energy (DOE) Contract No. DE-AC02-80ET-15601, Diagnostic Development and Support of MHD Test Facilities, developed diagnostic instruments for magnetohydrodynamic (MHD) power train data acquisition and for support of MHD component development test facilities. Microprocessor-controlled optical instruments, initially developed for Heat Recovery/Seed Recovery (HRSR) support, were refined, and new systems to measure temperatures and gas-seed-slag stream characteristics were developed. To further data acquisition and analysis capabilities, the diagnostic systems were interfaced with DIAL`s computers. Technical support was provided for the diagnostic needs of the national MHD research effort. DIAL personnel also cooperated with government agencies and private industries to improve the transformation of research and development results into processes, products and services applicable to their needs. The initial contract, Testing and Evaluation of Heat Recovery/Seed Recovery, established a data base on heat transfer, slagging effects on heat transfer surfaces, metal durability, secondary combustor performance, secondary combustor design requirements, and other information pertinent to the design of HR/SR components at the Coal-Fired Flow Facility (CFFF). To accomplish these objectives, a combustion test stand was constructed that simulated MHD environments, and mathematical models were developed and evaluated for the heat transfer in hot-wall test sections. Two transitions occurred during the span of this contract. In May 1983, the objectives and title of the contract changed from Testing and Evaluation of Heat Recovery/Seed Recovery to Diagnostic Development and Support of MHD Test Facilities. In July 1988, the research laboratory`s name changed from the MHD Energy Center to the Diagnostic Instrumentation and Analysis Laboratory.

  6. CLOSURE OF THE FAST FLUX TEST FACILITY (FFTF) CURRENT STATUS & FUTURE PLANS

    SciTech Connect (OSTI)

    BURKE, T.M.

    2005-04-13

    Deactivation activities are currently in progress at the Fast Flux Test Facility. These deactivation activities are intended to remove most hazardous materials and prepare the facility for final disposition. The two major hazards to be removed are the nuclear fuel and the alkali metal (most sodium) coolant. The fuel and coolant removal activities are proceeding well and are expected to complete in 2006. Plant systems are being shut down as allowed by completion of various fuel and coolant removal actions. A Decommissioning Environmental Impact Statement is in progress to evaluate a range of potential final disposition end states.

  7. Sludge treatment facility preliminary siting study for the sludge treatment project (A-13B)

    SciTech Connect (OSTI)

    WESTRA, A.G.

    1999-06-24

    This study evaluates various sites in the 100 K area and 200 areas of Hanford for locating a treatment facility for sludge from the K Basins. Both existing facilities and a new standalone facility were evaluated. A standalone facility adjacent to the AW Tank Farm in the 200 East area of Hanford is recommended as the best location for a sludge treatment facility.

  8. Enterprise Assessments Review of the Savannah River Site Salt Waste Processing Facility Construction Quality and Startup Test Plans – June 2015

    Office of Energy Efficiency and Renewable Energy (EERE)

    Review of the Savannah River Site Salt Waste Processing Facility Construction Quality and Startup Test Plans

  9. Testing of a Continuous Sampling Mercury CEM at the EPA-Rotary Kiln Incinerator Simulator Facility

    SciTech Connect (OSTI)

    D.P. Baldwin; S.J. Bajic; D.E. Eckels; D.S. Zamzow

    2002-04-12

    This report has been prepared to document the performance of the continuous sampling mercury monitoring system developed by Ames Laboratory for use as a continuous emission monitor (CEM). This work was funded by the U.S. Department of Energy, Office of Environmental Management, Office of Science and Technology, through the Mixed Waste Focus Area. The purpose of the project is to develop instrumentation and methods for spectroscopic field-monitoring applications. During FY01 this included continued development and testing of an echelle spectrometer system for the detection of mercury (Hg) by atomic absorption. Due to the relatively poor limits of detection for Hg by optical emission techniques, the CEM has been designed for the detection of elemental Hg by optical absorption. The sampling system allows continuous introduction of stack gas into the CEM for analysis of elemental and total Hg in the gas stream. A heated pyrolysis tube is used in this system to convert oxidized Hg compounds to elemental Hg prior to analysis for total Hg. The pyrolysis tube is bypassed to measure elemental Hg. The CEM is designed to measure the elemental Hg concentration of the gas sample, measure the total Hg concentration, perform a zero check (analysis of room air), and then re-zero the system (to correct for any instrumental drift that occurs over time). This is done in an automated, sequential measurement cycle to provide continuous monitoring of Hg concentrations in the stack gas. The continuous sampling Hg CEM was tested at the EPA-Rotary Kiln in Durham, NC at the beginning of FY02. This report describes the characteristics and performance of the system and the results of the field tests performed at EPA. The Hg CEM system was developed in response to the need of DOE and other organizations to monitor Hg that may be released during the processing or combustion of hazardous or mixed-waste materials. The promulgation of regulations limiting the release of Hg and requiring continuous monitoring of stack gases from combustion and treatment processes would seriously impact the operations of DOE waste treatment facilities. Therefore, it is important to develop and validate techniques that adequately meet proposed sensitivity and accuracy requirements. The most likely form of validation for such a technique involves comparison of CEM results with a reference test method for a test combustion system. Therefore, the CEM system was tested at EPA by monitoring Hg emissions in a natural gas combustion exhaust (that was spiked with Hg) while simultaneously collecting samples using the Ontario-Hydro mercury speciation method as the reference method. The CEM results were available continuously during the on-line monitoring that was performed. The results of the reference method sampling were received a number of weeks after the testing at EPA. These results are discussed in this report, with a comparison and evaluation of the reference method and Hg CEM data.

  10. Steam atmosphere dryer project: System development and field test. Final report

    SciTech Connect (OSTI)

    NONE

    1999-02-01

    The objective of this project was to develop and demonstrate the use of a superheated steam atmosphere dryer as a highly improved alternative to conventional hot air-drying systems, the present industrial standard method for drying various wet feedstocks. The development program plan consisted of three major activities. The first was engineering analysis and testing of a small-scale laboratory superheated steam dryer. This dryer provided the basic engineering heat transfer data necessary to design a large-scale system. The second major activity consisted of the design, fabrication, and laboratory checkout testing of the field-site prototype superheated steam dryer system. The third major activity consisted of the installation and testing of the complete 250-lb/hr evaporation rate dryer and a 30-kW cogeneration system in conjunction with an anaerobic digester facility at the Village of Bergen, NY. Feedstock for the digester facility at the Village of Bergen, NY. Feedstock for the digester was waste residue from a nearby commercial food processing plant. The superheated steam dryer system was placed into operation in August 1996 and operated successfully through March 1997. During this period, the dryer processed all the material from the digester to a powdered consistency usable as a high-nitrogen-based fertilizer.

  11. Facility for Advanced Accelerator Experimental Tests at SLAC (FACET) Conceptual Design Report

    SciTech Connect (OSTI)

    Amann, J.; Bane, K.; /SLAC

    2009-10-30

    This Conceptual Design Report (CDR) describes the design of FACET. It will be updated to stay current with the developing design of the facility. This CDR begins as the baseline conceptual design and will evolve into an 'as-built' manual for the completed facility. The Executive Summary, Chapter 1, gives an introduction to the FACET project and describes the salient features of its design. Chapter 2 gives an overview of FACET. It describes the general parameters of the machine and the basic approaches to implementation. The FACET project does not include the implementation of specific scientific experiments either for plasma wake-field acceleration for other applications. Nonetheless, enough work has been done to define potential experiments to assure that the facility can meet the requirements of the experimental community. Chapter 3, Scientific Case, describes the planned plasma wakefield and other experiments. Chapter 4, Technical Description of FACET, describes the parameters and design of all technical systems of FACET. FACET uses the first two thirds of the existing SLAC linac to accelerate the beam to about 20GeV, and compress it with the aid of two chicanes, located in Sector 10 and Sector 20. The Sector 20 area will include a focusing system, the generic experimental area and the beam dump. Chapter 5, Management of Scientific Program, describes the management of the scientific program at FACET. Chapter 6, Environment, Safety and Health and Quality Assurance, describes the existing programs at SLAC and their application to the FACET project. It includes a preliminary analysis of safety hazards and the planned mitigation. Chapter 7, Work Breakdown Structure, describes the structure used for developing the cost estimates, which will also be used to manage the project. The chapter defines the scope of work of each element down to level 3.

  12. Operational Philosophy for the Advanced Test Reactor National Scientific User Facility

    SciTech Connect (OSTI)

    J. Benson; J. Cole; J. Jackson; F. Marshall; D. Ogden; J. Rempe; M. C. Thelen

    2013-02-01

    In 2007, the Department of Energy (DOE) designated the Advanced Test Reactor (ATR) as a National Scientific User Facility (NSUF). At its core, the ATR NSUF Program combines access to a portion of the available ATR radiation capability, the associated required examination and analysis facilities at the Idaho National Laboratory (INL), and INL staff expertise with novel ideas provided by external contributors (universities, laboratories, and industry). These collaborations define the cutting edge of nuclear technology research in high-temperature and radiation environments, contribute to improved industry performance of current and future light-water reactors (LWRs), and stimulate cooperative research between user groups conducting basic and applied research. To make possible the broadest access to key national capability, the ATR NSUF formed a partnership program that also makes available access to critical facilities outside of the INL. Finally, the ATR NSUF has established a sample library that allows access to pre-irradiated samples as needed by national research teams.

  13. CLOSURE OF THE FAST FLUX TEST FACILITY (FFTF) HISTORY & STATUS & FUTURE PLANS

    SciTech Connect (OSTI)

    FARABEE, O.A.

    2006-02-24

    In 1993, the US Department of Energy (DOE) decided to shut down the Fast Flux Test Facility (FFTF) due to lack of national missions that justified the annual operating budget of approximately $88M/year. The initial vision was to ''deactive'' the facility to an industrially and radiologically safe condition to allow long-term, minimal surveillance storage until approximately 2045. This approach would minimize near term cash flow and allow the radioactive decay of activated components. The final decontamination and decommissioning (D and D) would then be performed using then-current methodology in a safe and efficient manner. the philosophy has now changed to close coupling the initial deactivation with final D and D. This paper presents the status of the facility and focuses on the future challenge of sodium removal.

  14. STATUS OF NEW 2.5 MEV TEST FACILITY AT SNS

    SciTech Connect (OSTI)

    Aleksandrov, Alexander V; Champion, Mark; Crofford, Mark T; Kang, Yoon W; Menshov, Alexander A; Roseberry, Jr., R Tom; Stockli, Martin P; Webster, Anthony W; Welton, Robert F; Zhukov, Alexander P

    2014-01-01

    A new 2.5MeV beam test facility is being built at SNS. It consists of a 65 keV H- ion source, a 2.5MeV RFQ, a beam line with various beam diagnostics and a 6 kW beam dump. The facility is capable of producing one-ms-long pulses at 60Hz repetition rate with up to 50mA peak current. The commissioning with reduced average beam power is planned for fall 2014 to verify operation of all systems. The full power operation is scheduled to begin in 2015. The status of the facility will be presented as well as a discussion of the future R&D program.

  15. Nuclear facility licensing, documentaion, and reviews, and the SP-100 test site experience

    SciTech Connect (OSTI)

    Cornwell, B.C.; Deobald, T.L.; Bitten, E.J.

    1991-06-01

    The required approvals and permits to test a nuclear facility are extensive. Numerous regulatory requirements result in the preparation of documentation to support the approval process. The principal regulations for the SP-100 Ground Engineering System (GES) include the National Environmental Policy Act, Clean Air Act, and Atomic Energy Act. The documentation prepared for the SP-100 Nuclear Assembly Test (NAT) included an Environmental Assessment, state permit applications, and Safety Analysis Reports. This paper discusses the regulation documentation requirements and the SP-100 NAT Test Site experience. 12 refs., 2 figs., 2 tabs.

  16. Advanced Instrumentation, Information and Control (II&C) Research and Development Facility Buildout and Project Execution of LWRS II&C Pilot Projects 1 and 3

    SciTech Connect (OSTI)

    Ronald Farris; Johanna Oxstrand; Gregory Weatherby

    2011-09-01

    The U.S. Department of Energy (DOE) is sponsoring research, development, and deployment on light water reactor sustainability (LWRS), in which the Idaho National Laboratory (INL) is working closely with nuclear utilities to develop technologies and solutions to help ensure the safe operational life extension of current reactors. As technologies are introduced that change the operation of the plant, the LWRS pilot projects can help identify their best-advanced uses and help demonstrate the safety of these technologies. In early testing of operator performance given these emerging technologies will ensure the safety and usability of systems prior to large-scale deployment and costly verification and validation at the plant. The aim of these collaborations, demonstrations, and approaches are intended to lessen the inertia that sustains the current status quo of today's II&C systems technology, and to motivate transformational change and a shift in strategy to a long-term approach to II&C modernization that is more sustainable. Research being conducted under Pilot Project 1 regards understanding the conditions and behaviors that can be modified, either through process improvements and/or technology deployment, to improve the overall safety and efficiency of outage control at nuclear facilities. The key component of the research in this pilot project is accessing the delivery of information that will allow researchers to simulate the control room, outage control center (OCC) information, and plant status data. The simulation also allows researchers to identify areas of opportunity where plant operating status and outage activities can be analyzed to increase overall plant efficiency. For Pilot Project 3 the desire is to demonstrate the ability of technology deployment and the subsequent impact on maximizing the 'Collective Situational Awareness' of the various stakeholders in a commercial nuclear power plant. Specifically, the desire is to show positive results in plant status control, information management, knowledge management, and 'Real-Time-Truth' as it relates to the current plant conditions. The following report includes two attachments; each attachment represents Pilot Project 1 and 3. The two attachments also provide a report on two distinct milestones that were completed and are described below: M3L11IN06030307 - Complete initiation of two pilot projects Complete initiation of pilot projects on real-time configuration management and control to overcome limitations with existing permanent instrumentation and real-time awareness of plant configurations; two candidate projects that consider low-cost wireless technology for in situ configuration monitoring and candidate technologies and an information architecture for outage management and control will be initiated with utilities. M3L11IN06030309 - Complete data collection, R&D plans, and agreements needed to conduct the two pilot projects Complete data collection conducted at pilot project utilities to support real-time configuration management and outage control center pilot studies conducted; R&D plan for pilot projects produced and needed agreements established to support R&D activities.

  17. Spent nuclear fuel project, Cold Vacuum Drying Facility human factors engineering (HFE) analysis: Results and findings

    SciTech Connect (OSTI)

    Garvin, L.J.

    1998-07-17

    This report presents the background, methodology, and findings of a human factors engineering (HFE) analysis performed in May, 1998, of the Spent Nuclear Fuels (SNF) Project Cold Vacuum Drying Facility (CVDF), to support its Preliminary Safety Analysis Report (PSAR), in responding to the requirements of Department of Energy (DOE) Order 5480.23 (DOE 1992a) and drafted to DOE-STD-3009-94 format. This HFE analysis focused on general environment, physical and computer workstations, and handling devices involved in or directly supporting the technical operations of the facility. This report makes no attempt to interpret or evaluate the safety significance of the HFE analysis findings. The HFE findings presented in this report, along with the results of the CVDF PSAR Chapter 3, Hazards and Accident Analyses, provide the technical basis for preparing the CVDF PSAR Chapter 13, Human Factors Engineering, including interpretation and disposition of findings. The findings presented in this report allow the PSAR Chapter 13 to fully respond to HFE requirements established in DOE Order 5480.23. DOE 5480.23, Nuclear Safety Analysis Reports, Section 8b(3)(n) and Attachment 1, Section-M, require that HFE be analyzed in the PSAR for the adequacy of the current design and planned construction for internal and external communications, operational aids, instrumentation and controls, environmental factors such as heat, light, and noise and that an assessment of human performance under abnormal and emergency conditions be performed (DOE 1992a).

  18. THE PROJECT-X INJECTOR EXPERIMENT: A NOVEL HIGH PERFORMANCE FRONT-END FOR A FUTURE HIGH POWER PROTON FACILITY AT FERMILAB

    SciTech Connect (OSTI)

    Nagaitsev, S.; et al,

    2013-09-25

    A multi-MW proton facility, Project X, has been proposed and is currently under development at Fermilab. We are carrying out a program of research and development aimed at integrated systems testing of critical components comprising the front end of Project X. This program, known as the Project X Injector Experiment (PXIE), is being undertaken as a key component of the larger Project X R&D program. The successful completion of this program will validate the concept for the Project X front end, thereby minimizing a primary technical risk element within Project X. PXIE is currently under construction at Fermilab and will be completed over the period FY12-17. PXIE will include an H* ion source, a CW 2.1-MeV RFQ and two superconductive RF (SRF) cryomodules providing up to 25 MeV energy gain at an average beam current of 1 mA (upgradable to 2 mA). Successful systems testing will also demonstrate the viability of novel front end technologies that are expected find applications beyond Project X.

  19. Calendar year 2003 : annual site enviromental report for Tonopah Test Range, Nevada and Kauai Test Facility, Hawaii.

    SciTech Connect (OSTI)

    Wagner, Katrina; Sanchez, Rebecca V.; Mayeux, Lucie; Koss, Susan I.; Salinas, Stephanie A.

    2004-09-01

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, manages TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2003. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 450.1, Environmental Protection Program (DOE 2003) and DOE Order 231.1 Chg 2., Environment, Safety, and Health Reporting (DOE 1996).

  20. Calendar year 2007 annual site environmental report for Tonopah Test Range, Nevada and Kauai Test Facility, Hawaii,

    SciTech Connect (OSTI)

    Agogino, Karen; Sanchez, Rebecca

    2008-09-30

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation (Sandia), a wholly owned subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE)/National Nuclear Security Administration (NNSA), through the Sandia Site Offi ce (SSO), in Albuquerque, NM, administers the contract and oversees contractor operations at TTR and KTF. Sandia manages and conducts operations at TTR in support of the DOE/NNSA’s Weapons Ordnance Program and has operated the site since 1957. Washington Group International subcontracts to Sandia in administering most of the environmental programs at TTR. Sandia operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2007. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia is responsible only for those environmental program activities related to its operations. The DOE/NNSA/Nevada Site Offi ce (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 450.1, Environmental Protection Program (DOE 2007a) and DOE Manual 231.1-1A, Environment, Safety, and Health Reporting Manual (DOE 2007).

  1. Calendar year 2002 annual site environmental report for Tonopah Test Range, Nevada and Kauai Test Facility, Hawaii.

    SciTech Connect (OSTI)

    Wagner, Katrina; Sanchez, Rebecca V.; Mayeux, Lucie; Koss, Susan I.; Salinas, Stephanie A.

    2003-09-01

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, oversees TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2002. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 5400.1, General Environmental Protection Program (DOE 1990) and DOE Order 231.1, Environment, Safety, and Health Reporting (DOE 1996).

  2. Facilities

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

    2 - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced Nuclear Energy Nuclear

  3. Facilities

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

    3 - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced Nuclear Energy Nuclear

  4. Final deactivation project report on the Integrated Process Demonstration Facility, Building 7602 Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    1997-09-01

    The purpose of this report is to document the condition of the Integrated Process Demonstration Facility (Building 7602) at Oak Ridge National Laboratory (ORNL) after completion of deactivation activities by the High Ranking Facilities Deactivation Project (HRFDP). This report identifies the activities conducted to place the facility in a safe and environmentally sound condition prior to transfer to the U.S. Department of Energy (DOE) Environmental Restoration EM-40 Program. This report provides a history and description of the facility prior to commencing deactivation activities and documents the condition of the building after completion of all deactivation activities. Turnover items, such as the Post-Deactivation Surveillance and Maintenance (S&M) Plan, remaining hazardous and radioactive materials inventory, radiological controls, Safeguards and Security, and supporting documentation provided in the Office of Nuclear Material and Facility Stabilization Program (EM-60) Turnover package are discussed.

  5. Design of the Long-term Waste Management Facility for Historic LLRW Port Hope Project - 13322

    SciTech Connect (OSTI)

    Campbell, Don; Barton, David; Case, Glenn

    2013-07-01

    The Municipality of Port Hope is located on the northern shores of Lake Ontario approximately 100 km east of Toronto, Ontario, Canada. Starting in the 1930's, radium and later uranium processing by Eldorado Gold Mines Limited (subsequently Eldorado Nuclear Limited) (Eldorado) at their refinery in Port Hope resulted in the generation of process residues and wastes that were disposed of indiscriminately throughout the Municipality until about the mid-1950's. These process residues contained radium (Ra- 226), uranium, arsenic and other contaminants. Between 1944 and 1988, Eldorado was a Federal Crown Corporation, and as such, the Canadian Federal Government has assumed responsibility for the clean-up and long-term management of the historic waste produced by Eldorado during this period. The Port Hope Project involves the construction and development of a new long-term waste management facility (LTWMF), and the remediation and transfer of the historic wastes located within the Municipality of Port Hope to the new LTWMF. The new LTWMF will consist of an engineered above-ground containment mound designed to contain and isolate the wastes from the surrounding environment for the next several hundred years. The design of the engineered containment mound consists of a primary and secondary composite base liner system and composite final cover system, made up of both natural materials (e.g., compacted clay, granular materials) and synthetic materials (e.g., geo-synthetic clay liner, geo-membrane, geo-textiles). The engineered containment mound will cover an area of approximately 13 hectares and will contain the estimated 1.2 million cubic metres of waste that will be generated from the remedial activities within Port Hope. The LTWMF will also include infrastructure and support facilities such as access roads, administrative offices, laboratory, equipment and personnel decontamination facilities, waste water treatment plant and other ancillary facilities. Preliminary construction activities for the Port Hope LTWMF commenced in 2012 and are scheduled to continue over the next few years. The first cell of the engineered containment mound is scheduled to be constructed in 2015 with waste placement into the Port Hope LTWMF anticipated over the following seven year period. (authors)

  6. A decade of radiological and shielding experience at the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Bunch, W.L.

    1990-01-01

    The Fast Flux Test Facility (FFTF) was designed to permit irradiation testing of fuels and materials to support the commercial development of liquid-metal-cooled fast reactors (LMRs). A secondary objective was to gain experience in the design, construction, and operation of a relatively large LMR. The radiological experience gained from the operation of the facility as it applies to the area of radiation protection and shielding is presented. Experience from 8 yr of FFTF operation has demonstrated that radiological safety can be achieved in large LMRs. Layout of plant equipment in shielded compartments, careful operational planning, and adherence to procedures have combined to minimize personnel doses at FFTF and the release of radioactivity to the environment. The experience derived form the design, construction, and operation of FFTF should be of inestimable value in supporting future LMR development.

  7. Development of a propulsion system and component test facility for advanced radioisotope powered Mars Hopper platforms

    SciTech Connect (OSTI)

    Robert C. O'Brien; Nathan D. Jerred; Steven D. Howe

    2011-02-01

    Verification and validation of design and modeling activities for radioisotope powered Mars Hopper platforms undertaken at the Center for Space Nuclear Research is essential for proof of concept. Previous research at the center has driven the selection of advanced material combinations; some of which require specialized handling capabilities. The development of a closed and contained test facility to forward this research is discussed within this paper.

  8. Evaluation of the Netherlands International Test Facility for Smart Grids

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

    Evaluation of the Netherlands' International Test Facility for Smart Grids B. Palmintier and A. Pratt National Renewable Energy Laboratory Technical Report NREL/TP-5D00-63638 June 2015 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 This report is available at no cost from the National Renewable Energy Laboratory (NREL) at www.nrel.gov/publications. Contract No.

  9. Active test of head-end facility at Rokkasho reprocessing plant

    SciTech Connect (OSTI)

    Yamamoto, Yoshiro; Tanaka, Satoshi; Kawabe, Shuji; Kamada, Yoshiaki

    2007-07-01

    During the first step, the second and the third step of Active Test (AT) at Rokkasho Reprocessing Plant (RRP), the performances of the Head-end Facility were checked, mainly for shearing and dissolution: shearing force and shearing time were the values as expected and concentration of U and Pu in dissolution solution were the values as expected. And safety requirement for acidity in dissolution solution was satisfied. (authors)

  10. Test Plan: Sludge Treatment Project Corrosion Process Chemistry Follow-on Testing

    SciTech Connect (OSTI)

    Delegard, Calvin H.; Schmidt, Andrew J.; Poloski, Adam P.

    2007-08-17

    This test plan was prepared by the Pacific Northwest National Laboratory (PNNL) under contract with Fluor Hanford (FH). The test plan describes the scope and conditions to be used to perform laboratory-scale testing of the Sludge Treatment Project (STP) hydrothermal treatment of K Basin sludge. The STP, managed for the U. S. Department of Energy (DOE) by FH, was created to design and operate a process to eliminate uranium metal from the sludge prior to packaging for Waste Isolation Pilot Plant (WIPP) by using high temperature liquid water to accelerate the reaction, produce uranium dioxide from the uranium metal, and safely discharge the hydrogen. The proposed testing builds on the approach and laboratory test findings for both K Basin sludge and simulated sludge garnered during prior testing from September 2006 to March 2007. The outlined testing in this plan is designed to yield further understanding of the nature of the chemical reactions, the effects of compositional and process variations and the effectiveness of various strategies to mitigate the observed high shear strength phenomenon observed during the prior testing. These tests are designed to provide process validation and refinement vs. process development and design input. The expected outcome is to establish a level of understanding of the chemistry such that successful operating strategies and parameters can be implemented within the confines of the existing STP corrosion vessel design. In July 2007, the DOE provided direction to FH regarding significant changes to the scope of the overall STP. As a result of the changes, FH directed PNNL to stop work on most of the planned activities covered in this test plan. Therefore, it is unlikely the testing described here will be performed. However, to preserve the test strategy and details developed to date, the test plan has been published.

  11. Recovery Efficiency Test Project Phase 2 activity report, Volume 1

    SciTech Connect (OSTI)

    Overbey, W.K. Jr.; Salamy, S.P.; Locke, C.D.

    1989-02-01

    The purpose of Phase II operations of the Recovery Efficiency Test Project is to enhance the natural production of the well and evaluate the relative improvement as a function of the type of stimulation conducted. Another purpose is to compare the stimulated production performance of the horizontal well with vertical wells in the field. The objectives considered for Phase II operations and plans were: (1) Develop a rationale for a systematic approach to designing stimulations for the well. (2) Conduct a series of stimulations designed to optimize the fluids, injection rates, proppant volumes and general approach to stimulating a horizontal well with similar geologic conditions. (3) Develop and test a method or methods for determining the geometry of stimulation-induced fractures. (4) Conduct tests and analyze the results to determine the efficiency of stimulation operations. The technical approach pursued in developing plans to accomplish three objectives was to: (1) Review the data needs for all objectives and obtain that data first. (2) Identify the operating geologic, geomechanical, and reservoir parameters that need additional clarification or definition. (3) Investigate existing models which could be used to plan or evaluate stimulation on the well and the reservoir. (4) Plan for analysis and verification of models and approaches.

  12. Recovery Efficiency Test Project: Phase 1, Activity report

    SciTech Connect (OSTI)

    Overbey, W.K. Jr.; Carden, R.S.; Kirr, J.N.

    1987-04-01

    The recovery Efficiency Test well project addressed a number of technical issues. The primary objective was to determine the increased efficiency gas recovery of a long horizontal wellbore over that of a vertical wellbore and, more specifically, what improvements can be expected from inducing multiple hydraulic fractures from such a wellbore. BDM corporation located, planned, and drilled a long radius turn horizontal well in the Devonian shale Lower Huron section in Wayne County, West Virginia, demonstrating that state-of-the-art technology is capable of drilling such wells. BDM successfully tested drilling, coring, and logging in a horizontal well using air as the circulating medium; conducted reservoir modeling studies to protect flow rates and reserves in advance of drilling operations; observed two phase flow conditions in the wellbore not observed previously; cored a fracture zone which produced gas; observed that fractures in the core and the wellbore were not systematically spaced (varied from 5 to 68 feet in different parts of the wellbore); observed that highest gas show rates reported by the mud logger corresponded to zone with lowest fracture spacing (five feet) or high fracture frequency. Four and one-half inch casting was successfully installed in the borehole and was equipped to isolate the horizontal section into eight (8) zones for future testing and stimulation operations. 6 refs., 48 figs., 10 tabs.

  13. MHK Projects/QSEIF Grant Sea Testing | Open Energy Information

    Open Energy Info (EERE)

    Organization Tidal Energy Pty Ltd Project Technology *MHK TechnologiesDavidson Hill Venturi DHV Turbine Project Licensing Environmental Monitoring and Mitigation Efforts See...

  14. Categorical Exclusion 4567, MPLE Test Stand Replacement Project

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

    and Guidelines DA 14 - Approval of technical exchange arrangements DA 15 - International umbrella agreements for energy R&D Facility Operations DB 1.2 - Training exercises and...

  15. The intermountain power project commissioning - Subsynchronous torsional interaction tests

    SciTech Connect (OSTI)

    Wu, C.T.; Peterson, K.J. ); Pinko, R.J.; Kankam, M.D.; Baker, D.H. )

    1988-10-01

    Subsyncronous torsional vibration as a result of electrochemical interaction between the HVDC controls and a turbine-generator was first discovered during the commissioning of the Square Butte Project in 1977. The level of interaction between the HVDC controls and the turbine-generator depends on several interacting factors: the characteristic torsional frequencies of the turbine-generator, the bandwidth of the HVDC controls and the relative strength of the connecting ac system. For the Intermountain Power Project (IPP), early analysis of these interacting factors indicated that there exist definite potential for subsynchronous oscillation to occur. The calculated torsional frequencies of the IPP units showed that the first mode frequency is 14.0 Hz and is within the typical bandwidth of an HVDC control which is between 10-20 Hz. The HVDC controls, therefore, can influence the torsional stability of the IPP units. Further, the IPP turbine-generators are required to operate isolated on the HVDC rectifier terminal, with no other interconnecting ac network. This ''radial'' mode of operation will result in maximum interaction between the converter station and the IPP units. It became obvious that special measure must be implemented in the design of the IPP HVDC control system to modify its typical characteristics to avoid the occurrence of the subsynchronous oscillation. This paper presents the results of the subsynchronous torsional interaction (SSTI) tests that were performed during the commissioning of the IPP Unit 1 and the HVDC Transmission system.

  16. An Experimental Test Facility to Support Development of the Fluoride Salt Cooled High Temperature Reactor

    SciTech Connect (OSTI)

    Yoder Jr, Graydon L; Aaron, Adam M; Cunningham, Richard Burns; Fugate, David L; Holcomb, David Eugene; Kisner, Roger A; Peretz, Fred J; Robb, Kevin R; Wilgen, John B; Wilson, Dane F

    2014-01-01

    The need for high-temperature (greater than 600 C) energy exchange and delivery systems is significantly increasing as the world strives to improve energy efficiency and develop alternatives to petroleum-based fuels. Liquid fluoride salts are one of the few energy transport fluids that have the capability of operating at high temperatures in combination with low system pressures. The Fluoride Salt-Cooled High-Temperature Reactor design uses fluoride salt to remove core heat and interface with a power conversion system. Although a significant amount of experimentation has been performed with these salts, specific aspects of this reactor concept will require experimental confirmation during the development process. The experimental facility described here has been constructed to support the development of the Fluoride Salt Cooled High Temperature Reactor concept. The facility is capable of operating at up to 700 C and incorporates a centrifugal pump to circulate FLiNaK salt through a removable test section. A unique inductive heating technique is used to apply heat to the test section, allowing heat transfer testing to be performed. An air-cooled heat exchanger removes added heat. Supporting loop infrastructure includes a pressure control system; trace heating system; and a complement of instrumentation to measure salt flow, temperatures, and pressures around the loop. The initial experiment is aimed at measuring fluoride salt heat transfer inside a heated pebble bed similar to that used for the core of the pebble bed advanced high-temperature reactor. This document describes the details of the loop design, auxiliary systems used to support the facility, the inductive heating system, and facility capabilities.

  17. REVIEW OF FAST FLUX TEST FACILITY (FFTF) FUEL EXPERIMENTS FOR STORAGE IN INTERIM STORAGE CASKS (ISC)

    SciTech Connect (OSTI)

    CHASTAIN, S.A.

    2005-10-24

    Appendix H, Section H.3.3.10.11 of the Final Safety Analysis Report (FSAR), provides the limits to be observed for fueled components authorized for storage in the Fast Flux Test Facility (FFTF) spent fuel storage system. Currently, the authorization basis allows standard driver fuel assemblies (DFA), as described in the FSAR Chapter 17, Section 17.5.3.1, to be stored provided decay power per assembly is {le} 250 watts, post-irradiation time is four years minimum, average assembly burn-up is 150,000 MWD/MTHM maximum and the pre-irradiation enrichment is 29.3% maximum (per H.3.3.10.11). In addition, driver evaluation (DE), core characterizer assemblies (CCA), and run-to-cladding-breach (RTCB) assemblies are included based on their similarities to a standard DFA. Ident-69 pin containers with fuel pins from these DFAs can also be stored. Section H.3.3.10.11 states that fuel types outside the specification criteria above will be addressed on a case-by-case basis. There are many different types of fuel and blanket experiments that were irradiated in the FFTF which now require offload to the spent fuel storage system. Two reviews were completed for a portion of these special type fuel components to determine if placement into the Core Component Container (CCC)/Interim Storage Cask (ISC) would require any special considerations or changes to the authorization basis. Project mission priorities coupled with availability of resources and analysts prevented these evaluations from being completed as a single effort. Areas of review have included radiological accident release consequences, radiological shielding adequacy, criticality safety, thermal limits, confinement, and stress. The results of these reviews are available in WHC-SD-FF-RPT-005, Rev. 0 and 1, ''Review of FFTF Fuel Experiments for Storage at ISA'', (Reference I), which subsequently allowed a large portion of these components to be included in the authorization basis (Table H.3.3-21). The report also identified additional components and actions in Section 3.0 and Table 3 that require further evaluation. The purpose of this report is to evaluate another portion of the remaining inventory (i.e., delayed neutron signal fuel, blanket assemblies, highly enriched assemblies, newly loaded Ident-69 pin containers, and returned fuel) to ensure it can be safely off loaded to the FFTF spent fuel storage system.

  18. Advanced Test Reactor National Scientific User Facility (ATR NSUF) Monthly Report November 2014

    SciTech Connect (OSTI)

    Soelberg, Renae

    2014-11-01

    Advanced Test Reactor National Scientific User Facility (ATR NSUF) Monthly Report November 2014 Highlights Rory Kennedy and Sarah Robertson attended the American Nuclear Society Winter Meeting and Nuclear Technology Expo in Anaheim, California, Nov. 10-13. ATR NSUF exhibited at the technology expo where hundreds of meeting participants had an opportunity to learn more about ATR NSUF. Dr. Kennedy briefed the Nuclear Engineering Department Heads Organization (NEDHO) on the workings of the ATR NSUF. • Rory Kennedy, James Cole and Dan Ogden participated in a reactor instrumentation discussion with Jean-Francois Villard and Christopher Destouches of CEA and several members of the INL staff. • ATR NSUF received approval from the NE-20 office to start planning the annual Users Meeting. The meeting will be held at INL, June 22-25. • Mike Worley, director of the Office of Innovative Nuclear Research (NE-42), visited INL Nov. 4-5. Milestones Completed • Recommendations for the Summer Rapid Turnaround Experiment awards were submitted to DOE-HQ Nov. 12 (Level 2 milestone due Nov. 30). Major Accomplishments/Activities • The University of California, Santa Barbara 2 experiment was unloaded from the GE-2000 at HFEF. The experiment specimen packs will be removed and shipped to ORNL for PIE. • The Terrani experiment, one of three FY 2014 new awards, was completed utilizing the Advanced Photon Source MRCAT beamline. The experiment investigated the chemical state of Ag and Pd in SiC shell of irradiated TRISO particles via X-ray Absorption Fine Structure (XAFS) spectroscopy. Upcoming Meetings/Events • The ATR NSUF program review meeting will be held Dec. 9-10 at L’Enfant Plaza. In addition to NSUF staff and users, NE-4, NE-5 and NE-7 representatives will attend the meeting. Awarded Research Projects Boise State University Rapid Turnaround Experiments (14-485 and 14-486) Nanoindentation and TEM work on the T91, HT9, HCM12A and 9Cr ODS specimens has been completed at CAES by Boise State PI Janelle Wharry and Cory Dolph. PI Corey Dolph returned in early November to complete their research by performing nanoindentation on unirradiated specimens that will be used as a baseline for their research.

  19. Structural analysis of fuel assembly clads for the Upgraded Transient Reactor Test Facility (TREAT Upgrade)

    SciTech Connect (OSTI)

    Ewing, T.F.; Wu, T.S.

    1986-01-01

    The Upgraded Transient Reactor Test Facility (TREAT Upgrade) is designed to test full-length, pre-irradiated fuel pins of the type used in large LMFBRs under accident conditions, such as severe transient overpower and loss-of-coolant accidents. In TREAT Upgrade, the central core region is to contain new fuel assemblies of higher fissile loadings to maximize the energy deposition to the test fuel. These fuel assemblies must withstand normal peak clad temperatures of 850/sup 0/C for hundreds of test transients. Due to high temperatures and gradients predicted in the clad, creep and plastic strain effects are significant, and the clad structural behavior cannot be analyzed by conventional linear techniques. Instead, the detailed elastic-plastic-creep behavior must be followed along the time-dependent load history. This paper presents details of the structural evaluations of the conceptual TREAT Upgrade fuel assembly clads.

  20. Facilities | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Dual Axis Radiographic Hydrodynamic Test (DARHT) Facility, Los Alamos National ... Contained Firing Facility Dual Axis Radiographic Hydrodynamic Test Facility High ...

  1. Necessity and Requirements of a Collaborative Effort to Develop a Large Wind Turbine Blade Test Facility in North America

    SciTech Connect (OSTI)

    Cotrell, J.; Musial, W.; Hughes, S.

    2006-05-01

    The wind power industry in North America has an immediate need for larger blade test facilities to ensure the survival of the industry. Blade testing is necessary to meet certification and investor requirements and is critical to achieving the reliability and blade life needed for the wind turbine industry to succeed. The U.S. Department of Energy's (DOE's) Wind Program is exploring options for collaborating with government, private, or academic entities in a partnership to build larger blade test facilities in North America capable of testing blades up to at least 70 m in length. The National Renewable Energy Laboratory (NREL) prepared this report for DOE to describe the immediate need to pursue larger blade test facilities in North America, categorize the numerous prospective partners for a North American collaboration, and document the requirements for a North American test facility.

  2. Building State-of-the-Art Wind Technology Testing Facilities (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2012-03-01

    The new Wind Technology Test Center is the only facility in the nation capable of testing wind turbine blades up to 90 meters in length. A critical factor to wind turbine design and development is the ability to test new designs, components, and materials. In addition, wind turbine blade manufacturers are required to test their blades as part of the turbine certification process. The National Renewable Energy Laboratory (NREL) partnered with the U.S. Department of Energy (DOE) Wind Program and the Massachusetts Clean Energy Center (MassCEC) to design, construct, and operate the Wind Technology Center (WTTC) in Boston, Massachusetts. The WTTC offers a full suite of certification tests for turbine blades up to 90 meters in length. NREL worked closely with MTS Systems Corporation to develop the novel large-scale test systems needed to conduct the static and fatigue tests required for certification. Static tests pull wind turbine blades horizontally and vertically to measure blade deflection and strains. Fatigue tests cycle the blades millions of times to simulate what a blade goes through in its lifetime on a wind turbine. For static testing, the WTTC is equipped with servo-hydraulic winches and cylinders that are connected to the blade through cables to apply up to an 84-mega Newton meter maximum static bending moment. For fatigue testing, MTS developed a commercial version of NREL's patented resonant excitation system with hydraulic cylinders that actuate linear moving masses on the blade at one or more locations. This system applies up to a 21-meter tip-to-tip fatigue test tip displacement to generate 20-plus years of cyclic field loads in a matter of months. NREL also developed and supplied the WTTC with an advanced data acquisition system capable of measuring and recording hundreds of data channels at very fast sampling rates while communicating with test control systems.

  3. AP1000 Design Basis Event Simulation at the APEX-1000 Test Facility

    SciTech Connect (OSTI)

    Wright, Richard F.; Groome, John

    2004-07-01

    The AP1000 is a 1000 MWe advanced nuclear power plant that uses passive safety features to enhance plant safety and to provide significant and measurable improvements in plant simplification, reliability, investment protection and plant costs. The AP1000 relies heavily on the 600 MWe AP600 which received design certification in 1999. A critical part of the AP600 design certification process involved the testing of the passive safety systems. A one-fourth height, one-fourth pressure test facility, APEX-600, was constructed at the Oregon State University to study design basis events, and to provide a body of data to be used to validate the computer models used to analyze the AP600. This facility was extensively modified to reflect the design changes for AP1000 including higher power in the electrically heated rods representing the reactor core, and changes in the size of the pressurizer, core makeup tanks and automatic depressurization system. Several design basis events are being simulated at APEX-1000 including a double-ended direct vessel injection (DEDVI) line break and a 2-inch cold leg break. These tests show that the core remains covered with ample margin until gravity injection is established regardless of the initiating event. The tests also show that liquid entrainment from the upper plenum which is proportional to the reactor power does not impact the ability of the passive core cooling system to keep the core covered. (authors)

  4. Search for underground openings for in situ test facilities in crystalline rock

    SciTech Connect (OSTI)

    Wollenberg, H.A.; Strisower, B.; Corrigan, D.J.; Graf, A.N.; O'Brien, M.T.; Pratt, H.; Board, M.; Hustrulid, W.

    1980-01-01

    With a few exceptions, crystalline rocks in this study were limited to plutonic rocks and medium to high-grade metamorphic rocks. Nearly 1700 underground mines, possibly occurring in crystalline rock, were initially identified. Application of criteria resulted in the identification of 60 potential sites. Within this number, 26 mines and 4 civil works were identified as having potential in that they fulfilled the criteria. Thirty other mines may have similar potential. Most of the mines identified are near the contact between a pluton and older sedimentary, volcanic and metamorphic rocks. However, some mines and the civil works are well within plutonic or metamorphic rock masses. Civil works, notably underground galleries associated with pumped storage hydroelectric facilities, are generally located in tectonically stable regions, in relatively homogeneous crystalline rock bodies. A program is recommended which would identify one or more sites where a concordance exists between geologic setting, company amenability, accessibility and facilities to conduct in situ tests in crystalline rock.

  5. A modified heat leak test facility employing a closed-cycle helium refrigerator

    SciTech Connect (OSTI)

    Boroski, W.N.

    1996-01-01

    A Heat Leak Test Facility (HLTF) has been in use at Fermilab for many years. The apparatus has successfully measured the thermal performance of a variety of cryostat components under simulated operating conditions. While an effective tool in the cryostat design process, the HLTF has several limitations. Temperatures are normally fixed at cryogen boiling points and run times are limited to cryogen inventory. Moreover, close personnel attention is required to maintain system inventories and sustain system equilibrium. To provide longer measurement periods without perturbation and to minimize personnel interaction, a new heat leak measurement facility (HLTF-2) has been designed that incorporates a closed-cycle helium refrigerator. The two-stage refrigerator provides cooling to the various temperature stations of the HLTF while eliminating the need for cryogens. Eliminating cryogen inventories has resulted in a reduction of the amount of direct personnel attention required.

  6. Feasibility of establishing and operating a generic oil shale test facility

    SciTech Connect (OSTI)

    Not Available

    1986-12-01

    The December 19, 1985, Conference Report on House Joint Resolution 465, Further continuing appropriations for Fiscal Year 1986, included instruction to DOE to conduct a feasibility study for a generic oil shale test facility. The study was completed, as directed, and its findings are documented in this report. To determine the feasibility of establishing and operating such a facility, the following approach was used: examine the nature of the resource, and establish and basic functions associated with recovery of the resource; review the history of oil shale development to help put the present discussion in perspective; describe a typical oil shale process; define the relationship between each oil shale system component (mining, retorting, upgrading, environmental) and its cost. Analyze how research could reduce costs; and determine the scope of potential research for each oil shale system component.

  7. The Role of the Federal Project Director: Lessons from the National Ignition Facility

    Broader source: Energy.gov [DOE]

    The National Ignition Facility (NIF) Facility is home of the world’s largest laser.  With 192 laser beams that can deliver more than 60 times the energy of any previous laser system, NIF represents...

  8. Definition of Capabilities Needed for a Single Event Effects Test Facility

    SciTech Connect (OSTI)

    Riemer, Bernie; Gallmeier, Franz X.

    2014-12-01

    The Federal Aviation Administration (FAA) is contemplating new regulations mandating testing of the vulnerability of flight-critical avionics to single event effects (SEE). A limited number of high-energy neutron test facilities currently serve the SEE industrial and institutional research community. The FAA recognizes that existing facilities have insufficient test capacity to meet new demand from such mandates; it desires more flexible irradiation capabilities to test complete, large systems and would like capabilities to address greater concerns for thermal neutrons. For this reason, the FAA funded this study by Spallation Neutron Source (SNS) staff with the ultimate aim of developing options for SEE test facilities using high-energy neutrons at the SNS complex. After an investigation of current SEE test practices and assessment of future testing requirements, three concepts were identified covering a range of test functionality, neutron flux levels, and fidelity to the atmospheric neutron spectrum. The costs and times required to complete each facility were also estimated. SEE testing is generally performed by accelerating the event rate to a point where the effects are still dominated by single events and double event causes of failures are negligible. In practice, acceleration factors of as high as 106 are applicable for component testing, whereas for systems testing acceleration factors of 104 seem to be the upper limit. It is strongly desirable that the irradiation facility be tunable over a large range of high-energy neutron fluxes of 102 - 104 n/cm²/s for systems testing and from 104 - 107 n/cm²/s for components testing. The most capable, most flexible, and highest-test-capacity option is a new stand-alone target station named the High-Energy neutron Test Station (HETS). It is also the most expensive option, with a cost to complete of approximately $100 million. Dual test enclosures would allow for simultaneous testing activity effectively doubling overall test capacity per HETS operating hour. Using about 1 kilowatt (kW) of proton power extracted from the accelerator before injection in the accumulator ring, its operation would be unnoticeable by neutron scattering users at the SNS target station. The H beam laser stripping technique would allow for control of beam power on the HETS target independent from power delivered to the SNS. Large systems with frontal areas of up to 1 x 2 m² could be accommodated with integral high-energy flux values (above 10 megaelectron-volt, or MeV) to at most 104 n/cm²/s; components could also be tested with flux levels to at most 107 n/cm²/s on beam sizes of up to 0.2 x 0.2 m². Selectable moderating material and neutron filters would allow tailoring of the neutron spectrum to user demands; charged particle deflectors could be switched to allow or deflect protons, pions, and muons. It is estimated that HETS would take 5 years to complete after award of contract, including engineering design and construction. Commissioning would take at least another 6 months. Interference with SNS principal operations was not considered in the construction time estimate; connection of the proton transport line and tunnel from the accelerator high energy beam transport (HEBT) and construction around existing site utilities would require careful planning and coordination with beam operations at the SNS. A high-energy (HE) neutron test facility using an available beam line on the SNS target station is a technically and financially attractive option. Inspired by the new ChipIR instrument on the ISIS TS 2 spallation source in the UK, a similar facility could be placed on an unused beam line in the SNS instrument hall [e.g., on beam line 8 (both A and B channels would be needed) or on beam line 10]. The performance would approach that of an HETS (~80%), but it would be operationally more limited, with only a single user at a time. Space is more limited, so the maximum system size would be about half of that in an HETS. Flexibility to tailor the spectrum would be somewhat more limited. While this concept was not as fully developed and characterized, preliminary work indicates very high HE flux levels should be possible, with ample thermal neutrons as well. Flux control would be more difficult than at HETS because proton power on target be whatever the SNS was operating at for neutron scattering. Neutron attenuation devices would have to be employed with as-yet undetermined control resolution. However, no new buildings would be needed, and the necessary utilities are already present in the SNS Experiment Hall. The estimated cost for a beam line option is around $15 million; the time to complete would be 3 years after award of contract, plus at least 6 months for commissioning. Interference of construction activities with SNS operations should be negligible. This option would require negotiation with the Department of Energy Basic Energy Sciences (BES) office -- the primary stakeholder of SNS -- for an application outside the usual scope of neutron scattering sciences. Furthermore, these presently open beam lines are highly desirable locations for proposed neutron scattering instruments and obtaining one of them for an SEE test facility will come only with persuasive and timely arguments to SNS leadership and the DOE BES. The third option is a tunnel extension/target cave facility providing the most basic system-level irradiation capability with minimal flexibility. Again not as well developed a concept as HETS, it would use a laser-stripping technique like an HETS, redirecting protons to a tunnel similar to the initial HETS proton transport tunnel. Indeed, this concept is intended to be upgradable to a full HETS facility. Only a small fraction of a watt of proton power would be used in this basic configuration, though. An uncooled target and primitive shielding arrangement would provide beam on modestly sized systems that must be placed in close proximity to the target. The neutron fluence would be less uniform over the system than with the HETS or the beam line option. A data acquisition room and support area would be located on the ground level; access to the target cave would be via elevator and/or stairway. As a result of the required excavation, new tunnel construction, shielding, data acquisition building, utilities, and other items, the estimated cost is $30 million. The time to complete is expected be more than 3 years; here again construction interference with SNS operations has not been accounted for, but it could have a significant impact.

  9. Fort Irwin integrated resource assessment. Volume 3: Sitewide Energy Project identification for buildings and facilities

    SciTech Connect (OSTI)

    Keller, J.M.; Dittmer, A.L.; Elliott, D.B.; McMordie, K.L.; Richman, E.E.; Stucky, D.J.; Wahlstrom, R.R.; Hadley, D.L.

    1995-02-01

    The U.S. Army Forces Command (FORSCOM) has tasked the U.S. Department of Energy (DOE) Federal Energy Management Program (FEMP), supported by the Pacific Northwest Laboratory, to identify, evaluate, and assist in acquiring all cost-effective energy projects at Fort Irwin. This is part of a model program that PNL is designing to support energy-use decisions in the federal sector. This report provides the results of the fossil fuel and electric energy resource opportunity (ERO) assessments performed by PNL at the FORSCOM Fort Irwin facility located near Barstow, California. It is a companion report to Volume 1, Executive Summary, and Volume 2, Baseline Detail. The results of the analyses of EROs are presented in 16 common energy end-use categories (e.g., boilers and furnaces, service hot water, and building lighting). A narrative description of each ERO is provided, along with a table detailing information on the installed cost, energy and dollar savings; impacts on operations and maintenance (O&M); and, when applicable, a discussion of energy supply and demand, energy security, and environmental issues. A description of the evaluation methodologies and technical and cost assumptions is also provided for each ERO. Summary tables present the cost-effectiveness of energy end-use equipment before and after the implementation of each ERO and present the results of the life-cycle cost (LCC) analysis indicating the net present valve (NPV) and savings-to-investment ratio (SIR) of each ERO.

  10. Measurement of fenestration net energy performance: Considerations leading to development of a Mobile Window Thermal Test (MoWitt) facility

    SciTech Connect (OSTI)

    Klems, J.H.

    1988-08-01

    The authors present a detailed consideration of the energy flows entering a building space and the effect of random measurement errors on determining fenestration performance. Estimates of error magnitudes are made for a passive test cell; they show that a more accurate test facility is needed for reliable measurements on fenestration systems with thermal resistance 2-10 times that of single glazing or with shading coefficients less than 0.7. A test facility of this type, built at Lawrence Berkeley Laboratory, is described. The effect of random errors in this facility is discussed and computer calculations of its performance are presented. The discussion shows that, for any measurement facility, random errors are most serious in nighttime measurements, and systematic errors are most important in daytime measurements. It is concluded that, for this facility, errors from both sources should be small.

  11. User Facilities | U.S. DOE Office of Science (SC)

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

    Facilities High Energy Physics (HEP) HEP Home About Research Facilities User Facilities Fermilab Accelerator Complex Facility for Advanced Accelerator Experimental Tests (FACET) Accelerator Test Facility (ATF) Facility Ops Projects, Missions, and Status Science Highlights Benefits of HEP Funding Opportunities Advisory Committees Community Resources Contact Information High Energy Physics U.S. Department of Energy SC-25/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301)

  12. Mixed and Low-Level Treatment Facility Project. Appendix B, Waste stream engineering files, Part 1, Mixed waste streams

    SciTech Connect (OSTI)

    Not Available

    1992-04-01

    This appendix contains the mixed and low-level waste engineering design files (EDFS) documenting each low-level and mixed waste stream investigated during preengineering studies for Mixed and Low-Level Waste Treatment Facility Project. The EDFs provide background information on mixed and low-level waste generated at the Idaho National Engineering Laboratory. They identify, characterize, and provide treatment strategies for the waste streams. Mixed waste is waste containing both radioactive and hazardous components as defined by the Atomic Energy Act and the Resource Conservation and Recovery Act, respectively. Low-level waste is waste that contains radioactivity and is not classified as high-level waste, transuranic waste, spent nuclear fuel, or 11e(2) byproduct material as defined by DOE 5820.2A. Test specimens of fissionable material irradiated for research and development only, and not for the production of power or plutonium, may be classified as low-level waste, provided the concentration of transuranic is less than 100 nCi/g. This appendix is a tool that clarifies presentation format for the EDFS. The EDFs contain waste stream characterization data and potential treatment strategies that will facilitate system tradeoff studies and conceptual design development. A total of 43 mixed waste and 55 low-level waste EDFs are provided.

  13. A West Valley Demonstration Project Milestone - Achieving Certification to Ship Waste to the Nevada Test Site

    SciTech Connect (OSTI)

    Jackson, J. P.; Pastor, R. S.

    2002-02-28

    The West Valley Demonstration Project (WVDP) has successfully pretreated and vitrified nearly all of the 600,000 gallons of liquid high-level radioactive waste that was generated at the site of the only commercial nuclear fuel reprocessing plant to have operated in the United States. Low-level waste (LLW) generated during the course of the cleanup effort now requires disposal. Currently the WVDP only ships Class A LLW for off-site disposal. It has been shipping Class A wastes to Envirocare of Utah, Inc. since 1997. However, the WVDP may also have a future need to ship Class B and Class C waste, which Envirocare is not currently authorized to accept. The Nevada Test Site (NTS), a U.S. Department of Energy (DOE) facility, can accept all three waste classifications. The WVDP set a goal to receive certification to begin shipping Class A wastes to NTS by 2001. Formal certification/approval was granted by the DOE Nevada Operations Office on July 12, 2001. This paper discusses how the WVDP contractor, West Valley Nuclear Services Company (WVNSCO), completed the activities required to achieve NTS certification in 2001 to ship waste to its facility. The information and lessons learned provided are significant because the WVDP is the only new generator receiving certification based on an NTS audit in January 2001 that resulted in no findings and only two observations--a rating that is unparalleled in the DOE Complex.

  14. SLUDGE TREATMENT PROJECT PHASE 1 SLUDGE STORAGE OPTIONS ASSESSMENT OF T PLANT VERSUS ALTERNATE STORAGE FACILITY

    SciTech Connect (OSTI)

    RUTHERFORD WW; GEUTHER WJ; STRANKMAN MR; CONRAD EA; RHOADARMER DD; BLACK DM; POTTMEYER JA

    2009-04-29

    The CH2M HILL Plateau Remediation Company (CHPRC) has recommended to the U.S. Department of Energy (DOE) a two phase approach for removal and storage (Phase 1) and treatment and packaging for offsite shipment (Phase 2) of the sludge currently stored within the 105-K West Basin. This two phased strategy enables early removal of sludge from the 105-K West Basin by 2015, allowing remediation of historical unplanned releases of waste and closure of the 100-K Area. In Phase 1, the sludge currently stored in the Engineered Containers and Settler Tanks within the 105-K West Basin will be transferred into sludge transport and storage containers (STSCs). The STSCs will be transported to an interim storage facility. In Phase 2, sludge will be processed (treated) to meet shipping and disposal requirements and the sludge will be packaged for final disposal at a geologic repository. The purpose of this study is to evaluate two alternatives for interim Phase 1 storage of K Basin sludge. The cost, schedule, and risks for sludge storage at a newly-constructed Alternate Storage Facility (ASF) are compared to those at T Plant, which has been used previously for sludge storage. Based on the results of the assessment, T Plant is recommended for Phase 1 interim storage of sludge. Key elements that support this recommendation are the following: (1) T Plant has a proven process for storing sludge; (2) T Plant storage can be implemented at a lower incremental cost than the ASF; and (3) T Plant storage has a more favorable schedule profile, which provides more float, than the ASF. Underpinning the recommendation of T Plant for sludge storage is the assumption that T Plant has a durable, extended mission independent of the K Basin sludge interim storage mission. If this assumption cannot be validated and the operating costs of T Plant are borne by the Sludge Treatment Project, the conclusions and recommendations of this study would change. The following decision-making strategy, which is dependent on the confidence that DOE has in the long term mission for T Plant, is proposed: (1) If the confidence level in a durable, extended T Plant mission independent of sludge storage is high, then the Sludge Treatment Project (STP) would continue to implement the path forward previously described in the Alternatives Report (HNF-39744). Risks to the sludge project can be minimized through the establishment of an Interface Control Document (ICD) defining agreed upon responsibilities for both the STP and T Plant Operations regarding the transfer and storage of sludge and ensuring that the T Plant upgrade and operational schedule is well integrated with the sludge storage activities. (2) If the confidence level in a durable, extended T Plant mission independent of sludge storage is uncertain, then the ASF conceptual design should be pursued on a parallel path with preparation of T Plant for sludge storage until those uncertainties are resolved. (3) Finally, if the confidence level in a durable, extended T Plant mission independent of sludge storage is low, then the ASF design should be selected to provide independence from the T Plant mission risk.

  15. Material Open Test Assembly Specimen Retrieval from Hanford's Shielded Material Facility

    SciTech Connect (OSTI)

    Valdez, Patrick LJ; Rinker, Michael W.

    2009-06-14

    Hanford’s 324 Building, the Shielded Material Facility (SMF), was developed to provide containment for research and fabrication development studies on highly radioactive metallic and ceramic nuclear reactor fuels and structural materials. Between 1983 and 1992, the SMF was used in support of the Department of Energy (DOE)-funded Fast Flux Test Facility (FFTF) Materials Open Test Assembly (MOTA) program. In this program, metallurgical specimens were irradiated in FFTF and then sent to SMF for processing and storage in two cabinets. This effort was abruptly ended in early 1990s due to programmatic shifts within the DOE, leaving many specimens unexamined. In recent years, these specimens have become of high value to new DOE programs. Pacific Northwest National Laboratory (PNNL) was tasked with retrieving specimens from one of the cabinets in support of fuel clad and duct development for the Advanced Fuel Cycle Initiative. Cesium contamination of the cell and failure of the overhead crane system utilized for opening the cabinets prevented PNNL from using the built-in hot cell equipment to gain access to the cabinets. PNNL designed and tested a lifting device to fit through a standard 10 inch diameter mechanical manipulator port in the SMF South Cell wall. The tool was successfully deployed in June 2008 with the support of Washington Closure Hanford.

  16. Evaluation of flow oscillation during long-term cooling experiments in the APEX integral test facility

    SciTech Connect (OSTI)

    Bessette, D.; Marzo, M. di

    1996-12-31

    The Westinghouse Electric Corporation has developed a new, advanced light water reactor, the AP600, and has submitted the design for U.S. Nuclear Regulatory Commission certification. Westinghouse conducted supporting testing programs to provide experimental data to validate its computer codes used to analyze the performance of the AP600 design. One of these facilities was a reduced-pressure, reduced-height (1:4) integral system test facility located at Oregon State University-the Advanced Plant Experiment (APEX). The governing objective of the testing program was to evaluate system depressurization, transition to in-containment refueling water storage tank (IRWST) injection, and long-term cooling. A key feature in the long-term cooling data from some of the APEX experiments is flow oscillations that begin upon return to saturated conditions at the core exit. In this paper, the mechanism for these oscillations is explained, their relevance to the AP600 is discussed, and conclusions about their safety significance are drawn.

  17. Power Hardware-in-the-Loop (PHIL) Testing Facility for Distributed Energy Storage (Poster)

    SciTech Connect (OSTI)

    Neubauer.J.; Lundstrom, B.; Simpson, M.; Pratt, A.

    2014-06-01

    The growing deployment of distributed, variable generation and evolving end-user load profiles presents a unique set of challenges to grid operators responsible for providing reliable and high quality electrical service. Mass deployment of distributed energy storage systems (DESS) has the potential to solve many of the associated integration issues while offering reliability and energy security benefits other solutions cannot. However, tools to develop, optimize, and validate DESS control strategies and hardware are in short supply. To fill this gap, NREL has constructed a power hardware-in-the-loop (PHIL) test facility that connects DESS, grid simulator, and load bank hardware to a distribution feeder simulation.

  18. AVTA Federal Fleet PEV Readiness Data Logging and Characterization Study for NASA White Sands Test Facility

    SciTech Connect (OSTI)

    Stephen Schey; Jim Francfort

    2014-10-01

    This report focuses on the NASA White Sands Test Facility (WSTF) fleet to identify daily operational characteristics of select vehicles and report findings on vehicle and mission characterizations to support the successful introduction of plug-in electric vehicles (PEVs) into the agencies’ fleets. Individual observations of these selected vehicles provide the basis for recommendations related to electric vehicle adoption and whether a battery electric vehicle (BEV) or plug-in hybrid electric vehicle (PHEV) (collectively plug-in electric vehicles, or PEVs) can fulfill the mission requirements.

  19. Automated Testing of Supercomputers ANL/ALCF/TM-13/3 Argonne Leadership Computing Facility

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

    Automated Testing of Supercomputers ANL/ALCF/TM-13/3 Argonne Leadership Computing Facility Availability of This Report This report is available, at no cost, at http://www.osti.gov/bridge. It is also available on paper to the U.S. Department of Energy and its contractors, for a processing fee, from: U.S. Department of Energy Offce of Scientifc and Technical Information P.O. Box 62 Oak Ridge, TN 37831-0062 phone (865) 576-8401 fax (865) 576-5728 reports@adonis.osti.gov Disclaimer This report was

  20. Recovery efficiency test project, Phase 2 activity report

    SciTech Connect (OSTI)

    Overbey, W.K. Jr.; Salamy, S.P.; Locke, C.D.

    1989-02-01

    The Recovery Efficiency Test well project addressed a number of technical issues. The primary objective was to determine the increased efficiency of gas recovery of a long horizontal wellbore over that of a vertical wellbore and, more specifically, what improvements can be expected from inducing multiple hydraulic fractures from such a wellbore. This volume contains appendices for: (1) supporting material and procedures for data frac'' stimulation of zone 6 using nitrogen and nitrogen foam; (2) supporting material and procedures for stimulation no. 1 nitrogen gas frac on zone no. 1; (3) supporting material and procedures for stimulation no. 2 in zone no. 1 using liquid CO{sub 2}; (4) supporting material and procedures for frac no. 3 on zone no.1 using nitrogen foam and proppant; (5) supporting material and procedures for stimulation no. 4 in zones 2--3 and 4 using nitrogen foam and proppant; (6) supporting materials and procedures for stimulation no. 5 in zones 5 and 8; and (7) fracture diagnostics reports and supporting materials.

  1. Dynamic effect of sodium-water reaction in fast flux test facility power addition sodium pipes

    SciTech Connect (OSTI)

    Huang, S.N.; Anderson, M.J.

    1990-03-01

    The Fast Flux Facility (FFTF) is a demonstration and test facility of the sodium-cooled fast breeder reactor. A power addition'' to the facility is being considered to convert some of the dumped, unused heat into electricity generation. Components and piping systems to be added are sodium-water steam generators, sodium loop extensions from existing dump heat exchangers to sodium-water steam generators, and conventional water/steam loops. The sodium loops can be subjected to the dynamic loadings of pressure pulses that are caused by postulated sodium leaks and subsequent sodium-water reaction in the steam generator. The existing FFTF secondary pipes and the new power addition sodium loops were evaluated for exposure to the dynamic effect of the sodium-water reaction. Elastic and simplified inelastic dynamic analyses were used in this feasibility study. The results indicate that both the maximum strain and strain range are within the allowable limits. Several cycles of the sodium-water reaction can be sustained by the sodium pipes that are supported by ordinary pipe supports and seismic restraints. Expensive axial pipe restraints to withstand the sodium-water reaction loads are not needed, because the pressure-pulse-induced alternating bending stresses act as secondary stresses and the pressure pulse dynamic effect is a deformation-controlled quantity and is self-limiting. 14 refs., 7 figs., 3 tabs.

  2. Evaluation of Dynamic Behavior of Pile Foundations for Interim Storage Facilities Through Geotechnical Centrifuge Tests

    SciTech Connect (OSTI)

    Shizuo Tsurumaki; Hiroyuki Watanabe; Akira Tateishi; Kenichi Horikoshi; Shunichi Suzuki

    2002-07-01

    In Japan, there is a possibility that interim storage facilities for recycled nuclear fuel resources may be constructed on quaternary layers, rather than on hard rock. In such a case, the storage facilities need to be supported by pile foundations or spread foundations to meet the required safety level. The authors have conducted a series of experimental studies on the dynamic behavior of storage facilities supported by pile foundations. A centrifuge modeling technique was used to satisfy the required similitude between the reduced size model and the prototype. The centrifuge allows a high confining stress level equivalent to prototype deep soils to be generated (which is considered necessary for examining complex pile-soil interactions) as the soil strength and the deformation are highly dependent on the confining stress. The soil conditions were set at as experimental variables, and the results are compared. Since 2000, the Nuclear Power Engineering Corporation (NUPEC) has been conducting these research tests under the auspices on the Ministry of Economy, Trade and Industry of Japan. (authors)

  3. Evaluation of the Initial Isothermal Physics Measurements at the Fast Flux Test Facility, a Prototypic Liquid Metal Fast Breeder Reactor

    SciTech Connect (OSTI)

    John D. Bess

    2010-03-01

    The Fast Flux Test Facility (FFTF) was a 400-MWt, sodium-cooled, low-pressure, high-temperature, fast-neutron flux, nuclear fission reactor plant designed for the irradiation testing of nuclear reactor fuels and materials for the development of liquid metal fast breeder reactors (LMFBRs). The FFTF was fueled with plutonium-uranium mixed oxide (MOX) and reflected by Inconel-600. Westinghouse Hanford Company operated the FFTF as part of the Hanford Engineering Development Laboratory (HEDL) for the U.S. Department of Energy on the Hanford Site near Richland, Washington. Although the FFTF was a testing facility not specifically designed to breed fuel or produce electricity, it did provide valuable information for LMFBR projects and base technology programs in the areas of plant system and component design, component fabrication, prototype testing, and site construction. The major objectives of the FFTF were to provide a strong, disciplined engineering base for the LMFBR program, provide fast flux testing for other U.S. programs, and contribute to the development of a viable self-sustaining competitive U.S. LMFBR industry. During its ten years of operation, the FFTF acted as a national research facility to test advanced nuclear fuels, materials, components, systems, nuclear power plant operating and maintenance procedures, and active and passive reactor safety technologies; it also produced a large number of isotopes for medical and industrial users, generated tritium for the U.S. fusion research program, and participated in cooperative, international research work. Prior to the implementation of the reactor characterization program, a series of isothermal physics measurements were performed; this acceptance testing program consisted of a series of control rod worths, critical rod positions, subcriticality measurements, maximum reactivity addition rates, shutdown margins, excess reactivity, and isothermal temperature coefficient reactivity. The results of these experiments were of particular importance because they provide extensive information which can be directly applied to the design of large LMFBR’s. It should be recognized that the data presented in the initial report were evaluated only to the extent necessary to ensure that adequate data were obtained. Later reports provided further interpretation and detailed comparisons with prediction techniques. The conclusion of the isothermal physics measurements was that the FFTF nuclear characteristics were essentially as designed and all safety requirements were satisfied. From a nuclear point of view, the FFTF was qualified to proceed into power operation mode. The FFTF was completed in 1978 and first achieved criticality on February 9, 1980. Upon completion of the isothermal physics and reactor characterization programs, the FFTF operated for ten years from April 1982 to April 1992. Reactor operations of the FFTF were terminated and the reactor facility was then defueled, deactivated, and placed into cold standby condition. Deactivation of the reactor was put on hold from 1996 to 2000 while the U.S. Department of Energy examined alternative uses for the FFTF but then announced the permanent deactivation of the FFTF in December 2001. Its core support basket was later drilled in May 2005, so as to remove all remaining sodium coolant. On April 17, 2006, the American Nuclear Society designated the FFTF as a “National Nuclear Historic Landmark”.

  4. EA-1035: Relocation of the Weapons Component Testing Facility Los Alamos National Laboratory, Los Alamos, New Mexico

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of the proposal to relocate the Weapons Component Testing Facility from Building 450 to Building 207, both within Technical Area 16, at the U.S....

  5. Department of Energy Designates the Idaho National Laboratory Advanced Test Reactor as a National Scientific User Facility

    Broader source: Energy.gov [DOE]

    WASHINGTON, DC - The U.S. Department of Energy (DOE) today designated the Idaho National Laboratory's (INL) Advanced Test Reactor (ATR) as a National Scientific User Facility.  Establishing the ATR...

  6. Advanced Test Reactor Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    Lisa Harvego; Brion Bennett

    2011-11-01

    U.S. Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Advanced Test Reactor Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. U.S. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool to develop the radioactive waste management basis.

  7. CoolCab Truck Testing Project Update (Presentation)

    SciTech Connect (OSTI)

    Proc, K.

    2007-10-31

    Presentation describes the CoolCab project, a DOE/NREL initiative to design efficient thermal management systems in heavy trucks to eliminate idling and reduce petroleum consumption.

  8. Project Impact Assessments … Building America FY14 Field Test...

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

    ... on project priorities and approach, and helps us interpret DOE priorities. - David Springer, Davis Energy Group ARBI Team Much of the research undertaken in Building America is ...

  9. Rotor dynamic analysis of GCEP (Gas Centrifuge Enrichment Plant) Tails Withdrawal Test Facility AC-12 compressor

    SciTech Connect (OSTI)

    Spencer, J.W.

    1982-01-22

    The reliable operation of the centrifugal compressors utilized in the gaseous diffusion process is of great importance due to the critical function of these machines in product and tails withdrawal, cascade purge and evacuation processes, the purge cascade and product booster applications. The same compressors will be used in equally important applications within the Gas Centrifuge Enrichment Plant (GCEP). In response to concern over the excessive vibration exhibited by the AC-12 compressor in the No. 3 position of the GCEP Tails Withdrawal Test Facility, a rotor-bearing dynamic analysis was performed on the compressor. This analysis included the acquisition and reduction of compressor vibration data, characterization and modeling of the rotorbearing system, a computer dynamic study, and recommendations for machine modification. The compressor dynamic analysis was performed for rotor speeds of 9000 rpm and 7200 to 7800 rpm, which includes all possible opreating speeds of the compressor in the GCEP Test Facility. While the analysis was performed on this particular AC-12 compressor, the results should be pertinent to other AC-12 applications as well. Similar diagnostic and analytical techniques can be used to evaluate operation of other types of centrifugal compressors.

  10. DOE Community-/Facility-Scale Tribal Renewable Energy Project Development and Finance Workshop

    Office of Energy Efficiency and Renewable Energy (EERE)

    This interactive workshop will walk participants through five steps to help tribes understand the process for and potential pitfalls of developing community- and facility-scale renewable energy...

  11. DWPF (Defense Waste Processing Facility) canister impact testing and analyses for the Transportation Technology Center

    SciTech Connect (OSTI)

    Farnsworth, R.K.; Mishima, J.

    1988-12-01

    A legal weight truck cask design has been developed for the US Department of Energy by GA Technologies, Inc. The cask will be used to transport defense high-level waste canisters produced by the Defense Waste Processing Facility (DWPF) at the Savannah River Plant. The development of the cask required the collection of impact data for the DWPF canisters. The Materials Characterization Center (MCC) performed this work under the guidance of the Transportation Technology Center (TTC) at Sandia National Laboratories. Two full-scale DWPF canisters filled with nonradioactive borosilicate glass were impacted under ''normal'' and ''hypothetical'' accident conditions. Two canisters, supplied by the DWPF, were tested. Each canister was vertically dropped on the bottom end from a height of either 0.3 m or 9.1 m (for normal or hypothetical accident conditions, respectively). The structural integrity of each canister was then examined using helium leak and dye penetrant testing. The canisters' diameters and heights, which had been previously measured, were then remeasured to determine how the canister dimensions had changed. Following structural integrity testing, the canisters were flaw leak tested. For transportation flaw leak testing, four holes were fabricated into the shell of canister A-27 (0.3 m drop height). The canister was then transported a total distance of 2069 miles. During transport, the waste form material that fell from each flaw was collected to determine the amount of size distribution of each flaw release. 2 refs., 8 figs., 12 tabs.

  12. Safety and licensing issues that are being addressed by the Power Burst Facility test programs. [PWR; BWR

    SciTech Connect (OSTI)

    McCardell, R.K.; MacDonald, P.E.

    1980-01-01

    This paper presents an overview of the results of the experimental program being conducted in the Power Burst Facility and the relationship of these results to certain safety and licensing issues. The safety issues that were addressed by the Power-Cooling-Mismatch, Reactivity Initiated Accident, and Loss of Coolant Accident tests, which comprised the original test program in the Power Burst Facility, are discussed. The resolution of these safety issues based on the results of the thirty-six tests performed to date, is presented. The future resolution of safety issues identified in the new Power Burst Facility test program which consists of tests which simulate BWR and PWR operational transients, anticipated transients without scram, and severe fuel damage accidents, is described.

  13. Mixed and Low-Level Waste Treatment Facility project. Appendix A, Environmental and regulatory planning and documentation: Draft

    SciTech Connect (OSTI)

    Not Available

    1992-04-01

    Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report, Appendix A, Environmental & Regulatory Planning & Documentation, identifies the regulatory requirements that would be imposed on the operation or construction of a facility designed to process the INEL`s waste streams. These requirements are contained in five reports that discuss the following topics: (1) an environmental compliance plan and schedule, (2) National Environmental Policy Act requirements, (3) preliminary siting requirements, (4) regulatory justification for the project, and (5) health and safety criteria.

  14. RESULTS OF THE EXTRACTION-SCRUB-STRIP TESTING USING AN IMPROVED SOLVENT FORMULATION AND SALT WASTE PROCESSING FACILITY SIMULATED WASTE

    SciTech Connect (OSTI)

    Peters, T.; Washington, A.; Fink, S.

    2012-01-09

    The Office of Waste Processing, within the Office of Technology Innovation and Development, is funding the development of an enhanced solvent - also known as the next generation solvent (NGS) - for deployment at the Savannah River Site to remove cesium from High Level Waste. The technical effort is a collaborative effort between Oak Ridge National Laboratory (ORNL) and Savannah River National Laboratory (SRNL). As part of the program, the Savannah River National Laboratory (SRNL) has performed a number of Extraction-Scrub-Strip (ESS) tests. These batch contact tests serve as first indicators of the cesium mass transfer solvent performance with actual or simulated waste. The test detailed in this report used simulated Tank 49H material, with the addition of extra potassium. The potassium was added at 1677 mg/L, the maximum projected (i.e., a worst case feed scenario) value for the Salt Waste Processing Facility (SWPF). The results of the test gave favorable results given that the potassium concentration was elevated (1677 mg/L compared to the current 513 mg/L). The cesium distribution value, DCs, for extraction was 57.1. As a comparison, a typical D{sub Cs} in an ESS test, using the baseline solvent formulation and the typical waste feed, is {approx}15. The Modular Caustic Side Solvent Extraction Unit (MCU) uses the Caustic-Side Solvent Extraction (CSSX) process to remove cesium (Cs) from alkaline waste. This process involves the use of an organic extractant, BoBCalixC6, in an organic matrix to selectively remove cesium from the caustic waste. The organic solvent mixture flows counter-current to the caustic aqueous waste stream within centrifugal contactors. After extracting the cesium, the loaded solvent is stripped of cesium by contact with dilute nitric acid and the cesium concentrate is transferred to the Defense Waste Processing Facility (DWPF), while the organic solvent is cleaned and recycled for further use. The Salt Waste Processing Facility (SWPF), under construction, will use the same process chemistry. The Office of Waste Processing (EM-31) expressed an interest in investigating the further optimization of the organic solvent by replacing the BoBCalixC6 extractant with a more efficient extractant. This replacement should yield dividends in improving cesium removal from the caustic waste stream, and in the rate at which the caustic waste can be processed. To that end, EM-31 provided funding for both the Savannah River National Laboratory (SRNL) and the Oak Ridge National Laboratory (ORNL). SRNL wrote a Task Technical Quality and Assurance Plan for this work. As part of the envisioned testing regime, it was decided to perform an ESS test using a simulated waste that simulated a typical envisioned SWPF feed, but with added potassium to make the waste more challenging. Potassium interferes in the cesium removal, and its concentration is limited in the feed to <1950 mg/L. The feed to MCU has typically contained <500 mg/L of potassium.

  15. MHK Projects/Gulf of Mexico Ocean test | Open Energy Information

    Open Energy Info (EERE)

    Gulf of Mexico Ocean test < MHK Projects Jump to: navigation, search << Return to the MHK database homepage Loading map... "minzoom":false,"mappingservice":"googlemaps3","type":"R...

  16. MHK Projects/Wave Star Energy 1 10 Scale Model Test | Open Energy...

    Open Energy Info (EERE)

    Star Energy 1 10 Scale Model Test < MHK Projects Jump to: navigation, search << Return to the MHK database homepage Loading map... "minzoom":false,"mappingservice":"googlemaps3","...

  17. Major Partner Test Sites

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

    Major Test Partners Once a technology is ready to be tested at pilot or commercial scale, the cost of building a test facility becomes significant -- often beyond the funding provided for any one project. It then becomes critical to test the technology at a pre-existing facility willing to test experimental technologies. Not surprisingly, most commercial facilities are hesitant to interfere with their operations to experiment, but others, with a view towards the future, welcome promising

  18. Activities to support the liquefied gaseous fuels spill test facility program. Final report

    SciTech Connect (OSTI)

    Sheesley, D.; King, S.B.; Routh, T.

    1997-03-01

    Approximately a hundred years ago the petrochemical industry was in its infancy, while the chemical industry was already well established. Today, both of these industries, which are almost indistinguishable, are a substantial part of the makeup of the U.S. economy and the lifestyle we enjoy. It is difficult to identify a single segment of our daily lives that isn`t affected by these industries and the products or services they make available for our use. Their survival and continued function in a competitive world market are necessary to maintain our current standard of living. The occurrence of accidents in these industries has two obvious effects: (1) the loss of product during the accident and future productivity because of loss of a portion of a facility or transport medium, and (2) the potential loss of life or injury to individuals, whether workers, emergency responders, or members of the general public. A great deal of work has been conducted at the Liquefied Gaseous Fuels Spill test Facility (LGFSTF) on hazardous spills. WRI has conducted accident investigations as well as provided information on the research results via the internet and bibliographies.

  19. Los Alamos DP West Plutonium Facility decontamination project, 1978-1981

    SciTech Connect (OSTI)

    Garde, R.; Cox, E.J.; Valentine, A.M.

    1982-09-01

    The DP West Plutonium Facility operated by the Los Alamos National Laboratory, Los Alamos, New Mexico was decontaminated between April 1978 and April 1981. The facility was constructed in 1944 to 1945 to produce plutonium metal and fabricate parts for nuclear weapons. It was continually used as a plutonium processing and research facility until mid-1978. Decontamination operations included dismantling and removing gloveboxes and conveyor tunnels; removing process systems, utilities, and exhaust ducts; and decontaminating all remaining surfaces. This report describes glovebox and conveyor tunnel separations, decontamination techniques, health and safety considerations, waste management procedures, and costs of the operation.

  20. First Beam Waist Measurements in the Final Focus Beam Line at the KEK Accelerator Test Facility

    SciTech Connect (OSTI)

    Bai, Sha; Aryshev, Alexander; Bambade, Philip; McCormick, Doug; Bolzon, Benoit; Gao, Jie; Tauchi, Toshiaki; Zhou, Feng; /SLAC

    2012-06-22

    The ATF2 project is the final focus system prototype for the ILC and CLIC linear collider projects, with a purpose to reach a 37 nm vertical beam size at the interaction point using compact optics based on a novel scheme of local chromaticity correction. Construction of all components and installation were completed at the end of 2008. An initial commissioning phase followed in 2009, using larger than nominal {beta} functions at the interaction point, corresponding to reduced demagnification factors in comparison to the design, to limit effects from higher-order optical aberrations and hence simplify beam tuning procedures while key instrumentation was being tested and calibrated. In this paper, first measurements of dispersion and Twiss parameters are presented based on scanning the beam during this period with a set of tungsten wires located just behind the interaction point, using two complementary analysis methods.

  1. Neutron measurements from beam-target reactions at the ELISE neutral beam test facility

    SciTech Connect (OSTI)

    Xufei, X. Fan, T.; Nocente, M.; Gorini, G.; Bonomo, F.; Franzen, P.; Fröschle, M.; Grosso, G.; Tardocchi, M.; Grünauer, F.; Pasqualotto, R.

    2014-11-15

    Measurements of 2.5 MeV neutron emission from beam-target reactions performed at the ELISE neutral beam test facility are presented in this paper. The measurements are used to study the penetration of a deuterium beam in a copper dump, based on the observation of the time evolution of the neutron counting rate from beam-target reactions with a liquid scintillation detector. A calculation based on a local mixing model of deuterium deposition in the target up to a concentration of 20% at saturation is used to evaluate the expected neutron yield for comparison with data. The results are of relevance to understand neutron emission associated to beam penetration in a solid target, with applications to diagnostic systems for the SPIDER and MITICA Neutral Beam Injection prototypes.

  2. Capture cavity cryomodule for quantum beam experiment at KEK superconducting RF test facility

    SciTech Connect (OSTI)

    Tsuchiya, K.; Hara, K.; Hayano, H.; Kako, E.; Kojima, Y.; Kondo, Y.; Nakai, H.; Noguchi, S.; Ohuchi, N.; Terashima, A.; Horikoshi, A.; Semba, T.

    2014-01-29

    A capture cavity cryomodule was fabricated and used in a beam line for quantum beam experiments at the Superconducting RF Test Facility (STF) of the High Energy Accelerator Research Organization in Japan. The cryomodule is about 4 m long and contains two nine-cell cavities. The cross section is almost the same as that of the STF cryomodules that were fabricated to develop superconducting RF cavities for the International Linear Collider. An attempt was made to reduce the large deflection of the helium gas return pipe (GRP) that was observed in the STF cryomodules during cool-down and warm-up. This paper briefly describes the structure and cryogenic performance of the captures cavity cryomodule, and also reports the measured displacement of the GRP and the cavity-containing helium vessels during regular operation.

  3. Verification of maximum impact force for interim storage cask for the Fast Flux Testing Facility

    SciTech Connect (OSTI)

    Chen, W.W.; Chang, S.J.

    1996-06-01

    The objective of this paper is to perform an impact analysis of the Interim Storage Cask (ISC) of the Fast Flux Test Facility (FFTF) for a 4-ft end drop. The ISC is a concrete cask used to store spent nuclear fuels. The analysis is to justify the impact force calculated by General Atomics (General Atomics, 1994) using the ILMOD computer code. ILMOD determines the maximum force developed by the concrete crushing which occurs when the drop energy has been absorbed. The maximum force, multiplied by the dynamic load factor (DLF), was used to determine the maximum g-level on the cask during a 4-ft end drop accident onto the heavily reinforced FFTF Reactor Service Building`s concrete surface. For the analysis, this surface was assumed to be unyielding and the cask absorbed all the drop energy. This conservative assumption simplified the modeling used to qualify the cask`s structural integrity for this accident condition.

  4. Demonstration of two-beam acceleration and 30 GHz power production in the CLIC Test Facility

    SciTech Connect (OSTI)

    Bossart, R.; Braun, H. H.; Carron, G.; Chanudet, M.; Chautard, F.; Delahaye, J. P.; Godot, J. C.; Hutchins, S.; Martinez, C.; Suberlucq, G.; Tenenbaum, P.; Thorndahl, L.; Trautner, H.; Valentini, M.; Wilson, I.; Wuensch, W. [CERN, 1211 Geneva 23 (Switzerland)

    1999-05-07

    The Compact Linear Collider (CLIC) Test Facility (CTF II) at CERN has recently demonstrated Two-Beam power production and acceleration at 30 GHz. With 41 MW of 30 GHz power produced in 14 ns pulses at a repetition rate of 5 Hz, the main beam has been accelerated by 28 MeV. The 30 GHz RF power is extracted in low impedance decelerating structures from a low-energy, high-current 'drive beam' which runs parallel to the main beam. The average current in the drive-beam train is 25 A, while the peak current exceeds 2 kA. Crosschecks between measured drive-beam charge, 30 GHz power and main-beam energy gain are in good agreement. In this paper, some relevant experimental and technical issues on drive-beam generation, two-beam power production and acceleration are presented.

  5. Compressed Air System Project Improves Production at a Candy Making Facility

    SciTech Connect (OSTI)

    2002-03-01

    The H.B. Reese Company successfully completed an upgrade of this compressed air system at its facility in Hershey, PA. The plant took two compressors offline while increasing throughput and quality.

  6. Nuclear Facilities Production Facilities

    National Nuclear Security Administration (NNSA)

    Facilities Production Facilities Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. Sand 2011-4582P. ENERGY U.S. DEPARTMENT OF Gamma Irradiation Facility (GIF) The GIF provides test cells for the irradiation of experiments with high-intensity gamma ray sources. The main features

  7. Physics of sup 238 Pu production in the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Rawlins, J.A.; Schmittroth, F.A.; Mann, F.M.; Schenter, R.E.; Lu, A.H.; Carter, L.L.; Wootan, D.W.; Schwarz, R.A.; Brager, H.R.; Matsumoto, W.Y.

    1989-11-01

    Westinghouse Hanford Company conducted an assessment of producing {sup 238}Pu in the Fast Flux Test Facility (FFTF), a U.S. Department of Energy (DOE) reactor located near Richland, Washington. The goal of the assessment was to determine whether the FFTF can produce at least 15 kg/yr of {sup 238}Pu to support the needs of the U.S. space program. Plutonium-238, with its 87.7-yr half-life and relatively pure alpha-particle decay mode, is an ideal power source for deep-space missions. The DOE is evaluating options for future {sup 238}Pu production, and the FFTF is a preferred candidate. The key technical issue for FFTF production is the isotopic purity of the product plutonium. FFTF production of at least 15 kg/yr of {sup 238}Pu is feasible. An FFTF physics test was completed and will reduce the large calculational uncertainties in {sup 236}Pu content, and the final test results will allow final production assembly design optimization. Use of the FFTF for {sup 238}Pu production can satisfy the needs of the U.S. space program for many years with a modern reactor that has an outstanding operational record.

  8. Generic TriBITS PRoject, Build, Test, and Install Quick Reference...

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

    Test, and Install Quick Reference Guide Ross Bartlett Oak Ridge National Laboratory CASL-U-2014-0075-000-a CASL-U-2014-0075-000-a Generic TriBITS PRoject, Build, Test, and ...

  9. Manhattan Project: Safety and the Trinity Test, July 1945

    Office of Scientific and Technical Information (OSTI)

    Trinity test radiation safety team SAFETY AND THE TRINITY TEST (Trinity Test Site, July 1945) Events > Dawn of the Atomic Era, 1945 The War Enters Its Final Phase, 1945 Debate Over How to Use the Bomb, Late Spring 1945 The Trinity Test, July 16, 1945 Safety and the Trinity Test, July 1945 Evaluations of Trinity, July 1945 Potsdam and the Final Decision to Bomb, July 1945 The Atomic Bombing of Hiroshima, August 6, 1945 The Atomic Bombing of Nagasaki, August 9, 1945 Japan Surrenders, August

  10. Manhattan Project: The Trinity Test, July 16, 1945

    Office of Scientific and Technical Information (OSTI)

    Trinity test, July 16, 1945 THE TRINITY TEST (Trinity Test Site, July 16, 1945) Events > Dawn of the Atomic Era, 1945 The War Enters Its Final Phase, 1945 Debate Over How to Use the Bomb, Late Spring 1945 The Trinity Test, July 16, 1945 Safety and the Trinity Test, July 1945 Evaluations of Trinity, July 1945 Potsdam and the Final Decision to Bomb, July 1945 The Atomic Bombing of Hiroshima, August 6, 1945 The Atomic Bombing of Nagasaki, August 9, 1945 Japan Surrenders, August 10-15, 1945 The

  11. The University of Minnesota aquifer thermal energy storage (ATES) field test facility -- system description, aquifer characterization, and results of short-term test cycles

    SciTech Connect (OSTI)

    Walton, M.; Hoyer, M.C.; Eisenreich, S.J.; Holm, N.L.; Holm, T.R.; Kanivetsky, R.; Jirsa, M.A.; Lee, H.C.; Lauer, J.L.; Miller, R.T.; Norton, J.L.; Runke, H. )

    1991-06-01

    Phase 1 of the Aquifer Thermal Energy Storage (ATES) Project at the University of Minnesota was to test the feasibility, and model, the ATES concept at temperatures above 100{degrees}C using a confined aquifer for the storage and recovery of hot water. Phase 1 included design, construction, and operation of a 5-MW thermal input/output field test facility (FTF) for four short-term ATES cycles (8 days each of heat injection, storage, and heat recover). Phase 1 was conducted from May 1980 to December 1983. This report describes the FTF, the Franconia-Ironton-Galesville (FIG) aquifer used for the test, and the four short-term ATES cycles. Heat recovery; operational experience; and thermal, chemical, hydrologic, and geologic effects are all included. The FTF consists of monitoring wells and the source and storage well doublet completed in the FIG aquifer with heat exchangers and a fixed-bed precipitator between the wells of the doublet. The FIG aquifer is highly layered and a really anisotropic. The upper Franconia and Ironton-Galesville parts of the aquifer, those parts screened, have hydraulic conductivities of {approximately}0.6 and {approximately}1.0 m/d, respectively. Primary ions in the ambient ground water are calcium and magnesium bicarbonate. Ambient temperature FIG ground water is saturated with respect to calcium/magnesium bicarbonate. Heating the ground water caused most of the dissolved calcium to precipitate out as calcium carbonate in the heat exchanger and precipitator. Silica, calcium, and magnesium were significantly higher in recovered water than in injected water, suggesting dissolution of some constituents of the aquifer during the cycles. Further work on the ground water chemistry is required to understand water-rock interactions.

  12. CLOSURE REPORT FOR CORRECTIVE ACTION UNIT 115: AREA 25 TEST CELL A FACILITY, NEVADA TEST SITE, NEVADA

    SciTech Connect (OSTI)

    NA

    2006-03-01

    This Closure Report (CR) describes the activities performed to close CAU 115, Area 25 Test Cell A Facility, as presented in the NDEP-approved SAFER Plan (NNSA/NSO, 2004). The SAFER Plan includes a summary of the site history, process knowledge, and closure standards. This CR provides a summary of the completed closure activities, documentation of waste disposal, and analytical and radiological data to confirm that the remediation goals were met and to document final site conditions. The approved closure alternative as presented in the SAFER Plan for CAU 115 (NNSA/NSO, 2004) was clean closure; however, closure in place was implemented under a Record of Technical Change (ROTC) to the SAFER Plan when radiological surveys indicated that the concrete reactor pad was radiologically activated and could not be decontaminated to meet free release levels. The ROTC is included as Appendix G of this report. The objectives of closure were to remove any trapped residual liquids and gases, dispose regulated and hazardous waste, decontaminate removable radiological contamination, demolish and dispose aboveground structures, remove the dewar as a best management practice (BMP), and characterize and restrict access to all remaining radiological contamination. Radiological contaminants of concern (COCs) included cobalt-60, cesium-137, strontium-90, uranium-234/235/236/238, and plutonium-239/240. Additional COCs included Resource Conservation and Recovery Act (RCRA) metals, polychlorinated biphenyls (PCBs), and asbestos.

  13. Facility Floorplan

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

    Facility Floorplan

  14. Closure of the Fast Flux Test Facility: Current Status and Future Plans

    SciTech Connect (OSTI)

    Farabee, O.A.; Witherspoon, W.V.

    2008-01-15

    The Fast Flux Test Facility (FFTF) was a 400 MWt sodium cooled fast reactor designed and constructed in the 1970's. The original purpose of the facility was to develop and test advanced fuels and materials for the liquid metal fast breeder reactor program. The facility operated very successfully from 1982 through 1992, fulfilling its original mission as well as other identified missions. However, in 1993 the Department of Energy concluded that there was no longer a need for the FFTF and thus ordered that it be shut down. Following eight years of additional study of potential new missions, the final decision to shut down the facility was made in 2001. (During this eight year period the plant was maintained in a condition to allow safe and efficient shut down or restart). The complete closure of the FFTF consists of the following phases: - Deactivation - removal/stabilization of hazards to allow long-term storage (2001-2009); - Surveillance and maintenance - minimum cost compliant storage (2010-2015); - Decontamination and decommissioning (2016-2024). All of the FFTF fuel has been removed from the site except the sodium-bonded fuel that is destined for transportation to Idaho National Laboratory for final disposition. The sodium-bonded fuel had metallic sodium inside of the fuel pin to increase the heat transfer from the fuel pellet to the clad in order to reduce pellet centerline temperature. Three hundred and seventy-six (376) fuel assemblies have been washed (sodium removed) and transferred to storage at other Hanford locations. The majority of the spent fuel is stored in interim storage casks designed for a 50 year storage life, holding seven assemblies each. All sodium systems have been drained and the sodium stored under an inert gas blanket at ambient temperature in a Sodium Storage Facility at the FFTF site. This facility consists of four large tanks and associated piping. The main contaminants are sodium-22, cesium-137 and tritium. The sodium-potassium (NaK) that was used as an intermediate cooling fluid in several FFTF systems has been drained and removed or flushed to sodium systems where it became mixed with the sodium. The in-containment hot cell has minimal sodium contamination, is currently inerted with argon and is being used for loading of the T-3 transportation cask with the sodium-bonded fuel for transportation to Idaho National Laboratory. The majority of the fuel handling machines are still operational and being used for loading the sodium-bonded fuel into the T-3 casks. This equipment will be shut down immediately following completion of shipment of the sodium-bonded fuel. The majority of hotel systems are still operating. Four of the eight 400-ton chillers have been shut down and four of the cooling towers have been shut down. The argon system is operational and supplying gas for sodium systems cover gas, in-containment hot cell atmosphere and fuel handling systems. The nitrogen system remains in service supplying cover gas to the demineralized water system and fire suppression systems. Eleven of the facilities nineteen transformers containing polychlorinated biphenyls (PCBs) have been removed and significant re-routing of power has been performed to support the long term minimum cost surveillance mode. Future plans include the complete deactivation, the long-term surveillance and maintenance, the sodium disposition and the decontamination and decommissioning The most complex and costly activity during the decontamination and decommissioning phase will be the removal of the 'residual sodium' in the sodium systems. It was impractical to remove the residual sodium during the systems draining evolution. It is estimated that approximately 24,000 liters (6,400 gallons) remain within the systems. The complexity of design of the FFTF exceeds any sodium facility in the United States in which sodium removal has occurred. There are a total of 21 miles of sodium piping in the FFTF as well as three large vessels (the reactor vessel and two spent fuel pool vessels) that will require partial disassembly and drilling in order react/remove remaining sodium.

  15. Recovery Efficiency Test Project: Phase 1, Activity report

    SciTech Connect (OSTI)

    Overbey, W.K. Jr.; Wilkins, D.W.; Keltch, B.; Saradji, B.; Salamy, S.P.

    1988-04-01

    This report is the second volume of the Recovery Efficiency Test Phase I Report of Activities. Volume 1 covered selection, well planning, drilling, coring, logging and completion operations. This volume reports on well testing activities, reclamation activities on the drilling site and access roads, and the results of physical and mechanical properties tests on the oriented core material obtained from a horizontal section of the well. 3 refs., 21 figs., 10 tabs.

  16. Ground-water monitoring compliance projects for Hanford Site facilities: Progress Report for the Period July 1 to September 30, 1987

    SciTech Connect (OSTI)

    Not Available

    1987-11-01

    This report documents the progress of four Hanford Site ground-water monitoring projects for the period from July 1 to September 310, 1987. The four disposal facilities are the 300 Area Process Trenches, 183-H Solar Evaporation Basins, 200 Area Low-Level Burial Grounds, and Nonradioactive Dangerous Waste (NRDW) Landfill. This report is the fifth in a series of periodic status reports. During this reporting period, field activities consisted of completing repairs on five monitoring wells originally present around the 183-H Basins and completing construction of 25 monitoring wells around the 200 Area Burial Grounds. The 14 wells in the 200 East Area were completed by Kaiser Engineers Hanford (KEH) and the 11 wells in the 200 West Area were compelted by ONWEGO Well Drilling. The NRDW Landfill interim characterization report was submitted to the WDOE and the USEPA in August 1987. Analytical results for the 300 Area, 183-H, and the NRDW Landfill indicate no deviations from previously established trends. Results from the NRDW Land-fill indiate that the facility has no effect on the ground-water quality beneath the facility, except for the detection of coliform bacteria. A possible source of this contamination is the solid-waste lanfill (SWL) adjacent to the NRDW Landfill. Ground-water monitoring data for the NRDW and SWL will be evaluated together in the future. Aquifer testing was completed in the 25 new wells surrounding the 200 Area buiral grounds. 13 refs., 19 refs., 13 tabs.

  17. Annual report for RCRA groundwater monitoring projects at Hanford Site facilities for 1995

    SciTech Connect (OSTI)

    Hartman, M.J.

    1996-02-01

    This report presents the annual hydrogeologic evaluation of 19 Resource Conservation and Recovery Act of 1976 facilities and 1 nonhazardous waste facility at the US Department of Energy`s Hanford Site. Although most of the facilities no longer receive dangerous waste, a few facilities continue to receive dangerous waste constituents for treatment, storage, or disposal. The 19 Resource Conservation and Recovery Act facilities comprise 29 waste management units. Nine of the units are monitored under groundwater quality assessment status because of elevated levels of contamination indicator parameters. The impact of those units on groundwater quality, if any, is being investigated. If dangerous waste or waste constituents have entered groundwater, their concentration profiles, rate, and extent of migration are evaluated. Groundwater is monitored at the other 20 units to detect leakage, should it occur. This report provides an interpretation of groundwater data collected at the waste management units between October 1994 and September 1995. Groundwater quality is described for the entire Hanford Site. Widespread contaminants include nitrate, chromium, carbon tetrachloride, tritium, and other radionuclides.

  18. Project W320 heel jet secondary catch mechanism lateral load test - test report

    SciTech Connect (OSTI)

    Bellomy, J.R.

    1994-12-01

    This test report summarizes testing activities and documents the results of the lateral load test performed on the Heel Jet Secondary Catch Mechanism.

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

    SciTech Connect (OSTI)

    NIRIDER, L.T.

    2003-08-06

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

  20. New facility design and work method for the quantitative fit testing laboratory. Master's thesis

    SciTech Connect (OSTI)

    Ward, G.F.

    1989-05-01

    The United States Air Force School of Aerospace Medicine (USAFSAM) tests the quantitative fit of masks which are worn by military personnel during nuclear, biological, and chemical warfare. Subjects are placed in a Dynatech-Frontier Fit Testing Chamber, salt air is fed into the chamber, and samples of air are drawn from the mask and the chamber. The ratio of salt air outside the mask to salt air inside the mask is called the quantitative fit factor. A motion-time study was conducted to evaluate the efficiency of the layout and work method presently used in the laboratory. A link analysis was done to determine equipment priorities, and the link data and design guidelines were used to develop three proposed laboratory designs. The proposals were evaluated by projecting the time and motion efficiency, and the energy expended working in each design. Also evaluated were the lengths of the equipment links for each proposal, and each proposal's adherence to design guidelines. A mock-up was built of the best design proposal, and a second motion-time study was run. Results showed that with the new laboratory and work procedures, the USAFSAM analyst could test 116 more subjects per year than are currently tested. Finally, the results of a questionnaire given to the analyst indicated that user acceptance of the work area improved with the new design.

  1. Facility Effluent Monitoring Plan for the Spent Nuclear Fuel (SNF) Project

    SciTech Connect (OSTI)

    HUNACEK, G.S.

    2000-08-01

    A facility effluent monitoring plan is required by the US. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document was prepared using the specific guidelines identified in Westinghouse Hanford Company (WHC)-EP-0438-1, ''A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans'', and assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the third revision to the original annual report. This document is reviewed annually even if there are no operational changes, and it is updated as necessary.

  2. Spent nuclear fuel project cold vacuum drying facility vacuum and purge system design description

    SciTech Connect (OSTI)

    IRWIN, J.J.

    1998-11-30

    This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Vacuum and Purge System (VPS) . The SDD was developed in conjunction with HNF-SD-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-002, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the VPS equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

  3. Design and calibration of a test facility for MLI thermal performance measurements below 80K

    SciTech Connect (OSTI)

    Boroski, W.; Kunzelman, R.; Ruschman, M.; Schoo, C.

    1992-04-01

    The design geometry of the SSC dipole cryostat includes active thermal radiation shields operating at 80K and 20K respectively. Extensive measurements conducted in a Heat Leak Test Facility (HLTF) have been used to evaluate the thermal performance of candidate multilayer insulation (MLI) systems for the 80K thermal shield, with the present system design based upon those measurement results. With the 80K MLI geometry established, efforts have focused on measuring the performance of MLI systems near 20K. A redesign of the HLTF has produced a measurement facility capable of conducting measurements with the warm boundary fixed at 80K and the cold boundary variable from 10K to 50K. Removing the 80K shield permits measurements with a warm boundary at 300K. The 80K boundary consists of a copper shield thermally anchored to a liquid nitrogen reservoir. The cold boundary consists of a copper anchor plate whose temperature is varied through boil-off gas from a 500 liter helium supply dewar. A transfer line heat exchanger supplies the boil-off gas to the anchor plate at a constant and controlled rate. The gas, which serves as cooling gas, is routed through a copper cooling tube soldered into the anchor plate. Varying the cooling gas flow rate varies the amount of refrigeration supplied to the anchor plate, thereby determining the plate temperature. A resistance heater installed on the anchor plate is regulated by a cryogenic temperature controller to provide final temperature control. Heat leak values are measured using a heatmeter which senses heat flow as a temperature gradient across a fixed thermal impedance. Since the thermal conductivity of the thermal impedance changes with temperature, the heatmeter is calibrated at key cold boundary temperatures. Thus, the system is capable of obtaining measurement data under a variety of system conditions. 7 refs.

  4. SLUDGE TREATMENT PROJECT KOP DISPOSITION - THERMAL AND GAS ANALYSIS FOR THE COLD VACUUM DRYING FACILITY

    SciTech Connect (OSTI)

    SWENSON JA; CROWE RD; APTHORPE R; PLYS MG

    2010-03-09

    The purpose of this document is to present conceptual design phase thermal process calculations that support the process design and process safety basis for the cold vacuum drying of K Basin KOP material. This document is intended to demonstrate that the conceptual approach: (1) Represents a workable process design that is suitable for development in preliminary design; and (2) Will support formal safety documentation to be prepared during the definitive design phase to establish an acceptable safety basis. The Sludge Treatment Project (STP) is responsible for the disposition of Knock Out Pot (KOP) sludge within the 105-K West (KW) Basin. KOP sludge consists of size segregated material (primarily canister particulate) from the fuel and scrap cleaning process used in the Spent Nuclear Fuel process at K Basin. The KOP sludge will be pre-treated to remove fines and some of the constituents containing chemically bound water, after which it is referred to as KOP material. The KOP material will then be loaded into a Multi-Canister Overpack (MCO), dried at the Cold Vacuum Drying Facility (CVDF) and stored in the Canister Storage Building (CSB). This process is patterned after the successful drying of 2100 metric tons of spent fuel, and uses the same facilities and much of the same equipment that was used for drying fuel and scrap. Table ES-l present similarities and differences between KOP material and fuel and between MCOs loaded with these materials. The potential content of bound water bearing constituents limits the mass ofKOP material in an MCO load to a fraction of that in an MCO containing fuel and scrap; however, the small particle size of the KOP material causes the surface area to be significantly higher. This relatively large reactive surface area represents an input to the KOP thermal calculations that is significantly different from the calculations for fuel MCOs. The conceptual design provides for a copper insert block that limits the volume available to receive KOP material, enhances heat conduction, and functions as a heat source and sink during drying operations. This use of the copper insert represents a significant change to the thermal model compared to that used for the fuel calculations. A number of cases were run representing a spectrum of normal and upset conditions for the drying process. Dozens of cases have been run on cold vacuum drying of fuel MCOs. Analysis of these previous calculations identified four cases that provide a solid basis for judgments on the behavior of MCO in drying operations. These four cases are: (1) Normal Process; (2) Degraded vacuum pumping; (3) Open MCO with loss of annulus water; and (4) Cool down after vacuum drying. The four cases were run for two sets of input parameters for KOP MCOs: (1) a set of parameters drawn from safety basis values from the technical data book and (2) a sensitivity set using parameters selected to evaluate the impact of lower void volume and smaller particle size on MCO behavior. Results of the calculations for the drying phase cases are shown in Table ES-2. Cases using data book safety basis values showed dry out in 9.7 hours and heat rejection sufficient to hold temperature rise to less than 25 C. Sensitivity cases which included unrealistically small particle sizes and corresponding high reactive surface area showed higher temperature increases that were limited by water consumption. In this document and in the attachment (Apthorpe, R. and M.G. Plys, 2010) cases using Technical Databook safety basis values are referred to as nominal cases. In future calculations such cases will be called safety basis cases. Also in these documents cases using parameters that are less favorable to acceptable performance than databook safety values are referred to as safety cases. In future calculations such cases will be called sensitivity cases or sensitivity evaluations Calculations to be performed in support of the detailed design and formal safety basis documentation will expand the calculations presented in this document to include: additional features of the drying cycle, more realistic treatment of uranium metal consumption during oxidation, larger water inventory, longer time scales, and graphing of results of hydrogen gas concentration.

  5. Advanced Test Reactor Core Modeling Update Project Annual Report for Fiscal Year 2013

    SciTech Connect (OSTI)

    David W. Nigg

    2013-09-01

    Legacy computational reactor physics software tools and protocols currently used for support of Advanced Test Reactor (ATR) core fuel management and safety assurance, and to some extent, experiment management, are inconsistent with the state of modern nuclear engineering practice, and are difficult, if not impossible, to verify and validate (V&V) according to modern standards. Furthermore, the legacy staff knowledge required for effective application of these tools and protocols from the 1960s and 1970s is rapidly being lost due to staff turnover and retirements. In late 2009, the Idaho National Laboratory (INL) initiated a focused effort, the ATR Core Modeling Update Project, to address this situation through the introduction of modern high-fidelity computational software and protocols. This aggressive computational and experimental campaign will have a broad strategic impact on the operation of the ATR, both in terms of improved computational efficiency and accuracy for support of ongoing DOE programs as well as in terms of national and international recognition of the ATR National Scientific User Facility (NSUF).

  6. Environmental assessment of facility operations at the U.S. Department of Energy Grand Junction Projects Office, Grand Junction, Colorado

    SciTech Connect (OSTI)

    1996-06-01

    The US Department of Energy (DOE) has prepared a sitewide environmental assessment (EA) of the proposed action to continue and expand present-day activities on the DOE Grand Junction Projects Office (GJPO) facility in Grand Junction, Colorado. Because DOE-GJPO regularly proposes and conducts many different on-site activities, DOE decided to evaluate these activities in one sitewide EA rather than in multiple, activity-specific documents. On the basis of the information and analyses presented in the EA, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment, as defined by the National Environmental Policy Act (NEPA) of 1969. Therefore, preparation of an environmental impact statement is not required for facility operations, and DOE is issuing this Finding of No Significant Impact (FONSI).

  7. Developing Renewable Energy Projects Larger Than 10 MWs at Federal Facilities (Book)

    SciTech Connect (OSTI)

    Not Available

    2013-03-01

    To accomplish Federal goals for renewable energy, sustainability, and energy security, large-scale renewable energy projects must be developed and constructed on Federal sites at a significant scale with significant private investment. The U.S. Department of Energy's Federal Energy Management Program (FEMP) helps Federal agencies meet these goals and assists agency personnel navigate the complexities of developing such projects and attract the necessary private capital to complete them. This guide is intended to provide a general resource that will begin to develop the Federal employee's awareness and understanding of the project developer's operating environment and the private sector's awareness and understanding of the Federal environment. Because the vast majority of the investment that is required to meet the goals for large-scale renewable energy projects will come from the private sector, this guide has been organized to match Federal processes with typical phases of commercial project development. The main purpose of this guide is to provide a project development framework to allow the Federal Government, private developers, and investors to work in a coordinated fashion on large-scale renewable energy projects. The framework includes key elements that describe a successful, financially attractive large-scale renewable energy project.

  8. Compressed Air Project Improves Efficiency and Production at Harland Publishing Facility

    SciTech Connect (OSTI)

    2002-05-01

    Case study describing a project which configured a printing machine so that it consumes less compressed air and required lower pressure to operate effectively. Project replicated throughout the company, leading to energy cost savings of $200,000 per year, or 2.9 million kilowatt-hours.

  9. CENTRAL STORAGE FACILITY PROJECT IN COLOMBIA TO PROVIDE THE SAFE STORAGE AND PROTECTION OF HIGH-ACTIVITY RADIOACTIVE SOURCES

    SciTech Connect (OSTI)

    Greenberg, Raymond; Wright, Kyle A.; McCaw, Erica E.; Vallejo, Jorge

    2009-10-07

    The Global Threat Reduction Initiative (GTRI) reduces and protects vulnerable nuclear and radiological material located at civilian sites worldwide. Internationally, over 40 countries are cooperating with GTRI to enhance the security of these materials. The GTRI program has worked successfully with foreign countries to remove and protect nuclear and radioactive materials, including orphaned and disused high-activity sources. GTRI began cooperation with the Republic of Colombia in April 2004. This cooperation has been a resounding success by securing forty high-risk sites, consolidating disused/orphan sources at an interim secure national storage facility, and developing a comprehensive approach to security, training, and sustainability. In 2005 the Colombian Ministry of Mines and Energy requested the Department of Energys support in the construction of a new Central Storage Facility (CSF). In December 2005, the Ministry selected to construct this facility at the Institute of Geology and Mining (Ingeominas) site in Bogota. This site already served as Colombias national repository, where disused sources were housed in various buildings around the complex. The CSF project was placed under contract in May 2006, but environmental issues and public protests, which led to a class action lawsuit against the Colombian Government, forced the Ministry to quickly suspend activities, thereby placing the project in jeopardy. Despite these challenges, however, the Ministry of Mines and Energy worked closely with public and environmental authorities to resolve these issues, and continued to be a strong advocate of the GTRI program. In June 2008, the Ministry of Mines and Energy was granted the construction and environmental licenses. As a result, construction immediately resumed and the CSF was completed by December 2008. A commissioning ceremony was held for the new facility in January 2009, which was attended by representatives from the Department of Energy, U.S. Embassy, and the Ministry of Mines and Energy, including the Minister and Vice Minister.

  10. Portsmouth Proposed Plan for the Process Buildings and Complex Facilities Decontamination and Decommissioning Evaluation Project

    Broader source: Energy.gov [DOE]

    DOE has evaluated alternatives for demolishing the buildings at the Portsmouth Site. Two remedial alternatives were developed for consideration. This Proposed Plan describes the required no-action alternative (Alternative 1) and a D&D alternative (Alternative 2). The preferred alternative is Alternative 2, controlled demolition of the process buildings and complex facilities.

  11. Status Review of Wildlife Mitigation at Columbia Basin Hydroelectric Projects, Oregon Facilities, Final Report.

    SciTech Connect (OSTI)

    Bedrossian, Karen L.

    1984-08-01

    The report presents a review and documentation of existing information on wildlife resources at Columbia River Basin hydroelectric facilities within Oregon. Effects of hydroelectric development and operation; existing agreements; and past, current and proposed wildlife mitigation, enhancement, and protection activities were considered. (ACR)

  12. Review of project definition studies of possible on-site uses of superconducting super collider assets and facilities

    SciTech Connect (OSTI)

    1994-12-01

    This document reports on the results of a peer review and evaluation of studies made of potential uses of assets from the terminated Superconducting Super Collider (SSC) project. These project definition studies focused on nine areas of use of major assets and facilities at the SSC site near Waxahachie, Texas. The studies were undertaken as part of the effort to maximize the value of the investment made in the SSC and were supported by two sets of grants, one to the Texas National Research Laboratory Commission (TNRLC) and the second to various universities and other institutions for studies of ideas raised by a public call for expressions of interest. The Settlement Agreement, recently signed by the Department of Energy (DOE) and TNRLC, provides for a division of SSC property. As part of the goal of maximizing the value of the SSC investment, the findings contained in this report are thus addressed to officials in both the Department and TNRLC. In addition, this review had several other goals: to provide constructive feedback to those doing the studies; to judge the benefits and feasibility (including funding prospects) of the projects studied; and to help worthy projects become reality by matching projects with possible funding sources.

  13. Review of project definition studies of possible on-site uses of superconducting super collider assets and facilities. Final report

    SciTech Connect (OSTI)

    1994-12-01

    This document reports on the results of a peer review and evaluation of studies made of potential uses of assets from the terminated Superconducting Super Collider (SSC) project. These project definition studies focused on nine areas of use of major assets and facilities at the SSC site near Waxahachie, Texas. The studies were undertaken as part of the effort to maximize the value of the investment made in the SSC and were supported by two sets of grants, one to the Texas National Research Laboratory Commission (TNRLC) and the second to various universities and other institutions for studies of ideas raised by a public call for expressions of interest. The Settlement Agreement, recently signed by the Department of Energy (DOE) and TNRLC, provides for a division of SSC property. As part of the goal of maximizing the value of the SSC investment, the findings contained in this report are thus addressed to officials in both the Department and TNRLC. In addition, this review had several other goals: to provide constructive feedback to those doing the studies; to judge the benefits and feasibility (including funding prospects) of the projects studied; and to help worthy projects become reality by matching projects with possible funding sources.

  14. Alabama Project Testing Potential for Combining CO2 Storage with Enhanced

    Energy Savers [EERE]

    Methane Recovery | Department of Energy Project Testing Potential for Combining CO2 Storage with Enhanced Methane Recovery Alabama Project Testing Potential for Combining CO2 Storage with Enhanced Methane Recovery June 16, 2010 - 1:00pm Addthis Washington, DC -- Field testing the potential for combining geologic carbon dioxide (CO2) storage with enhanced methane recovery is underway at a site in Alabama by a U.S. Department of Energy (DOE) team of regional partners. Members of the Southeast

  15. Vulnerability Assessments and Resilience Planning at Federal Facilities. Preliminary Synthesis of Project

    SciTech Connect (OSTI)

    Moss, R. H.; Delgado, A.; Malone, E L.

    2015-08-15

    U.S. government agencies are now directed to assess the vulnerability of their operations and facilities to climate change and to develop adaptation plans to increase their resilience. Specific guidance on methods is still evolving based on the many different available frameworks. Agencies have been experimenting with these frameworks and approaches. This technical paper synthesizes lessons and insights from a series of research case studies conducted by the investigators at facilities of the U.S. Department of Energy and the Department of Defense. The purpose of the paper is to solicit comments and feedback from interested program managers and analysts before final conclusions are published. The paper describes the characteristics of a systematic process for prioritizing needs for adaptation planning at individual facilities and examines requirements and methods needed. It then suggests a framework of steps for vulnerability assessments at Federal facilities and elaborates on three sets of methods required for assessments, regardless of the detailed framework used. In a concluding section, the paper suggests a roadmap to further develop methods to support agencies in preparing for climate change. The case studies point to several preliminary conclusions; (1) Vulnerability assessments are needed to translate potential changes in climate exposure to estimates of impacts and evaluation of their significance for operations and mission attainment, in other words into information that is related to and useful in ongoing planning, management, and decision-making processes; (2) To increase the relevance and utility of vulnerability assessments to site personnel, the assessment process needs to emphasize the characteristics of the site infrastructure, not just climate change; (3) A multi-tiered framework that includes screening, vulnerability assessments at the most vulnerable installations, and adaptation design will efficiently target high-risk sites and infrastructure; (4) Vulnerability assessments can be connected to efforts to improve facility resilience to motivate participation; and (5) Efficient, scalable methods for vulnerability assessment can be developed, but additional case studies and evaluation are required.

  16. NREL: Research Facilities - Webmaster

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

    Your name: Your email address: Your message: Send Message Printable Version Research Facilities Home Laboratories Test & User Facilities Laboratories & Facilities by Technology...

  17. Thermal hydraulic performance testing of printed circuit heat exchangers in a high-temperature helium test facility

    SciTech Connect (OSTI)

    Sai K. Mylavarapu; Xiaodong Sun; Richard E. Glosup; Richard N. Christensen; Michael W. Patterson

    2014-04-01

    In high-temperature gas-cooled reactors, such as a very high temperature reactor (VHTR), an intermediate heat exchanger (IHX) is required to efficiently transfer the core thermal output to a secondary fluid for electricity generation with an indirect power cycle and/or process heat applications. Currently, there is no proven high-temperature (750800 C or higher) compact heat exchanger technology for high-temperature reactor design concepts. In this study, printed circuit heat exchanger (PCHE), a potential IHX concept for high-temperature applications, has been investigated for their heat transfer and pressure drop characteristics under high operating temperatures and pressures. Two PCHEs, each having 10 hot and 10 cold plates with 12 channels (semicircular cross-section) in each plate are fabricated using Alloy 617 plates and tested for their performance in a high-temperature helium test facility (HTHF). The PCHE inlet temperature and pressure were varied from 85 to 390 C/1.02.7 MPa for the cold side and 208790 C/1.02.7 MPa for the hot side, respectively, while the mass flow rate of helium was varied from 15 to 49 kg/h. This range of mass flow rates corresponds to PCHE channel Reynolds numbers of 950 to 4100 for the cold side and 900 to 3900 for the hot side (corresponding to the laminar and laminar-to-turbulent transition flow regimes). The obtained experimental data have been analyzed for the pressure drop and heat transfer characteristics of the heat transfer surface of the PCHEs and compared with the available models and correlations in the literature. In addition, a numerical treatment of hydrodynamically developing and hydrodynamically fully-developed laminar flow through a semicircular duct is presented. Relations developed for determining the hydrodynamic entrance length in a semicircular duct and the friction factor (or pressure drop) in the hydrodynamic entry length region for laminar flow through a semicircular duct are given. Various hydrodynamic entrance region parameters, such as incremental pressure drop number, apparent Fanning friction factor, and hydrodynamic entrance length in a semicircular duct have been numerically estimated.

  18. Cold Vacuum Drying (CVD) Facility Diesel Generator Fire Protection

    SciTech Connect (OSTI)

    SINGH, G.

    2000-04-25

    This Acceptance Test Procedure (ATP) has been prepared to demonstrate that the Fire Protection and Detection System installed by Project W-441 (Cold Vacuum Drying Facility and Diesel Generator Building) functions as required by project specifications.

  19. Facility for high heat flux testing of irradiated fusion materials and components using infrared plasma arc lamps

    SciTech Connect (OSTI)

    Sabau, Adrian S; Ohriner, Evan Keith; Kiggans, Jim; Harper, David C; Snead, Lance Lewis; Schaich, Charles Ross

    2014-01-01

    A new high-heat flux testing facility using water-wall stabilized high-power high-pressure argon Plasma Arc Lamps (PALs) has been developed for fusion applications. It can handle irradiated plasma facing component materials and mock-up divertor components. Two PALs currently available at ORNL can provide maximum incident heat fluxes of 4.2 and 27 MW/m2 over a heated area of 9x12 and 1x10 cm2, respectively, which are fusion-prototypical steady state heat flux conditions. The facility will be described and the main differences between the photon-based high-heat flux testing facilities, such as PALs, and the e-beam and particle beam facilities more commonly used for fusion HHF testing are discussed. The components of the test chamber were designed to accommodate radiation safety and materials compatibility requirements posed by high-temperature exposure of low levels irradiated tungsten articles. Issues related to the operation and temperature measurements during testing are presented and discussed.

  20. The John Deere E diesel Test & Research Project

    SciTech Connect (OSTI)

    Fields, Nathan; Mitchell, William E.

    2008-09-23

    Three non-road Tier II emissions compliant diesel engines manufactured by John Deere were placed on a durability test plan of 2000 hours each at full load, rated speed (FLRS). The fuel was a blend of 10% fuel ethanol and 90% low sulfur #2 diesel fuel. Seven operational failures involving twenty seven fuel system components occurred prior to completion of the intended test plan. Regulated emissions measured prior to component failure indicated compliance to Tier II certification goals for the observed test experience. The program plan included operating three non-road Tier II diesel engines for 2000 hours each monitoring the regulated emissions at 500 hour intervals for changes/deterioration. The program was stopped prematurely due to number and frequency of injection system failures. The failures and weaknesses observed involved injector seat and valve wear, control solenoid material incompatibility, injector valve deposits and injector high pressure seal cavitation erosion. Future work should target an E diesel fuel standard that emphasizes minimum water content, stability, lubricity, cetane neutrality and oxidation resistance. Standards for fuel ethanol need to require water content no greater than the base diesel fuel standard. Lubricity bench test standards may need new development for E diesel.

  1. West Valley Demonstration Project Phase I Decommissioning- Facility Disposition Partnering Performance Agreement

    Broader source: Energy.gov [DOE]

    The Department of Energy, West Valley Demonstration Project (DOE-WVDP) and CH2M Hill B&W West Valley (CHBWV) are committed to continuous improvement and will utilize principles of the DOE...

  2. Development of explosive event scale model testing capability at Sandia`s large scale centrifuge facility

    SciTech Connect (OSTI)

    Blanchat, T.K.; Davie, N.T.; Calderone, J.J.

    1998-02-01

    Geotechnical structures such as underground bunkers, tunnels, and building foundations are subjected to stress fields produced by the gravity load on the structure and/or any overlying strata. These stress fields may be reproduced on a scaled model of the structure by proportionally increasing the gravity field through the use of a centrifuge. This technology can then be used to assess the vulnerability of various geotechnical structures to explosive loading. Applications of this technology include assessing the effectiveness of earth penetrating weapons, evaluating the vulnerability of various structures, counter-terrorism, and model validation. This document describes the development of expertise in scale model explosive testing on geotechnical structures using Sandia`s large scale centrifuge facility. This study focused on buried structures such as hardened storage bunkers or tunnels. Data from this study was used to evaluate the predictive capabilities of existing hydrocodes and structural dynamics codes developed at Sandia National Laboratories (such as Pronto/SPH, Pronto/CTH, and ALEGRA). 7 refs., 50 figs., 8 tabs.

  3. Dual axis radiographic hydrodynamic test facility. Final environmental impact statement, Volume 2: Public comments and responses

    SciTech Connect (OSTI)

    1995-08-01

    On May 12, 1995, the U.S. Department of Energy (DOE) issued the draft Dual Axis Radiographic Hydrodynamic Test Facility Environmental Impact Statement (DARHT EIS) for review by the State of New Mexico, Indian Tribes, local governments, other Federal agencies, and the general public. DOE invited comments on the accuracy and adequacy of the draft EIS and any other matters pertaining to their environmental reviews. The formal comment period ran for 45 days, to June 26, 1995, although DOE indicated that late comments would be considered to the extent possible. As part of the public comment process, DOE held two public hearings in Los Alamos and Santa Fe, New Mexico, on May 31 and June 1, 1995. In addition, DOE made the draft classified supplement to the DARHT EIS available for review by appropriately cleared individuals with a need to know the classified information. Reviewers of the classified material included the State of New Mexico, the U.S. Environmental Protection Agency, the Department of Defense, and certain Indian Tribes. Volume 2 of the final DARHT EIS contains three chapters. Chapter 1 includes a collective summary of the comments received and DOE`s response. Chapter 2 contains the full text of the public comments on the draft DARHT EIS received by DOE. Chapter 3 contains DOE`s responses to the public comments and an indication as to how the comments were considered in the final EIS.

  4. Climax Granite, Nevada Test Site, as a host for a rock mechanics test facility related to the geologic disposal of high level nuclear wastes

    SciTech Connect (OSTI)

    Heuze, F.E.

    1981-02-01

    This document discusses the potential of the Climax pluton, at the Nevada Test Site, as the host for a granite mechanics test facility related to the geologic disposal of high-level nuclear waste. The Climax granitic pluton has been the site of three nuclear weapons effects tests: Hard Hat, Tiny Tot, and Piledriver. Geologic exploration and mapping of the granite body were performed at the occasion of these tests. Currently, it is the site Spent Fuel Test (SFT-C) conducted in the vicinity of and at the same depth as that of the Piledriver drifts. Significant exploration, mapping, and rock mechanics work have been performed and continue at this Piledriver level - the 1400 (ft) level - in the context of SFT-C. Based on our technical discussions, and on the review of the significant geological and rock mechanics work already achieved in the Climax pluton, based also on the ongoing work and the existing access and support, it is concluded that the Climax site offers great opportunities for a rock mechanics test facility. It is not claimed, however, that Climax is the only possible site or the best possible site, since no case has been made for another granite test facility in the United States. 12 figures, 3 tables.

  5. Beam Homogeneity Dependence on the Magnetic Filter Field at the IPP Test Facility MANITU

    SciTech Connect (OSTI)

    Franzen, P.; Fantz, U.

    2011-09-26

    The homogeneity of the extracted current density from the large RF driven negative hydrogen ion sources of the ITER neutral beam system is a critical issue for the transmission of the negative ion beam through the accelerator and the beamline components. As a first test, the beam homogeneity at the IPP long pulse test facility MANITU is measured by means of the divergence and the stripping profiles obtained with a spatially resolved Doppler-shift spectroscopy system. Since MANITU is typically operating below the optimum perveance, an increase in the divergence corresponds to a lower local extracted negative ion current density if the extraction voltage is constant. The beam H{sub {alpha}} Doppler-shift spectroscopy is a rather simple tool, as no absolute calibration - both for the wavelength and the emission - is necessary. Even no relative calibration of the different used lines of sight is necessary for divergence and stripping profiles as these quantities can be obtained by the line broadening of the Doppler-shifted peak and the ratio of the integral of the stripping peak to the integral of the Doppler-shifted peak, respectively. The paper describes the H{sub {alpha}} MANITU Doppler-shift spectroscopy system which is now operating routinely and the evaluation methods of the divergence and the stripping profiles. Beam homogeneity measurements are presented for different extraction areas and magnetic filter field configurations both for Hydrogen and Deuterium operation; the results are compared with homogeneity measurements of the source plasma. The stripping loss measurements are compared with model calculations.

  6. Geotechnical characterization of the North Ramp of the Exploratory Studies Facility: Yucca Mountain Site Characterization Project. Volume 2, NRG corehole data appendices

    SciTech Connect (OSTI)

    Brechtel, C.E.; Lin, Ming; Martin, E.; Kessel, D.S.

    1995-05-01

    This report presents the results of the geological and geotechnical characterization of the Miocene volcanic tuff rocks of the Timber Mountain and Paintbrush groups that the tunnel boring machine will encounter during excavations of the Exploratory Studies Facility (ESF) North Ramp. The information in this report was developed to support the design of the ESF North Ramp. The ESF is being constructed by the DOE as part of the Yucca Mountain Project site characterization activities. The purpose of these activities is to evaluate the potential to locate the national high-level nuclear waste repository on land within and adjacent to the Nevada Test Site (NTS), Nye County, Nevada. This report was prepared as part of the Soil and Rock Properties Studies in accordance with the 8.3.1.14.2 Study Plan to Provide Soil and Rock Properties. This is volume 2 which contains NRG Corehole Data for each of the NRG Holes.

  7. Spent Nuclear Fuel Project path forward: nuclear safety equivalency to comparable NRC-licensed facilities

    SciTech Connect (OSTI)

    Garvin, L.J.

    1995-11-01

    This document includes the Technical requirements which meet the nuclear safety objectives of the NRC regulations for fuel treatment and storage facilities. These include requirements regarding radiation exposure limits, safety analysis, design and construction. This document also includes administrative requirements which meet the objectives of the major elements of the NRC licensing process. These include formally documented design and safety analysis, independent technical review, and oppportunity for public involvement.

  8. DOE - NNSA/NFO -- EM Underground Test Area (UGTA) Project

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

    Groundwater NNSA/NFO Language Options U.S. DOE/NNSA - Nevada Field Office Click to subscribe to NNSS News Groundwater Characterization Environmental Restoration photo Click here to learn about ongoing groundwater characterization activities at the Nevada National Security Site via a video on our YouTube channel. Click here to open an interactive map that shows deep sub-surface contamination sites identified as a result of historic underground nuclear testing. From 1951 to 1992, 828 underground

  9. Preliminary studies of tunnel interface response modeling using test data from underground storage facilities.

    SciTech Connect (OSTI)

    Sobolik, Steven Ronald; Bartel, Lewis Clark

    2010-11-01

    In attempting to detect and map out underground facilities, whether they be large-scale hardened deeply-buried targets (HDBT's) or small-scale tunnels for clandestine border or perimeter crossing, seismic imaging using reflections from the tunnel interface has been seen as one of the better ways to both detect and delineate tunnels from the surface. The large seismic impedance contrast at the tunnel/rock boundary should provide a strong, distinguishable seismic response, but in practice, such strong indicators are often lacking. One explanation for the lack of a good seismic reflection at such a strong contrast boundary is that the damage caused by the tunneling itself creates a zone of altered seismic properties that significantly changes the nature of this boundary. This report examines existing geomechanical data that define the extent of an excavation damage zone around underground tunnels, and the potential impact on rock properties such as P-wave and S-wave velocities. The data presented from this report are associated with sites used for the development of underground repositories for the disposal of radioactive waste; these sites have been excavated in volcanic tuff (Yucca Mountain) and granite (HRL in Sweden, URL in Canada). Using the data from Yucca Mountain, a numerical simulation effort was undertaken to evaluate the effects of the damage zone on seismic responses. Calculations were performed using the parallelized version of the time-domain finitedifference seismic wave propagation code developed in the Geophysics Department at Sandia National Laboratories. From these numerical simulations, the damage zone does not have a significant effect upon the tunnel response, either for a purely elastic case or an anelastic case. However, what was discovered is that the largest responses are not true reflections, but rather reradiated Stoneley waves generated as the air/earth interface of the tunnel. Because of this, data processed in the usual way may not correctly image the tunnel. This report represents a preliminary step in the development of a methodology to convert numerical predictions of rock properties to an estimation of the extent of rock damage around an underground facility and its corresponding seismic velocity, and the corresponding application to design a testing methodology for tunnel detection.

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

    SciTech Connect (OSTI)

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

    2002-02-26

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

  11. Underground Test Area Quality Assurance Project Plan Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Irene Farnham

    2011-05-01

    This Quality Assurance Project Plan (QAPP) provides the overall quality assurance (QA) program requirements and general quality practices to be applied to the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Underground Test Area (UGTA) Sub-Project (hereafter the Sub-Project) activities. The requirements in this QAPP are consistent with DOE Order 414.1C, Quality Assurance (DOE, 2005); U.S. Environmental Protection Agency (EPA) Guidance for Quality Assurance Project Plans for Modeling (EPA, 2002); and EPA Guidance on the Development, Evaluation, and Application of Environmental Models (EPA, 2009). The QAPP Revision 0 supersedes DOE--341, Underground Test Area Quality Assurance Project Plan, Nevada Test Site, Nevada, Revision 4.

  12. Generic TriBITS Project, Build, Test, and Install Reference Guide

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

    Generic TriBITS Project, Build, Test, and Install Reference Guide Author: Roscoe A. Bartlett Contact: bartlett.roscoe@gmail.com Date: 2015-08-27 Version: tribitsstart-1317-g4908e4...

  13. DOE Announces $11 Million for Seven New Projects to Test New Options for

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

    Optimal Efficiency of the U.S. Electric Grid | Department of Energy $11 Million for Seven New Projects to Test New Options for Optimal Efficiency of the U.S. Electric Grid DOE Announces $11 Million for Seven New Projects to Test New Options for Optimal Efficiency of the U.S. Electric Grid January 15, 2016 - 1:52pm Addthis News Media Contact 202-586-4940 DOENews@hq.doe.gov WASHINGTON- The Energy Department's (DOE) Advanced Research Projects Agency-Energy (ARPA-E) today announced $11 million

  14. The 1993 baseline biological studies and proposed monitoring plan for the Device Assembly Facility at the Nevada Test Site

    SciTech Connect (OSTI)

    Woodward, B.D.; Hunter, R.B.; Greger, P.D.; Saethre, M.B.

    1995-02-01

    This report contains baseline data and recommendations for future monitoring of plants and animals near the new Device Assembly Facility (DAF) on the Nevada Test Site (NTS). The facility is a large structure designed for safely assembling nuclear weapons. Baseline data was collected in 1993, prior to the scheduled beginning of DAF operations in early 1995. Studies were not performed prior to construction and part of the task of monitoring operational effects will be to distinguish those effects from the extensive disturbance effects resulting from construction. Baseline information on species abundances and distributions was collected on ephemeral and perennial plants, mammals, reptiles, and birds in the desert ecosystems within three kilometers (km) of the DAF. Particular attention was paid to effects of selected disturbances, such as the paved road, sewage pond, and the flood-control dike, associated with the facility. Radiological monitoring of areas surrounding the DAF is not included in this report.

  15. Mixed and low-level waste treatment facility project. Volume 3, Waste treatment technologies (Draft)

    SciTech Connect (OSTI)

    Not Available

    1992-04-01

    The technology information provided in this report is only the first step toward the identification and selection of process systems that may be recommended for a proposed mixed and low-level waste treatment facility. More specific information on each technology will be required to conduct the system and equipment tradeoff studies that will follow these preengineering studies. For example, capacity, maintainability, reliability, cost, applicability to specific waste streams, and technology availability must be further defined. This report does not currently contain all needed information; however, all major technologies considered to be potentially applicable to the treatment of mixed and low-level waste are identified and described herein. Future reports will seek to improve the depth of information on technologies.

  16. RH-LLW Disposal Facility Project CD-2/3 to Design/Build Proposal Reconciliation Report

    SciTech Connect (OSTI)

    Annette L. Schafer

    2012-06-01

    A reconciliation plan was developed and implemented to address potential gaps and responses to gaps between the design/build vendor proposals and the Critical Decision-2/3 approval request package for the Remote-Handled Low Level Waste Disposal Facility Project. The plan and results of the plan implementation included development of a reconciliation team comprised of subject matter experts from Battelle Energy Alliance and the Department of Energy Idaho Operations Office, identification of reconciliation questions, reconciliation by the team, identification of unresolved/remaining issues, and identification of follow-up actions and subsequent approvals of responses. The plan addressed the potential for gaps to exist in the following areas: • Department of Energy Order 435.1, “Radioactive Waste Management,” requirements, including the performance assessment, composite analysis, monitoring plan, performance assessment/composite analysis maintenance plan, and closure plan • Environmental assessment supporting the National Environmental Policy Act • Nuclear safety • Safeguards and security • Emplacement operations • Requirements for commissioning • General project implementation. The reconciliation plan and results of the plan implementation are provided in a business-sensitive project file. This report provides the reconciliation plan and non-business sensitive summary responses to identified gaps.

  17. Simulated Irradiation of Samples in HFIR for use as Possible Test Materials in the MPEX (Material Plasma Exposure Experiment) Facility

    SciTech Connect (OSTI)

    Ellis, Ronald James; Rapp, Juergen

    2014-01-01

    The importance of Plasma Material Interaction (PMI) is a major concern in fusion reactor design and analysis. The Material-Plasma Exposure eXperiment (MPEX) facility will explore PMI under fusion reactor plasma conditions. Samples with accumulated displacements per atom (DPA) damage produced by irradiations in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL) will be studied in the MPEX facility. The project presented in this paper involved performing assessments of the induced radioactivity and resulting radiation fields of a variety of potential fusion reactor materials. The scientific code packages MCNP and SCALE were used to simulate irradiation of the samples in HFIR; generation and depletion of nuclides in the material and the subsequent composition, activity levels, gamma radiation fields, and resultant dose rates as a function of cooling time. These state-of-the-art simulation methods were used in addressing the challenge of the MPEX project to minimize the radioactive inventory in the preparation of the samples for inclusion in the MPEX facility.

  18. Research Facilities | NREL

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

    Research Facilities Our state-of-the-art facilities are available to industry entrepreneurs, engineers, scientists, and universities for researching and developing their energy technologies. Our researchers and technicians who operate these labs and facilities are ready to work with you and share their expertise. Alphabetical Listings Laboratories Test and User Facilities Popular Facilities Energy Systems Integration Facility Integrated Biorefinery Research Facility Process Development

  19. Storage of LWR spent fuel in air: Volume 1: Design and operation of a spent fuel oxidation test facility

    SciTech Connect (OSTI)

    Thornhill, C.K.; Campbell, T.K.; Thornhill, R.E.

    1988-12-01

    This report describes the design and operation and technical accomplishments of a spent-fuel oxidation test facility at the Pacific Northwest Laboratory. The objective of the experiments conducted in this facility was to develop a data base for determining spent-fuel dry storage temperature limits by characterizing the oxidation behavior of light-water reactor (LWR) spent fuels in air. These data are needed to support licensing of dry storage in air as an alternative to spent-fuel storage in water pools. They are to be used to develop and validate predictive models of spent-fuel behavior during dry air storage in an Independent Spent Fuel Storage Installation (ISFSI). The present licensed alternative to pool storage of spent fuel is dry storage in an inert gas environment, which is called inerted dry storage (IDS). Licensed air storage, however, would not require monitoring for maintenance of an inert-gas environment (which IDS requires) but does require the development of allowable temperature limits below which UO/sub 2/ oxidation in breached fuel rods would not become a problem. Scoping tests at PNL with nonirradiated UO/sub 2/ pellets and spent-fuel fragment specimens identified the need for a statistically designed test matrix with test temperatures bounding anticipated maximum acceptable air-storage temperatures. This facility was designed and operated to satisfy that need. 7 refs.

  20. Closure Report for Corrective Action Unit 116: Area 25 Test Cell C Facility, Nevada National Security Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2011-09-29

    This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 116, Area 25 Test Cell C Facility. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 [as amended March 2010]). CAU 116 consists of the following two Corrective Action Sites (CASs), located in Area 25 of the Nevada National Security Site: (1) CAS 25-23-20, Nuclear Furnace Piping and (2) CAS 25-41-05, Test Cell C Facility. CAS 25-41-05 consisted of Building 3210 and the attached concrete shield wall. CAS 25-23-20 consisted of the nuclear furnace piping and tanks. Closure activities began in January 2007 and were completed in August 2011. Activities were conducted according to Revision 1 of the Streamlined Approach for Environmental Restoration Plan for CAU 116 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2008). This CR provides documentation supporting the completed corrective actions and provides data confirming that closure objectives for CAU 116 were met. Site characterization data and process knowledge indicated that surface areas were radiologically contaminated above release limits and that regulated and/or hazardous wastes were present in the facility.