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Sample records for demonstration project vitrification

  1. Vitrification facility at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    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

  2. Functional description of the West Valley Demonstration Project Vitrification Facility

    International Nuclear Information System (INIS)

    Borisch, R.R.; McMahon, C.L.

    1990-07-01

    The primary objective of the West Valley Demonstration Project (WVDP) is the solidification of approximately 2.1 million liters (560,000 gallons) of high-level radioactive waste (HLW) which resulted from the operation of a nuclear fuel reprocessing plant. Since the original plant was not built to accommodate the processing of waste beyond storage in underground tanks, HLW solidification by vitrification presented numerous engineering challenges. Existing facilities required redesign and conversion to meet their new purpose. Vitrification technology and systems needed to be created and then tested. Equipment modifications, identified from cold test results, were incorporated into the final equipment configuration to be used for radioactive (hot) operations. Cold operations have defined the correct sequence and optimal functioning of the equipment to be used for vitrification and have verified the process by which waste will be solidified into borosilicate glass

  3. Vitrification process equipment design for the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Chapman, C.C.; Drosjack, W.P.

    1988-10-01

    The vitrification process and equipment design is nearing completion for the West Valley Project. This report provides the basis and current status for the design of the major vessels and equipment within the West Valley Vitrification Plant. A review of the function and key design features of the equipment is also provided. The major subsystems described include the feed preparation and delivery systems, the melter, the canister handling systems, and the process off-gas system. 11 refs., 33 figs., 4 tabs

  4. Project summary, 116-B-6-1 crib ISV [in situ vitrification] demonstration project

    International Nuclear Information System (INIS)

    Koegler, S.S.

    1989-01-01

    The 116-B Crib Demonstration Project is intended to demonstrate the emerging in situ vitrification (ISV) technology to immobilize or destroy hazardous and radioactive chemicals at an actual site. In situ vitrification is the conversion of contaminated soil into a durable glass and crystalline product through joule heating. The 116-B crib site was chosen for the demonstration because it contains both radioactive and hazardous chemicals (e.g., chromium) and presents a potential threat to environment. The project will involve sampling and analysis of the soil beneath the crib, a small-scale ISV test to verify operating parameters, vitrification of the crib, and analysis of the vitrified soil. 5 figs

  5. Design of equipment used for high-level waste vitrification at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Vance, R.F.; Brill, B.A.; Carl, D.E.

    1997-06-01

    The equipment as designed, started, and operated for high-level radioactive waste vitrification at the West Valley Demonstration Project in western New York State is described. Equipment for the processes of melter feed make-up, vitrification, canister handling, and off-gas treatment are included. For each item of equipment the functional requirements, process description, and hardware descriptions are presented

  6. Development of analytical cell support for vitrification at the West Valley Demonstration Project. Topical report

    Energy Technology Data Exchange (ETDEWEB)

    Barber, F.H.; Borek, T.T.; Christopher, J.Z. [and others

    1997-12-01

    Analytical and Process Chemistry (A&PC) support is essential to the high-level waste vitrification campaign at the West Valley Demonstration Project (WVDP). A&PC characterizes the waste, providing information necessary to formulate the recipe for the target radioactive glass product. High-level waste (HLW) samples are prepared and analyzed in the analytical cells (ACs) and Sample Storage Cell (SSC) on the third floor of the main plant. The high levels of radioactivity in the samples require handling them in the shielded cells with remote manipulators. The analytical hot cells and third floor laboratories were refurbished to ensure optimal uninterrupted operation during the vitrification campaign. New and modified instrumentation, tools, sample preparation and analysis techniques, and equipment and training were required for A&PC to support vitrification. Analytical Cell Mockup Units (ACMUs) were designed to facilitate method development, scientist and technician training, and planning for analytical process flow. The ACMUs were fabricated and installed to simulate the analytical cell environment and dimensions. New techniques, equipment, and tools could be evaluated m in the ACMUs without the consequences of generating or handling radioactive waste. Tools were fabricated, handling and disposal of wastes was addressed, and spatial arrangements for equipment were refined. As a result of the work at the ACMUs the remote preparation and analysis methods and the equipment and tools were ready for installation into the ACs and SSC m in July 1995. Before use m in the hot cells, all remote methods had been validated and four to eight technicians were trained on each. Fine tuning of the procedures has been ongoing at the ACs based on input from A&PC technicians. Working at the ACs presents greater challenges than had development at the ACMUs. The ACMU work and further refinements m in the ACs have resulted m in a reduction m in analysis turnaround time (TAT).

  7. Development of analytical cell support for vitrification at the West Valley Demonstration Project. Topical report

    International Nuclear Information System (INIS)

    Barber, F.H.; Borek, T.T.; Christopher, J.Z.

    1997-12-01

    Analytical and Process Chemistry (A ampersand PC) support is essential to the high-level waste vitrification campaign at the West Valley Demonstration Project (WVDP). A ampersand PC characterizes the waste, providing information necessary to formulate the recipe for the target radioactive glass product. High-level waste (HLW) samples are prepared and analyzed in the analytical cells (ACs) and Sample Storage Cell (SSC) on the third floor of the main plant. The high levels of radioactivity in the samples require handling them in the shielded cells with remote manipulators. The analytical hot cells and third floor laboratories were refurbished to ensure optimal uninterrupted operation during the vitrification campaign. New and modified instrumentation, tools, sample preparation and analysis techniques, and equipment and training were required for A ampersand PC to support vitrification. Analytical Cell Mockup Units (ACMUs) were designed to facilitate method development, scientist and technician training, and planning for analytical process flow. The ACMUs were fabricated and installed to simulate the analytical cell environment and dimensions. New techniques, equipment, and tools could be evaluated m in the ACMUs without the consequences of generating or handling radioactive waste. Tools were fabricated, handling and disposal of wastes was addressed, and spatial arrangements for equipment were refined. As a result of the work at the ACMUs the remote preparation and analysis methods and the equipment and tools were ready for installation into the ACs and SSC m in July 1995. Before use m in the hot cells, all remote methods had been validated and four to eight technicians were trained on each. Fine tuning of the procedures has been ongoing at the ACs based on input from A ampersand PC technicians. Working at the ACs presents greater challenges than had development at the ACMUs. The ACMU work and further refinements m in the ACs have resulted m in a reduction m in

  8. Operating experience during high-level waste vitrification at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Valenti, P.J.; Elliott, D.I.

    1999-01-01

    This report provides a summary of operational experiences, component and system performance, and lessons learned associated with the operation of the Vitrification Facility (VF) at the West Valley Demonstration Project (WVDP). The VF was designed to convert stored high-level radioactive waste (HLW) into a stable waste form (borosilicate glass) suitable for disposal in a federal repository. Following successful completion on nonradioactive test, HLW processing began in July 1995. Completion of Phase 1 of HLW processing was reached on 10 June 1998 and represented the processing of 9.32 million curies of cesium-137 (Cs-137) and strontium-90 (Sr-90) to fill 211 canisters with over 436,000 kilograms of glass. With approximately 85% of the total estimated curie content removed from underground waste storage tanks during Phase 1, subsequent operations will focus on removal of tank heel wastes

  9. West Valley Demonstration Project vitrification process equipment Functional and Checkout Testing of Systems (FACTS)

    International Nuclear Information System (INIS)

    Carl, D.E.; Paul, J.; Foran, J.M.; Brooks, R.

    1990-01-01

    The Vitrification Facility (VF) at the West Valley Demonstration Project was designed to convert stored radioactive waste into a stable glass for disposal in a federal repository. The Functional and Checkout Testing of Systems (FACTS) program was conducted from 1984 to 1989. During this time new equipment and processes were developed, installed, and implemented. Thirty-seven FACTS tests were conducted, and approximately 150,000 kg of glass were made by using nonradioactive materials to simulate the radioactive waste. By contrast, the planned radioactive operation is expected to produce approximately 500,000 kg of glass. The FACTS program demonstrated the effectiveness of equipment and procedures in the vitrification system, and the ability of the VF to produce quality glass on schedule. FACTS testing also provided data to validate the WVNS waste glass qualification method and verify that the product glass would meet federal repository acceptance requirements. The system was built and performed to standards which would have enabled it to be used in radioactive service. As a result, much of the VF tested, such as the civil construction, feed mixing and holding vessels, and the off-gas scrubber, will be converted for radioactive operation. The melter was still in good condition after being at temperature for fifty-eight of the sixty months of FACTS. However, the melter exceeded its recommended design life and will be replaced with a similar melter. Components that were not designed for remote operation and maintenance will be replaced with remote-use items. The FACTS testing was accomplished with no significant worker injury or environmental releases. During the last FACTS run, the VF processes approximated the remote-handling system that will be used in radioactive operations. Following this run the VF was disassembled for conversion to a radioactive process. Functional and checkout testing of new components will be performed prior to radioactive operation

  10. Scaled Vitrification System III (SVS III) Process Development and Laboratory Tests at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Jain, V.; Barnes, S.M.; Bindi, B.G.; Palmer, R.A.

    2000-01-01

    At the West Valley Demonstration Project (WVDP),the Vitrification Facility (VF)is designed to convert the high-level radioactive waste (HLW)stored on the site to a stable glass for disposal at a Department of Energy (DOE)-specified federal repository. The Scaled Vitrification System III (SVS-III)verification tests were conducted between February 1995 and August 1995 as a supplemental means to support the vitrification process flowsheet, but at only one seventh the scale.During these tests,the process flowsheet was refined and optimized. The SVS-III test series was conducted with a focus on confirming the applicability of the Redox Forecasting Model, which was based on the Index of Feed Oxidation (IFO)developed during the Functional and Checkout Testing of Systems (FACTS)and SVS-I tests. Additional goals were to investigate the prototypical feed preparation cycle and test the new target glass composition. Included in this report are the basis and current designs of the major components of the Scale Vitrification System and the results of the SVS-III tests.The major subsystems described are the feed preparation and delivery, melter, and off-gas treatment systems. In addition,the correlation between the melter's operation and its various parameters;which included feed rate,cold cap coverage,oxygen reduction (redox)state of the glass,melter power,plenum temperature,and airlift analysis;were developed

  11. Los Alamos National Laboratory simulated sludge vitrification demonstration

    International Nuclear Information System (INIS)

    Cicero, C.A.; Bickford, D.F.; Bennert, D.M.; Overcamp, T.J.

    1994-01-01

    Technologies are being developed to convert hazardous and mixed wastes to a form suitable for permanent disposal. Vitrification, which has been declared the Best Demonstrated Available Technology (BDAT) for high-level radioactive waste disposal by the EPA, is capable of producing a highly durable wasteform that minimizes disposal volumes through organic destruction, moisture evaporation, and porosity reduction. However, this technology must be demonstrated over a range of waste characteristics, including compositions, chemistries, moistures, and physical characteristics to ensure that it is suitable for hazardous and mixed waste treatment. This project plans to demonstrate vitrification of simulated wastes that are considered representatives of wastes found throughout the DOE complex. For the most part, the primary constituent of the wastes is flocculation aids, such as Fe(OH) 3 , and natural filter aids, such as diatomaceous earth and perlite. The filter aids consist mostly of silica, which serves as an excellent glass former; hence, the reason why vitrification is such a viable option. LANL is currently operating a liquid waste processing plant which produces an inorganic sludge similar to other waste water treatment streams. Since this waste has characteristics that make it suitable for vitrification and the likelihood of success is high, it shall be tested at CU. The objective of this task is to characterize the process behavior and glass product formed upon vitrification of simulated LANL sludge. The off-gases generated from the production runs will also be characterized to help further develop vitrification processes for mixed and low level wastes

  12. A COMPREHENSIVE TECHNICAL REVIEW OF THE DEMONSTRATION BULK VITRIFICATION SYSTEM

    International Nuclear Information System (INIS)

    SCHAUS, P.S.

    2006-01-01

    In May 2006, CH2M Hill Hanford Group, Inc. chartered an Expert Review Panel (ERP) to review the current status of the Demonstration Bulk Vitrification System (DBVS). It is the consensus of the ERP that bulk vitrification is a technology that requires further development and evaluation to determine its potential for meeting the Hanford waste stabilization mission. No fatal flaws (issues that would jeopardize the overall DBVS mission that cannot be mitigated) were found, given the current state of the project. However, a number of technical issues were found that could significantly affect the project's ability to meet its overall mission as stated in the project ''Justification of Mission Need'' document, if not satisfactorily resolved. The ERP recognizes that the project has changed from an accelerated schedule demonstration project to a formally chartered project that must be in full compliance with DOE 413.3 requirements. The perspective of the ERP presented herein, is measured against the formally chartered project as stated in the approved Justification of Mission Need document. A justification of Mission Need document was approved in July 2006 which defined the objectives for the DBVS Project. In this document, DOE concluded that bulk vitrification is a viable technology that requires additional development to determine its potential applicability to treatment of a portion of the Hanford low activity waste. The DBVS mission need statement now includes the following primary objectives: (1) process approximately 190,000 gallons of Tank S-109 waste into fifty 100 metric ton boxes of vitrified product; (2) store and dispose of these boxes at Hanford's Integrated Disposal Facility (IDF); (3) evaluate the waste form characteristics; (4) gather pilot plant operability data, and (5) develop the overall life cycle system performance of bulk vitrification and produce a comparison of the bulk vitrification process to building a second LAW Immobilization facility or other

  13. Transportable Vitrification System Demonstration on Mixed Waste

    International Nuclear Information System (INIS)

    Zamecnik, J.R.; Whitehouse, J.C.; Wilson, C.N.; Van Ryn, F.R.

    1998-01-01

    This paper describes preliminary results from the first demonstration of the Transportable Vitrification System (TVS) on actual mixed waste. The TVS is a fully integrated, transportable system for the treatment of mixed and low-level radioactive wastes. The demonstration was conducted at Oak Ridge's East Tennessee Technology Park (ETTP), formerly known as the K-25 site. The purpose of the demonstration was to show that mixed wastes could be vitrified safely on a 'field' scale using joule-heated melter technology and obtain information on system performance, waste form durability, air emissions, and costs

  14. The In Situ Vitrification Project

    International Nuclear Information System (INIS)

    Buelt, J.L.

    1988-10-01

    The Columbia Section of the American Society of Civil Engineers (ASCE) is pleased to submit the In Situ Vitrification (ISV) Project to the Pacific Northwest Council for consideration as the Outstanding Civil Engineering Achievement. The ISV process, developed by Battelle-Northwest researchers beginning in 1980, converts contaminated soils and sludges to a glass and crystalline product. In this way it stabilizes hazardous chemical and radioactive wastes and makes them chemically inert. This report describes the process. A square array of four molybdenum electrodes is inserted into the ground to the desired treatment depth. Because soil is not electrically conductive when the moisture has been driven off, a conductive mixture of flaked graphite and glass frit is placed among the electrodes as a starter path. An electrical potential is applied to the electrodes to establish an electric current in the starter path. The resultant power heats the starter path and surrounding soil to 2000/degree/C, well above the initial soil-melting temperature of 1100/degree/C to 1400/degree/C. The graphite starter path is eventually consumed by oxidation, and the current is transferred to the molten soil, which is electrically conductive. As the molten or vitrified zone grows, it incorporates radionuclides and nonvolatile hazardous elements, such as heavy metals, and destroys organic components by pyrolysis. 2 figs

  15. Commercialization project of Ulchin vitrification

    International Nuclear Information System (INIS)

    Jo, Hyun-Jun; Kim, Cheon-Woo; Hwang, Tae-Won

    2011-01-01

    The Ulchin Vitrification Facility (UVF), to be used for the vitirification of low- and intermediate-level radioactive waste (LILW) generated by nuclear power plants (NPPs), is the world's first commercial facility using Cold Crucible Induction Melter (CCIM) technology. The construction of the facility was begun in 2005 and was completed in 2007. From December 2007 to September 2009, all key performance tests, such as the system functional test, the cold test, the hot test, and the real waste test, were successfully carried out. The UVF commenced commercial operation in October 2009 for the vitrification of radioactive waste. (author)

  16. Design and operating features of the high-level waste vitrification system for the West Valley demonstration project

    International Nuclear Information System (INIS)

    Siemens, D.H.; Beary, M.M.; Barnes, S.M.; Berger, D.N.; Brouns, R.A.; Chapman, C.C.; Jones, R.M.; Peters, R.D.; Peterson, M.E.

    1986-03-01

    A liquid-fed joule-heated ceramic melter system is the reference process for immobilization of the high-level liquid waste in the US and several foreign countries. This system has been under development for over ten years at Pacific Northwest Laboratory and other national laboratories operated for the US Department of Energy. Pacific Northwest Laboratory contributed to this research through its Nuclear Waste Treatment Program and used applicable data to design and test melters and related systems using remote handling of simulated radioactive wastes. This report describes the equipment designed in support of the high-level waste vitrification program at West Valley, New York. Pacific Northwest Laboratory worked closely with West Valley Nuclear Services Company to design a liquid-fed ceramic melter, a liquid waste preparation and feed tank and pump, an off-gas treatment scrubber, and an enclosed turntable for positioning the waste canisters. Details of these designs are presented including the rationale for the design features and the alternatives considered

  17. Zeolite Vitrification Demonstration Program nonradioactive-process operations summary

    International Nuclear Information System (INIS)

    Bryan, G.H.; Knox, C.A.; Goles, R.G.; Ethridge, L.J.; Siemens, D.H.

    1982-09-01

    The Submerged Demineralizer System is a process developed to decontaminate high-activity level water at Three Mile Island by sorbing the activity (primarily Cs and Sr) onto beds of zeolite. Pacific Northwest Laboratory's Zeolite Vitrification Demonstration Program has the responsibility of demonstrating the full-scale vitrification of this zeolite material. The first phase of this program has been to develop a glass formulation and demonstrate the vitrification process with the use of nonradioactive materials. During this phase, four full-scale nonradioactive demonstration runs were completed. The same zeolite mixture being used in the SDS system was loaded with nonradioactive isotopes of Cs and Sr, dried, blended with glass-forming chemicals and fed to a canister in an in-can melter furnace. During each run, the gaseous effluents were sampled. After each run, glass samples were removed and analyzed

  18. Hanford Waste Vitrification Project overview and status

    International Nuclear Information System (INIS)

    Swenson, L.D.; Smets, J.L.

    1993-01-01

    The Hanford Waste Vitrification Project (HWVP) is being constructed at the US DOE's Hanford Site in Richland, WA. Engineering and design are being accomplished by Fluor Daniel Inc. in Irvine, CA. Technical input is furnished by Westinghouse Hanford Co. and construction management services by UE ampersand C-Catalytic Inc. The HWVP will immobilize high level nuclear waste in a glass matrix for eventual disposal in the federal repository. The HWVP consists of several structures, the major ones being the Vitrification Building, the Canister Storage Building, fan house, sand filter, waste hold tank, pump house, and administration and construction facilities. Construction started in April 1992 with the clearing and grubbing activities that prepared the site for fencing and construction preparation. Several design packages have been released for procurement activities. The most significant package release is for the Canister Storage Building, which will be the first major structure to be constructed

  19. Progress of the Hanford Bulk Vitrification Project ICVTM Testing Program

    International Nuclear Information System (INIS)

    Witwer, K.S.; Woolery, D.W.; Dysland, E.J.

    2006-01-01

    In June 2004, the Bulk Vitrification Project was initiated with the intent to engineer, construct and operate a full-scale bulk vitrification pilot-plant to treat low-activity tank waste from Hanford tank 241-S-109. The project, managed by CH2M HILL Hanford Group, Inc., and performed by AMEC Earth and Environmental, Inc. (AMEC), will develop and operate a full-scale demonstration facility to exhibit the effectiveness of the bulk vitrification process under actual operating conditions. Since project initiation, testing has been undertaken using crucible-scale, 1/6 linear (engineering) scale, and full-scale vitrification equipment. Crucible-scale testing, coupled with engineering-scale testing, helps establish process limitations of selected glass formulations. Full-scale testing provides critical design verification of the In Container Vitrification (ICV) TM process both prior to and during operation of the demonstration facility. Beginning in late 2004, several full-scale tests have been performed at AMEC's test site, located adjacent to the U.S. Department of Energy's Hanford Site, in Richland, WA. Early testing involved verification of melt startup methodology, followed by subsequent full-melt testing to validate critical design parameters and demonstrate the 'Bottom-Up, Feed While Melt' process. As testing has progressed, design improvements have been identified and incorporated into each successive test. Full scale testing at AMEC's test site is currently scheduled to complete in 2006, with continued full-scale operational testing at the demonstration facility on the Hanford Site starting in 2007. Additional engineering scale testing will validate recommended glass formulations that have been provided by the Pacific Northwest National Laboratory (PNNL). This testing is expected to continue through 2006. This paper discusses the progress of the full-scale and engineering scale testing performed to date. Crucible-scale testing, a critical step in developing

  20. Utilization of the Pilot Scale Demonstration Facility for Vitrification of Low and Intermediate Level Radioactive Wastes

    International Nuclear Information System (INIS)

    Oh, Won Zin; Choi, W. K.; Jung, C. H.; Won, H. J.; Song, P. S.; Min, B. Y.; Park, H. S.; Jung, K. K.; Yun, K. S.

    2005-10-01

    A series of maintenance and repair work for normalization of the pilot scale vitrification demonstration facility was completed successfully to develop the waste treatment in high temperature and melting technology. It was investigated that the treatment of combustible and non-combustible wastes produced at the KAERI site is technically feasible in the pilot scale vitrification demonstration facility which is designed to be able to treat various kinds of radioactive wastes such as combustible and non-combustible wastes including soil and concrete. The vitrification test facility can be used as the R and D and the technology demonstration facility for melt decontamination of the metallic wastes which have a fixed specification. The modification of the RI storage room in the pilot scale vitrification demonstration facility and the licensing according to the facility modification were completed for the R and D on melt decontamination of dismantled metallic wastes which is carrying out as one of the national long-term R and D projects on nuclear energy. The lab-scale melt decontamination apparatus was installed in modified RI storage room and the characteristics of melt decontamination will be examined using various metallic wastes. It is expected that the economical feasibility on the volume reduction and recycle of metallic wastes will be escalated in the present situation when the unit cost for waste disposal has the tendency to grow up gradually. Therefore, the pilot scale vitrification demonstration facility can be used for the technology development for the volume reduction and recycle of the metallic wastes generated from on-going projects on the decommissioning of research reactors and the environmental restoration of uranium conversion plant, and for the treatment of radioactive solid wastes produced at the KAERI site

  1. Utilization of the Pilot Scale Demonstration Facility for Vitrification of Low and Intermediate Level Radioactive Wastes

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Won Zin; Choi, W. K.; Jung, C. H.; Won, H. J.; Song, P. S.; Min, B. Y.; Park, H. S.; Jung, K. K.; Yun, K. S

    2005-10-15

    A series of maintenance and repair work for normalization of the pilot scale vitrification demonstration facility was completed successfully to develop the waste treatment in high temperature and melting technology. It was investigated that the treatment of combustible and non-combustible wastes produced at the KAERI site is technically feasible in the pilot scale vitrification demonstration facility which is designed to be able to treat various kinds of radioactive wastes such as combustible and non-combustible wastes including soil and concrete. The vitrification test facility can be used as the R and D and the technology demonstration facility for melt decontamination of the metallic wastes which have a fixed specification. The modification of the RI storage room in the pilot scale vitrification demonstration facility and the licensing according to the facility modification were completed for the R and D on melt decontamination of dismantled metallic wastes which is carrying out as one of the national long-term R and D projects on nuclear energy. The lab-scale melt decontamination apparatus was installed in modified RI storage room and the characteristics of melt decontamination will be examined using various metallic wastes. It is expected that the economical feasibility on the volume reduction and recycle of metallic wastes will be escalated in the present situation when the unit cost for waste disposal has the tendency to grow up gradually. Therefore, the pilot scale vitrification demonstration facility can be used for the technology development for the volume reduction and recycle of the metallic wastes generated from on-going projects on the decommissioning of research reactors and the environmental restoration of uranium conversion plant, and for the treatment of radioactive solid wastes produced at the KAERI site.

  2. Transportable vitrification system demonstration on mixed waste. Revision 1

    International Nuclear Information System (INIS)

    Zamecnik, J.R.; Whitehouse, J.C.; Wilson, C.N.; Van Ryn, F.R.

    1998-01-01

    The Transportable Vitrification System (TVS) is a large scale, fully integrated, vitrification system for the treatment of low-level and mixed wastes in the form of sludges, soils, incinerator ash, and many other waste streams. It was demonstrated on surrogate waste at Clemson University and at the Oak Ridge Reservation (ORR) prior to treating actual mixed waste. Treatment of a combination of dried B and C Pond sludge and CNF sludge was successfully demonstrated at ORR in 1997. The demonstration produced 7,616 kg of glass from 7,328 kg of mixed wastes with a 60% reduction in volume. Glass formulations for the wastes treated were developed using a combination of laboratory crucible studies with the actual wastes and small melter studies at Clemson with both surrogate and actual wastes. Initial characterization of the B and C Pond sludge had not shown the presence of carbon or fluoride, which required a modified glass formulation be developed to maintain proper glass redox and viscosity. The CNF sludge challenges the glass formulations due to high levels of phosphate and iron. The demonstration was delayed several times by permitting problems, a glass leak, and electrical problems. The demonstration showed that the two wastes could be successfully vitrified, although the design glass production rate was not achieved. The glass produced met the Universal Treatment Standards and the emissions from the TVS were well within the allowable permit limits

  3. Transportable vitrification system demonstration on mixed waste. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Zamecnik, J.R.; Whitehouse, J.C. [Westinghouse Savannah River Co., Aiken, SC (United States); Wilson, C.N. [Lockheed Martin Hanford Corp., Richland, WA (United States); Van Ryn, F.R. [Bechtel Jacobs Co., Oak Ridge, TN (United States)

    1998-04-22

    The Transportable Vitrification System (TVS) is a large scale, fully integrated, vitrification system for the treatment of low-level and mixed wastes in the form of sludges, soils, incinerator ash, and many other waste streams. It was demonstrated on surrogate waste at Clemson University and at the Oak Ridge Reservation (ORR) prior to treating actual mixed waste. Treatment of a combination of dried B and C Pond sludge and CNF sludge was successfully demonstrated at ORR in 1997. The demonstration produced 7,616 kg of glass from 7,328 kg of mixed wastes with a 60% reduction in volume. Glass formulations for the wastes treated were developed using a combination of laboratory crucible studies with the actual wastes and small melter studies at Clemson with both surrogate and actual wastes. Initial characterization of the B and C Pond sludge had not shown the presence of carbon or fluoride, which required a modified glass formulation be developed to maintain proper glass redox and viscosity. The CNF sludge challenges the glass formulations due to high levels of phosphate and iron. The demonstration was delayed several times by permitting problems, a glass leak, and electrical problems. The demonstration showed that the two wastes could be successfully vitrified, although the design glass production rate was not achieved. The glass produced met the Universal Treatment Standards and the emissions from the TVS were well within the allowable permit limits.

  4. Hanford Waste Vitrification Plant - the project and process systems

    International Nuclear Information System (INIS)

    Swenson, L.D.; Miller, W.C.; Smith, R.A.

    1990-01-01

    The Hanford Waste Vitrification Plant (HWVP) project is scheduled to start construction on the Hanford reservation in southeastern Washington State in 1991. The project will immobilize the liquid high-level defense waste stored there. The HWVP represents the third phase of the U.S. Department of Energy (DOE) activities that are focused on the permanent disposal of high-level radioactive waste, building on the experience of Defense Waste Processing Facility (DWPF) at the Savannah River site, South Carolina, and of the West Valley Demonstration Plant (WVDP), New York. This sequential approach to disposal of the country's commercial and defense high-level radioactive waste allows HWVP to make extensive use of lessons learned from the experience of its predecessors, using mature designs from the earlier facilities to achieve economies in design and construction costs while enhancing operational effectiveness

  5. PNL vitrification technology development project glass formulation strategy for LLW vitrification

    International Nuclear Information System (INIS)

    Kim, D.; Hrma, P.R.; Westsik, J.H. Jr.

    1996-03-01

    This Glass Formulation Strategy describes development approaches to optimize glass compositions for Hanford's low-level waste vitrification between now and the projected low-level waste facility start-up in 2005. The objectives of the glass formulation task are to develop optimized glass compositions with satisfactory long-term durability, acceptable processing characteristics, adequate flexibility to handle waste variations, maximize waste loading to practical limits, and to develop methodology to respond to further waste variations

  6. In situ vitrification: Demonstrated capabilities and potential applications

    International Nuclear Information System (INIS)

    Luey, J.K.

    1993-01-01

    A large-scale demonstration of the in situ vitrification (ISV) process was performed in April 1990 on the 116-B-6A Crib in the 100 Area of the Hanford Site in southeastern Washington. The 116-B-6A Crib is a radioactive mixed waste site and was selected to demonstrate the applicability of ISV to soils contaminated with mixed wastes common to many US Department of Energy (DOE) sites. Results from the demonstration show that the ISV process is a viable remediation technology for contaminated soils. The demonstration of the ISV process on an actual contaminated soil site followed research and development efforts by the Pacific Northwest Laboratory (PNL) over the last 10 years. PNL's research has led to the development of the ISV process as a viable remediation technology for contaminated soils and the creation of a commercial supplier of ISV services, Geosafe Corporation. Development efforts for ISV applications other than treatment of contaminated soils, by PNL and in collaboration with Oak Ridge National Laboratory (ORNL) and Idaho National Engineering Laboratory (INEL), show the ISV process has potential applicability for remediating buried waste sites, remediating underground storage tanks, and enabling the placement of subsurface vitrified barriers and engineered structures. This paper discusses the results from the April 1990 large-scale demonstration and provides a general overview of the current capabilities of the ISV process for contaminated soils. In addition, this paper outlines some of the technical issues associated with other ISV applications and provides a qualitative discussion of the level of effort needed to resolve these technical issues

  7. Waste Vitrification Projects Throughout the US Initiated by SRS

    International Nuclear Information System (INIS)

    Jantzen, C.M.; Whitehouse, J.C.; Smith, M.E.; Pickett, J.B.; Peeler, D.K.

    1998-05-01

    Technologies are being developed by the U. S. Department of Energy's (DOE) Nuclear Facility sites to convert high-level, low-level, and mixed wastes to a solid stabilized waste form for permanent disposal. Vitrification is one of the most important and environmentally safest technologies being developed. The Environmental Protection Agency (EPA) has declared vitrification the best demonstrated available technology for high-level radioactive waste and produced a Handbook of Vitrification Technologies for Treatment of Hazardous and Radioactive Waste. The Defense Waste Processing Facility being tested at will soon start vitrifying the high-level waste at. The DOE Office of Technology Development has taken the position that mixed waste needs to be stabilized to the highest level reasonably possible to ensure that the resulting waste forms will meet both current and future regulatory specifications. Vitrification produces durable waste forms at volume reductions up to 97%. Large reductions in volume minimize long-term storage costs making vitrification cost effective on a life cycle basis

  8. Savannah River Site waste vitrification projects initiated throughout the United States: Disposal and recycle options

    International Nuclear Information System (INIS)

    Jantzen, C.M.

    2000-01-01

    A vitrification process was developed and successfully implemented by the US Department of Energy's (DOE) Savannah River Site (SRS) and at the West Valley Nuclear Services (WVNS) to convert high-level liquid nuclear wastes (HLLW) to a solid borosilicate glass for safe long term geologic disposal. Over the last decade, SRS has successfully completed two additional vitrification projects to safely dispose of mixed low level wastes (MLLW) (radioactive and hazardous) at the SRS and at the Oak Ridge Reservation (ORR). The SRS, in conjunction with other laboratories, has also demonstrated that vitrification can be used to dispose of a wide variety of MLLW and low-level wastes (LLW) at the SRS, at ORR, at the Los Alamos National Laboratory (LANL), at Rocky Flats (RF), at the Fernald Environmental Management Project (FEMP), and at the Hanford Waste Vitrification Project (HWVP). The SRS, in conjunction with the Electric Power Research Institute and the National Atomic Energy Commission of Argentina (CNEA), have demonstrated that vitrification can also be used to safely dispose of ion-exchange (IEX) resins and sludges from commercial nuclear reactors. In addition, the SRS has successfully demonstrated that numerous wastes declared hazardous by the US Environmental Protection Agency (EPA) can be vitrified, e.g. mining industry wastes, contaminated harbor sludges, asbestos containing material (ACM), Pb-paint on army tanks and bridges. Once these EPA hazardous wastes are vitrified, the waste glass is rendered non-hazardous allowing these materials to be recycled as glassphalt (glass impregnated asphalt for roads and runways), roofing shingles, glasscrete (glass used as aggregate in concrete), or other uses. Glass is also being used as a medium to transport SRS americium (Am) and curium (Cm) to the Oak Ridge Reservation (ORR) for recycle in the ORR medical source program and use in smoke detectors at an estimated value of $1.5 billion to the general public

  9. Tolerancing requirements for remote handling at the Hanford vitrification project

    International Nuclear Information System (INIS)

    Keenan, R.M.; Bullis, R.E.; Van Katwijk, C.

    1993-01-01

    The Hanford Waste Vitrification Plant is being designed by Fluor Daniel, Inc. with WasteChem Corporation as Fluor Daniel's major subcontractor specializing in vitrification and remote system technologies. United Engineers and Constructors/Catalytic (UE ampersand C) will construct the plant. Westinghouse Hanford Company (WHC) is the Project Integration manager, manager and as the plant operator provides technical direction to the Architect/Engineer team (A/E) and constructor on behalf of the Department of Energy - Richland Field Office. The A/E has developed, in cooperation with UE ampersand C, WHC and DOE, a new and innovative approach to installations of the many remote nozzles and electrical connectors that must be installed to demanding tolerances. This paper summarizes the key elements of the HWVP approach

  10. Hanford Waste Vitrification Plant Project Waste Form Qualification Program Plan

    International Nuclear Information System (INIS)

    Randklev, E.H.

    1993-06-01

    The US Department of Energy has created a waste acceptance process to help guide the overall program for the disposal of high-level nuclear waste in a federal repository. This Waste Form Qualification Program Plan describes the hierarchy of strategies used by the Hanford Waste Vitrification Plant Project to satisfy the waste form qualification obligations of that waste acceptance process. A description of the functional relationship of the participants contributing to completing this objective is provided. The major activities, products, providers, and associated scheduling for implementing the strategies also are presented

  11. Subsurface Planar Vitrification Treatment of Problematic TRU Wastes: Status of a Technology Demonstration Program

    International Nuclear Information System (INIS)

    Morse, M.K.; Nowack, B.R.; Thompson, L.E.

    2006-01-01

    This paper provides a status of the In Situ Transuranic Waste Delineation and Removal Project in which the GeoMelt R Subsurface Planar Vitrification TM (SPV TM ) process is being evaluated for the in situ treatment of burial sites containing remote handled mixed transuranic (TRU) waste. The GeoMelt R SPV TM process was invented and patented by Geosafe Corporation. AMEC holds the exclusive worldwide license to use this technology. The current project is part of a three-phase demonstration program to evaluate the effectiveness of the GeoMelt R SPV TM process to treat waste contained in vertical pipe units (VPUs) and caissons that were used for the disposal of remote handled transuranic wastes located at Hanford's 618-10 and 618-11 burial grounds. This project is being performed for the US Department of Energy (DOE) for use at the Hanford site and other DOE installations. The Phase I evaluation determined that removal and treatment of the 618-10/11 VPUs are beyond what can be safely accomplished using conventional excavation methods. Accordingly, a careful stepwise non-intrusive delineation approach and treatment using the GeoMelt R SPV TM technology, followed by removal, characterization, and disposal of the resulting inert vitrified mass was identified as the preferred alternative. Phase II of the project, which started in July 2004, included a full-scale non-radioactive demonstration of AMEC's GeoMelt R SPV TM process on a mock VPU configured to match the actual VPUs. The non-radioactive demonstration (completed in May 2005) was performed to confirm the approach and design before proceeding to a radioactive ('hot') demonstration on an actual VPU. This demonstration took approximately 130 hours, processed the entire mock VPU, and resulted in a vitrified monolith weighing an estimated 90 tonnes. [1] Plans for a radioactive demonstration on an actual VPU are being developed for CY 2006. In addition to demonstrating GeoMelt R SPV TM , delineation techniques are being

  12. Test Summary Report INEEL Sodium-Bearing Waste Vitrification Demonstration RSM-01-1

    Energy Technology Data Exchange (ETDEWEB)

    Goles, Ronald W.; Perez, Joseph M.; Macisaac, Brett D.; Siemer, Darryl D.; Mccray, John A.

    2001-05-21

    The U.S. Department of Energy's Idaho National Engineering and Environmental Laboratory is storing large amounts of radioactive and mixed wastes. Most of the sodium-bearing wastes have been calcined, but about a million gallons remain uncalcined, and this waste does not meet current regulatory requirements for long-term storage and/or disposal. As a part of the Settlement Agreement between DOE and the State of Idaho, the tanks currently containing SBW are to be taken out of service by December 31, 2012, which requires removing and treatment the remaining SBW. Vitrification is the option for waste disposal that received the highest weighted score against the criteria used. Beginning in FY 2000, the INEEL high-level waste program embarked on a program for technology demonstration and development that would lead to conceptual design of a vitrification facility in the event that vitrification is the preferred alternative for SBW disposal. The Pacific Northwest National Laborator's Research-Scale Melter was used to conduct these initial melter-flowsheet evaluations. Efforts are underway to reduce the volume of waste vitrified, and during the current test, an overall SBW waste volume-reduction factor of 7.6 was achieved.

  13. ''Cold crucible'' vitrification projects for low and high active waste

    International Nuclear Information System (INIS)

    Roux, P.; Jouan, A.

    1998-01-01

    In continuity of the CEA HLW vitrification process experienced for more than 20 years in industrial operations in Cogema reprocessing plants (Marcoule and La Hague), CEA has developed an advanced extended performance cold crucible glass melter to address a wider range of waste like LLW, ILW and in particular waste with very corrosive species or requiring glass with higher elaboration temperature. In the cold crucible melter the bath of molten glass is directly heated by induction while the walls are cooled in order to freeze a protective glass layer. This technology subsequently allows high glass throughput while keeping the flexibility, the maintainability and low secondary waste generation related to a small metallic melter. Its recent use in the glass industry and the thousands of hours of pilot tests performed on inactive surrogates have demonstrated the maturity of this technology and its flexibility of use for processing most of the waste generated at nuclear facilities. SGN has therefore proposed this technology in Italy and Korea and in USA in the frame of the Hanford Privatization phase 1 A feasibility study. Main features of this study but also tests results with Hanford surrogates and active samples are discussed. (author)

  14. Solar renovation demonstration projects

    Energy Technology Data Exchange (ETDEWEB)

    Bruun Joergensen, O [ed.

    1998-10-01

    In the framework of the IEA SHC Programme, a Task on building renovation was initiated, `Task 20, Solar Energy in Building Renovation`. In a part of the task, Subtask C `Design of Solar Renovation Projects`, different solar renovation demonstration projects were developed. The objective of Subtask C was to demonstrate the application of advanced solar renovation concepts on real buildings. This report documents 16 different solar renovation demonstration projects including the design processes of the projects. The projects include the renovation of houses, schools, laboratories, and factories. Several solar techniques were used: building integrated solar collectors, glazed balconies, ventilated solar walls, transparent insulation, second skin facades, daylight elements and photovoltaic systems. These techniques are used in several simple as well as more complex system designs. (au)

  15. Photovoltaic demonstration projects

    Energy Technology Data Exchange (ETDEWEB)

    Kaut, W [Commission of the European Communities, Brussels (Belgium); Gillett, W B; Hacker, R J [Halcrow Gilbert Associates Ltd., Swindon (GB)

    1992-12-31

    This publication, comprising the proceedings of the fifth contractor`s meeting organized by the Commission of the European Communities, Directorate-General for Energy, provides an overview of the photovoltaic demonstration projects which have been supported in the framework of the energy demonstration programme since 1983. It includes reports by each of the contractors who submitted proposals in 1987 and 1988, describing progress within their projects. Projects accepted from earlier calls for proposals and not yet completed were reviewed by a rapporteur and are discussed in the summary section. The results of the performance monitoring of all projects and the lessons drawn from the practical experience of the projects are also presented in the summaries and conclusions. Contractors whose projects were submitted in 1989 were also present at the meeting and contributed to the reported discussions. This proceeding is divided into four sessions (General, Housing, technical presentations, other applications) and 24 papers are offered.

  16. Hanford Waste Vitrification Plant technical background document for best available radionuclide control technology demonstration

    Energy Technology Data Exchange (ETDEWEB)

    Carpenter, A.B.; Skone, S.S.; Rodenhizer, D.G.; Marusich, M.V. (Ebasco Services, Inc., Bellevue, WA (USA))

    1990-10-01

    This report provides the background documentation to support applications for approval to construct and operate new radionuclide emission sources at the Hanford Waste Vitrification Plant (HWVP) near Richland, Washington. The HWVP is required to obtain permits under federal and state statutes for atmospheric discharges of radionuclides. Since these permits must be issued prior to construction of the facility, draft permit applications are being prepared, as well as documentation to support these permits. This report addresses the applicable requirements and demonstrates that the preferred design meets energy, environmental, and economic criteria for Best Available Radionuclide Control Technology (BARCT) at HWVP. 22 refs., 11 figs., 25 tabs.

  17. Hanford Waste Vitrification Plant technical background document for best available radionuclide control technology demonstration

    International Nuclear Information System (INIS)

    Carpenter, A.B.; Skone, S.S.; Rodenhizer, D.G.; Marusich, M.V.

    1990-10-01

    This report provides the background documentation to support applications for approval to construct and operate new radionuclide emission sources at the Hanford Waste Vitrification Plant (HWVP) near Richland, Washington. The HWVP is required to obtain permits under federal and state statutes for atmospheric discharges of radionuclides. Since these permits must be issued prior to construction of the facility, draft permit applications are being prepared, as well as documentation to support these permits. This report addresses the applicable requirements and demonstrates that the preferred design meets energy, environmental, and economic criteria for Best Available Radionuclide Control Technology (BARCT) at HWVP. 22 refs., 11 figs., 25 tabs

  18. Photovoltaic demonstration projects

    Energy Technology Data Exchange (ETDEWEB)

    Gillett, W B; Hacker, R J; Kaut, W [eds.

    1991-01-01

    This book, the proceedings of the fourth PV-Contractors' Meeting organized by the Commission of the European Communities, Directorate-General for Energy, held at Brussels on 21 and 22 November 1989, provides an overview of the photovoltaic demonstration projects which have been supported in the framework of the Energy Demonstration Program since 1983. It includes reports by each of the contractors who submitted proposals in 1983, 1984, 1985 and 1986, describing progress with their projects. Summaries of the discussions held at the meeting, which included contractors whose projects were submitted in 1987, are also presented. The different technologies which are being demonstrated concern the modules, the cabling of the array, structure design, storage strategy and power conditioning. The various applications include desalination, communications, dairy farms, water pumping, and warning systems. Papers have been processed separately for inclusion on the data base.

  19. Photovoltaic demonstration projects 2

    Energy Technology Data Exchange (ETDEWEB)

    Gillett, W B; Hacker, R J [Halcrow (William) and Partners, Swindon (UK); Kaut, W [eds.

    1989-01-01

    This book, the proceedings of the third Photovoltaic Contractors' Meeting organised by the Commission of the European Communities, Directorate-General for Energy provides an overview of the photovoltaic demonstration projects which have been supported by the Energy Directorate of the Commission of the European Communities since 1983. It includes reports by each of the contractors who submitted proposals in 1983, 1984 and 1985, describing progress with their projects. The different technologies which are being demonstrated concern the modules, the cabling of the array, structure design, storage strategy and power conditioning. The various applications include powering of houses, villages, recreation centres, water desalination, communications, dairy farms, water pumping and warning systems. (author).

  20. Oak Ridge National Laboratory West End Treatment Facility simulated sludge vitrification demonstration, Revision 1

    International Nuclear Information System (INIS)

    Cicero, C.A.; Bickford, D.F.; Bennert, D.M.; Overcamp, T.J.

    1994-01-01

    Technologies are being developed by the US Department of Energy's (DOE) Nuclear Facility sites to convert hazardous and mixed wastes to a form suitable for permanent disposal. Vitrification, which has been declared the Best Demonstrated Available Technology for high-level radioactive waste disposal by the EPA, is capable of producing a highly durable wasteform that minimizes disposal volumes through organic destruction, moisture evaporation, and porosity reduction. However, this technology must be demonstrated over a range of waste characteristics, including compositions, chemistries, moistures, and physical characteristics to ensure that it is suitable for hazardous and mixed waste treatment. These wastes are typically wastewater treatment sludges that are categorized as listed wastes due to the process origin or organic solvent content, and usually contain only small amounts of hazardous constituents. The Oak Ridge National Laboratory's (ORNL) West End Treatment Facility's (WETF) sludge is considered on of these representative wastes. The WETF is a liquid waste processing plant that generates sludge from the biodenitrification and precipitation processes. An alternative wasteform is needed since the waste is currently stored in epoxy coated carbon steel tanks, which have a limited life. Since this waste has characteristics that make it suitable for vitrification with a high likelihood of success, it was identified as a suitable candidate by the Mixed Waste Integrated Program (MWIP) for testing at CU. The areas of special interest with this sludge are (1) minimum nitrates, (2) organic destruction, and (3) waste water treatment sludges containing little or no filter aid

  1. Rocky Flats Plant precipitate sludge surrogate vitrification demonstration. Technical Task Plan

    International Nuclear Information System (INIS)

    Cicero, C.A.; Bickford, D.F.; Bennert, D.M.; Overcamp, T.J.

    1994-01-01

    Technologies are being developed by the US Department of Energy's (DOE) Nuclear Facility sites to convert hazardous and mixed wastes to a form suitable for permanent disposal. The preferred disposal method would be one that is capable of consistently producing a durable leach resistant wasteform, while simultaneously minimizing disposal volumes. Vitrification, which has been declared the Best Demonstrated Available Technology (BDAT) for high-level radioactive waste disposal by the EPA, is capable of producing a highly durable wasteform that minimizes disposal volumes through organic destruction, moisture evaporation, and porosity reduction. However, this technology must be demonstrated over a range of waste characteristics, including compositions, chemistries, moistures, and physical characteristics to ensure that it is suitable for hazardous and mixed waste treatment

  2. Smart Grid Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Miller, Craig [National Rural Electric Cooperative Association, Arlington, VA (United States); Carroll, Paul [National Rural Electric Cooperative Association, Arlington, VA (United States); Bell, Abigail [National Rural Electric Cooperative Association, Arlington, VA (United States)

    2015-03-11

    The National Rural Electric Cooperative Association (NRECA) organized the NRECA-U.S. Department of Energy (DOE) Smart Grid Demonstration Project (DE-OE0000222) to install and study a broad range of advanced smart grid technologies in a demonstration that spanned 23 electric cooperatives in 12 states. More than 205,444 pieces of electronic equipment and more than 100,000 minor items (bracket, labels, mounting hardware, fiber optic cable, etc.) were installed to upgrade and enhance the efficiency, reliability, and resiliency of the power networks at the participating co-ops. The objective of this project was to build a path for other electric utilities, and particularly electrical cooperatives, to adopt emerging smart grid technology when it can improve utility operations, thus advancing the co-ops’ familiarity and comfort with such technology. Specifically, the project executed multiple subprojects employing a range of emerging smart grid technologies to test their cost-effectiveness and, where the technology demonstrated value, provided case studies that will enable other electric utilities—particularly electric cooperatives— to use these technologies. NRECA structured the project according to the following three areas: Demonstration of smart grid technology; Advancement of standards to enable the interoperability of components; and Improvement of grid cyber security. We termed these three areas Technology Deployment Study, Interoperability, and Cyber Security. Although the deployment of technology and studying the demonstration projects at coops accounted for the largest portion of the project budget by far, we see our accomplishments in each of the areas as critical to advancing the smart grid. All project deliverables have been published. Technology Deployment Study: The deliverable was a set of 11 single-topic technical reports in areas related to the listed technologies. Each of these reports has already been submitted to DOE, distributed to co-ops, and

  3. Hanford Waste Vitrification Project Building limited scope risk assessment

    International Nuclear Information System (INIS)

    Braun, D.J.; Lindberg, S.E.; Reardon, M.F.; Wilson, G.P.

    1992-10-01

    A limited scope risk assessment was performed on the preliminary design of a high-level waste interim storage facility. The Canister Storage Building (CSB) facility will be built to support remediation at the US Department of Energy Hanford Site in Washington State. The CSB will be part of the support facilities for a high level Hanford Waste Vitrification Plant (HWVP). The limited scope risk assessment is based on a preliminary design which uses forced air circulation systems to move air through the building vault. The current building design calls for natural circulation to move air through the building vault

  4. Tidd PFBC demonstration project

    Energy Technology Data Exchange (ETDEWEB)

    Marrocco, M. [American Electric Power, Columbus, OH (United States)

    1997-12-31

    The Tidd project was one of the first joint government-industry ventures to be approved by the US Department of Energy (DOE) in its Clean Coal Technology Program. In March 1987, DOE signed an agreement with the Ohio Power Company, a subsidiary of American Electric Power, to refurbish the then-idle Tidd plant on the banks of the Ohio River with advanced pressurized fluidized bed technology. Testing ended after 49 months of operation, 100 individual tests, and the generation of more than 500,000 megawatt-hours of electricity. The demonstration plant has met its objectives. The project showed that more than 95 percent of sulfur dioxide pollutants could be removed inside the advanced boiler using the advanced combustion technology, giving future power plants an attractive alternative to expensive, add-on scrubber technology. In addition to its sulfur removal effectiveness, the plant`s sustained periods of steady-state operation boosted its availability significantly above design projections, heightening confidence that pressurized fluidized bed technology will be a reliable, baseload technology for future power plants. The technology also controlled the release of nitrogen oxides to levels well below the allowable limits set by federal air quality standards. It also produced a dry waste product that is much easier to handle than wastes from conventional power plants and will likely have commercial value when produced by future power plants.

  5. In situ vitrification demonstration for the stabilization of buried wastes at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Jacobs, G.K.; Spalding, B.P.; Carter, J.G.; Koegler, S.S.

    1987-01-01

    A demonstration of In Situ Vitrification (ISV) technology for the stabilization of radioactively contaminated soil sites at the Oak Ridge National Laboratory (ORNL) was successfully completed during July 1987. This demonstration is the first application of the ISV process not performed at the Hanford Site, where the technology was developed and patented by Pacific Northwest Laboratory (PNL). The joint ORNL-PNL pilot-scale demonstration was performed on a 3/8-scale trench (2 m deep x 1 m wide x 10 m long) that was constructed to simulate a typical seepage trench used for liquid low-level radioactive waste disposal at ORNL from 1951 to 1966. In the ISV process, electrodes are inserted around a volume of contaminated soil, power is applied to the electrodes, and the entire mass is melted from the surface of the soil down through the contaminated zone, thus making a glassy-to-microcrystalline waste form that incorporates the contaminants. Gases produced during the melting are collected, treated, monitored, and released through an off-gas process trailer. In the ORNL demonstration, a 25-t mass of melted rock approximately 1.2 m thick x 2.1 m wide x 4.9 m long was formed during 110 h of operation that consumed approximately 29 MWh of power. Data obtained on the operational performance of the test and waste-form durability will be used to assess the feasibility of applying the ISV technology to an actual waste trench

  6. In situ vitrification demonstration at Pit 1, Oak Ridge National Laboratory. Volume 1: Results of treatability study

    International Nuclear Information System (INIS)

    Spalding, B.P.; Naney, M.T.; Cline, S.R.; Bogle, M.A.

    1997-12-01

    A treatability study was initiated in October 1993 to apply in situ vitrification (ISV) to at least two segments of Oak Ridge National Laboratory (ORNL) seepage Pit 1 by the end of fiscal year (FY) 1995. This treatability study was later extended to include all of Pit 1 and was performed to support a possible Interim Record of Decision or removal action for closure of one or more of the seepage pits and trenches beginning as early as FY 1997. This treatability study was carried out to establish the field-scale technical performance of ISV for (1) attaining the required depth, nominally 15 ft, to incorporate source contamination within and beneath the pits; (2) demonstrating field capability for the overlap of melt settings which will be necessary to achieve fused, melted segments of the source contamination; (3) demonstrating off-gas handling technology for accommodating and minimizing the volatilization of 137 Cs; (4) demonstrating adequate site characterization techniques to predict ISV melting kinetics, processing temperatures, and product durability; and (5) promoting public acceptance of ISV technology by demonstrating its safety, implementability, site impacts, and air emissions and by coordinating the treatability study within the regulatory closure process. In April 1996 an expulsion of an estimated 10% of the 196 Mg (216 tons) melt body occurred resulting in significant damage to ISV equipment and, ultimately, led to an indefinite suspension of further ISV operations at Pit 1. This report summarizes the technical accomplishments and status of the project in fulfilling these objectives through September 1997

  7. In situ vitrification demonstration at Pit 1, Oak Ridge National Laboratory. Volume 1: Results of treatability study

    Energy Technology Data Exchange (ETDEWEB)

    Spalding, B.P.; Naney, M.T.; Cline, S.R.; Bogle, M.A. [Oak Ridge National Lab., TN (United States). Environmental Sciences Div.; Tixier, J.S. [Pacific Northwest National Lab., Richland, WA (United States)

    1997-12-01

    A treatability study was initiated in October 1993 to apply in situ vitrification (ISV) to at least two segments of Oak Ridge National Laboratory (ORNL) seepage Pit 1 by the end of fiscal year (FY) 1995. This treatability study was later extended to include all of Pit 1 and was performed to support a possible Interim Record of Decision or removal action for closure of one or more of the seepage pits and trenches beginning as early as FY 1997. This treatability study was carried out to establish the field-scale technical performance of ISV for (1) attaining the required depth, nominally 15 ft, to incorporate source contamination within and beneath the pits; (2) demonstrating field capability for the overlap of melt settings which will be necessary to achieve fused, melted segments of the source contamination; (3) demonstrating off-gas handling technology for accommodating and minimizing the volatilization of {sup 137}Cs; (4) demonstrating adequate site characterization techniques to predict ISV melting kinetics, processing temperatures, and product durability; and (5) promoting public acceptance of ISV technology by demonstrating its safety, implementability, site impacts, and air emissions and by coordinating the treatability study within the regulatory closure process. In April 1996 an expulsion of an estimated 10% of the 196 Mg (216 tons) melt body occurred resulting in significant damage to ISV equipment and, ultimately, led to an indefinite suspension of further ISV operations at Pit 1. This report summarizes the technical accomplishments and status of the project in fulfilling these objectives through September 1997.

  8. Dynamic wall demonstration project

    Energy Technology Data Exchange (ETDEWEB)

    Nakatsui, L.; Mayhew, W.

    1990-12-01

    The dynamic wall concept is a ventilation strategy that can be applied to a single family dwelling. With suitable construction, outside air can be admitted through the exterior walls of the house to the interior space to function as ventilation air. The construction and performance monitoring of a demonstration house built to test the dynamic wall concept in Sherwood Park, Alberta, is described. The project had the objectives of demonstrating and assessing the construction methods; determining the cost-effectiveness of the concept in Alberta; analyzing the operation of the dynamic wall system; and determining how other components and systems in the house interact with the dynamic wall. The exterior wall construction consisted of vinyl siding, spun-bonded polyolefin-backed (SBPO) rigid fiberglass sheathing, 38 mm by 89 mm framing, fiberglass batt insulation and 12.7 mm drywall. The mechanical system was designed to operate in the dynamic (negative pressure) mode, however flexibility was provided to allow operation in the static (balanced pressure) mode to permit monitoring of the walls as if they were in a conventional house. The house was monitored by an extensive computerized monitoring system. Dynamic wall operation was dependent on pressure and temperature differentials between indoor and outdoor as well as wind speed and direction. The degree of heat gain was found to be ca 74% of the indoor-outdoor temperature differential. Temperature of incoming dynamic air was significantly affected by solar radiation and measurement of indoor air pollutants found no significant levels. 4 refs., 34 figs., 11 tabs.

  9. Remote maintenance demonstration tests at a pilot plant for high level waste vitrification

    International Nuclear Information System (INIS)

    Selig, M.

    1984-01-01

    The remote maintenance and replacement technique designed for a radioactive vitrification plant have been developed and tested in a full scale handling mockup and in an inactive pilot plants by the Central Engineering Department of the Karlsruhe Nuclear Research Center. As a result of the development work and the tests it has been proved that the remote maintenance technique and remote handling equipment can be used without any technical problems and are suited for application in a radioactive waste vitrification plant

  10. West Valley Demonstration Project annual report

    International Nuclear Information System (INIS)

    1986-01-01

    In FY 1985 the most challenging goal of the Project to date, the start of verification testing of major subsystems of the Vitrification System, was accomplished. Individual testing of subsystems was completed in FY 1985 allowing for the start of integrated testing of all major portions of the Vitrification System. Other accomplishments during this period included completion of cleanup of the first of several former reprocessing cells, the first phase of testing and operation of the system which will solidify low-level liquid wastes and the beginning of construction to support installation of the Supernatant Treatment System which will be used to remove the radioactive fission products from the supernatant

  11. Hanford Waste Vitrification Plant Project advanced conceptual design summary report

    International Nuclear Information System (INIS)

    Anderson, T.D.

    1988-11-01

    The Hanford Waste Vitrification Plant (HWVP) will immobilize Hanford defense liquid high-level waste in borosilicate glass in preparation for shipment to a geologic repository. The shipment of the waste to the repository will satisfy an objective in the President's Defense Waste Management Plan. The glass product will be cast into stainless steel canisters, which will be sealed and stored at Hanford until they are shipped. This document summarizes work performed during the Advance Conceptual Design (ACD) of the HWVP. In the Reference Conceptual Design phase, which preceded the ACD, a number of design issues were identified with the potential to improve cost effectiveness, safety, constructibility, and operability. The ACD addressed and evaluated these design issues. Implementation of recommendations derived from ACD work will occur in subsequent design phases. The next design phase is preliminary design which will be followed by detailed design and construction. Net potential cost improvements of more than $36.9M were identified along with improvements in safety, constructibility, and operability. No negative schedule impacts will result from implementation of the improvements. 11 refs., 5 figs., 3 tabs

  12. Vitrification of highly-loaded SDS zeolites

    International Nuclear Information System (INIS)

    Siemens, D.H.; Bryan, G.H.; Knowlton, D.E.; Knox, C.A.

    1982-11-01

    Pacific Northwest Laboratory (PNL) is demonstrating a vitrification system designed for immobilization of highly loaded SDS zeolites. The Zeolite Vitrification Demonstration Project (ZVDP) utilizes an in-can melting process. All steps of the process have been demonstrated, from receipt of the liners through characterization of the vitrified product. The system has been tested with both nonradioactive and radioactive zeolite material. Additional high-radioactivity demonstrations are scheduled to begin in FY-83. 5 figures, 4 tables

  13. A pilot plant demonstration of the vitrification of radioactive solutions using microwave power

    International Nuclear Information System (INIS)

    Morrell, M.S.; Hardwick, W.H.; Murphy, V.; Wace, P.F.

    1986-01-01

    A process has been developed that exploits the characteristics of microwave heating for the vitrification of high-level radioactive liquid waste. This process, microwave vitrification, has been successfully operated at pilot plant scale in an active cell using simulated liquid waste containing several curies of radioactivity. Excellent decontamination factors have been achieved for both volatiles and nonvolatiles with an average ruthenium decontamination factor of 490 and a gross alpha emitter decontamination factor of 100,000. Almost all the radioactivity is incorporated in a glass block

  14. Demonstrating compliance with WAPS 1.3 in the Hanford waste vitrification plant process

    Energy Technology Data Exchange (ETDEWEB)

    Bryan, M.F.; Piepel, G.F.; Simpson, D.B.

    1996-03-01

    The high-level waste (HLW) vitrification plant at the Hanford Site was being designed to immobilize transuranic and high-level radioactive waste in borosilicate glass. This document describes the statistical procedure to be used in verifying compliance with requirements imposed by Section 1.3 of the Waste Acceptance Product Specifications (WAPS, USDOE 1993). WAPS 1.3 is a specification for ``product consistency,`` as measured by the Product Consistency Test (PCT, Jantzen 1992b), for each of three elements: lithium, sodium, and boron. Properties of a process batch and the resulting glass are largely determined by the composition of the feed material. Empirical models are being developed to estimate some property values, including PCT results, from data on feed composition. These models will be used in conjunction with measurements of feed composition to control the HLW vitrification process and product.

  15. Hanford Waste Vitrification Plant technical background document for toxics best available control technology demonstration

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-10-01

    This document provides information on toxic air pollutant emissions to support the Notice of Construction for the proposed Hanford Waste Vitrification Plant (HWVP) to be built at the the Department of Energy Hanford Site near Richland, Washington. Because approval must be received prior to initiating construction of the facility, state and federal Clean Air Act Notices of construction are being prepared along with necessary support documentation.

  16. Hanford Waste Vitrification Plant technical background document for toxics best available control technology demonstration

    International Nuclear Information System (INIS)

    1992-10-01

    This document provides information on toxic air pollutant emissions to support the Notice of Construction for the proposed Hanford Waste Vitrification Plant (HWVP) to be built at the the Department of Energy Hanford Site near Richland, Washington. Because approval must be received prior to initiating construction of the facility, state and federal Clean Air Act Notices of construction are being prepared along with necessary support documentation

  17. Low-Level Waste Vitrification Plant Project contracting strategy decision analysis report

    Energy Technology Data Exchange (ETDEWEB)

    Felise, P.; Phillips, J.D.

    1994-10-17

    Ten basic contracting strategies were developed after a review of past strategies that had been used at the Hanford Site, other US Department of Energy (DOE) sites, other US government agencies, and in the private sector. As applicable to the Low-Level Waste Vitrification Plant (LLWVP) Project, each strategy was described and depicted in a schedule format to assess compatibility with the Hanford Federal Facility Agreement and Consent Order, al so known as the Tri-Party Agreement (Ecology et al. 1994) milestones, key decision points, and other project requirements. The-pro and con aspects of each strategy also were tabulated. Using this information as a basis, the LLWVP Project team members, along with representatives of Tank Waste Remediation System (TWRS) Engineering, TWRS Programs, and Procurement Materials Management, formed a Westinghouse Hanford Company (WHC) evaluation team to select the best strategy. Kepner-Tregoe decision analysis techniques were used in facilitated meetings to arrive at the best balanced choice.

  18. Low-Level Waste Vitrification Plant Project contracting strategy decision analysis report

    International Nuclear Information System (INIS)

    Felise, P.; Phillips, J.D.

    1994-01-01

    Ten basic contracting strategies were developed after a review of past strategies that had been used at the Hanford Site, other US Department of Energy (DOE) sites, other US government agencies, and in the private sector. As applicable to the Low-Level Waste Vitrification Plant (LLWVP) Project, each strategy was described and depicted in a schedule format to assess compatibility with the Hanford Federal Facility Agreement and Consent Order, al so known as the Tri-Party Agreement (Ecology et al. 1994) milestones, key decision points, and other project requirements. The-pro and con aspects of each strategy also were tabulated. Using this information as a basis, the LLWVP Project team members, along with representatives of Tank Waste Remediation System (TWRS) Engineering, TWRS Programs, and Procurement Materials Management, formed a Westinghouse Hanford Company (WHC) evaluation team to select the best strategy. Kepner-Tregoe decision analysis techniques were used in facilitated meetings to arrive at the best balanced choice

  19. Earth Science Capability Demonstration Project

    Science.gov (United States)

    Cobleigh, Brent

    2006-01-01

    A viewgraph presentation reviewing the Earth Science Capability Demonstration Project is shown. The contents include: 1) ESCD Project; 2) Available Flight Assets; 3) Ikhana Procurement; 4) GCS Layout; 5) Baseline Predator B Architecture; 6) Ikhana Architecture; 7) UAV Capability Assessment; 8) The Big Picture; 9) NASA/NOAA UAV Demo (5/05 to 9/05); 10) NASA/USFS Western States Fire Mission (8/06); and 11) Suborbital Telepresence.

  20. Alderney 5 complex demonstration project

    Energy Technology Data Exchange (ETDEWEB)

    Stewart, D. [High Performance Energy Systems, Halifax, NS (Canada)

    2008-07-01

    The Halifax Regional Municipality (HRM) is the largest municipality in Atlantic Canada. This presentation described the flagship facility and the energy efficiency retrofit of five HRM-owned buildings called the Alderney 5 complex. The 5 objectives of the demonstration project involved a district-scale cooling project; replacement of chillers with harbour cooling; and replacement of a high exergy system with a low exergy system. Synergies and challenges of the project were also identified. The presentation also referred to borehole thermal energy storage; existing Halifax Harbour cooling; Halifax Harbour temperatures; cold energy geothermal borehole field; and the benefits of advanced concentric boreholes. A project update and progress to date were also provided. The Alderney 5 project represents the first concentric borehole technology for use to store and retrieve cold energy. tabs., figs.

  1. Test Summary Report Vitrification Demonstration of an Optimized Hanford C-106/AY-102 Waste-Glass Formulation

    International Nuclear Information System (INIS)

    Goles, Ronald W.; Buchmiller, William C.; Hymas, Charles R.; MacIsaac, Brett D.

    2002-01-01

    In order to further the goal of optimizing Hanford?s HLW borosilicate flowsheet, a glass formulation effort was launched to develop an advanced high-capacity waste form exhibiting acceptable leach and crystal formation characteristics. A simulated C-106/AY-102 waste envelop inclusive of LAW pretreatment products was chosen as the subject of these nonradioactive optimization efforts. To evaluate this optimized borosilicate waste formulation under continuous dynamic vitrification conditions, a research-scale Joule-heated ceramic melter was used to demonstrate the advanced waste form?s flowsheet. The main objectives of this melter test was to evaluate (1) the processing characteristics of the newly formulated C-106/AY-102 surrogate melter-feed stream, (2) the effectiveness of sucrose as a glass-oxidation-state modifier, and (3) the impact of this reductant upon processing rates

  2. Plasma hearth process demonstration project

    International Nuclear Information System (INIS)

    Geimer, R.M.; Gillins, R.L.

    1995-01-01

    The Plasma Hearth Process (PHP) demonstration project is one of the key technology projects in the US Department of Energy (DOE) Office of Technology Development Mixed Waste Focus Area. The PHP is a high temperature thermal treatment process using a plasma arc torch in a stationary, refractory lined chamber that destroys organics and stabilizes the residuals in a nonleaching, vitrified waste form, greatly improving the disposability of the waste. This paper describes the PHP system and summarizes test results to date, including volume reduction, destruction and removal efficiencies for organic wastes, and emission characteristics. Tests performed so far demonstrate that the PHP adresses DOE mixed waste final waste form requirements and US Environmental Protection Agency Toxicity Characteristic Leaching Procedure requirements

  3. West Valley Demonstration Project annual report to Congress

    International Nuclear Information System (INIS)

    1990-01-01

    By the end of the fiscal year, the West Valley Demonstration Project had processed 757,000 litres of liquid high-level waste, removing most of the radioactive constituents by ion exchange. The radioactive ion exchange material is being stored in an underground tank pending its incorporation, along with sludge still in the tank, into borosilicate glass. The decontaminated salt solution was solidified into a cement low-level waste form which has been reviewed and endorsed by the Nuclear Regulatory Commission. Five tests of the waste glass melter system were completed. A Notice of Intent was published to prepare a joint federal/state Environmental Impact Statement. Design of the Vitrification Facility, a major milestone, was completed and construction of the facility enclosure has begun. A Department of Energy Tiger Team and Technical Safety Appraisal of the Project found no undue risks to worker or public health and safety or the environment

  4. Prototypical Rod Consolidation Demonstration Project

    International Nuclear Information System (INIS)

    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

  5. Clean Coal Diesel Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Robert Wilson

    2006-10-31

    A Clean Coal Diesel project was undertaken to demonstrate a new Clean Coal Technology that offers technical, economic and environmental advantages over conventional power generating methods. This innovative technology (developed to the prototype stage in an earlier DOE project completed in 1992) enables utilization of pre-processed clean coal fuel in large-bore, medium-speed, diesel engines. The diesel engines are conventional modern engines in many respects, except they are specially fitted with hardened parts to be compatible with the traces of abrasive ash in the coal-slurry fuel. Industrial and Municipal power generating applications in the 10 to 100 megawatt size range are the target applications. There are hundreds of such reciprocating engine power-plants operating throughout the world today on natural gas and/or heavy fuel oil.

  6. Final Report for the Demonstration of Plasma In-situ Vitrification at the 904-65G K-Reactor Seepage Basin

    Energy Technology Data Exchange (ETDEWEB)

    Blundy, R.F. [Westinghouse Savannah River Company, AIKEN, SC (United States); Zionkowki, P.G.

    1997-12-22

    The In-situ Vitrification (ISV) process potentially offers the most stable waste-form for containment of radiologically contaminated soils while minimizing personnel contamination. This is a problem that is extensive, and at the same time unique, to the US Department of Energy`s (DOE) Weapons Complex. An earlier ISV process utilized joule heating of the soil to generate the subsurface molten glass product. However previous test work has indicated that the Savannah river Site soils (SRS) may not be entirely suitable for vitrification by joule heating due to their highly refractory nature. The concept of utilizing a plasma torch for soil remediation by in-situ vitrification has recently been developed, and laboratory test work on a 100 kW unit has indicated a potentially successful application with SRS soils. The Environmental Restoration Division (ERD) of Westinghouse Savannah River Company (WSRC) conducted the first field scale demonstration of this process at the (904-65G) K-Reactor Seepage Basin in October 1996 with the intention of determining the applicability and economics of the process for remediation of a SRS radioactive seepage basin. The demonstration was successful in completing three vitrification runs, including two consecutive runs that fused together adjacent columns of glass to form a continuous monolith. This report describes the demonstration, documents the engineering data that was obtained, summarizes the process economics and makes recommendations for future development of the process and equipment.

  7. Final Report for the Demonstration of Plasma In-situ Vitrification at the 904-65G K-Reactor Seepage Basin

    International Nuclear Information System (INIS)

    Blundy, R.F.; Zionkowki, P.G.

    1997-01-01

    The In-situ Vitrification (ISV) process potentially offers the most stable waste-form for containment of radiologically contaminated soils while minimizing personnel contamination. This is a problem that is extensive, and at the same time unique, to the US Department of Energy's (DOE) Weapons Complex. An earlier ISV process utilized joule heating of the soil to generate the subsurface molten glass product. However previous test work has indicated that the Savannah river Site soils (SRS) may not be entirely suitable for vitrification by joule heating due to their highly refractory nature. The concept of utilizing a plasma torch for soil remediation by in-situ vitrification has recently been developed, and laboratory test work on a 100 kW unit has indicated a potentially successful application with SRS soils. The Environmental Restoration Division (ERD) of Westinghouse Savannah River Company (WSRC) conducted the first field scale demonstration of this process at the (904-65G) K-Reactor Seepage Basin in October 1996 with the intention of determining the applicability and economics of the process for remediation of a SRS radioactive seepage basin. The demonstration was successful in completing three vitrification runs, including two consecutive runs that fused together adjacent columns of glass to form a continuous monolith. This report describes the demonstration, documents the engineering data that was obtained, summarizes the process economics and makes recommendations for future development of the process and equipment

  8. Exploration Medical System Demonstration Project

    Science.gov (United States)

    Chin, D. A.; McGrath, T. L.; Reyna, B.; Watkins, S. D.

    2011-01-01

    A near-Earth Asteroid (NEA) mission will present significant new challenges including hazards to crew health created by exploring a beyond low earth orbit destination, traversing the terrain of asteroid surfaces, and the effects of variable gravity environments. Limited communications with ground-based personnel for diagnosis and consultation of medical events require increased crew autonomy when diagnosing conditions, creating treatment plans, and executing procedures. Scope: The Exploration Medical System Demonstration (EMSD) project will be a test bed on the International Space Station (ISS) to show an end-to-end medical system assisting the Crew Medical Officers (CMO) in optimizing medical care delivery and medical data management during a mission. NEA medical care challenges include resource and resupply constraints limiting the extent to which medical conditions can be treated, inability to evacuate to Earth during many mission phases, and rendering of medical care by a non-clinician. The system demonstrates the integration of medical technologies and medical informatics tools for managing evidence and decision making. Project Objectives: The objectives of the EMSD project are to: a) Reduce and possibly eliminate the time required for a crewmember and ground personnel to manage medical data from one application to another. b) Demonstrate crewmember's ability to access medical data/information via a software solution to assist/aid in the treatment of a medical condition. c) Develop a common data management architecture that can be ubiquitously used to automate repetitive data collection, management, and communications tasks for all crew health and life sciences activities. d) Develop a common data management architecture that allows for scalability, extensibility, and interoperability of data sources and data users. e) Lower total cost of ownership for development and sustainment of peripheral hardware and software that use EMSD for data management f) Provide

  9. Dynamic Underground Stripping Demonstration Project

    International Nuclear Information System (INIS)

    Aines, R.; Newmark, R.; McConachie, W.; Rice, D.; Ramirez, A.; Siegel, W.; Buettner, M.; Daily, W.; Krauter, P.; Folsom, E.; Boegel, A.J.; Bishop, D.; udel, K.

    1992-03-01

    LLNL is collaborating with the UC Berkeley College of Engineering to develop and demonstrate a system of thermal remediation and underground imaging techniques for use in rapid cleanup of localized underground spills. Called ''Dynamic Stripping'' to reflect the rapid and controllable nature of the process, it will combine steam injection, direct electrical heating, and tomographic geophysical imaging in a cleanup of the LLNL gasoline spill. In the first 8 months of the project, a Clean Site engineering test was conducted to prove the field application of the techniques before moving to the contaminated site in FY 92

  10. Prototypical Rod Consolidation Demonstration Project

    International Nuclear Information System (INIS)

    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 2 discusses the following topics: Fuel Rod Extraction System Test Results and Analysis Reports and Clamping Table Test Results and Analysis Reports

  11. Prototypical Rod Consolidation Demonstration Project

    International Nuclear Information System (INIS)

    1993-05-01

    The objective of Phase III 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 II 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 III effort the system was tested on a component, subsystem, and system level. Volume IV provides the Operating and Maintenance Manual for the Prototypical Rod Consolidation System that was installed at the Cold Test Facility. This document, Book 1 of Volume IV, discusses: Process overview functional descriptions; Control system descriptions; Support system descriptions; Maintenance system descriptions; and Process equipment descriptions

  12. Prototypical Rod Consolidation Demonstration Project

    International Nuclear Information System (INIS)

    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 9 discusses the following topics: Integrated System Normal Operations Test Results and Analysis Report; Integrated System Off-Normal Operations Test Results and Analysis Report; and Integrated System Maintenance Operations Test Results and Analysis Report

  13. Prototypical Rod Consolidation Demonstration Project

    International Nuclear Information System (INIS)

    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 8 discusses Control System SOT Tests Results and Analysis Report. This is a continuation of Book 7

  14. Prototypical Rod Construction Demonstration Project

    International Nuclear Information System (INIS)

    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 3 discusses the following topics: Downender Test Results and Analysis Report; NFBC Canister Upender Test Results and Analysis Report; Fuel Assembly Handling Fixture Test Results and Analysis Report; and Fuel Canister Upender Test Results and Analysis Report

  15. Prototypical Rod Consolidation Demonstration Project

    International Nuclear Information System (INIS)

    1993-05-01

    The objective of Phase III 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 II 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 III effort the system was tested on a component, subsystem, and system level. Volume IV provides the Operating and Maintenance Manual for the Prototypical Rod Consolidation System that was installed at the Cold Test Facility. This document, Book 4 of Volume IV, discusses: Off-normal operating and recovery procedures; Emergency response procedures; Troubleshooting procedures; and Preventive maintenance procedures

  16. Processing the THOREX waste at the West Valley demonstration project

    International Nuclear Information System (INIS)

    Barnes, S.M.; Schiffhauer, M.A.

    1994-01-01

    This paper focuses on several options for neutralizing the THOREX and combining it with the PUREX wastes. Neutralization testing with simulated wastes (nonradioactive chemicals) was performed to evaluate the neutralization reactions and the reaction product generation. Various methods for neutralizing the THOREX solution were examined to determine their advantages and disadvantages relative to the overall project objectives and compatibility with the existing process. The primary neutralization process selection criteria were safety and minimizing the potential delays prior to vitrification. The THOREX neutralization method selected was direct addition to the high pH PUREX wastes within Tank 8D-2. Laboratory testing with simulated waste has demonstrated rapid neutralization of the THOREX waste acid. Test results for various direct addition scenarios has established the optimum process operating conditions which provide the largest safety margins

  17. Vitrification melter study

    International Nuclear Information System (INIS)

    Jones, J.A.

    1995-04-01

    This report presents the results of a study performed to identify the most promising vitrification melter technologies that the Department of Energy (EM-50) might pursue with available funding. The primary focus was on plasma arc systems and graphite arc melters. The study was also intended to assist EM-50 in evaluating competing technologies, formulating effective technology strategy, developing focused technology development projects, and directing the work of contractors involved in vitrification melter development

  18. Prototypical Rod Consolidation Demonstration Project

    International Nuclear Information System (INIS)

    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 4 discusses the following topics: Rod Compaction/Loading System Test Results and Analysis Report; Waste Collection System Test Results and Analysis Report; Waste Container Transfer Fixture Test Results and Analysis Report; Staging and Cutting Table Test Results and Analysis Report; and Upper Cutting System Test Results and Analysis Report

  19. Dynamic underground stripping demonstration project

    International Nuclear Information System (INIS)

    Newmark, R.L.

    1992-04-01

    LLNL is collaborating with the UC Berkeley College of Engineering to develop and demonstrate a system of thermal remediation techniques for rapid cleanup of localized underground spills. Called dynamic stripping to reflect the rapid and controllable nature of the process, it will combine steam injection, direct electrical heating, and tomographic geophysical imaging in a cleanup of the LLNL gasoline spill. In the first eight months of the project, a Clean Site engineering test was conducted to prove the field application of the techniques. Tests then began on the contaminated site in FY 1992. This report describes the work at the Clean Site, including design and performance criteria, test results, interpretations, and conclusions. We fielded 'a wide range of new designs and techniques, some successful and some not. In this document, we focus on results and performance, lessons learned, and design and operational changes recommended for work at the contaminated site. Each section focuses on a different aspect of the work and can be considered a self-contained contribution

  20. Prototypical Rod Consolidation Demonstration Project

    International Nuclear Information System (INIS)

    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 5 discusses the following topics: Lower Cutting System Test Results and Analysis Report; NFBC Loading System Test Results and Analysis Report; Robotic Bridge Transporter Test Results and Analysis Report; RM-10A Remotec Manipulator Test Results and Analysis Report; and Manipulator Transporter Test Results and Analysis Report

  1. Vitrification Facility integrated system performance testing report

    International Nuclear Information System (INIS)

    Elliott, D.

    1997-01-01

    This report provides a summary of component and system performance testing associated with the Vitrification Facility (VF) following construction turnover. The VF at the West Valley Demonstration Project (WVDP) was designed to convert stored radioactive waste into a stable glass form for eventual disposal in a federal repository. Following an initial Functional and Checkout Testing of Systems (FACTS) Program and subsequent conversion of test stand equipment into the final VF, a testing program was executed to demonstrate successful performance of the components, subsystems, and systems that make up the vitrification process. Systems were started up and brought on line as construction was completed, until integrated system operation could be demonstrated to produce borosilicate glass using nonradioactive waste simulant. Integrated system testing and operation culminated with a successful Operational Readiness Review (ORR) and Department of Energy (DOE) approval to initiate vitrification of high-level waste (HLW) on June 19, 1996. Performance and integrated operational test runs conducted during the test program provided a means for critical examination, observation, and evaluation of the vitrification system. Test data taken for each Test Instruction Procedure (TIP) was used to evaluate component performance against system design and acceptance criteria, while test observations were used to correct, modify, or improve system operation. This process was critical in establishing operating conditions for the entire vitrification process

  2. Readiness review plan for the in situ vitrification demonstration of Seepage Pit 1 in Waste Area Grouping 7

    International Nuclear Information System (INIS)

    1995-05-01

    A treatability study is planned that encompasses the application of in situ vitrification (ISV) to at least two segments of the Oak Ridge National Laboratory Seepage Pit I during the third quarter of fiscal year 1995. Before the treatability study can be initiated, the proposed activity must be subjected to an Operational Readiness Review (ORR). ORR is a structured methodology of determining readiness to proceed as outlined in Martin Marietta Energy Systems, Inc. (Energy Systems), Environmental Restoration Waste Management Procedure ER/C-P1610, which provides Energy Systems organizations assurance that the work to be performed is consistent with management's expectations and that the subject activity is ready to proceed safely. The readiness review plan provides details of the review plan overview and the scope of work to be performed. The plan also identifies individuals and position responsibilities for implementing the activity. The management appointed Readiness Review Board (RRB) has been identified. A Field Readiness Review Team (FRT), a management appointed multidisciplinary group, has been established (1) to evaluate the ISV treatability study, (2) to identify and assemble supporting objective evidences of the readiness to proceed, and (3) to assist the team leader in presenting the evidences to the RRB. A major component of RRB is the formulation of readiness review criteria months before the operation. A comprehensive readiness review tree (a positive logic tree) is included, which identifies the activities required for the development of the readiness criteria. The readiness review tree serves as a tool to prevent the omission of an item that could affect system performance. All deficiencies identified in the review will be determined as prestart findings and must be resolved before the project is permitted to proceed. The final approval of the readiness to proceed will be the decision of RRB

  3. The integrated melter off-gas treatment systems at the West Valley Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Vance, R.F. [West Valley Nuclear Services Co., Inc., NY (United States)

    1995-02-01

    The West Valley Demonstration Project was established by Public Law 96-368, the {open_quotes}West Valley Demonstration Project Act, {close_quotes} on October 1, l980. Under this act, Congress directed the Department of Energy to carry out a high level radioactive waste management demonstration project at the Western New York Nuclear Service Center in West Valley, New York. The purpose of this project is to demonstrate solidification techniques which can be used for preparing high level radioactive waste for disposal. In addition to developing this technology, the West Valley Demonstration Project Act directs the Department of Energy to: (1) develop containers suitable for permanent disposal of the high level waste; (2) transport the solidified high level waste to a Federal repository; (3) dispose of low level and transuranic waste produced under the project; and (4) decontaminate and decommission the facilities and materials associated with project activities and the storage tanks originally used to store the liquid high level radioactive waste. The process of vitrification will be used to solidify the high level radioactive liquid wastes into borosilicate glass. This report describes the functions, the controlling design criteria, and the resulting design of the melter off-gas treatment systems which are used in the vitrification process.

  4. Small-scale integrated demonstration of high-level radioactive waste processing and vitrification using actual SRP waste

    International Nuclear Information System (INIS)

    Woolsey, G.B.; Baumgarten, P.K.; Eibling, R.E.; Ferguson, R.B.

    1981-01-01

    A small-scale pilot plant for chemical processing and vitrification of actual high-level waste has been constructed at the Savannah River Laboratory (SRL). This fully integrated facility has been constructed in six shielded cells and has eight major unit operations. Equipment performance and processing characteristics of the unit operations are reported

  5. Engineered Geothermal System Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Petty, Susan

    2014-06-19

    In June 2009, AltaRock Energy began field work on a project supported by the U.S. Department of Energy entitled “Use of Multiple Stimulations to Improve Economics of Engineered Geothermal Systems in Shallow High Temperature Intrusives.” The goal of the project was to develop an Engineered Geothermal System (EGS) in the portion of The Geysers geothermal field operated by the Northern California Power Agency (NCPA). The project encountered several problems while deepening Well E-7 which culminated in the suspension of field activities in September 2009. Some of the problems encountered are particular to The Geysers area, while others might be encountered in any geothermal field, and they might be avoided in future operations.

  6. Vehicle to Grid Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Willett Kempton; Meryl Gardner; Michael Hidrue; Fouad Kamilev; Sachin Kamboj; Jon Lilley; Rodney McGee; George Parsons; Nat Pearre; Keith Trnka

    2010-12-31

    This report summarizes the activities and accomplishments of a two-year DOE-funded project on Grid-Integrated Vehicles (GIV) with vehicle to grid power (V2G). The project included several research and development components: an analysis of US driving patterns; an analysis of the market for EVs and V2G-capable EVs; development and testing of GIV components (in-car and in-EVSE); interconnect law and policy; and development and filing of patents. In addition, development activities included GIV manufacturing and licensing of technologies developed under this grant. Also, five vehicles were built and deployed, four for the fleet of the State of Delaware, plus one for the University of Delaware fleet.

  7. DOE's annealing prototype demonstration projects

    International Nuclear Information System (INIS)

    Warren, J.; Nakos, J.; Rochau, G.

    1997-01-01

    One of the challenges U.S. utilities face in addressing technical issues associated with the aging of nuclear power plants is the long-term effect of plant operation on reactor pressure vessels (RPVs). As a nuclear plant operates, its RPV is exposed to neutrons. For certain plants, this neutron exposure can cause embrittlement of some of the RPV welds which can shorten the useful life of the RPV. This RPV embrittlement issue has the potential to affect the continued operation of a number of operating U.S. pressurized water reactor (PWR) plants. However, RPV material properties affected by long-term irradiation are recoverable through a thermal annealing treatment of the RPV. Although a dozen Russian-designed RPVs and several U.S. military vessels have been successfully annealed, U.S. utilities have stated that a successful annealing demonstration of a U.S. RPV is a prerequisite for annealing a licensed U.S. nuclear power plant. In May 1995, the Department of Energy's Sandia National Laboratories awarded two cost-shared contracts to evaluate the feasibility of annealing U.S. licensed plants by conducting an anneal of an installed RPV using two different heating technologies. The contracts were awarded to the American Society of Mechanical Engineers (ASME) Center for Research and Technology Development (CRTD) and MPR Associates (MPR). The ASME team completed its annealing prototype demonstration in July 1996, using an indirect gas furnace at the uncompleted Public Service of Indiana's Marble Hill nuclear power plant. The MPR team's annealing prototype demonstration was scheduled to be completed in early 1997, using a direct heat electrical furnace at the uncompleted Consumers Power Company's nuclear power plant at Midland, Michigan. This paper describes the Department's annealing prototype demonstration goals and objectives; the tasks, deliverables, and results to date for each annealing prototype demonstration; and the remaining annealing technology challenges

  8. 40 CFR 117.14 - Demonstration projects.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 21 2010-07-01 2010-07-01 false Demonstration projects. 117.14 Section... DETERMINATION OF REPORTABLE QUANTITIES FOR HAZARDOUS SUBSTANCES Applicability § 117.14 Demonstration projects... research or demonstration projects relating to the prevention, control, or abatement of hazardous substance...

  9. Photovoltaic demonstration project. Final report

    International Nuclear Information System (INIS)

    Jicarilla Apache Tribe

    2002-01-01

    The Jicarilla Apache Nation is in Rio Arriba County in North Central New Mexico. The photovoltaic project was installed at the Dulce High School in the town of Dulce. Dulce is in the most northern part of the reservation near the New Mexico/Colorado boundary and can be reached from the New Mexico State Capitol in Santa Fe, hence to the town of Chama along U.S. Highway 84 to the junction of U.S. Highway 64. Dulce is about 12 miles west of the junction along U.S. Highway 64. Dulce community is in the mountainous part of the Nation with a population of about 4000. No industry exists in the community, however, a few commercial sites do exist such as a motel, restaurants, gas stations, food and liquor stores

  10. Navy fuel cell demonstration project.

    Energy Technology Data Exchange (ETDEWEB)

    Black, Billy D.; Akhil, Abbas Ali

    2008-08-01

    This is the final report on a field evaluation by the Department of the Navy of twenty 5-kW PEM fuel cells carried out during 2004 and 2005 at five Navy sites located in New York, California, and Hawaii. The key objective of the effort was to obtain an engineering assessment of their military applications. Particular issues of interest were fuel cell cost, performance, reliability, and the readiness of commercial fuel cells for use as a standalone (grid-independent) power option. Two corollary objectives of the demonstration were to promote technological advances and to improve fuel performance and reliability. From a cost perspective, the capital cost of PEM fuel cells at this stage of their development is high compared to other power generation technologies. Sandia National Laboratories technical recommendation to the Navy is to remain involved in evaluating successive generations of this technology, particularly in locations with greater environmental extremes, and it encourages their increased use by the Navy.

  11. Modern methods of project handling - lean management during the deconstruction of nuclear facilities as illustrated by the vitrification plant VEK

    International Nuclear Information System (INIS)

    Freund, Christina; Gentes, Sascha; Dux, Joachim; Reinelt, Joachim

    2011-01-01

    The authors describe the positive experiences from the project handling during the WAK deconstruction process including the implementation of the so called lean management that is supposed to optimize the timing and cost specific approaches. The practical application includes the planning, the licensing application and in case of licensing the realization of the project. Enhancement of transparency and information flow are reached by periodic last planner sessions. Time management and exact scheduling are central parts of the project handling. The contract partners, authorities and consultants are involved at an early state of the project. After shutdown of the vitrification plant VEK the planning for the deconstruction licensing application according to the atomic law have been started.

  12. West Valley Demonstration Project, West Valley, New York: Annual report

    International Nuclear Information System (INIS)

    1989-01-01

    Under the West Valley Demonstration Project Act, Public Law 96-368, liquid high-level radioactive waste stored at the Western New York Nuclear Services Center, West Valley, New York, that resulted from spent nuclear fuel reprocessing operations conducted between 1966 and 1972, is to be solidified in borosilicate glass and transported to a federal repository for geologic disposal. A major milestone was reached in May 1988 when the Project began reducing the volume of the liquid high-level waste. By the end of 1988, approximately 15 percent of the initial inventory had been processed into two waste streams. The decontaminated low-level liquid waste is being solidified in cement. The high-level waste stream is being stored in an underground tank pending its incorporation into borosilicate glass. Four tests of the waste glass melter system were completed. These tests confirmed equipment operability, control system reliability, and provided samples of waste glass for durability testing. In mid-1988, the Department validated an integrated cost and schedule plan for activities required to complete the production of the waste borosilicate glass. Design of the radioactive Vitrification Facility continued

  13. Evaluation of rubber modified asphalt demonstration projects

    Energy Technology Data Exchange (ETDEWEB)

    1994-01-01

    As part of the Ontario Government's medium-term scrap tire management strategy, 11 rubber modified asphalt demonstration projects were funded or completed, with 13 additional projects from small to large (1,500-65,000 passenger tire equivalents) approved for the 1993 paving season. This report presents the results of an August to November 1993 study of the 11 demonstration projects. The evaluation included a description of the technology; technical review of the projects; economic analysis; review of the environmental literature; environmental review of the projects; comparison of the projects with similar ones in other jurisdictions; and recommendations. Detailed information on asphalt technology is included in an appendix.

  14. Engineering-scale vitrification of commercial high-level waste

    International Nuclear Information System (INIS)

    Bonner, W.F.; Bjorklund, W.J.; Hanson, M.S.; Knowlton, D.E.

    1980-04-01

    To date, technology for immobilizing commercial high-level waste (HLW) has been extensively developed, and two major demonstration projects have been completed, the Waste Solidification Engineering Prototypes (WSEP) Program and the Nuclear Waste Vitrification Project (NWVP). The feasibility of radioactive waste solidification was demonstrated in the WSEP program between 1966 and 1970 (McElroy et al. 1972) using simulated power-reactor waste composed of nonradioactive chemicals and HLW from spent, Hanford reactor fuel. Thirty-three engineering-scale canisters of solidified HLW were produced during the operations. In early 79, the NWVP demonstrated the vitrification of HLW from the processing of actual commercial nuclear fuel. This program consisted of two parts, (1) waste preparation and (2) vitrification by spray calcination and in-can melting. This report presents results from the NWVP

  15. Irvine Smart Grid Demonstration, a Regional Smart Grid Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Yinger, Robert [Southern California Edison Company, Rosemead, CA (United States); Irwin, Mark [Southern California Edison Company, Rosemead, CA (United States)

    2015-12-29

    ISGD was a comprehensive demonstration that spanned the electricity delivery system and extended into customer homes. The project used phasor measurement technology to enable substation-level situational awareness, and demonstrated SCE’s next-generation substation automation system. It extended beyond the substation to evaluate the latest generation of distribution automation technologies, including looped 12-kV distribution circuit topology using URCIs. The project team used DVVC capabilities to demonstrate CVR. In customer homes, the project evaluated HAN devices such as smart appliances, programmable communicating thermostats, and home energy management components. The homes were also equipped with energy storage, solar PV systems, and a number of energy efficiency measures (EEMs). The team used one block of homes to evaluate strategies and technologies for achieving ZNE. A home achieves ZNE when it produces at least as much renewable energy as the amount of energy it consumes annually. The project also assessed the impact of device-specific demand response (DR), as well as load management capabilities involving energy storage devices and plug-in electric vehicle charging equipment. In addition, the ISGD project sought to better understand the impact of ZNE homes on the electric grid. ISGD’s SENet enabled end-to-end interoperability between multiple vendors’ systems and devices, while also providing a level of cybersecurity that is essential to smart grid development and adoption across the nation. The ISGD project includes a series of sub-projects grouped into four logical technology domains: Smart Energy Customer Solutions, Next-Generation Distribution System, Interoperability and Cybersecurity, and Workforce of the Future. Section 2.3 provides a more detailed overview of these domains.

  16. Tidd PFBC Demonstration Project, A DOE Assessment

    Energy Technology Data Exchange (ETDEWEB)

    National Energy Technology Laboratory

    2001-08-31

    The Clean Coal Technology (CCT) Demonstration Program is a government and industry co-funded technology development effort to demonstrate a new generation of innovative coal utilization processes. One goal of the program is to furnish the energy marketplace with a variety of energy efficient, environmentally superior coal-based technologies. Demonstration projects seek to establish the commercial feasibility of the most promising coal technologies that have proceeded beyond the proof-of-concept stage. This report is a post-project assessment of the DOE CCT Demonstration Program, the Tidd PFBC Demonstration Project. A major objective of the CCT Program is to provide the technical data necessary for the private sector to proceed confidently with the commercial replication of the demonstrated technologies. An essential element of meeting this goal is the dissemination of results from the demonstration projects. This post-project assessment (PPA) report is an independent DOE appraisal of the successes that the completed project had in achieving its objectives and aiding in the commercialization of the demonstrated technology. The report also provides an assessment of the expected technical, environmental, and economic performance of the commercial version of the technology, as well as an analysis of the commercial market.

  17. Medicare Demonstration Projects and Evaluation Reports

    Data.gov (United States)

    U.S. Department of Health & Human Services — The Centers for Medicare and Medicaid Services (CMS) conducts and sponsors a number of innovative demonstration projects to test and measure the effect of potential...

  18. Overview of the West Valley Vitrification Facility transfer cart control system

    International Nuclear Information System (INIS)

    Bradley, E.C.; Rupple, F.R.

    1993-01-01

    Oak Ridge National Laboratory (ORNL) has designed the control system for the West Valley Demonstration Project Vitrification Facility transfer cart. The transfer cart will transfer canisters of vitrified high-level waste remotely within the Vitrification Facility. The control system will operate the cart under battery power by wireless control. The equipment includes cart mounted control electronics, battery charger, control pendants, engineer's console, and facility antennas

  19. Prototypical Consolidation Demonstration Project: Final report

    International Nuclear Information System (INIS)

    Gili, J.A.; Poston, V.K.

    1993-11-01

    This is the final report of the Prototypical Consolidation Demonstration Project, which was funded by the US Department of Energy's Office of Civilian Radioactive Waste Management. The project had two objectives: (a) to develop and demonstrate a prototype of production-scale equipment for the dry, horizontal consolidation and packaging of spent nuclear fuel rods from commercial boiling water reactor and pressurized water reactor fuel assemblies, and (b) to report the development and demonstration results to the US Department of Energy, Idaho Operations Office. This report summarizes the activities and conclusions of the project management contractor, EG ampersand G Idaho, Inc., and the fabrication and testing contractor, NUS Corporation (NUS). The report also presents EG ampersand G Idaho's assessments of the equipment and procedures developed by NUS

  20. Milliken Station Demonstration Project FDG retrofit update

    Energy Technology Data Exchange (ETDEWEB)

    Alder, R.C.; Jackson, C.E.; O`Dea, D.T. [and others

    1994-12-31

    The Milliken Clean Coal Demonstration Project is one of the nine Clean Coal Projects selected for funding in Round 4 of the U.S. DOE`s Clean Coal Demonstration Program. The project`s sponsor is New York State Electric and Gas Corporation (NYSEG). Project team members include CONSOL Inc., Saarberg-Holter-Umwelttechnik (SHU), NALCO/FuelTech, Stebbins Engineering and Manufacturing Co., DHR Technologies, and CE Air Preheater. Gilbert/Commonwealth is the Architect/Engineer and Construction Manager for the flue gas desulfurization (FGD) retrofit. The project will provide full-scale demonstration of a combination of innovative emission-reducing technologies and plant upgraded for the control of sulfur dioxide (SO{sub 2}) and nitrogen oxides (NO{sub x}) emissions from a coal-fired steam generator without a significant loss of station efficiency. The overall project goals are the following: 98% SO{sub 2} removal efficiency using limestone while burning high sulfur coal; up to 70% NO{sub x} reduction using the NOXOUT selective non-catalytic reduction (SNCR) technology in conjunction with combustion modifications; minimization of solid waste by producing marketable by-products including commercial grade gypsum, calcium chloride, and fly ash; zero wastewater discharge; maintenance of station efficiency by using a high efficiency heat-pipe air heater system and a low-power-consuming scrubber system. The demonstration project is being conducted at NYSEG`s Milliken Station, located in Lansing, New York. Milliken Station has two 150-MWe pulverized coal-fired units built in the 1950s by Combustion Engineering. The SHU FGD process and the combustion modifications are being installed on both units, but the NOXOUT process, Plant Economic Optimization Advisor (PEOA), and the high-efficiency air heater system will be installed on only one unit.

  1. CALDERON COKEMAKING PROCESS/DEMONSTRATION PROJECT

    International Nuclear Information System (INIS)

    Albert Calderon

    1998-01-01

    This project deals with the demonstration of a coking process using proprietary technology of Calderon, with the following objectives geared to facilitate commercialization: (1) making coke of such quality as to be suitable for use in hard-driving, large blast furnaces; (2) providing proof that such process is continuous and environmentally closed to prevent emissions; (3) demonstrating that high-coking-pressure (non-traditional) coal blends which cannot be safely charged into conventional by-product coke ovens can be used in the Calderon process; and (4) demonstrating that coke can be produced economically, at a level competitive with coke imports. The activities of the past quarter were focused on the following: Conducting bench-scale tests to produce coke and acceptable tar from the process to satisfy Koppers, a prospective stakeholder; Consolidation of the project team players to execute the full size commercial cokemaking reactor demonstration; and Progress made in advancing the design of the full size commercial cokemaking reactor

  2. Vitrification operational experiences and lessons learned at the WVDP

    International Nuclear Information System (INIS)

    Hamel, W.F. Jr.; Sheridan, M.J.; Valenti, P.J.

    1997-01-01

    The Vitrification Facility (VF) at the West Valley Demonstration Project (WVDP) commenced full, high-level radioactive waste (HLW) processing activities in July 1996. The HLW consists of a blend of washed plutonium-uranium extraction (PUREX) sludge, neutralized thorium extraction (THOREX) waste, and cesium-loaded zeolite. The waste product is borosilicate glass contained in stainless steel canisters, sealed for eventual disposal in a federal repository. This paper discusses the WVDP vitrification process, focusing on operational experience and lessons learned during the first year of continuous, remote operation

  3. Resource Roads demonstration project : final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-15

    British Columbia's vast network of resource roads are considered to be amongst the most dangerous, high-risk workplaces in the province. Resource roads, also known as industrial roads, forest service roads, or petroleum development roads, present several unique safety challenges as workplaces. They are built for the purpose of access, egress and transport of materials, resources, equipment and people. However, the lack the same diligence of enforcement and a consistent design, construction, maintenance and standard for use as public highways or municipal roads. There are also safety challenges related to public use of resource roads. This report presented a project, called ResourceRoads by WorkSafe BC that focused on the organization and implementation of a management structure that would provide a system of coordination and a process of compliance for the users of the defined road systems. The project was based on information gathered in two forest districts of Prince George and the South Peace Forest Districts. A committee consisting of the actual owner of the road and other users was formed. The report presented a history of British Columbia's resource road system, and discussed resource roads as industrial workplaces and worksites, as well as resource road fatality statistics. The demonstration project was outlined in terms of project leadership; scope; strategic objectives; project purpose; performance objectives; project communication; demonstration areas; and project stages. Project fundamentals and project findings were also presented along with recommendations and responses to the Auditor General report and the Forest Safety Ombudsman report. It was concluded that potential uses of new technologies for resource road vehicles should be reviewed. tabs., figs.

  4. Hanford Waste Vitrification Plant applied technology plan

    International Nuclear Information System (INIS)

    Kruger, O.L.

    1990-09-01

    This Applied Technology Plan describes the process development, verification testing, equipment adaptation, and waste form qualification technical issues and plans for resolution to support the design, permitting, and operation of the Hanford Waste Vitrification Plant. The scope of this Plan includes work to be performed by the research and development contractor, Pacific Northwest Laboratory, other organizations within Westinghouse Hanford Company, universities and companies with glass technology expertise, and other US Department of Energy sites. All work described in this Plan is funded by the Hanford Waste Vitrification Plant Project and the relationship of this Plan to other waste management documents and issues is provided for background information. Work to performed under this Plan is divided into major areas that establish a reference process, develop an acceptable glass composition envelope, and demonstrate feed processing and glass production for the range of Hanford Waste Vitrification Plant feeds. Included in this work is the evaluation and verification testing of equipment and technology obtained from the Defense Waste Processing Facility, the West Valley Demonstration Project, foreign countries, and the Hanford Site. Development and verification of product and process models and other data needed for waste form qualification documentation are also included in this Plan. 21 refs., 4 figs., 33 tabs

  5. Supercompaction/grouting demonstration project: Final report

    International Nuclear Information System (INIS)

    1987-01-01

    The purpose of this supercompaction demonstration project was to allow Martin Marietta Energy Systems, Inc. (The Company), to obtain cost analysis and performance information on volume reduction and waste encapsulation of solid, low-level contaminated waste (SLW). Ultimately, this information will be used to help define a waste disposal process for SLW that is acceptable to regulatory agencies and the US Department of Energy, Oak Ridge Operations (DOE/ORO). The technical objectives of the demonstration project were: (1) to obtain detailed performance data on each of the compacted barrels; (2) evaluate operating performance problems that may have occurred; (3) describe in detail the compaction and encapsulation process; and (4) to obtain operating cost data for the performance of this demonstration

  6. Hanford Waste Vitrification Plant

    International Nuclear Information System (INIS)

    Larson, D.E.; Allen, C.R.; Kruger, O.L.; Weber, E.T.

    1991-10-01

    The Hanford Waste Vitrification Plant (HWVP) is being designed to immobilize pretreated Hanford high-level waste and transuranic waste in borosilicate glass contained in stainless steel canisters. Testing is being conducted in the HWVP Technology Development Project to ensure that adapted technologies are applicable to the candidate Hanford wastes and to generate information for waste form qualification. Empirical modeling is being conducted to define a glass composition range consistent with process and waste form qualification requirements. Laboratory studies are conducted to determine process stream properties, characterize the redox chemistry of the melter feed as a basis for controlling melt foaming and evaluate zeolite sorption materials for process waste treatment. Pilot-scale tests have been performed with simulated melter feed to access filtration for solids removal from process wastes, evaluate vitrification process performance and assess offgas equipment performance. Process equipment construction materials are being selected based on literature review, corrosion testing, and performance in pilot-scale testing. 3 figs., 6 tabs

  7. In situ vitrification demonstration at Pit 1, Oak Ridge National Laboratory. Volume 2: Site characterization report of the Pit 1 area

    Energy Technology Data Exchange (ETDEWEB)

    Spalding, B.P.; Bogle, M.A.; Cline, S.R.; Naney, M.T.; Gu, B.

    1997-12-01

    A treatability study was initiated in October 1993, initially encompassing the application of in situ vitrification (ISV) to at least two segments of Oak Ridge National Laboratory (ORNL) seepage Pit 1 by the end of fiscal year (FY) 1995. This treatability study was to have supported a possible Interim Record of Decision (IROD) or removal action for closure of one or more of the seepage pits and trenches as early as FY 1997. The Remedial Investigation/Feasibility Study for Waste Area Grouping (WAG) 7, which contains these seven seepage pits and trenches, will probably not begin until after the year 2000. This treatability study will establish the field-scale technical performance of ISV for (1) attaining the required depth, nominally 15 ft, to incorporate source contamination within and beneath the pits; (2) demonstrating field capability to overlap melt settings that are necessary to achieve fused, melted segments of the source contamination; (3) demonstrating off-gas handling technology for accommodating and minimizing the volatilization of {sup 137}Cs; (4) demonstrating adequate site characterization techniques to predict ISV melting kinetics, processing temperatures, and product durability; and (5) promoting public acceptance of ISV technology by demonstrating its safety, implementability, site impacts, and air emissions and by coordinating the treatability study within the regulatory closure process. This report summarizes the site characterization information gathered through the end of September 1996 which supports the planning and assessment of ISV for Pit 1 (objective 4 above).

  8. In situ vitrification demonstration at Pit 1, Oak Ridge National Laboratory. Volume 2: Site characterization report of the Pit 1 area

    International Nuclear Information System (INIS)

    Spalding, B.P.; Bogle, M.A.; Cline, S.R.; Naney, M.T.; Gu, B.

    1997-12-01

    A treatability study was initiated in October 1993, initially encompassing the application of in situ vitrification (ISV) to at least two segments of Oak Ridge National Laboratory (ORNL) seepage Pit 1 by the end of fiscal year (FY) 1995. This treatability study was to have supported a possible Interim Record of Decision (IROD) or removal action for closure of one or more of the seepage pits and trenches as early as FY 1997. The Remedial Investigation/Feasibility Study for Waste Area Grouping (WAG) 7, which contains these seven seepage pits and trenches, will probably not begin until after the year 2000. This treatability study will establish the field-scale technical performance of ISV for (1) attaining the required depth, nominally 15 ft, to incorporate source contamination within and beneath the pits; (2) demonstrating field capability to overlap melt settings that are necessary to achieve fused, melted segments of the source contamination; (3) demonstrating off-gas handling technology for accommodating and minimizing the volatilization of 137 Cs; (4) demonstrating adequate site characterization techniques to predict ISV melting kinetics, processing temperatures, and product durability; and (5) promoting public acceptance of ISV technology by demonstrating its safety, implementability, site impacts, and air emissions and by coordinating the treatability study within the regulatory closure process. This report summarizes the site characterization information gathered through the end of September 1996 which supports the planning and assessment of ISV for Pit 1 (objective 4 above)

  9. NUCLA Circulating Atmospheric Fluidized Bed Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    1992-02-01

    The objective of this DOE Cooperative Agreement is to conduct a cost-shared clean coal technology project to demonstrate the feasibility of circulating fluidized bed combustion technology and to evaluate economic, environmental, and operational benefits of CFB steam generators on a utility scale. At the conclusion of the Phase 2 program, testing related to satisfying these objectives was completed. Data analysis and reporting are scheduled for completion by October 1991. (VC)

  10. Innovative vitrification for soil remediation

    International Nuclear Information System (INIS)

    Jetta, N.W.; Patten, J.S.; Hart, J.G.

    1995-01-01

    The objective of this DOE demonstration program is to validate the performance and operation of the Vortec Cyclone Melting System (CMS trademark) for the processing of LLW contaminated soils found at DOE sites. This DOE vitrification demonstration project has successfully progressed through the first two phases. Phase 1 consisted of pilot scale testing with surrogate wastes and the conceptual design of a process plant operating at a generic DOE site. The objective of Phase 2, which is scheduled to be completed the end of FY 95, is to develop a definitive process plant design for the treatment of wastes at a specific DOE facility. During Phase 2, a site specific design was developed for the processing of LLW soils and muds containing TSCA organics and RCRA metal contaminants. Phase 3 will consist of a full scale demonstration at the DOE gaseous diffusion plant located in Paducah, KY. Several DOE sites were evaluated for potential application of the technology. Paducah was selected for the demonstration program because of their urgent waste remediation needs as well as their strong management and cost sharing financial support for the project. During Phase 2, the basic nitrification process design was modified to meet the specific needs of the new waste streams available at Paducah. The system design developed for Paducah has significantly enhanced the processing capabilities of the Vortec vitrification process. The overall system design now includes the capability to shred entire drums and drum packs containing mud, concrete, plastics and PCB's as well as bulk waste materials. This enhanced processing capability will substantially expand the total DOE waste remediation applications of the technology

  11. Catalytic hydrotreatment of refinery waste: Demonstration project

    Energy Technology Data Exchange (ETDEWEB)

    1989-01-01

    The object of this project and report is to produce liquid hydrocarbons by the catalytic hydroprocessing of solid refinery wastes (hard pitches) in order to improve the profitability of deep conversion processes and reduce the excess production of heavy fuels. The project was mostly carried out on the ASVAHL demonstration platform site, at Solaize, and hard pitches were produced primarily by deasphalting of atmospheric or vacuum distillation residues. The project includes two experimental phases and an economic evaluation study phase. In Phase 1, two granular catalysts were used to transform pitch into standard low sulfur fuel oil: a continuously moving bed, with demetallation and conversion catalyst; a fixed bed, with hydrorefining catalyst. In Phase 2 of the project, it was proven that a hydrotreatment process using a finely dispersed catalyst in the feedstock, can, under realistic operating conditions, transform with good yields hard pitch into distillates that can be refined through standard methods. In Phase 3 of the project, it was shown that the economics of such processes are tightly linked to the price differential between white'' and black'' oil products, which is expected to increase in the future. Furthermore, the evolution of environmental constraints will impel the use of such methods, thus avoiding the coproduction of polluting solid residues. 11 figs., 1 tab.

  12. Southern Nevada Alternative Fuels Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Hyde, Dan; Fast, Matthew

    2009-12-31

    The Southern Nevada Alternative Fuels Program is designed to demonstrate, in a day-to-day bus operation, the reliability and efficiency of a hydrogen bus operation under extreme conditions. By using ICE technology and utilizing a virtually emission free fuel, benefits to be derived include air quality enhancement and vehicle performance improvements from domestically produced, renewable energy sources. The project objective is to help both Ford and the City demonstrate and evaluate the performance characteristics of the E-450 H2ICE shuttle buses developed by Ford, which use a 6.8-liter supercharged Triton V-10 engine with a hydrogen storage system equivalent to 29 gallons of gasoline. The technology used during the demonstration project in the Ford buses is a modified internal combustion engine that allows the vehicles to run on 100% hydrogen fuel. Hydrogen gives a more thorough fuel burn which results in more power and responsiveness and less pollution. The resultant emissions from the tailpipe are 2010 Phase II compliant with NO after treatment. The City will lease two of these E-450 H2ICE buses from Ford for two years. The buses are outfitted with additional equipment used to gather information needed for the evaluation. Performance, reliability, safety, efficiency, and rider comments data will be collected. The method of data collection will be both electronically and manually. Emissions readings were not obtained during the project. The City planned to measure the vehicle exhaust with an emissions analyzer machine but discovered the bus emission levels were below the capability of their machine. Passenger comments were solicited on the survey cards. The majority of comments were favorable. The controllable issues encountered during this demonstration project were mainly due to the size of the hydrogen fuel tanks at the site and the amount of fuel that could be dispensed during a specified period of time. The uncontrollable issues encountered during this

  13. CALDERON COKEMAKING PROCESS/DEMONSTRATION PROJECT

    International Nuclear Information System (INIS)

    Albert Calderon

    1999-01-01

    This project deals with the demonstration of a coking process using proprietary technology of Calderon, with the following objectives geared to facilitate commercialization: (1) making coke of such quality as to be suitable for use in hard-driving, large blast furnaces; (2) providing proof that such process is continuous and environmentally closed to prevent emissions; (3) demonstrating that high-coking-pressure (non-traditional) coal blends which cannot be safely charged into conventional by-product coke ovens can be used in the Calderon process; and (4) demonstrating that coke can be produced economically, at a level competitive with coke imports. The activities of the past quarter were focused on the following: Consolidation of the team of stakeholders; Move the site for the commercial demonstration to LTV Steel, Cleveland, Ohio; Permitting for new site; Site specific engineering; Cost update of the project as it relates to the Cleveland location; FETC update; DCAA audit; and Updated endorsement of Calderon process by Ohio EPA and U.S. EPA, Region 5

  14. Nuclear Desalination Demonstration Project (NDDP) in India

    International Nuclear Information System (INIS)

    Tewari, P.K.; Misra, B.M.

    2001-01-01

    In order to gainfully employ the years of experience and expertise in various aspects of desalination activity, BARC (India) has undertaken installation of a hybrid nuclear desalination plant coupled to 170 MW(e) PHWR station at Kalpakkam, Chennai in the Southeast coast of India. The integrated system, called the Nuclear Desalination Demonstration Project (NDDP), will thus meet the dual needs of process water for nuclear power plant and drinking water for the neighbouring people. NDDP aims for demonstrating the safe and economic production of good quality water by nuclear desalination of seawater. It comprises a 4500 m 3 /d Multistage Flash (MSF) and a 1800 m 3 /d Reverse Osmosis (RO) plant. MSF section uses low pressure steam from Madras Atomic Power Station (MAPS), Kalpakkam. The objectives of the NDDP (Kalpakkam) are as follows: to establish the indigenous capability for the design, manufacture, installation and operation of nuclear desalination plants; to generate necessary design inputs and optimum process parameters for large scale nuclear desalination plant; to serve as a demonstration project to IAEA welcoming participation from interested member states. The hybrid plant is envisaged to have a number of advantages: a part of high purity desalted water produced from MSF plant will be used for the makeup demineralised water requirement (after necessary polishing) for the power station; blending of the product water from RO and MSF plants would provide requisite quality drinking water; the RO plant will continue to be operated to provide the water for drinking purposes during the shutdown of the power station

  15. Calderon cokemaking process/demonstration project

    International Nuclear Information System (INIS)

    Albert Calderon

    1998-01-01

    This project deals with the demonstration of a coking process using proprietary technology of Calderon, with the following objectives geared to facilitate commercialization: (i) making coke of such quality as to be suitable for use in hard-driving, large blast furnaces; (ii) providing proof that such process is continuous and environmentally closed to prevent emissions; (iii) demonstrating that high-coking-pressure (non-traditional) coal blends which cannot be safely charged into conventional by-product coke ovens can be used in the Calderon process; and (iv) demonstrating that coke can be produced economically, at a level competitive with coke imports. The activities of the past quarter were focused on the following: Consolidation of the project team-players; Recruiting Koppers Industries as an additional stakeholder; Developing a closed system for the production of binder pitch from tar in the Calderon coking process as the incentive for Koppers to join the team; Gathering appropriate equipment for conducting a set of experiments at bench scale to simulate tar quality produced from the Calderon coking process for the production of binder pitch; and Further progress made in the design of the commercial coking reactor

  16. Demonstration Project. Consumer reactions to peak prices

    International Nuclear Information System (INIS)

    Lindskoug, Stefan

    2006-06-01

    The purpose and aim of the project is to look at the risk of capacity shortage in the Swedish electricity supply system during excessively cold periods of weather. A risk that has increased in recent years. A growing number of analysts emphasize the importance of high spot prices actually leading to a reduction in demand. Through increased consumer sensitivity as regards pricing, the power system can be run safely with smaller generation reserves. In addition, market price fluctuation is estimated to become more stable and predictable. The purpose of the Demonstration Project is to demonstrate methods or business concepts that lead to the demand for electricity on a national level being reduced at times of high spot prices. The need for the measures to be profitable for the parties involved is an important starting point. A general problem associated with research and development projects is that the participants feel selected and special attention is paid them, hence they will make an extra effort to improve the results. We were aware of this fact when setting up the trials, which is why we introduced the trials as an offer from the electricity supplier to take part in a commercial assessment using a new price list. For this reason we concealed the marked research aim with Elforsk as a backer. Evaluating the results of questionnaires and detailed interviews does not give cause to suppose the results are in any way affected by such conditions. The conclusion of this project is that controlling load at the customer end is an economic alternative to the investment of new production resources

  17. Secure Interoperable Open Smart Grid Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Magee, Thoman [Consolidated Edison Company Of New York, Inc., NY (United States)

    2014-12-28

    The Consolidated Edison, Inc., of New York (Con Edison) Secure Interoperable Open Smart Grid Demonstration Project (SGDP), sponsored by the United States (US) Department of Energy (DOE), demonstrated that the reliability, efficiency, and flexibility of the grid can be improved through a combination of enhanced monitoring and control capabilities using systems and resources that interoperate within a secure services framework. The project demonstrated the capability to shift, balance, and reduce load where and when needed in response to system contingencies or emergencies by leveraging controllable field assets. The range of field assets includes curtailable customer loads, distributed generation (DG), battery storage, electric vehicle (EV) charging stations, building management systems (BMS), home area networks (HANs), high-voltage monitoring, and advanced metering infrastructure (AMI). The SGDP enables the seamless integration and control of these field assets through a common, cyber-secure, interoperable control platform, which integrates a number of existing legacy control and data systems, as well as new smart grid (SG) systems and applications. By integrating advanced technologies for monitoring and control, the SGDP helps target and reduce peak load growth, improves the reliability and efficiency of Con Edison’s grid, and increases the ability to accommodate the growing use of distributed resources. Con Edison is dedicated to lowering costs, improving reliability and customer service, and reducing its impact on the environment for its customers. These objectives also align with the policy objectives of New York State as a whole. To help meet these objectives, Con Edison’s long-term vision for the distribution grid relies on the successful integration and control of a growing penetration of distributed resources, including demand response (DR) resources, battery storage units, and DG. For example, Con Edison is expecting significant long-term growth of DG

  18. Nucla circulating atmospheric fluidized bed demonstration project

    Energy Technology Data Exchange (ETDEWEB)

    Keith, Raymond E.

    1991-10-01

    Colorado-Ute Electric Association began a study to evaluate options for upgrading and extending the life of its Nucla power station in 1982. Located in southwestern Colorado near the town of Nucla, this station was commissioned in 1959 with a local bituminous coal as its design fuel for three identical stoker-fired units, each rated at 12.6 MW(e). Poor station efficiency, high fuel costs, and spiraling boiler maintenance costs forced the Nucla Station into low priority in the CUEA dispatch order as early as 1981. Among the options CUEA considered was to serve as a host utility to demonstrate Atmospheric Fluidized Bed Combustion (AFBC) technology. The anticipated environmental benefits and apparent attractive economics of a circulating AFBC led to Colorado-Ute's decision to proceed with the design and construction of a demonstration project in 1984 at the Nucla facility.

  19. The HADES demonstration and pilot project

    International Nuclear Information System (INIS)

    Bruyn, D.de; Meynendonckx, P.; Neerdael, B.; Noynaert, L.; Voet, M.; Volckaert, G.; Bonne, A.

    1988-01-01

    This report deals with the activities of SCK/CEN and its subcontractors performed during the years 1986-87 in the framework of the HADES demonstration and pilot project, which is carried out in the geological Boom clay formation underlying the nuclear research establishment at Mol. This demonstration and pilot project is sponsored by the Commission of the European Communities under contract number Fl1W-004 B (B) in the framework of Part B of the CEC programme on radioactive waste management and disposal. The actions undertaken and reported here deal essentially with design and engineering activities in preparation for the construction of a test drift and of a mine-by-test directly related to this construction test and of a combined irradiation/heating test to be performed later on in this test drift. A time schedule for the various tests planned to be made in the test drift has also been worked out taking into account time and spatial dependencies

  20. Education & Collection Facility GSHP Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Joplin, Jeff [Denver Museum of Nature and Science, Denver, CO (United States)

    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

  1. Project management plan : Dallas Integrated Corridor Management (ICM) demonstration project.

    Science.gov (United States)

    2010-12-01

    The Dallas Integrated Corridor Management System Demonstration Project is a multi-agency, de-centralized operation which will utilize a set of regional systems to integrate the operations of the corridor. The purpose of the Dallas ICM System is to im...

  2. Medium Duty Electric Vehicle Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Mackie, Robin J. D. [Smith Electric Vehicles Corporation, Kansas City, MO (United States)

    2015-05-31

    The Smith Electric Vehicle Demonstration Project (SDP) was integral to the Smith business plan to establish a manufacturing base in the United States (US) and produce a portfolio of All Electric Vehicles (AEV’s) for the medium duty commercial truck market. Smith focused on the commercial depot based logistics market, as it represented the market that was most ready for the early adoption of AEV technology. The SDP enabled Smith to accelerate its introduction of vehicles and increase the size of its US supply chain to support early market adoption of AEV’s that were cost competitive, fully met the needs of a diverse set of end users and were compliant with Federal safety and emissions requirements. The SDP accelerated the development and production of various electric drive vehicle systems to substantially reduce petroleum consumption, reduce vehicular emissions of greenhouse gases (GHG), and increase US jobs.

  3. Controlled Hydrogen Fleet and Infrastructure Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Scott Staley

    2010-03-31

    This program was undertaken in response to the US Department of Energy Solicitation DE-PS30-03GO93010, resulting in this Cooperative Agreement with the Ford Motor Company and BP to demonstrate and evaluate hydrogen fuel cell vehicles and required fueling infrastructure. Ford initially placed 18 hydrogen fuel cell vehicles (FCV) in three geographic regions of the US (Sacramento, CA; Orlando, FL; and southeast Michigan). Subsequently, 8 advanced technology vehicles were developed and evaluated by the Ford engineering team in Michigan. BP is Ford's principal partner and co-applicant on this project and provided the hydrogen infrastructure to support the fuel cell vehicles. BP ultimately provided three new fueling stations. The Ford-BP program consists of two overlapping phases. The deliverables of this project, combined with those of other industry consortia, are to be used to provide critical input to hydrogen economy commercialization decisions by 2015. The program's goal is to support industry efforts of the US President's Hydrogen Fuel Initiative in developing a path to a hydrogen economy. This program was designed to seek complete systems solutions to address hydrogen infrastructure and vehicle development, and possible synergies between hydrogen fuel electricity generation and transportation applications. This project, in support of that national goal, was designed to gain real world experience with Hydrogen powered Fuel Cell Vehicles (H2FCV) 'on the road' used in everyday activities, and further, to begin the development of the required supporting H2 infrastructure. Implementation of a new hydrogen vehicle technology is, as expected, complex because of the need for parallel introduction of a viable, available fuel delivery system and sufficient numbers of vehicles to buy fuel to justify expansion of the fueling infrastructure. Viability of the fuel structure means widespread, affordable hydrogen which can return a reasonable profit to

  4. Wave Power Demonstration Project at Reedsport, Oregon

    Energy Technology Data Exchange (ETDEWEB)

    Mekhiche, Mike [Principal Investigator; Downie, Bruce [Project Manager

    2013-10-21

    Ocean wave power can be a significant source of large‐scale, renewable energy for the US electrical grid. The Electrical Power Research Institute (EPRI) conservatively estimated that 20% of all US electricity could be generated by wave energy. Ocean Power Technologies, Inc. (OPT), with funding from private sources and the US Navy, developed the PowerBuoy to generate renewable energy from the readily available power in ocean waves. OPT's PowerBuoy converts the energy in ocean waves to electricity using the rise and fall of waves to move the buoy up and down (mechanical stroking) which drives an electric generator. This electricity is then conditioned and transmitted ashore as high‐voltage power via underwater cable. OPT's wave power generation system includes sophisticated techniques to automatically tune the system for efficient conversion of random wave energy into low cost green electricity, for disconnecting the system in large waves for hardware safety and protection, and for automatically restoring operation when wave conditions normalize. As the first utility scale wave power project in the US, the Wave Power Demonstration Project at Reedsport, OR, will consist of 10 PowerBuoys located 2.5 miles off the coast. This U.S. Department of Energy Grant funding along with funding from PNGC Power, an Oregon‐based electric power cooperative, was utilized for the design completion, fabrication, assembly and factory testing of the first PowerBuoy for the Reedsport project. At this time, the design and fabrication of this first PowerBuoy and factory testing of the power take‐off subsystem are complete; additionally the power take‐off subsystem has been successfully integrated into the spar.

  5. Mock Site Licensing Demonstration Project. Final report

    International Nuclear Information System (INIS)

    Roop, R.D.

    1986-06-01

    The Mock Site Licensing Demonstration Project developed the Low-Level Radioactive Waste Siting Simulation, a role-playing exercise designed to facilitate the process of siting and licensing disposal facilities for low-level waste (LLW). This report describes the development, contant, and usefulness of the siting simulation. The simulation was designed by Harvard University's Program on Negotiation; it can be conducted at a workshop or conference, involves 14 or more participants, and requires about eight hours to complete. The simulation consists of two sessions. In the first, participants negotiate the selection of siting criteria, and in the second, a preferred site for a facility is chosen from three candidate sites. The project sponsored two workshops (in Boston, Massachusetts and Richmond, Virginia) in which the simulation was conducted for persons involved in planning for LLW. It is concluded that the siting simulation can be useful in three ways: (1) as a tool for information dissemination, (2) as a vehicle that can foste communication among parties in conflict, and (3) as a step toward consensus building and conflict resolution. The DOE National Low-Level Waste Management Program is now making the siting simulation available for use by states, regional compacts, and other organizations involved in development of LLW disposal facilities

  6. Calderon cokemaking process/demonstration project

    International Nuclear Information System (INIS)

    Albert Calderon

    1996-01-01

    This project which deals with the demonstration of a full size commercial coking retort using Calderon's proprietary technology for making metallurgical coke ran into a commercialization problem by virtue that the designed retort for two (2) tons of coke/hour necessitates thirty-two (32) retorts to produce the 500,000 tons of coke per year for a commercial plant. Bechtel Mining and Metals prepared a cost estimate of the commercial plant which indicated the commercial plant would not be economically feasible. The activity during this reporting period was directed to making changes to the design of the coking retort in order to reduce the number of retorts required for a 500,000 ton/year commercial coke facility. The result of this activity resulted in the drastic reduction of the number of retorts to eight (8) with each retort projected to produce 8.17 tons of coke/hour. Such decrease in number of retorts makes the Calderon technology quite competitive and therefore commercially feasible

  7. Small-scale integrated demonstration of high-level radioactive waste processing and vitrification using actual SRP waste

    International Nuclear Information System (INIS)

    Ferguson, R.B.; Woolsey, G.B.; Galloway, R.M.; Baumgarten, P.M.; Eibling, R.E.

    1980-01-01

    Experiments have been made to demonstrate the feasibility of immobilizing SRP high-level waste in borosilicate glass. Results to date are encouraging. Equipment performance and processing characteristics for solidifying small batches of actual SRP waste have agreed well with previous experience with small- and large-scale tests synthetic waste, and with theoretical predictions

  8. Exploration Medical System Demonstration (EMSD) Project

    Science.gov (United States)

    Chin, Duane

    2012-01-01

    The Exploration Medical System Demonstration (EMSD) is a project under the Exploration Medical Capability (ExMC) element managed by the Human Research Program (HRP). The vision for the EMSD is to utilize ISS as a test bed to show that several medical technologies needed for an exploration mission and medical informatics tools for managing evidence and decision making can be integrated into a single system and used by the on-orbit crew in an efficient and meaningful manner. Objectives: a) Reduce and even possibly eliminate the time required for on-orbit crew and ground personnel (which include Surgeon, Biomedical Engineer (BME) Flight Controller, and Medical Operations Data Specialist) to access and move medical data from one application to another. b) Demonstrate that the on-orbit crew has the ability to access medical data/information using an intuitive and crew-friendly software solution to assist/aid in the treatment of a medical condition. c) Develop a common data management framework and architecture that can be ubiquitously used to automate repetitive data collection, management, and communications tasks for all crew health and life sciences activities.

  9. Solidification and vitrification life-cycle economics study

    International Nuclear Information System (INIS)

    Gimpel, R.F.

    1992-01-01

    Solidification (making concrete) and vitrification (making glass) are frequently the treatment methods recommended for treating inorganic or radioactive wastes. Ex-situ solidification and vitrification are the competing methods for treating in excess of 450 000 cm 3 of low-level radioactive and mixed wastes at the Fernald Environmental Management Project (FEMP) located near Cincinnati, Ohio. This paper summarizes a detailed study done to: (1) compare the economics of the solidification and vitrification processes, (2) determine if the stigma assigned to vitrification is warranted and, (3) determine if investing millions of dollars into vitrification development, along with solidification development, at Fernald is warranted

  10. Demonstration of the Defense Waste Processing Facility vitrification process for Tank 42 radioactive sludge -- Glass preparation and characterization

    International Nuclear Information System (INIS)

    Bibler, N.E.; Fellinger, T.L.; Marshall, K.M.; Crawford, C.L.; Cozzi, A.D.; Edwards, T.B.

    1999-01-01

    The Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) is currently processing and immobilizing the radioactive high level waste sludge at SRS into a durable borosilicate glass for final geological disposal. The DWPF has recently finished processing the first radioactive sludge batch, and is ready for the second batch of radioactive sludge. The second batch is primarily sludge from Tank 42. Before processing this batch in the DWPF, the DWPF process flowsheet has to be demonstrated with a sample of Tank 42 sludge to ensure that an acceptable melter feed and glass can be made. This demonstration was recently completed in the Shielded Cells Facility at SRS. An earlier paper in these proceedings described the sludge composition and processes necessary for producing an acceptable melter fee. This paper describes the preparation and characterization of the glass from that demonstration. Results substantiate that Tank 42 sludge after mixing with the proper amount of glass forming frit (Frit 200) can be processed to make an acceptable glass

  11. Brown Grease to Biodiesel Demonstration Project Report

    Energy Technology Data Exchange (ETDEWEB)

    San Francisco Public Utilities Commission; URS Corporation; Biofuels, Blackgold; Carollo Engineers

    2013-01-30

    program by other municipal agencies (as applicable). In order to accomplish the goals of the project, the following steps were performed: 1. Operation of a demonstration facility designed to receive 10,000 to 12,000 gallons of raw Trap Waste each day from private Trap Waste hauling companies. The demonstration facility was designed and built by Pacific Biodiesel Technologies (PBTech). The demonstration facility would also recover 300 gallons of Brown Grease per day from the raw Trap Waste. The recovered Brown Grease was expected to contain no more than 2% Moisture, Insolubles, and Unsaponifiables (MIU) combined. 2. Co-digestion of the side streams (generated during the recovery of 300 gallons of Brown Grease from the raw Trap Waste) with wastewater sludge in the WWTP's anaerobic digesters. The effects of the side streams on anaerobic digestion were quantified by comparison with baseline data. 3. Production of 240 gallons per day of ASTM D6751-S15 grade Biodiesel fuel via a Biodiesel conversion demonstration facility, with the use of recovered Brown Grease as a feedstock. The demonstration facility was designed and built by Blackgold Biofuels (BGB). Side streams from this process were also co-digested with wastewater sludge. Bench-scale anaerobic digestion testing was conducted on side streams from both demonstration facilities to determine potential toxicity and/or changes in biogas production in the WWTP anaerobic digester. While there is a lot of theoretical data available on the lab-scale production of Biodiesel from grease Trap Waste, this full-scale demonstration project was one of the first of its kind in the United States. The project's environmental impacts were expected to include: Reduction of greenhouse gas emissions by prevention of the release of methane at landfills. Although the combustion product of Biodiesel and Methane gas produced in the Anaerobic digester, Carbon Dioxide, is also a greenhouse gas; it is 20 times weaker for the same amount

  12. Innovative vitrification for soil remediation

    Energy Technology Data Exchange (ETDEWEB)

    Jetta, N.W.; Patten, J.S.; Hnat, J.G. [Vortec Corp., Collegeville, PA (United States)

    1995-10-01

    The objective of this DOE demonstration program is to validate the performance and operation of the Vortec Cyclone Melting System (CMS{trademark}) for the processing of LLW contaminated soils found at DOE sites. This DOE vitrification demonstration project has successfully progressed through the first two phases. Phase I consisted of pilot scale testing with surrogate wastes and the conceptual design of a process plant operating at a generic DOE site. The objective of Phase 2, which is scheduled to be completed the end of FY 95, is to develop a definitive process plant design for the treatment of wastes at a specific DOE facility. During Phase 2, a site specific design was developed for the processing of LLW soils and muds containing TSCA organics and RCRA metal contaminants. Phase 3 will consist of a full scale demonstration at the DOE gaseous diffusion plant located in Paducah, KY. Several DOE sites were evaluated for potential application of the technology. Paducah was selected for the demonstration program because of their urgent waste remediation needs as well as their strong management and cost sharing financial support for the project.

  13. MODIL cryocooler producibility demonstration project results

    International Nuclear Information System (INIS)

    Cruz, G.E.; Franks, R.M.

    1993-01-01

    The production of large quantities of spacecraft needed by SDIO will require a cultural change in design and production practices. Low rates production and the need for exceedingly high reliability has driven the industry to custom designed, hand crafted, and exhaustively tested satellites. These factors have mitigated against employing design and manufacturing cost reduction methods commonly used in tactical missile production. Additional challenges to achieving production efficiencies are presented by the SDI spacecraft mission requirement. IR sensor systems, for example, are comprised of subassemblies and components that require the design, manufacture, and maintenance of ultra precision tolerances over challenging operational lifetimes. These IR sensors demand the use of reliable, closed loop, cryogenic refrigerators or active cryocoolers to meet stringent system acquisition and pointing requirements. The authors summarize some spacecraft cryocooler requirements and discuss observations regarding Industry's current production capabilities of cryocoolers. The results of the Lawrence Livermore National Laboratory (LLNL) Spacecraft Fabrication and Test (SF and T) MODIL's Phase I producibility demonstration project is presented

  14. Vitrification development for mixed wastes

    International Nuclear Information System (INIS)

    Merrill, R.; Whittington, K.; Peters, R.

    1995-02-01

    Vitrification is a promising approach to waste-form immobilization. It destroys hazardous organic compounds and produces a durable and highly stable glass. Vitrification tests were performed on three surrogate wastes during fiscal year 1994; 183-H Solar Evaporation Basin waste from Hanford, bottom ash from the Oak Ridge TSCA incinerator, and saltcrete from Rocky Flats. Preliminary glass development involved melting trials followed by visual homogeneity examination, short-duration leach tests on glass specimens, and long-term leach tests on selected glasses. Viscosity and electrical conductivity measurements were taken for the most durable glass formulations. Results for the saltcrete are presented in this paper and demonstrate the applicability of vitrification technology to this mixed waste

  15. WSF Biodiesel Demonstration Project Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Washington State University; University of Idaho; The Glosten Associates, Inc.; Imperium Renewables, Inc.

    2009-04-30

    engines. Each test vessel did experience a microbial growth bloom that produced a build up of material in the fuel purifiers similar to material witnessed in the 2004 fuel test. A biocide was added with each fuel shipment and the problem subsided. In January of 2009, the WSF successfully completed an eleven month biodiesel fuel test using approximately 1,395,000 gallons of biodiesel blended fuels. The project demonstrated that biodiesel can be used successfully in marine vessels and that current ASTM specifications are satisfactory for marine vessels. Microbial growth in biodiesel diesel interface should be monitored. An inspection of the engines showed no signs of being negatively impacted by the test.

  16. HTI retrieval demonstration project execution plan

    International Nuclear Information System (INIS)

    Ellingson, D.R.

    1997-01-01

    This plan describes the process for demonstrating the retrieval of difficult Hanford tank waste forms utilizing commercial technologies and the private sector to conduct the operations. The demonstration is to be conducted in Tank 241-C-106

  17. Cryogenic Barrier Demonstration Project. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, L.A.; Yarmak, E.; Long, E.L.

    2000-03-01

    A long-term frozen soil barrier was implemented at the HRE (Homogeneous Reactor Experiment) Pond facility at the Oak Ridge National Laboratory in 1997. This was performed to verify the technical feasibility and costs of deploying a frozen barrier at a radiologically contaminated site. Work began in September 1996 and progressed through to December 1999. The frozen barrier has been operational since November 1997. Verification of the barrier integrity was performed independently by the EPA's SITE Program. This project showed frozen barriers offer a proven technology to retain below grade hazardous substances at relatively low costs with minimal effect on the environment.

  18. Biorefinery Demonstration Project Final Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    Lee, David [University of Georgia Research Foundation, Inc., Athens, GA (United States)

    2015-10-20

    In this project we focused on various aspects of biorefinery technology development including algal-biorefinery technology, thermochemical conversion of biomass to bio-oils and biochar; we tested characteristics and applications of biochars and evaluated nutrient cycling with wastewater treatment by the coupling of algal culture systems and anaerobic digestion. Key results include a method for reducing water content of bio-oil through atomized alcohol addition. The effect included increasing the pH and reducing the viscosity and cloud point of the bio-oil. Low input biochar production systems were evaluated via literature reviews and direct experimental work. Additionally, emissions were evaluated and three biochar systems were compared via a life cycle analysis. Attached growth systems for both algal cultivation and algal harvesting were found to be superior to suspended growth cultures. Nutrient requirements for algal cultivation could be obtained by the recycling of anaerobic digester effluents, thus experimentally showing that these two systems could be directly coupled. Twenty-two journal articles and six intellectual property applications resulted from the cumulative work that this project contributed to programmatically.

  19. An update on the quality assurance for the waste vitrification plants

    Energy Technology Data Exchange (ETDEWEB)

    Caplinger, W.H.; Shugars, D.L.; Carlson, M.K.

    1990-01-01

    Immobilization of high-level defense production wastes is an important step in environmental restoration. The best available technology for immobilization of this waste currently is by incorporation into borosilicate glass, i.e., vitrification. Three US sites are active in the design, construction, or operation of vitrification facilities. The status, facility description and Quality Assurance (QA) development for each facility was presented at the 1989 Energy Division Conference. This paper presents the developments since that time. The West Valley Demonstration Project (WVDP) in northwestern New York State has demonstrated the technology. At the Savannah River Site (SRS) in South Carolina the Defense Waste Processing Facility (DWPF) has completed design, construction is essentially complete, and preparation for operation is underway. The Hanford Waste Vitrification Plant (HWVP) in Washington State is in initial Detailed Design. 4 refs.

  20. An update on the quality assurance for the waste vitrification plants

    International Nuclear Information System (INIS)

    Caplinger, W.H.; Shugars, D.L.; Carlson, M.K.

    1990-01-01

    Immobilization of high-level defense production wastes is an important step in environmental restoration. The best available technology for immobilization of this waste currently is by incorporation into borosilicate glass, i.e., vitrification. Three US sites are active in the design, construction, or operation of vitrification facilities. The status, facility description and Quality Assurance (QA) development for each facility was presented at the 1989 Energy Division Conference. This paper presents the developments since that time. The West Valley Demonstration Project (WVDP) in northwestern New York State has demonstrated the technology. At the Savannah River Site (SRS) in South Carolina the Defense Waste Processing Facility (DWPF) has completed design, construction is essentially complete, and preparation for operation is underway. The Hanford Waste Vitrification Plant (HWVP) in Washington State is in initial Detailed Design. 4 refs

  1. Solar energy parking canopy demonstration project

    Energy Technology Data Exchange (ETDEWEB)

    Cylwik, Joe [City of Big Bear Lake, Big Bear, CA (United States); David, Lawrence [City of Big Bear Lake, Big Bear, CA (United States)

    2015-09-24

    The goal of this pilot/demonstration program is to measure the viability of using solar photovoltaic (PV) technology at three locations in a mountain community environment given the harsh weather conditions. An additional goal is to reduce long-term operational costs, minimize green house gas emissions, lower the dependency on energy produced from fossil fuels, and improve the working environment and health of city employees and residents.

  2. IGCC demonstration project status combustion engineering IGCC repowering project

    International Nuclear Information System (INIS)

    Glamuzina, R.W.; Allen, R.J.; Peletz, L.J.

    1993-01-01

    This demonstration project was originally conceived as the repowering of an existing plant facility, the Lakeside Station in Springfield, Illinois. The Owner, City Water, Light and Power (CWL ampersand P), has removed five of the original boilers and three of the original turbines. The buildings have had asbestos insulation removed and the interiors have been prepared for the construction of a single Integrated Gasification Combined Cycle (IGCC) process train that will generate a net output of 60 megawatts. The plant consists of a combined cycle (gas turbine, heat recovery steam generator, steam turbine) power train located in the existing buildings and a coal gasification system in a new building. The gasification system contains ABB CE's air-blown, entrained flow, two stage gasifier, an advanced hot gas desulfurization system by General Electric Environmental Services, Inc. and the necessary auxiliary systems. The plant is designed to produce a nominal 60 MW net output with an ambient air temperature of 95 degrees F and a cooling water temperature of 89 degrees F on either Natural Gas or Illinois No. 5 coal

  3. Poland petroleum refinery sludge lagoon demonstration project

    International Nuclear Information System (INIS)

    Altman, D.J.

    2000-01-01

    The US Department of Energy and the Institute for Ecology of Industrial Area have been working together to develop mutually beneficial, cost-effective environmental remediation technologies such as the demonstration of bioremediation techniques for the clean up of acidic petroleum sludge impacted soils at an oil refinery in southern Poland. After an expedited site characterization, treatability study, and a risk assessment study, a remediation strategy was devised. The waste material was composed primarily of high molecular weight paraffinic and polynuclear aromatic hydrocarbons. A biopile design which employed a combination of passive and active aeration in conjunction with nutrient and surfactant application as used to increase the biodegradation of the contaminants of concern

  4. NUCLA Circulating Atmospheric Fluidized Bed Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Keith, Raymond E.; Heller, Thomas J.; Bush, Stuart A.

    1991-01-01

    This Annual Report on Colorado-Ute Electric Association's NUCLA Circulating Fluidized Bed (CFB) Demonstration Program covers the period from February 1987 through December 1988. The outline for presentation in this report includes a summary of unit operations along with individual sections covering progress in study plan areas that commenced during this reporting period. These include cold-mode shakedown and calibration, plant commercial performance statistics, unit start-up (cold), coal and limestone preparation and handling, ash handling system performance and operating experience, tubular air heater, baghouse operation and performance, materials monitoring, and reliability monitoring. During this reporting period, the coal-mode shakedown and calibration plan was completed. (VC)

  5. 78 FR 22527 - TRICARE Access to Care Demonstration Project

    Science.gov (United States)

    2013-04-16

    ... DEPARTMENT OF DEFENSE Office of the Secretary TRICARE Access to Care Demonstration Project AGENCY... is to advise interested parties of a 2-year extension of the demonstration project in which the... project will continue through May 4, 2015. ADDRESSES: TRICARE Management Activity, Health Plan Operations...

  6. Testing of the West Valley Vitrification Facility transfer cart control system

    International Nuclear Information System (INIS)

    Halliwell, J.W.; Bradley, E.C.

    1995-01-01

    Oak Ridge National Laboratory (ORNL) has designed and tested the control system for the West Valley Demonstration Project Vitrification Facility transfer cart. The transfer cart will transfer canisters of vitrified high-level waste remotely within the Vitrification Facility. The control system operates the cart under battery power by wireless control. The equipment includes cart-mounted control electronics, battery charger, control pendants, engineer's console, and facility antennas. Testing was performed in several phases of development: (1) prototype equipment was built and tested during design, (2) board-level testing was then performed at ORNL during fabrication, and (3) system-level testing was then performed by ORNL at the fabrication subcontractor's facility for the completed cart system. These tests verified (1) the performance of the cart relative to design requirements and (2) operation of various built-in cart features. The final phase of testing is planned to be conducted during installation at the West Valley Vitrification Facility

  7. Technical and administrative approach for the West Valley Demonstration Project Safety Program

    International Nuclear Information System (INIS)

    Newsom, P.C.; Roberts, C.J.; Yuchien Yuan; Marchetti, S.

    1987-06-01

    The principal objective of the West Valley Demonstration Project (WVDP) is to vitrify the 2.2 million liters of high-level radioactive waste (HLW) stored at the Western New York Nuclear Service Center (WNYNSC). This simple statement of purpose, however, does not convey a sense of the complexity of the undertaking. The vitrification task is not only complex in and of itself, but requires a myriad of other activities to be accomplished on an intricate and fast paced schedule in order to support it. The West Valley Demonstration Project Act (P.L 96-368), U.S. Department of Energy Order DOE-5481.1A, Idaho Operations Office Order ID-5481.1 and standard nuclear industry practice all require that proposed systems and operations involving hazards not routinely encountered by the general public be analyzed to identify potential hazards and consequences, and to assure that reasonable measures are taken to eliminate, control, or mitigate these potential consequences. Virtually every substantive aspect of the WVDP involves hazards beyond those routinely encountered and accepted by the general public. In order to assure the safety of the public and the workers at the WVDP, a system of hazard identification, categorization, analysis and review has been established. In parallel with this system, a procedure for developing the minimum design specifications and quality assurance requirements has been developed for Project systems, components, and structures which play a role in the safety of a specific major facility or the overall Project. 29 refs., 3 figs., 6 tabs

  8. Demonstrating sustainable energy: A review-based model of sustainable energy demonstration projects

    NARCIS (Netherlands)

    Bossink, Bart

    2017-01-01

    This article develops a model of sustainable energy demonstration projects, based on a review of 229 scientific publications on demonstrations in renewable and sustainable energy. The model addresses the basic organizational characteristics (aim, cooperative form, and physical location) and learning

  9. Multiview Projection Using CADKEY Freeze-Frame Demonstrations.

    Science.gov (United States)

    Kelso, Robert P.; Ziai, M. Reza

    1988-01-01

    Describes a three-dimensional computer aided design software package, CADKEY, for demonstrating orthographic orthodirectional projection theory to a classroom. Provides several figures for showing the demonstrations. (Author/YP)

  10. Exposure Based Health Issues Project Report: Phase I of High Level Tank Operations, Retrieval, Pretreatment, and Vitrification Exposure Based Health Issues Analysis

    International Nuclear Information System (INIS)

    Stenner, Robert D.; Bowers, Harold N.; Kenoyer, Judson L.; Strenge, Dennis L.; Brady, William H.; Ladue, Buffi; Samuels, Joseph K.

    2001-01-01

    The Department of Energy (DOE) has the responsibility to understand the ''big picture'' of worker health and safety which includes fully recognizing the vulnerabilities and associated programs necessary to protect workers at the various DOE sites across the complex. Exposure analysis and medical surveillance are key aspects for understanding this big picture, as is understanding current health and safety practices and how they may need to change to relate to future health and safety management needs. The exposure-based health issues project was initiated to assemble the components necessary to understand potential exposure situations and their medical surveillance and clinical aspects. Phase I focused only on current Hanford tank farm operations and serves as a starting point for the overall project. It is also anticipated that once the pilot is fully developed for Hanford HLW (i.e., current operations, retrieval, pretreatment, vitrification, and disposal), the process and analysis methods developed will be available and applicable for other DOE operations and sites. The purpose of this Phase I project report is to present the health impact information collected regarding ongoing tank waste maintenance operations, show the various aspects of health and safety involved in protecting workers, introduce the reader to the kinds of information that will need to be analyzed in order to effectively manage worker safety

  11. Transportable Vitrification System: Operational experience gained during vitrification of simulated mixed waste

    International Nuclear Information System (INIS)

    Whitehouse, J.C.; Burket, P.R.; Crowley, D.A.; Hansen, E.K.; Jantzen, C.M.; Smith, M.E.; Singer, R.P.; Young, S.R.; Zamecnik, J.R.; Overcamp, T.J.; Pence, I.W. Jr.

    1996-01-01

    The Transportable Vitrification System (TVS) is a large-scale, fully-integrated, transportable, vitrification system for the treatment of low-level nuclear and mixed wastes in the form of sludges, soils, incinerator ash, and similar waste streams. The TVS was built to demonstrate the vitrification of actual mixed waste at U. S. Department of Energy (DOE) sites. Currently, Westinghouse Savannah River Company (WSRC) is working with Lockheed Martin Energy Systems (LMES) to apply field scale vitrification to actual mixed waste at Oak Ridge Reservation's (ORR) K-25 Site. Prior to the application of the TVS to actual mixed waste it was tested on simulated K-25 B and C Pond waste at Clemson University. This paper describes the results of that testing and preparations for the demonstration on actual mixed waste

  12. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2003

    International Nuclear Information System (INIS)

    2004-01-01

    This Annual Site Environmental Report for the West Valley Demonstration Project (WVDP or Project) is published to inform those with interest about environmental conditions at the WVDP. In accordance with U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting, the report summarizes calendar year (CY) 2003 environmental monitoring data so as to describe the performance of the WVDP's environmental management system (EMS), confirm compliance with standards and regulations, and highlight important programs. During 2003, cleanup of radioactive waste from the former nuclear fuels reprocessing plant that shut down operations in the 1970s was continued at the WVDP. The Project is located in western New York State, about 30 miles south of Buffalo, within the New York State-owned Western New York Nuclear Service Center (WNYNSC). The WVDP is being conducted in cooperation with the New York State Energy Research and Development Authority. Work activities at the WVDP during 2003 included: (1) maintaining canisters of vitrified high-level waste in a shielded facility; (2) shipping low-level radioactive waste offsite for disposal; (3) shipping packaged spent nuclear fuel assemblies to Idaho National Engineering and Environmental Laboratory; (4) constructing a facility where large high-activity components can be safely size-reduced and packaged for disposal; (5) decontaminating the fuel storage pool and the cask unloading pool; (6) decontaminating the general purpose cell and the process mechanical cell (also referred to as the head end cells); (7) cleanup of waste in the plutonium purification cell (south) and extraction cell number 2 in the main plant; (8) planning for decontamination and dismantlement of the vitrification facility; (9) continuing preparation of the Decommissioning and/or Long-Term Stewardship Environmental Impact Statement; and (10) monitoring the environment and managing contaminated areas within the Project facility premises

  13. Recycling and composting demonstration projects for the Memphis region

    Energy Technology Data Exchange (ETDEWEB)

    Muller, D. [Memphis and Shelby County Div. of Planning and Development, TN (United States)

    1992-05-01

    This report documents the development and implementation of the project entitled ``Recycling and Composting Demonstration Projects for the Memphis Region.`` The project was funded by the Energy Task Force of the Urban Consortium for Technology Initiatives. This Project was implemented by the staff of the Special Programs Section of the Memphis and Shelby County Division of Planning and Development. The project began November 1, 1990, and was completed December 31, 1991. The purpose of the project was to evaluate the feasibility of a variety of solid waste disposal alternatives.

  14. Recycling and composting demonstration projects for the Memphis region

    Energy Technology Data Exchange (ETDEWEB)

    Muller, D. (Memphis and Shelby County Div. of Planning and Development, TN (United States))

    1992-05-01

    This report documents the development and implementation of the project entitled Recycling and Composting Demonstration Projects for the Memphis Region.'' The project was funded by the Energy Task Force of the Urban Consortium for Technology Initiatives. This Project was implemented by the staff of the Special Programs Section of the Memphis and Shelby County Division of Planning and Development. The project began November 1, 1990, and was completed December 31, 1991. The purpose of the project was to evaluate the feasibility of a variety of solid waste disposal alternatives.

  15. Quality Assurance Project Plan for the treatability study of in situ vitrification of Seepage Pit 1 in Waste Area Grouping 7 at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    1995-07-01

    This Quality Assurance Project Plan (QAPjP) establishes the quality assurance procedures and requirements to be implemented for the control of quality-related activities for Phase 3 of the Treatability Study (TS) of In Situ Vitrification (ISV) of Seepage Pit 1, ORNL Waste Area Grouping 7. This QAPjP supplements the Quality Assurance Plan for Oak Ridge National Laboratory Environmental Restoration Program by providing information specific to the ISV-TS. Phase 3 of the TS involves the actual ISV melt operations and posttest monitoring of Pit 1 and vicinity. Previously, Phase 1 activities were completed, which involved determining the boundaries of Pit 1, using driven rods and pipes and mapping the distribution of radioactivity using logging tools within the pipes. Phase 2 involved sampling the contents, both liquid and solids, in and around seepage Pit 1 to determine their chemical and radionuclide composition and the spatial distribution of these attributes. A separate QAPjP was developed for each phase of the project. A readiness review of the Phase 3 activities presented QAPjP will be conducted prior to initiating field activities, and an Operational Acceptance, Test (OAT) will also be conducted with no contamination involved. After, the OAT is complete, the ISV process will be restarted, and the melt will be allowed to increase with depth and incorporate the radionuclide contamination at the bottom of Pit 1. Upon completion of melt 1, the equipment will be shut down and mobilized to an adjacent location at which melt 2 will commence

  16. Vitrification of NORM wastes

    International Nuclear Information System (INIS)

    Chapman, C.

    1994-05-01

    Vitrification of wastes is a relatively new application of none of man's oldest manufacturing processes. During the past 25 years it has been developed and accepted internationally for immobilizing the most highly radioactive wastes from spent nuclear fuel. By the year 2005, there will be nine operating high-level radioactive vitrification plants. Many of the technical ''lessons learned'' from this international program can be applied to much less hazardous materials such as naturally occurring radioactive material (NORM). With the deployment of low capital and operating cost systems, vitrification should become a broadly applied process for treating a large variety of wastes. In many situations, the wastes can be transformed into marketable products. This paper will present a general description of waste vitrification, summarize some of its key advantages, provide some test data for a small sample of one NORM, and suggest how this process may be applied to NORM

  17. INNOVATIVE FOSSIL FUEL FIRED VITRIFICATION TECHNOLOGY FOR SOIL REMEDIATION. SUMMARY REPORT

    International Nuclear Information System (INIS)

    J. Hnat; L.M. Bartone; M. Pineda

    2001-01-01

    This Summary Report summarizes the progress of Phases 3, 3A and 4 of a waste technology Demonstration Project sponsored under a DOE Environmental Management Research and Development Program and administered by the U.S. Department of Energy National Energy Technology Laboratory-Morgantown (DOE-NETL) for an ''Innovative Fossil Fuel Fired Vitrification Technology for Soil Remediation''. The Summary Reports for Phases 1 and 2 of the Program were previously submitted to DOE. The total scope of Phase 3 was to have included the design, construction and demonstration of Vortec's integrated waste pretreatment and vitrification process for the treatment of low level waste (LLW), TSCA/LLW and mixed low-level waste (MLLW). Due to funding limitations and delays in the project resulting from a law suit filed by an environmental activist and the extended time for DOE to complete an Environmental Assessment for the project, the scope of the project was reduced to completing the design, construction and testing of the front end of the process which consists of the Material Handling and Waste Conditioning (MH/C) Subsystem of the vitrification plant. Activities completed under Phases 3A and 4 addressed completion of the engineering, design and documentation of the Material Handling and Conditioning System such that final procurement of the remaining process assemblies can be completed and construction of a Limited Demonstration Project be initiated in the event DOE elects to proceed with the construction and demonstration testing of the MH/C Subsystem

  18. Test plan for glass melter system technologies for vitrification of hign-sodium content low-level radioactive liquid waste, Project No. RDD-43288

    International Nuclear Information System (INIS)

    Higley, B.A.

    1995-01-01

    This document provides a test plan for the conduct of combustion fired cyclone vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System, Low-Level Waste Vitrification Program. The vendor providing this test plan and conducting the work detailed within it is the Babcock ampersand Wilcox Company Alliance Research Center in Alliance, Ohio. This vendor is one of seven selected for glass melter testing

  19. Hydrogen fueling demonstration projects using compact PSA purification

    International Nuclear Information System (INIS)

    Ng, E.; Smith, T.

    2004-01-01

    'Full text:' Hydrogen fueling demonstration projects are critical to the success of hydrogen as an automotive fuel by building public awareness and demonstrating the technology required to produce, store, and dispense hydrogen. Over 75 of these demonstration projects have been undertaken or are in the planning stages world-wide, sponsored by both the public and private sectors. Each of these projects represents a unique combination of sponsors, participants, geographic location, and hydrogen production pathway. QuestAir Technologies Inc., as the industry leader in compact pressure swing adsorption equipment for purifying hydrogen, has participated in four hydrogen fueling demonstration projects with a variety of partners and in North America and Japan. QuestAir's experiences as a participant in the planning, construction, and commissioning of these demonstration projects will be presented in this paper. The unique challenges of each project and the critical success factors that must to be considered for successful deployment of high-profile, international, and multi-vendor collaborations will also be discussed. The paper will also provide insights on the requirements for hydrogen fueling demonstration projects in the future. (author)

  20. Training plan : Dallas Integrated Corridor Management (ICM) demonstration project.

    Science.gov (United States)

    2013-01-01

    The Dallas Area Rapid Transit (DART) is leading the US 75 Integrated Corridor Management (ICM) Demonstration Project for the Dallas region. Coordinated corridor operations and management is predicated on being able to share transportation information...

  1. Test report : Dallas Integrated Corridor Management (ICM) demonstration project.

    Science.gov (United States)

    2015-05-01

    The Dallas Area Rapid Transit (DART) is leading the US 75 Integrated Corridor Management (ICM) : Demonstration Project for the Dallas region. Coordinated corridor operations and management is : predicated on being able to share transportation informa...

  2. Final report : Dallas Integrated Corridor Management (ICM) Demonstration Project.

    Science.gov (United States)

    2015-08-01

    The Dallas Area Rapid Transit (DART) is leading the US-75 Integrated Corridor Management (ICM) Demonstration Project for the Dallas region. Coordinated corridor operations and management is predicated on being able to share transportation information...

  3. Radiation safety at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Hoffman, R.L.

    1997-01-01

    This is a report on the Radiation Safety Program at the West Valley Demonstration Project (WVDP). This Program covers a number of activities that support high-level waste solidification, stabilization of facilities, and decontamination and decommissioning activities at the Project. The conduct of the Program provides confidence that all occupational radiation exposures received during operational tasks at the Project are within limits, standards, and program requirements, and are as low as reasonably achievable

  4. The ethanol heavy-duty truck fleet demonstration project

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    This project was designed to test and demonstrate the use of a high- percentage ethanol-blended fuel in a fleet of heavy-duty, over-the- road trucks, paying particular attention to emissions, performance, and repair and maintenance costs. This project also represents the first public demonstration of the use of ethanol fuels as a viable alternative to conventional diesel fuel in heavy-duty engines.

  5. The Role of Demonstration Projects in Construction innovation processes

    DEFF Research Database (Denmark)

    Clausen, Lennie

    1999-01-01

    The article is describing the methodology of a case-study approach to the investigation of demonstration projects and their impact on the development of process and product innovations in the construction industry.......The article is describing the methodology of a case-study approach to the investigation of demonstration projects and their impact on the development of process and product innovations in the construction industry....

  6. Childhood Obesity Research Demonstration project: Cross-site evaluation method

    Science.gov (United States)

    The Childhood Obesity Research Demonstration (CORD) project links public health and primary care interventions in three projects described in detail in accompanying articles in this issue of Childhood Obesity. This article describes a comprehensive evaluation plan to determine the extent to which th...

  7. Equipment experience in a radioactive LFCM [liquid-fed ceramic melter] vitrification facility

    International Nuclear Information System (INIS)

    Holton, L.K. Jr.; Dierks, R.D.; Sevigny, G.J.; Goles, R.W.; Surma, J.E.; Thomas, N.M.

    1986-11-01

    Since October 1984, the Pacific Northwest Laboratory (PNL) has operated a pilot-scale radioactive liquid-fed ceramic melter (RLFCM) vitrification process in shielded manipulator hot cells. This vitrification facility is being operated for the Department of Energy (DOE) to remotely test vitrification equipment components in a radioactive environment and to develop design and operation data that can be applied to production-scale projects. This paper summarizes equipment and process experience obtained from the operations of equipment systems for waste feeding, waste vitrification, canister filling, canister handling, and vitrification off-gas treatment

  8. Vitrification of actinide solutions in SRS separations facilities

    International Nuclear Information System (INIS)

    Minichan, R.L.; Ramsey, W.G.

    1995-01-01

    The actinide vitrification system being developed at SRS provides the capability to convert specialized or unique forms of nuclear material into a stable solid glass product that can be safely shipped, stored or reprocessed according to the DOE complex mission. This project is an application of technology developed through funds from the Office of Technology Development (OTD). This technology is ideally suited for vitrifying relatively small quantities of fissile or special nuclear material since it is designed to be critically safe. Successful demonstration of this system to safely vitrify radioactive material could open up numerous opportunities for transferring this technology to applications throughout the DOE complex

  9. WEST VALLEY DEMONSTRATION PROJECT ANNUAL SITE ENVIRONMENTAL REPORT CALENDAR YEAR 2002

    International Nuclear Information System (INIS)

    2003-01-01

    This annual environmental monitoring report for the West Valley Demonstration Project (WVDP or Project) is published to inform those with interest about environmental conditions at the WVDP. In accordance with U.S. Department of Energy (DOE) Order 231.1, Environment, Safety, and Health Reporting, the report summarizes calendar year (CY) 2002 environmental monitoring data so as to describe the performance of the WVDP's environmental management system, confirm compliance with standards and regulations, and highlight important programs. In 2002, the West Valley Demonstration Project, the site of a DOE environmental cleanup activity operated by West Valley Nuclear Services Co. (WVNSCO), was in the final stages of stabilizing high-level radioactive waste (HLW) that remained at the site after commercial nuclear fuel reprocessing had been discontinued in the early 1970s. The Project is located in western New York State, about 30 miles south of Buffalo, within the New York State-owned Western New York Nuclear Service Center (WNYNSC). The WVDP is being conducted in cooperation with the New York State Energy Research and Development Authority (NYSERDA). Ongoing work activities at the WVDP during 2002 included: (1) completing HLW solidification and melter shutdown; (2) shipping low-level radioactive waste off-site for disposal; (3) constructing a facility where large high-activity components can be safely packaged for disposal; (4) packaging and removing spent materials from the vitrification facility; (5) preparing environmental impact statements for future activities; (6) removing as much of the waste left behind in waste tanks 8D-1 and 8D-2 as was reasonably possible; (7) removing storage racks, canisters, and debris from the fuel receiving and storage pool, decontaminating pool walls, and beginning shipment of debris for disposal; (8) ongoing decontamination in the general purpose cell and the process mechanical cell (also referred to as the head end cells); (9) planning

  10. WEST VALLEY DEMONSTRATION PROJECT ANNUAL SITE ENVIRONMENTAL REPORT CALENDAR YEAR 2002

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-09-12

    This annual environmental monitoring report for the West Valley Demonstration Project (WVDP or Project) is published to inform those with interest about environmental conditions at the WVDP. In accordance with U.S. Department of Energy (DOE) Order 231.1, Environment, Safety, and Health Reporting, the report summarizes calendar year (CY) 2002 environmental monitoring data so as to describe the performance of the WVDP's environmental management system, confirm compliance with standards and regulations, and highlight important programs. In 2002, the West Valley Demonstration Project, the site of a DOE environmental cleanup activity operated by West Valley Nuclear Services Co. (WVNSCO), was in the final stages of stabilizing high-level radioactive waste (HLW) that remained at the site after commercial nuclear fuel reprocessing had been discontinued in the early 1970s. The Project is located in western New York State, about 30 miles south of Buffalo, within the New York State-owned Western New York Nuclear Service Center (WNYNSC). The WVDP is being conducted in cooperation with the New York State Energy Research and Development Authority (NYSERDA). Ongoing work activities at the WVDP during 2002 included: (1) completing HLW solidification and melter shutdown; (2) shipping low-level radioactive waste off-site for disposal; (3) constructing a facility where large high-activity components can be safely packaged for disposal; (4) packaging and removing spent materials from the vitrification facility; (5) preparing environmental impact statements for future activities; (6) removing as much of the waste left behind in waste tanks 8D-1 and 8D-2 as was reasonably possible; (7) removing storage racks, canisters, and debris from the fuel receiving and storage pool, decontaminating pool walls, and beginning shipment of debris for disposal; (8) ongoing decontamination in the general purpose cell and the process mechanical cell (also referred to as the head end cells); (9

  11. Prototypical consolidation demonstration project - Final fuel recommendation report

    International Nuclear Information System (INIS)

    Piscitella, R.R.; Paskey, W.R.

    1987-01-01

    The Prototypical Consolidation Demonstration (PCD) Project will, in its final phase, conduct a demonstration of the equipment's ability to consolidate actual spent commercial fuel. Since budget and schedule limitations do not allow this demonstration to include all types of fuel assemblies, a selection process was utilized to identify the fuel types that would represent predominate fuel inventories and that would demonstrate the equipment's abilities. The Pressurized Water Reactor (PWR) fuel assemblies that were suggested for use in the PCD Project Hot Demonstration were Babcock and Wilcox (B and W) 15 x 15's, and Westinghouse (WE) 15 x 15's. The Boiling Water Reactor (BWR) fuel suggested was the General Electric (GE) 8 x 8

  12. A nationwide survey of patient centered medical home demonstration projects.

    Science.gov (United States)

    Bitton, Asaf; Martin, Carina; Landon, Bruce E

    2010-06-01

    The patient centered medical home has received considerable attention as a potential way to improve primary care quality and limit cost growth. Little information exists that systematically compares PCMH pilot projects across the country. Cross-sectional key-informant interviews. Leaders from existing PCMH demonstration projects with external payment reform. We used a semi-structured interview tool with the following domains: project history, organization and participants, practice requirements and selection process, medical home recognition, payment structure, practice transformation, and evaluation design. A total of 26 demonstrations in 18 states were interviewed. Current demonstrations include over 14,000 physicians caring for nearly 5 million patients. A majority of demonstrations are single payer, and most utilize a three component payment model (traditional fee for service, per person per month fixed payments, and bonus performance payments). The median incremental revenue per physician per year was $22,834 (range $720 to $91,146). Two major practice transformation models were identified--consultative and implementation of the chronic care model. A majority of demonstrations did not have well-developed evaluation plans. Current PCMH demonstration projects with external payment reform include large numbers of patients and physicians as well as a wide spectrum of implementation models. Key questions exist around the adequacy of current payment mechanisms and evaluation plans as public and policy interest in the PCMH model grows.

  13. Integrated monitoring and surveillance system demonstration project: Phase I accomplishments

    International Nuclear Information System (INIS)

    Aumeier, S.E.; Walters, B.G.; Crawford, D.C.

    1997-01-01

    The authors present the results of the Integrated Monitoring and Surveillance System (IMSS) demonstration project Phase I efforts. The rationale behind IMSS development is reviewed and progress in each of the 5 basic tasks is detailed. Significant results include decisions to use Echelon LonWorks networking protocol and Microsoft Access for the data system needs, a preliminary design for the plutonium canning system glovebox, identification of facilities and materials available for the demonstration, determination of possibly affected facility documentation, and a preliminary list of available sensor technologies. Recently imposed changes in the overall project schedule and scope are also discussed and budgetary requirements for competition of Phase II presented. The results show that the IMSS demonstration project team has met and in many cases exceeded the commitments made for Phase I deliverables

  14. Final Report - Navajo Electrification Demonstration Project - FY2004

    Energy Technology Data Exchange (ETDEWEB)

    Kenneth L. Craig, Interim General Manager

    2007-03-31

    The Navajo Electrification Demonstration Project (NEDP) is a multi-year projects which addresses the needs of unserved Navajo Nation residents without basic electricity services. The Navajo Nation is the United States' largest tribe, in terms of population and land. An estimated 18,000 Navajo Nation homes do not have basic grid-tied electricity--and this third year of funding, known as NEDP-3, provided 351 power line extensions to Navajo families.

  15. Hydrogen demonstration projects options in the Netherlands. Final report

    International Nuclear Information System (INIS)

    Bergsma, G.C.; Van der Werff, T.T.; Rooijers, F.J.

    1996-01-01

    Based on a survey of hydrogen demonstration projects, contacts with different actors and discussions in a sounding board for the study on the title subject, it is concluded that a conference can be organized where the possibilities of setting up hydrogen demonstration projects in the Netherlands can be discussed. The following projects offer good chances to be realized in the next few years: large-scale CO 2 storage in the underground, applying enhanced gas recovery. It appears to be a relatively cheap CO 2 emission reduction measure with a large potential. It can be combined with a hydrogen mixing project with the sale of hydrogen as a so-called eco-gas to consumers. There is little interest in the other options for CO 2 storage at coal gasification and the prompt supply of 100% H 2 to small-scale consumers. Hydrogen for cogeneration, fuel cells in the industry, hydrogen in road transport and hydrogen as a storage medium are projects in which some actors are interested. Hydrogen for air transport has a large potential to which only few parties in the Netherlands can anticipate. Hydrogen demonstration projects will show important surplus value when it is supported by a hydrogen research program. Such a program can be carried out in cooperation with several other programmes of the International Energy Agency, in Japan, Germany and a number of research programs of the Netherlands Agency for Energy and the Environment (Novem). 10 figs., 4 tabs., 33 refs

  16. Preliminary hazards analysis -- vitrification process

    International Nuclear Information System (INIS)

    Coordes, D.; Ruggieri, M.; Russell, J.; TenBrook, W.; Yimbo, P.

    1994-06-01

    This paper presents a Preliminary Hazards Analysis (PHA) for mixed waste vitrification by joule heating. The purpose of performing a PHA is to establish an initial hazard categorization for a DOE nuclear facility and to identify those processes and structures which may have an impact on or be important to safety. The PHA is typically performed during and provides input to project conceptual design. The PHA is then followed by a Preliminary Safety Analysis Report (PSAR) performed during Title 1 and 2 design. The PSAR then leads to performance of the Final Safety Analysis Report performed during the facility's construction and testing. It should be completed before routine operation of the facility commences. This PHA addresses the first four chapters of the safety analysis process, in accordance with the requirements of DOE Safety Guidelines in SG 830.110. The hazards associated with vitrification processes are evaluated using standard safety analysis methods which include: identification of credible potential hazardous energy sources; identification of preventative features of the facility or system; identification of mitigative features; and analyses of credible hazards. Maximal facility inventories of radioactive and hazardous materials are postulated to evaluate worst case accident consequences. These inventories were based on DOE-STD-1027-92 guidance and the surrogate waste streams defined by Mayberry, et al. Radiological assessments indicate that a facility, depending on the radioactive material inventory, may be an exempt, Category 3, or Category 2 facility. The calculated impacts would result in no significant impact to offsite personnel or the environment. Hazardous materials assessment indicates that a Mixed Waste Vitrification facility will be a Low Hazard facility having minimal impacts to offsite personnel and the environment

  17. Preliminary hazards analysis -- vitrification process

    Energy Technology Data Exchange (ETDEWEB)

    Coordes, D.; Ruggieri, M.; Russell, J.; TenBrook, W.; Yimbo, P. [Science Applications International Corp., Pleasanton, CA (United States)

    1994-06-01

    This paper presents a Preliminary Hazards Analysis (PHA) for mixed waste vitrification by joule heating. The purpose of performing a PHA is to establish an initial hazard categorization for a DOE nuclear facility and to identify those processes and structures which may have an impact on or be important to safety. The PHA is typically performed during and provides input to project conceptual design. The PHA is then followed by a Preliminary Safety Analysis Report (PSAR) performed during Title 1 and 2 design. The PSAR then leads to performance of the Final Safety Analysis Report performed during the facility`s construction and testing. It should be completed before routine operation of the facility commences. This PHA addresses the first four chapters of the safety analysis process, in accordance with the requirements of DOE Safety Guidelines in SG 830.110. The hazards associated with vitrification processes are evaluated using standard safety analysis methods which include: identification of credible potential hazardous energy sources; identification of preventative features of the facility or system; identification of mitigative features; and analyses of credible hazards. Maximal facility inventories of radioactive and hazardous materials are postulated to evaluate worst case accident consequences. These inventories were based on DOE-STD-1027-92 guidance and the surrogate waste streams defined by Mayberry, et al. Radiological assessments indicate that a facility, depending on the radioactive material inventory, may be an exempt, Category 3, or Category 2 facility. The calculated impacts would result in no significant impact to offsite personnel or the environment. Hazardous materials assessment indicates that a Mixed Waste Vitrification facility will be a Low Hazard facility having minimal impacts to offsite personnel and the environment.

  18. Global Inventory and Analysis of Smart Grid Demonstration Projects

    Energy Technology Data Exchange (ETDEWEB)

    Mulder, W.; Kumpavat, K.; Faasen, C.; Verheij, F.; Vaessen, P [DNV KEMA Energy and Sustainability, Arnhem (Netherlands)

    2012-10-15

    As the key enabler of a more sustainable, economical and reliable energy system, the development of smart grids has received a great deal of attention in recent times. In many countries around the world the benefits of such a system have begun to be investigated through a number of demonstration projects. With such a vast array of projects it can be difficult to keep track of changes, and to understand which best practices are currently available with regard to smart grids. This report aims to address these issues through providing a comprehensive outlook on the current status of smart grid projects worldwide.

  19. Residential Energy Efficiency Demonstration: Hawaii and Guam Energy Improvement Technology Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Earle, L. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Sparn, B. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Rutter, A. [Sustainability Solutions LLC (Guam); Briggs, D. [Naval Base Guam, Santa Rita (Guam)

    2014-03-01

    In order to meet its energy goals, the Department of Defense (DOD) has partnered with the Department of Energy (DOE) to rapidly demonstrate and deploy cost-effective renewable energy and energy-efficiency technologies. The scope of this project was to demonstrate tools and technologies to reduce energy use in military housing, with particular emphasis on measuring and reducing loads related to consumer electronics (commonly referred to as 'plug loads'), hot water, and whole-house cooling.

  20. Crawler Acquisition and Testing Demonstration Project Management Plan

    International Nuclear Information System (INIS)

    DEFIGH-PRICE, C.

    2000-01-01

    If the crawler based retrieval system is selected, this project management plan identifies the path forward for acquiring a crawler/track pump waste retrieval system, and completing sufficient testing to support deploying the crawler for as part of a retrieval technology demonstration for Tank 241-C-104. In the balance of the document, these activities will be referred to as the Crawler Acquisition and Testing Demonstration. During recent Tri-Party Agreement negotiations, TPA milestones were proposed for a sludge/hard heel waste retrieval demonstration in tank C-104. Specifically one of the proposed milestones requires completion of a cold demonstration of sufficient scale to support final design and testing of the equipment (M-45-03G) by 6/30/2004. A crawler-based retrieval system was one of the two options evaluated during the pre-conceptual engineering for C-104 retrieval (RPP-6843 Rev. 0). The alternative technology procurement initiated by the Hanford Tanks Initiative (HTI) project, combined with the pre-conceptual engineering for C-104 retrieval provide an opportunity to achieve compliance with the proposed TPA milestone M-45-03H. This Crawler Acquisition and Testing Demonstration project management plan identifies the plans, organizational interfaces and responsibilities, management control systems, reporting systems, timeline and requirements for the acquisition and testing of the crawler based retrieval system. This project management plan is complimentary to and supportive of the Project Management Plan for Retrieval of C-104 (RPP-6557). This project management plan focuses on utilizing and completing the efforts initiated under the Hanford Tanks Initiative (HTI) to acquire and cold test a commercial crawler based retrieval system. The crawler-based retrieval system will be purchased on a schedule to support design of the waste retrieval from tank C-104 (project W-523) and to meet the requirement of proposed TPA milestone M-45-03H. This Crawler

  1. District heating demonstration project. Swiecie, Poland. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-01

    In January 1997 the district heating company in Swiecie, Poland, was donated DKK 1.3 Mio. as a part of the environmental related energy sector programme by the Danish government for a demonstration project. The Danish consultancy company Carl Bro a/s was appointed to conduct the work. The project was finished in January 1999. The present final report outlines the activities of the demonstration project. The activities of the project were several. Carl Bro a/s elaborated tender documents and procured 79 heat meters for all the substrations in the city in order to prepare for the new energy law and a changed tariff system which was introduced in January 1999. Carl Bro a/s further supported ZEC Swiecie in the development of their new tariff system through information from Danish district heating companies. The demonstration project was designed in the first phase of the project. During the design period one engineer from Swiecie participated in a study tour to Denmark to learn about technical solutions to present problems in Poland. The training course focused on preparation of hot tap water. The site for the demonstation project was in the centre of Swiecie in a housing society located in Wojska Polskiego. The blocks 75 and 75A were selected for modernisation of the substations, and block no. 73 was appointed as a reference block in which only a heat meter was installed. Further, block 75A was equipped with thermostatic valves at all the radiators in the flats. The registered savings during the monitoring period were between 7% and 14%, and an increased comfort in the flats was observed. The housing society`s board of directors were so pleased with the project that by their initiative block no. 77 was refurbished in the same way as the blocks covered by the demonstration project. However, the activities were extended with individual heat meters and the introduction of a new tariff system for the block. The energy savings from this project were substantial, and today

  2. West Valley Demonstration Project, Waste Management Area #3 -- Closure Alternative I

    Energy Technology Data Exchange (ETDEWEB)

    Marschke, Stephen F. [Environmental Measurements Laboratory (EML), New York, NY (United States)

    2000-06-30

    The Draft Environmental Impact Statement for the completion of the West Valley Demonstration Project and closure and/or long-term management of facilities at the Western New York Nuclear Service Center divided the site into Waste Management Areas (WMAs), and for each WMA, presented the impacts associated with five potential closure alternatives. This report focuses on WMA 3 (the High-Level Waste (HLW) Storage Area (Tanks 8D-1 and 8D-2), the Vitrification Facility and other facilities) and closure Alternative I (the complete removal of all structures, systems and components and the release of the area for unrestricted use), and reestimates the impacts associated with the complete removal of the HLW tanks, and surrounding facilities. A 32-step approach was developed for the complete removal of Tanks 8D-1 and 8D-2, the Supernatant Treatment System Support Building, and the Transfer Trench. First, a shielded Confinement Structure would be constructed to reduce the shine dose rate and to control radioactivity releases. Similarly, the tank heels would be stabilized to reduce potential radiation exposures. Next, the tank removal methodology would include: 1) excavation of the vault cover soil, 2) removal of the vault roof, 3) cutting off the tank’s top, 4) removal of the stabilized heel remaining inside the tank, 5) cutting up the tank’s walls and floor, 6) removal of the vault’s walls, the perlite blocks, and vault floor, and 7) radiation surveying and backfilling the resulting hole. After the tanks are removed, the Confinement Structure would be decontaminated and dismantled, and the site backfilled and landscaped. The impacts (including waste disposal quantities, emissions, work-effort, radiation exposures, injuries and fatalities, consumable materials used, and costs) were estimated based on this 32 step removal methodology, and added to the previously estimated impacts for closure of the other facilities within WMA 3 to obtain the total impacts from

  3. Prospects for vitrification of mixed wastes at ANL-E

    International Nuclear Information System (INIS)

    Mazer, J.; No, Hyo.

    1993-01-01

    This report summarizes a study evaluating the prospects for vitrification of some of the mixed wastes at ANL-E. This project can be justified on the following basis: Some of ANL-E's mixed waste streams will be stabilized such that they can be treated as a low-level radioactive waste. The expected volume reduction that results during vitrification will significantly reduce the overall waste volume requiring disposal. Mixed-waste disposal options currently used by ANL-E may not be permissible in the near future without treatment technologies such as vitrification

  4. AN OPTICAL CHARACTER RECOGNITION RESEARCH AND DEMONSTRATION PROJECT.

    Science.gov (United States)

    1968

    RESEARCH AND DEVELOPMENT OF PROTOTYPE LIBRARY SYSTEMS WHICH UTILIZE OPTICAL CHARACTER RECOGNITION INPUT HAS CENTERED AROUND OPTICAL PAGE READERS AND DOCUMENT READERS. THE STATE-OF-THE-ART OF BOTH THESE OPTICAL SCANNERS IS SUCH THAT BOTH ARE ACCEPTABLE FOR LIBRARY INPUT PREPARATION. A DEMONSTRATION PROJECT UTILIZING THE TWO TYPES OF READERS, SINCE…

  5. 76 FR 12080 - TRICARE Access to Care Demonstration Project

    Science.gov (United States)

    2011-03-04

    ... parties of a Military Health System (MHS) Demonstration project under the authority of Title 10, U.S. Code... of Service (POS) deductibles and cost shares shall apply to these four unmanaged visits. Additionally... TRICARE authorized provider or UCC without incurring POS deductibles and cost shares. The ADSM and family...

  6. 76 FR 80907 - TRICARE Prime Urgent Care Demonstration Project

    Science.gov (United States)

    2011-12-27

    ... care including minor illness or injury for Active Duty Family Members enrolled in TRICARE Prime or.... Current data indicates that the ADFMs frequently need urgent care while traveling to new duty stations for... DEPARTMENT OF DEFENSE Office of the Secretary TRICARE Prime Urgent Care Demonstration Project...

  7. NRC assessment of the Department of Energy annealing demonstration project

    International Nuclear Information System (INIS)

    Jackson, D.A.; Malik, S.N.

    1997-01-01

    Thermal annealing is the only known method for mitigating the effects of neutron irradiation embrittlement in reactor pressure vessel (RPV) steels. In May 1996, the US Department of Energy (DOE) in conjunction with the American Society of Mechanical Engineers, Westinghouse, Cooperheat, Electric Power Research Institute (with participating utilities), Westinghouse Owner's Group, Consumers Power, Electricite' de France, Duquesne Light and the Central Research Institute of the Electric Power Industry (Japan) sponsored an annealing demonstration project (ADP) at Marble Hill. The Marble Hill Plant, located in Madison, Indiana, is a Westinghouse 4 loop design. The plant was nearly 70% completed when the project was canceled. Hence, the RPV was never irradiated. The paper will present highlights from the NRCs independent evaluation of the Marble Hill Annealing Demonstration Project

  8. SELENIUM TREATMENT/REMOVAL ALTERNATIVES DEMONSTRATION PROJECT - MINE WASTE TECHNOLOGY PROGRAM ACTIVITY III, PROJECT 20

    Science.gov (United States)

    This document is the final report for EPA's Mine WAste Technology Program (MWTP) Activity III, Project 20--Selenium Treatment/Removal Alternatives Demonstration project. Selenium contamination originates from many sources including mining operations, mineral processing, abandoned...

  9. A Nationwide Survey of Patient Centered Medical Home Demonstration Projects

    Science.gov (United States)

    Bitton, Asaf; Martin, Carina

    2010-01-01

    Background The patient centered medical home has received considerable attention as a potential way to improve primary care quality and limit cost growth. Little information exists that systematically compares PCMH pilot projects across the country. Design Cross-sectional key-informant interviews. Participants Leaders from existing PCMH demonstration projects with external payment reform. Measurements We used a semi-structured interview tool with the following domains: project history, organization and participants, practice requirements and selection process, medical home recognition, payment structure, practice transformation, and evaluation design. Results A total of 26 demonstrations in 18 states were interviewed. Current demonstrations include over 14,000 physicians caring for nearly 5 million patients. A majority of demonstrations are single payer, and most utilize a three component payment model (traditional fee for service, per person per month fixed payments, and bonus performance payments). The median incremental revenue per physician per year was $22,834 (range $720 to $91,146). Two major practice transformation models were identified—consultative and implementation of the chronic care model. A majority of demonstrations did not have well-developed evaluation plans. Conclusion Current PCMH demonstration projects with external payment reform include large numbers of patients and physicians as well as a wide spectrum of implementation models. Key questions exist around the adequacy of current payment mechanisms and evaluation plans as public and policy interest in the PCMH model grows. Electronic supplementary material The online version of this article (doi:10.1007/s11606-010-1262-8) contains supplementary material, which is available to authorized users. PMID:20467907

  10. Solidification and vitrification life-cycle economics study

    International Nuclear Information System (INIS)

    Gimpel, R.F.

    1992-01-01

    Solidification (making concrete) and vitrification (making glass) are frequently the treatment methods recommended for treating inorganic or radioactive wastes. Solidification is generally perceived as the most economical treatment method, whereas vitrification is considered (by many) as the most effective of all treatment methods. Unfortunately, vitrification has acquired the stigma that it is too expensive to receive further consideration as an alternative to solidification in high volume treatment applications. Ex situ solidification and vitrification are the competing methods for treating in excess of 450,000 m 3 of low-level radioactive and mixed waste at the Fernald Environmental Management Project (FEMP or simply, Fernald) located near Cincinnati, Ohio. This paper s a detailed study done to: compare the economics of the solidification and vitrification processes; determine if the stigma assigned to vitrification is warranted; determine if investing millions of dollars into vitrification development, along with solidification development, at Fernald is warranted. Common parameters were determined and detailed life-cycle cost estimates were made. Incorporating the unit costs into a computer spreadsheet allowed 'what if' scenarios to be performed. Some scenarios investigated included variation of: remediation times, amount of wastes treated, treatment efficiencies, electrical and material costs and escalation

  11. McIntosh Unit 4 PCFB demonstration project

    Energy Technology Data Exchange (ETDEWEB)

    Dodd, A.M. [Lakeland Electric and Water, FL (United States); Dryden, R.J. [Foster Wheeler Development Corp., San Diego, CA (United States); Morehead, H.T. [Westinghouse Electric Corp., Orlando, FL (United States)

    1997-12-31

    The City of Lakeland, Foster Wheeler Corporation and Westinghouse Electric Corporation have embarked on a utility scale demonstration of Pressurized Circulating Fluidized Bed (PCFB) technology at Lakeland`s McIntosh Power Station in Lakeland, Florida. The US Department of Energy will be providing approximately $195 million of funding for the project through two Cooperative Agreements under the auspices of the Clean Coal Technology Program. The project will involve the commercial demonstration of Foster Wheeler Pyroflow PCFB technology integrated with Westinghouse`s Hot Gas Filter (HGF) and power generation technologies. The total project duration will be approximately eight years and will be structured into three separate phases; two years of design and permitting, followed by an initial period of two years of fabrication and construction and concluding with a four year demonstration (commercial operation) period. It is expected that the project will show that Foster Wheeler`s Pyroflow PCFB technology coupled with Westinghouse`s HGF and power generation technologies represents a cost effective, high efficiency, low emissions means of adding greenfield generation capacity and that this same technology is also well suited for repowering applications.

  12. Habitat Demonstration Unit Project Leadership and Management Strategies

    Science.gov (United States)

    Kennedy, Kriss J.

    2011-01-01

    This paper gives an overview of the National Aeronautics and Space Administration (NASA) led multi-center Habitat Demonstration Unit (HDU) project leadership and management strategies. The HDU project team constructed and tested an analog prototype lunar surface habitat/laboratory called the Pressurized Excursion Module (PEM) during 2010. The prototype unit subsystems were integrated in a short amount of time, utilizing a tiger team approach that brought together over 20 habitation-related technologies and innovations from a variety of NASA centers. This paper describes the leadership and management strategies as well as lessons learned pertaining to leading and managing a multi-center diverse team in a rapid prototype environment. The PEM configuration went from a paper design to an operational surface habitat demonstration unit in less than 12 months. The HDU project is part of the strategic plan from the Exploration Systems Mission Directorate (ESMD) Directorate Integration Office (DIO) and the Exploration Mission Systems Office (EMSO) to test destination elements in analog environments. The 2011 HDU-Deep Space Habitat (DSH) configuration will build upon the PEM work, and emphasize validity of crew operations (remote working and living), EVA operations, mission operations, logistics operations, and science operations that might be required in a deep space context for Near Earth Object (NEO) exploration mission architectures. The 2011 HDU-DSH will be field-tested during the 2011 Desert Research and Technologies Studies (DRaTS) field tests. The HDU project is a "technology-pull" project that integrates technologies and innovations from multiple NASA centers. This project will repurpose the HDU 2010 demo unit that was field tested in the 2010 DRaTS, adding habitation functionality to the prototype unit. This paper will describe the strategy of establishing a multi-center project management team that put in place the key multi-center leadership skills and

  13. Design of microwave vitrification systems for radioactive waste

    International Nuclear Information System (INIS)

    White, T.L.; Wilson, C.T.; Schaick, C.R.; Bostick, W.D.

    1996-01-01

    Oak Ridge National Laboratory (ORNL) is involved in the research and development of high-power microwave heating systems for the vitrification of DOE radioactive sludges. Design criteria for a continuous microwave vitrification system capable of processing a surrogate filtercake sludge representative of a typical waste-water treatment operation are discussed. A prototype 915 MHz, 75 kW microwave vitrification system or 'microwave melter' is described along with some early experimental results that demonstrate a 4 to 1 volume reduction of a surrogate ORNL filtercake sludge

  14. Design of microwave vitrification systems for radioactive waste

    International Nuclear Information System (INIS)

    White, T.L.; Wilson, C.T.; Schaich, C.R.; Bostick, T.L.

    1995-01-01

    Oak Ridge National Laboratory (ORNL) is involved in the research and development of high-power microwave heating systems for the vitrification of Department of Energy (DOE) radioactive sludges. Design criteria for a continuous microwave vitrification system capable of processing a surrogate filtercake sludge representative of a typical waste-water treatment operation are discussed. A prototype 915-MHz, 75-kW microwave vitrification system or ''microwave melter'' is described along with some early experimental results that demonstrate a 4 to 1 volume reduction of a surrogate ORNL filtercake sludge

  15. Accelerated Innovation Deployment (AID) Demonstration Project : Intelligent Compaction and Infrared Scanning Projects

    Science.gov (United States)

    2018-02-01

    This report documents the Missouri Department of Transportation (MoDOT) demonstration grant award for field demonstration projects using intelligent compaction (IC) and infrared scanning (IR) (also called paver-mounted thermal profiles PMTP in the AA...

  16. FINDING SOLUTIONS AT THE WEST VALLEY DEMONSTRATION PROJECT

    International Nuclear Information System (INIS)

    Drake, John L.; Gramling, James M.; Houston, Helene M.

    2003-01-01

    The United States Department of Energy Office of Environmental Management (DOE-EM) faces a number of sizeable challenges as it begins to transform its mission from managing risk to reducing and eliminating risk throughout the DOE Complex. One of the greatest challenges being addressed by DOE-EM as this transformation takes place is accelerating the deactivation and decommissioning of thousands of facilities within the DOE Complex that were once used to support nuclear-related programs and projects. These facilities are now unused and aging. Finding solutions to complete the cleanup of these aging facilities more safely, efficiently, and effectively while reducing costs is critical to successfully meeting DOE-EM's cleanup challenge. The Large-Scale Demonstration and Deployment Project (LSDDP) of Hot Cells at the West Valley Demonstration Project (WVDP) is a near-term project funded through the DOE's National Energy Technology Laboratory (DOE-NETL) for the specific purpose of identifying, evaluating, demonstrating, and deploying commercially available technologies that are capable of streamlining the cleanup of hot cells in unused facilities while improving worker safety. Two DOE project sites are participating in this LSDDP: the WVDP site in West Valley, New York and the Hanford River Corridor Project (RCP) site in Richland, Washington. The WVDP site serves as the host site for the project. Technologies considered for demonstration and potential deployment at both LSDDP sites are targeted for application in hot cells that require the use of remote and semi-remote techniques to conduct various cleanup-related activities because of high radiation or high contamination levels. These hot cells, the type of cleanup activities being conducted, and technologies selected for demonstration are the main topics discussed in this paper. The range of cleanup-related activities addressed include in-situ characterization, size-reduction, contamination control, decontamination, in

  17. Rod consolidation at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Bailey, W.J.

    1986-12-01

    A rod consolidation demonstration with irradiated pressurized water reactor fuel was recently conducted by personnel from Nuclear Assurance Corporation and West Valley Nuclear Services Company at the West Valley Demonstration Project in West Valley, New York. The rod consolidation demonstration involved pulling all of the fuel rods from six fuel Assemblies. In general, the rod pulling proceeded smoothly. The highest compaction ratio attained was 1:8:1. Among the total of 1074 fuel rods were some known degraded rods (they had collapsed cladding, a result of in-reactor fuel densification), but no rods were broken or dropped during the demonstration. One aim was to gather information on the effect of rod consolidation operations on the integrity of the fuel rods during subsequent handling and storage. Another goal was to collect information on the condition and handling of intact, damaged, and failed fuel that has been in storage for an extended period. 9 refs., 8 figs., 1 tab

  18. Latest Changes to NASA's Laser Communication Relay Demonstration Project

    Science.gov (United States)

    Edwards, Bernard L.; Israel, David J.; Vithlani, Seema K.

    2018-01-01

    Over the last couple of years, NASA has been making changes to the Laser Communications Relay Demonstration Project (LCRD), a joint project between NASA's Goddard Space Flight Center (GSFC), the Jet Propulsion Laboratory, California Institute of Technology (JPL), and the Massachusetts Institute of Technology Lincoln Laboratory (MIT/LL). The changes made makes LCRD more like a future Earth relay system that has both high speed optical and radio frequency links. This will allow LCRD to demonstrate a more detailed concept of operations for a future operational mission critical Earth relay. LCRD is expected to launch in June 2019 and is expected to be followed a couple of years later with a prototype user terminal on the International Space Station. LCRD's architecture will allow it to serve as a testbed in space and this paper will provide an update of its planned capabilities and experiments.

  19. Integrated Monitoring and Surveillance System demonstration project. Phase 2 accomplishments

    International Nuclear Information System (INIS)

    Aumeier, S.E.; Walters, B.G.; Singleterry, R.C.

    1997-01-01

    The paper presents the results of the Integrated Monitoring and Surveillance System (IMSS) demonstration project Phase 2 efforts. the rationale behind IMSS development is reviewed and progress in each of the 5 basic tasks is detailed. Significant results include further development of the data acquisition system and procurement of necessary hardware/software, options and associated costs for plutonium canning systems and gloveboxes, initiation of facility modifications, determination of possibly affected facility documentation, results from sensor system trade study, and preliminary storage configuration designs. Resources invested during Phase 1 and Phase 2 are summarized and budgetary requirements for completion of Phase 3 presented. The results show that the IMSS demonstration project team has met and in many cases exceeded the commitments made for Phase 2 deliverables

  20. Radiological incident preparedness for community hospitals: a demonstration project.

    Science.gov (United States)

    Jafari, Mary Ellen

    2010-08-01

    In November 2007, the Wisconsin Division of Public Health Hospital Disaster Preparedness Program State Expert Panel on Radiation Emergencies issued a report titled The Management of Patients in a Radiological Incident. Gundersen Lutheran Health System was selected to conduct a demonstration project to implement the recommendations in that report. A comprehensive radiological incident response plan was developed and implemented in the hospital's Trauma and Emergency Center, including the purchase and installation of radiation detection and identification equipment, staff education and training, a tabletop exercise, and three mock incident test exercises. The project demonstrated that the State Expert Panel report provides a flexible template that can be implemented at community hospitals using existing staff for an approximate cost of $25,000.

  1. NUCLA Circulating Atmospheric Fluidized Bed Demonstration Project. 1990 Annual report

    Energy Technology Data Exchange (ETDEWEB)

    1992-02-01

    The objective of this DOE Cooperative Agreement is to conduct a cost-shared clean coal technology project to demonstrate the feasibility of circulating fluidized bed combustion technology and to evaluate economic, environmental, and operational benefits of CFB steam generators on a utility scale. At the conclusion of the Phase 2 program, testing related to satisfying these objectives was completed. Data analysis and reporting are scheduled for completion by October 1991. (VC)

  2. Isolated elders demonstration project : closer to home - a descriptive evaluation

    OpenAIRE

    Cusack, Sandra A.

    1996-01-01

    The purpose of this demonstration project is to support isolated elders through outreach. The goal is to get seniors "out of their homes" and back into the community, assisting them to make decisions and take action on their own behalf. The process involved training a group of volunteers to interview elders, using a mini-life review technique to encourage reminiscence. In listening to their stories, the volunteer's task was to discover the elder's needs and barriers to socialization, and to l...

  3. Controlled Hydrogen Fleet and Infrastructure Demonstration and Validation Project

    Energy Technology Data Exchange (ETDEWEB)

    Stottler, Gary

    2012-02-08

    General Motors, LLC and energy partner Shell Hydrogen, LLC, deployed a system of hydrogen fuel cell electric vehicles integrated with a hydrogen fueling station infrastructure to operate under real world conditions as part of the U.S. Department of Energy's Controlled Hydrogen Fleet and Infrastructure Validation and Demonstration Project. This technical report documents the performance and describes the learnings from progressive generations of vehicle fuel cell system technology and multiple approaches to hydrogen generation and delivery for vehicle fueling.

  4. One System Integrated Project Team: Retrieval And Delivery Of The Hanford Tank Wastes For Vitrification In The Waste Treatment Plant

    International Nuclear Information System (INIS)

    Harp, Benton J.; Kacich, Richard M.; Skwarek, Raymond J.

    2012-01-01

    The One System Integrated Project Team (IPT) was formed in late 2011 as a way for improving the efficiency of delivery and treatment of highly radioactive waste stored in underground tanks at the U.S. Department of Energy's (DOE's) 586-square-mile Hanford Site in southeastern Washington State. The purpose of the One System IPT is to improve coordination and integration between the Hanford's Waste Treatment Plant (WTP) contractor and the Tank Operations Contractor (TOC). The vision statement is: One System is a WTP and TOC safety conscious team that, through integrated management and implementation of risk-informed decision and mission-based solutions, will enable the earliest start of safe and efficient treatment of Hanford's tank waste, to protect the Columbia River, environment and public. The IPT is a formal collaboration between Bechtel National, Inc. (BNI), which manages design and construction of the WTP for the U.S. Department of Energy's Office of River Protection (DOEORP), and Washington River Protection Solutions (WRPS), which manages the TOC for ORP. More than fifty-six (56) million gallons of highly radioactive liquid waste are stored in one hundred seventy-seven (177) aging, underground tanks. Most of Hanford's waste tanks - one hundred forty-nine (149) of them - are of an old single-shell tank (SST) design built between 1944 and 1964. More than sixty (60) of these tanks have leaked in the past, releasing an estimated one million gallons of waste into the soil and threatening the nearby Columbia River. There are another twenty-eight (28) new double-shelled tanks (DSTs), built from 1968 to 1986, that provide greater protection to the environment. In 1989, DOE, the U.S. Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) signed a landmark agreement that required Hanford to comply with federal and state environmental standards. It also paved the way for agreements that set deadlines for retrieving the tank

  5. One System Integrated Project Team: Retrieval And Delivery Of The Hanford Tank Wastes For Vitrification In The Waste Treatment Plant

    Energy Technology Data Exchange (ETDEWEB)

    Harp, Benton J. [Department of Energy, Office of River Protection, Richland, Washington (United States); Kacich, Richard M. [Bechtel National, Inc., Richland, WA (United States); Skwarek, Raymond J. [Washington River Protection Solutions LLC, Richland, WA (United States)

    2012-12-20

    The One System Integrated Project Team (IPT) was formed in late 2011 as a way for improving the efficiency of delivery and treatment of highly radioactive waste stored in underground tanks at the U.S. Department of Energy's (DOE's) 586-square-mile Hanford Site in southeastern Washington State. The purpose of the One System IPT is to improve coordination and integration between the Hanford's Waste Treatment Plant (WTP) contractor and the Tank Operations Contractor (TOC). The vision statement is: One System is a WTP and TOC safety conscious team that, through integrated management and implementation of risk-informed decision and mission-based solutions, will enable the earliest start of safe and efficient treatment of Hanford's tank waste, to protect the Columbia River, environment and public. The IPT is a formal collaboration between Bechtel National, Inc. (BNI), which manages design and construction of the WTP for the U.S. Department of Energy's Office of River Protection (DOEORP), and Washington River Protection Solutions (WRPS), which manages the TOC for ORP. More than fifty-six (56) million gallons of highly radioactive liquid waste are stored in one hundred seventy-seven (177) aging, underground tanks. Most of Hanford's waste tanks - one hundred forty-nine (149) of them - are of an old single-shell tank (SST) design built between 1944 and 1964. More than sixty (60) of these tanks have leaked in the past, releasing an estimated one million gallons of waste into the soil and threatening the nearby Columbia River. There are another twenty-eight (28) new double-shelled tanks (DSTs), built from 1968 to 1986, that provide greater protection to the environment. In 1989, DOE, the U.S. Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) signed a landmark agreement that required Hanford to comply with federal and state environmental standards. It also paved the way for agreements that set deadlines for retrieving the tank

  6. One System Integrated Project Team: Retrieval and Delivery of Hanford Tank Wastes for Vitrification in the Waste Treatment Plant - 13234

    International Nuclear Information System (INIS)

    Harp, Benton J.; Kacich, Richard M.; Skwarek, Raymond J.

    2013-01-01

    The One System Integrated Project Team (IPT) was formed in late 2011 as a way for improving the efficiency of delivery and treatment of highly radioactive waste stored in underground tanks at the U.S. Department of Energy's (DOE's) 586-square-mile Hanford Site in southeastern Washington State. The purpose of the One System IPT is to improve coordination and integration between the Hanford's Waste Treatment Plant (WTP) contractor and the Tank Operations Contractor (TOC). The vision statement is: One System is a WTP and TOC safety-conscious team that, through integrated management and implementation of risk-informed decision and mission-based solutions, will enable the earliest start of safe and efficient treatment of Hanford's tank waste, to protect the Columbia River, environment and public. The IPT is a formal collaboration between Bechtel National, Inc. (BNI), which manages design and construction of the WTP for the U.S. Department of Energy's Office of River Protection (DOEORP), and Washington River Protection Solutions (WRPS), which manages the TOC for ORP. More than fifty-six (56) million gallons of highly radioactive liquid waste are stored in one hundred seventy-seven (177) aging, underground tanks. Most of Hanford's waste tanks - one hundred forty-nine (149) of them - are of an old single-shell tank (SST) design built between 1944 and 1964. More than sixty (60) of these tanks have leaked in the past, releasing an estimated one million gallons of waste into the soil and threatening the nearby Columbia River. There are another twenty-eight (28) new double-shelled tanks (DSTs), built from 1968 to 1986, that provide greater protection to the environment. In 1989, DOE, the U.S. Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) signed a landmark agreement that required Hanford to comply with federal and state environmental standards. It also paved the way for agreements that set deadlines for retrieving the tank

  7. One System Integrated Project Team: Retrieval and Delivery of Hanford Tank Wastes for Vitrification in the Waste Treatment Plant - 13234

    Energy Technology Data Exchange (ETDEWEB)

    Harp, Benton J. [U.S. Department of Energy, Office of River Protection, Post Office Box 550, Richland, Washington 99352 (United States); Kacich, Richard M. [Bechtel National, Inc., 2435 Stevens Center Place, Richland, Washington 99354 (United States); Skwarek, Raymond J. [Washington River Protection Solutions LLC, Post Office Box 850, Richland, Washington 99352 (United States)

    2013-07-01

    The One System Integrated Project Team (IPT) was formed in late 2011 as a way for improving the efficiency of delivery and treatment of highly radioactive waste stored in underground tanks at the U.S. Department of Energy's (DOE's) 586-square-mile Hanford Site in southeastern Washington State. The purpose of the One System IPT is to improve coordination and integration between the Hanford's Waste Treatment Plant (WTP) contractor and the Tank Operations Contractor (TOC). The vision statement is: One System is a WTP and TOC safety-conscious team that, through integrated management and implementation of risk-informed decision and mission-based solutions, will enable the earliest start of safe and efficient treatment of Hanford's tank waste, to protect the Columbia River, environment and public. The IPT is a formal collaboration between Bechtel National, Inc. (BNI), which manages design and construction of the WTP for the U.S. Department of Energy's Office of River Protection (DOEORP), and Washington River Protection Solutions (WRPS), which manages the TOC for ORP. More than fifty-six (56) million gallons of highly radioactive liquid waste are stored in one hundred seventy-seven (177) aging, underground tanks. Most of Hanford's waste tanks - one hundred forty-nine (149) of them - are of an old single-shell tank (SST) design built between 1944 and 1964. More than sixty (60) of these tanks have leaked in the past, releasing an estimated one million gallons of waste into the soil and threatening the nearby Columbia River. There are another twenty-eight (28) new double-shelled tanks (DSTs), built from 1968 to 1986, that provide greater protection to the environment. In 1989, DOE, the U.S. Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) signed a landmark agreement that required Hanford to comply with federal and state environmental standards. It also paved the way for agreements that set deadlines

  8. The Plasma Hearth Process demonstration project for mixed waste treatment

    International Nuclear Information System (INIS)

    Geimer, R.; Dwight, C.; McClellan, G.

    1994-01-01

    The Plasma Hearth Process (PHP) demonstration project is one of the key technology projects in the Department of Energy (DOE) Office of Technology Development (OTD) Mixed Waste Integrated Program (MWIP). Testing to date has yielded encouraging results in displaying potential applications for the PHP technology. Early tests have shown that a wide range of waste materials can be readily processed in the PHP and converted to a vitreous product. Waste materials can be treated in their original container as received at the treatment facility, without pretreatment. The vitreous product, when cooled, exhibits excellent performance in leach resistance, consistently exceeding the Environmental Protection Agency (EPA) Toxicity Characteristic Leaching Procedure (TCLP) requirements. Performance of the Demonstration System during test operations has been shown to meet emission requirements. An accelerated development phase, being conducted at both bench- and pilot-scale on both nonradioactive and radioactive materials, will confirm the viability of the process. It is anticipated that, as a result of this accelerated technology development and demonstration phase, the PHP will be ready for a final field-level demonstration within three years

  9. Vitrification: a solution for the wastes of wastes; La vitrification: ca chauffe pour les ultimes

    Energy Technology Data Exchange (ETDEWEB)

    Guihard, B. [Europlasma, 33 - Saint Medard en Jalles (France)

    1997-07-01

    The incineration of wastes generates other wastes (fly ashes) that concentrate a large amount of polluting substances (heavy metals, salts..). French law requires a stabilization of this kind of wastes before their storage. Today vitrification can be considered as an alternative to the stabilization and storage way, the vitrified products could be seen as an interesting material in the building industry or in road works. A few years ago the municipality of Bordeaux decided to launch a demonstration program and a REFIOM (fly ashes) vitrification unit has been operating since 1997. (A.C.)

  10. Vitrification of reactor wastes

    International Nuclear Information System (INIS)

    Jouan, A.

    1993-01-01

    The vitrification of low and intermediate level wastes from the NPP operation has been studied in the frame of a Franco-Czech agreement. The laboratory experiments concentrated on a search for a suitable borosilicate glass matrix which could incorporate relatively high quantities of boron and sodium, main components of liquid wastes from the WWER reactor type NPPs. A relatively wide area of waste compositions has been studied and properties of glasses suitable for the technology and waste disposal were measured. Great attention has been paid to the chemical stability (leachability), other properties like thermal dependence of viscosity and electrical conductivity of melts, and the microstructure of the final solidification product have also been evaluated. The feasibility of the vitrification process has been proved during pilot plant tests which were accomplished at the French establishment in Marcoule. The results of tests were promising. (authors). 4 tabs., 7 figs

  11. Vitrification of reactor wastes

    Energy Technology Data Exchange (ETDEWEB)

    Jouan, A [CEA Centre d` Etudes de la Vallee du Rhone, 30 - Marcoule (France). Dept. des Procedes de Retraitement; Sussmilch, J [Nuclear Research Institut, Rez (Czech Republic)

    1994-12-31

    The vitrification of low and intermediate level wastes from the NPP operation has been studied in the frame of a Franco-Czech agreement. The laboratory experiments concentrated on a search for a suitable borosilicate glass matrix which could incorporate relatively high quantities of boron and sodium, main components of liquid wastes from the WWER reactor type NPPs. A relatively wide area of waste compositions has been studied and properties of glasses suitable for the technology and waste disposal were measured. Great attention has been paid to the chemical stability (leachability), other properties like thermal dependence of viscosity and electrical conductivity of melts, and the microstructure of the final solidification product have also been evaluated. The feasibility of the vitrification process has been proved during pilot plant tests which were accomplished at the French establishment in Marcoule. The results of tests were promising. (authors). 4 tabs., 7 figs.

  12. Texas ''Recycled Content''/Advanced Green Builder Demonstration Home Project

    International Nuclear Information System (INIS)

    Fisk, P. III; Vittori, G.

    1993-01-01

    This paper presents an overview of principal issues addressed in the Advanced Green Builder Demonstration Home Project, with units to be constructed in Austin and Laredo. The project's objective is to introduce these distinct communities to a range of ''green'' housing materials and methods, emphasizing opportunities for recycled-content and by-product based construction materials. The project, principally funded by U.S. Department of Energy Oil Overcharge Funds administered by the Texas Governor's Energy Office, also is supported by several state, regional, and municipal agencies. As such, the project reflects a regional process, as open to adaptation to a region's natural resources as it is to its peoples. The design is specifically intended to bridge issues of social and family concerns, such as affordability, expandibility, and economic development. This is a result of a modular-based design framework, coupled with reliance on environmentally-conscious regional manufacture of by-product based materials. Environmental issues are addressed by establishing a user for pollutants considered major contributors to global concerns of acid rain (due to release of sulphur dioxide), global warming (due to release of carbon dioxide), and deforestation. The homes will be built without virgin wood products or portland cement

  13. Diesel fueled ship propulsion fuel cell demonstration project

    Energy Technology Data Exchange (ETDEWEB)

    Kumm, W.H. [Arctic Energies Ltd., Severna Park, MD (United States)

    1996-12-31

    The paper describes the work underway to adapt a former US Navy diesel electric drive ship as a 2.4 Megawatt fuel cell powered, US Coast Guard operated, demonstrator. The Project will design the new configuration, and then remove the four 600 kW diesel electric generators and auxiliaries. It will design, build and install fourteen or more nominal 180 kW diesel fueled molten carbonate internal reforming direct fuel cells (DFCs). The USCG cutter VINDICATOR has been chosen. The adaptation will be carried out at the USCG shipyard at Curtis Bay, MD. A multi-agency (state and federal) cooperative project is now underway. The USCG prime contractor, AEL, is performing the work under a Phase III Small Business Innovation Research (SBIR) award. This follows their successful completion of Phases I and II under contract to the US Naval Sea Systems (NAVSEA) from 1989 through 1993 which successfully demonstrated the feasibility of diesel fueled DFCs. The demonstrated marine propulsion of a USCG cutter will lead to commercial, naval ship and submarine applications as well as on-land applications such as diesel fueled locomotives.

  14. Staunton 1 Reclamation Demonstration Project. Progress report for 1977

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-12-01

    The Staunton 1 Reclamation Demonstration Project involves an evaluation of the reclamation process for a deep coal mine refuse system. A typical abandoned midwestern deep coal mine refuse site was selected, final land use was determined, baseline data were collected, engineering plans were developed and implemented, and a post-construction evaluation was begun. The project is a cooperative effort by two state agencies--the Abandoned Mined Land Reclamation Council of Illinois the Illinois Institute for Environmental Quality--and the U.S. Department of Energy through the Land Reclamation Program at Argonne National Laboratory. Current investigations are monitoring groundwater, surface water quality, aquatic ecosystems, revegetation, soil characteristics, erosion and runoff, soil microbial and soil fauna populations, wildlife, and economic effects of the reclamation effort. The research is a multidisciplinary approach to the concept of ecosystem response to reclamation.

  15. Photovoltaic test and demonstration project. [residential energy program

    Science.gov (United States)

    Forestieri, A. F.; Brandhorst, H. W., Jr.; Deyo, J. N.

    1976-01-01

    The considered project consists of three subprojects related to applications, device performance and diagnostics, and endurance testing. The objectives of the applications subproject include the determination of the operating characteristics for a variety of photovoltaic conversion systems. A system test facility is being constructed in this connection and a prototype residence experiment is to be conducted. Market demand for solar cells is to be stimulated by demonstrating suitability of solar cells for specific near-term applications. Activities conducted in connection with device performance studies and diagnostics are also discussed along with developments in the area of endurance testing.

  16. Cleanup criteria for the West Valley demonstration project

    International Nuclear Information System (INIS)

    Parrott, J.D.

    1999-01-01

    The US Nuclear Regulatory Commission (NRC) is prescribing decontamination and decommissioning (cleanup) criteria for the West Valley Demonstration Project and the West Valley, New York, site. The site is contaminated with various forms of residual radioactive contamination and contains a wide variety of radioactive waste. The NRC is planning to issue cleanup criteria for public comment in Fall 1999. Due to the complexity of the site, and the newness of NRC's cleanup criteria policy, applying NRC's cleanup criteria to this site will be an original regulatory undertaking. (author)

  17. North Village Ground Source Heat Pump Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Redderson, Jeff

    2015-08-03

    This project demonstrated the feasibility of converting from a traditional direct exchange system to a ground source heat pump system on a large scale, multiple building apartment complex on a university campus. A total of ten apartment buildings were converted using vertical well fields and a ground source loop that connected the 24 apartments in each building into a common system. The system has yielded significant operational savings in both energy and maintenance and transformed the living environments of these residential buildings for our students.

  18. West Valley Demonstration Project site environmental report calendar year 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-01

    This report represents a single, comprehensive source of off-site and on-site environmental monitoring data collected during 1998 by environmental monitoring personnel for the West Valley Demonstration Project (WVDP), West Valley, New York. The environmental monitoring program and results are discussed in the body of this report. The monitoring data are presented in the appendices. The data collected provide an historical record of radionuclide and radiation levels from natural and manmade sources in the survey area and document the quality of the groundwater on and around the WVDP and the quality of the air and water discharged by the WVDP.

  19. West Valley Demonstration Project site environmental report, calendar year 1999

    Energy Technology Data Exchange (ETDEWEB)

    None Available

    2000-06-01

    This report represents a single, comprehensive source of off-site and on-site environmental monitoring data collected during 1999 by environmental monitoring personnel for the West Valley Demonstration Project (WVDP), West Valley, New York. The environmental monitoring program and results are discussed in the body of this report. The monitoring data are presented in the appendices. The data collected provide an historical record of radionuclide and radiation levels from natural and manmade sources in the survey area and document the quality of the groundwater on and around the WVDP and the quality of the air and water discharged by the WVDP.

  20. Photovoltaic Test and Demonstration Project. [for solar cell power systems

    Science.gov (United States)

    Forestieri, A. F.; Brandhorst, H. W., Jr.; Deyo, J. N.

    1976-01-01

    The Photovoltaic Test and Demonstration Project was initiated by NASA in June, 1975, to develop economically feasible photovoltaic power systems suitable for a variety of terrestrial applications. Objectives include the determination of operating characteristic and lifetimes of a variety of solar cell systems and components and development of methodology and techniques for accurate measurements of solar cell and array performance and diagnostic measurements for solar power systems. Initial work will be concerned with residential applications, with testing of the first prototype system scheduled for June, 1976. An outdoor 10 kW array for testing solar power systems is under construction.

  1. West Valley Demonstration Project site environmental report, calendar year 1997

    Energy Technology Data Exchange (ETDEWEB)

    None

    1998-06-01

    This report represents a single, comprehensive source of off-site and on-site environmental monitoring data collected during 1997 by environmental monitoring personnel for the West Valley Demonstration Project (WVDP), West Valley, New York. The environmental monitoring program and results are discussed in the body of this report. The monitoring data are presented in the appendices. The data collected provide an historical record of radionuclide and radiation levels from natural and manmade sources in the survey area and document the quality of the groundwater on and around the WVDP and the quality of the air and water discharged by the WVDP.

  2. An overview of the West Valley demonstration project

    International Nuclear Information System (INIS)

    Hannum, W.H.; Boswell, M.B.; De Boer, T.K.; Duckworth, J.P.

    1984-01-01

    This session is titled ''DOE Special Waste Management Projects.'' West Valley and TMI are indeed special projects, in that they represent today's problems. They may well have been the two most visible symbols as to how nuclear wastes can poison the entire civilian nuclear power program. Each in its own way has been perceived as a major threat to the environment and to public health and safety; in both cases this threat has been perceived to be grossly more severe than it has been in fact. It is the Department of Energy' intent that both of these problems be made to disappear. This paper serves to introduce a series of paper describing the status of the West Valley Project. In the West Valley case substantial progress is being made and we believe we are well on the way toward transforming what has been a skeleton along the road to progress into positive and unmistakable evidence that high-level nuclear wastes such as those resulting from reprocessing can be managed, understood, and prepared for disposal by a straightforward adaptation and application of existing technologies. Further, we now have evidence that the costs of doing this are not exorbitant. Subsequent papers will describe waste characterization; the plans and designs for solidification; and the ancillary and supporting programs for handling effluents and wastes, for D and D to utilize existing facilities, and environmental support. In this paper we describe the history of this plant and the wastes being used in the demonstration; the legislation and intent of the Project; the accomplishments to date; and the projected schedule and costs

  3. Nucla circulating atmospheric fluidized bed demonstration project. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1991-10-01

    Colorado-Ute Electric Association began a study to evaluate options for upgrading and extending the life of its Nucla power station in 1982. Located in southwestern Colorado near the town of Nucla, this station was commissioned in 1959 with a local bituminous coal as its design fuel for three identical stoker-fired units, each rated at 12.6 MW(e). Poor station efficiency, high fuel costs, and spiraling boiler maintenance costs forced the Nucla Station into low priority in the CUEA dispatch order as early as 1981. Among the options CUEA considered was to serve as a host utility to demonstrate Atmospheric Fluidized Bed Combustion (AFBC) technology. The anticipated environmental benefits and apparent attractive economics of a circulating AFBC led to Colorado-Ute`s decision to proceed with the design and construction of a demonstration project in 1984 at the Nucla facility.

  4. U1/U2 crib groundwater biological treatment demonstration project

    International Nuclear Information System (INIS)

    Koegler, S.S.; Brouns, T.M.; Heath, W.O.

    1989-11-01

    The primary objective of the biological treatment project is to develop and demonstrate a process for Hanford groundwater remediation. Biodenitrification using facultative anaerobic microorganisms is a promising technology for the simultaneous removal of nitrates and organics from contaminated aqueous streams. During FY 1988, a consortium of Hanford groundwater microorganisms was shown to degrade both nitrates and carbon tetrachloride (CC1 4 ). A pilot-scale treatment system was designed and constructed based on the results of laboratory-and-bench-scale testing. This report summarizes the results of biological groundwater treatment studies performed during FY 1989 at the pilot-scale. These tests were conducted using a simulated Hanford groundwater with a continuous stirred-tank bioreactor, and a fluidized-bed bioreactor that was added to the pilot-scale treatment system in FY 1989. The pilot-scale system demonstrated continuous degradation of nitrates and CC1 4 in a simulated groundwater. 4 refs., 7 figs., 1 tab

  5. Wood to Bio-Methane demonstration project in the Netherlands

    Energy Technology Data Exchange (ETDEWEB)

    Van der Meijden, C.M.; Van der Drift, A.; Rietveld, G. [ECN Biomass and Energy Efficiency, Petten (Netherlands); Koenemann, J.W. [Dahlman Renewable Technology, P.O. Box 438, 3140 AK Maassluis (Netherlands); Sierhuis, W. [HVCgroup, P.O. Box 9199, 1800 GD, Alkmaar (Netherlands)

    2013-06-15

    The Energy research Centre of the Netherlands (ECN) has developed a biomass gasification technology, called the MILENA technology. The Milena gasification technology has a high cold gas efficiency and high methane yield, making it very suitable for gas engine and turbine applications as well as upgrading of the gas into Bio-Methane. An overall efficiency from biomass to power of over 30% is possible, whereas 70% efficiency is achievable from biomass to gas grid quality methane. HVC Group (situated in Alkmaar, North Holland) is a modern public service waste company. HVC converts waste streams which cannot be recycled into usable forms of energy. HVC has a 75 MWth waste wood boiler in operation which produces heat and electricity, and an anaerobic digester which converts domestic fruit, vegetable and garden waste into Bio-Methane. HVC expects an important role for Bio-Methane in the future and HVC has decided to join ECN with the development, demonstration and implementation of the MILENA Bio-Methane technology. Linked to the Bio-Methane demonstration project is the Netherlands Expertise Centre for Biomass Gasification. The MILENA demonstration project and the Gasification Expert Centre are supported by the following companies and organizations: HVC, TAQA, Gasunie, Dahlman, province of North Holland, the Alkmaar municipality and ECN. In 2010 and 2012 extensive lab-scale and pilot scale tests have been executed by ECN and HVC to proof that the gasification and gas cleaning technology is ready for commercial application. The final step in this test program was a duration test in the 800 kWth MILENA pilot plant coupled to the OLGA tar removal unit. The goal was to show high availability. The result of the test was an availability of the gasifier of 96% and an overall availability (including gas cooling and gas cleaning) of 85%. The results of the duration tests convinced HVC and the other partners that the technology is ready for scale-up. The results produced in the

  6. Choosing solidification or vitrification for low-level radioactive and mixed waste treatment

    International Nuclear Information System (INIS)

    Gimpel, R.F.

    1992-01-01

    Solidification (making concrete) and vitrification (making glass) are frequently the treatment methods recommended for treating inorganic or radioactive wastes. Solidification is generally perceived as the most economical treatment method. Whereas, vitrification is considered (by many) as the most effective of all treatment methods. Unfortunately, vitrification has acquired the stigma that it is too expensive to receive further consideration as an alternative to solidification in high volume treatment applications. Ironically, economic studies, as presented in this paper, show that vitrification may be more competitive in some high volume applications. Ex-situ solidification and vitrification are the competing methods for treating in excess of 450 000m 3 of low-level radioactive and mixed waste at the Fernald Environmental Management Project (FEMP or simply, Fernald) located near Cincinnati, Ohio. This paper summarizes how Fernald is choosing between solidification and vitrification as the primary waste treatment method

  7. Choosing solidification or vitrification for low-level radioactive and mixed waste treatment

    International Nuclear Information System (INIS)

    Gimpel, R.F.

    1992-01-01

    Solidification (making concrete) and vitrification (making glass) are frequently the treatment methods recommended for treating inorganic or radioactive wastes. Solidification is generally perceived as the most economical treatment method. Whereas, vitrification is considered (by many) as the most effective of all treatment methods. Unfortunately, vitrification has acquired the stigma that it is too expensive to receive further consideration as an alternative to solidification in high volume treatment applications. Ironically, economic studies, as presented in this paper, show that vitrification may be more competitive in some high volume applications. Ex-situ solidification and vitrification are the competing methods for treating in excess of 450,000 m 3 of low-level radioactive and mixed waste at the Fernald Environmental Management Project (FEMP or simply, Fernald) located near Cincinnati, Ohio. This paper summarized how Fernald is choosing between solidification and vitrification as the primary waste treatment method

  8. Missouri Soybean Association Biodiesel Demonstration Project: Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Ludwig, Dale [Missouri Soybean Association, Jefferson City, MO (United States); Hamilton, Jill [Sustainable Energy Strategies, Inc., Fairfax, VA (United States)

    2011-10-27

    The Missouri Soybean Association (MSA) and the National Biodiesel Board (NBB) partnered together to implement the MSA Biodiesel Demonstration project under a United States Department of Energy (DOE) grant. The goal of this project was to provide decision makers and fleet managers with information that could lead to the increased use of domestically produced renewable fuels and could reduce the harmful impacts of school bus diesel exhaust on children. This project was initiated in September 2004 and completed in April 2011. The project carried out a broad range of activities organized under four areas: 1. Petroleum and related industry education program for fuel suppliers; 2. Fleet evaluation program using B20 with a Missouri school district; 3. Outreach and awareness campaign for school district fleet managers; and 4. Support of ongoing B20 Fleet Evaluation Team (FET) data collection efforts with existing school districts. Technical support to the biodiesel industry was also provided through NBB’s Troubleshooting Hotline. The hotline program was established in 2008 to troubleshoot fuel quality issues and help facilitate smooth implementation of the RFS and is described in greater detail under Milestone A.1 - Promote Instruction and Guidance on Best Practices. As a result of this project’s efforts, MSA and NBB were able to successfully reach out to and support a broad spectrum of biodiesel users in Missouri and New England. The MSA Biodiesel Demonstration was funded through a FY2004 Renewable Energy Resources Congressional earmark. The initial focus of this project was to test and evaluate biodiesel blends coupled with diesel oxidation catalysts as an emissions reduction technology for school bus fleets in the United States. The project was designed to verify emissions reductions using Environmental Protection Agency (EPA) protocols, then document – with school bus fleet experience – the viability of utilizing B20 blends. The fleet experience was expected to

  9. Summary report on the Y-12 Sludge Detoxification Demonstration project

    International Nuclear Information System (INIS)

    Jolley, R.L.; Hollenbeck, P.E.; Kennerly, J.M.; Singh, S.P.N.

    1994-07-01

    The Y-12 Sludge Detoxification Demonstration was conducted in late 1988 at the Oak Ridge Gaseous Diffusion Plant (subsequently renamed the K-25 Site). The erstwhile Waste Management Technology Center (WMTC) managed the conduct of this waste treatment technology to assist the US Department of Energy/Oak Ridge Operations (DOE/ORO) in implementing the DOE Model. This demonstration was the first project selected by the Hazardous Waste Remedial Actions Program (HAZWRAP)(and funded by DOE) in which a private-sector vendor was contracted to demonstrate an innovative treatment process for treating some of the Oak Ridge Site's radioactive mixed wastes to enable their environmentally compliant disposal. Chem-Nuclear Systems, Inc. (CNSI) was the private-sector vendor selected to demonstrate its X*TRAX trademark process. Briefly, the X*TRAX trademark process consisted of thermally treating the sludge in an inert atmosphere (to remove the volatile components) to yield a dry residue (containing the nonvolatilized sludge components) and condensed liquids. The dry residue can then be immobilized in cementitious matrix for delisting and disposal in an industrial landfill; the condensed liquids can be disposed in, for example, an incinerator

  10. Demonstration of Autonomous Rendezvous Technology (DART) Project Summary

    Science.gov (United States)

    Rumford, TImothy E.

    2003-01-01

    Since the 1960's, NASA has performed numerous rendezvous and docking missions. The common element of all US rendezvous and docking is that the spacecraft has always been piloted by astronauts. Only the Russian Space Program has developed and demonstrated an autonomous capability. The Demonstration of Autonomous Rendezvous Technology (DART) project currently funded under NASA's Space Launch Initiative (SLI) Cycle I, provides a key step in establishing an autonomous rendezvous capability for the United States. DART's objective is to demonstrate, in space, the hardware and software necessary for autonomous rendezvous. Orbital Sciences Corporation intends to integrate an Advanced Video Guidance Sensor and Autonomous Rendezvous and Proximity Operations algorithms into a Pegasus upper stage in order to demonstrate the capability to autonomously rendezvous with a target currently in orbit. The DART mission will occur in April 2004. The launch site will be Vandenburg AFB and the launch vehicle will be a Pegasus XL equipped with a Hydrazine Auxiliary Propulsion System 4th stage. All mission objectives will be completed within a 24 hour period. The paper provides a summary of mission objectives, mission overview and a discussion on the design features of the chase and target vehicles.

  11. The Advanced Linked Extended Reconnaissance & Targeting Technology Demonstration project

    Science.gov (United States)

    Edwards, Mark

    2008-04-01

    The Advanced Linked Extended Reconnaissance & Targeting (ALERT) Technology Demonstration (TD) project is addressing many operational needs of the future Canadian Army's Surveillance and Reconnaissance forces. Using the surveillance system of the Coyote reconnaissance vehicle as an experimental platform, the ALERT TD project aims to significantly enhance situational awareness by fusing multi-sensor and tactical data, developing automated processes, and integrating beyond line-of-sight sensing. The project is exploiting important advances made in computer processing capability, displays technology, digital communications, and sensor technology since the design of the original surveillance system. As the major research area within the project, concepts are discussed for displaying and fusing multi-sensor and tactical data within an Enhanced Operator Control Station (EOCS). The sensor data can originate from the Coyote's own visible-band and IR cameras, laser rangefinder, and ground-surveillance radar, as well as from beyond line-of-sight systems such as mini-UAVs and unattended ground sensors. Video-rate image processing has been developed to assist the operator to detect poorly visible targets. As a second major area of research, automatic target cueing capabilities have been added to the system. These include scene change detection, automatic target detection and aided target recognition algorithms processing both IR and visible-band images to draw the operator's attention to possible targets. The merits of incorporating scene change detection algorithms are also discussed. In the area of multi-sensor data fusion, up to Joint Defence Labs level 2 has been demonstrated. The human factors engineering aspects of the user interface in this complex environment are presented, drawing upon multiple user group sessions with military surveillance system operators. The paper concludes with Lessons Learned from the project. The ALERT system has been used in a number of C4ISR

  12. WBP: The wood Brazilian BIG-GT demonstration project

    Energy Technology Data Exchange (ETDEWEB)

    Carpentieri, E. [Companhia Hidro Eletrica do Sao Francisco, Recife (Brazil)

    1993-12-31

    Brazil is one of the leading countries in the use of renewable energy. Most of its electricity comes from hydro power, about 200,000 barrels a day of ethanol from sugar cane is used as fuel, around 38% of the pig iron, and 20% of the steel production, uses charcoal as a reducing medium. Located in the tropics, with the sun shining all year round, and with its vast territory, the Country may be regarded as having all the basic conditions to develop a modern Biomass for Electricity industry. The conjunction of those characteristics with, the necessity of developing new energy resources for electricity production in the Northeast of the Country, the results of the studies made by Princeton University, Shell and Chesf, the progress achieved by the BIG-GT (Biomass Integrated Gasification Gas Turbine) technology in Europe, and the organization of the Global Environment Facility (GEF), provided the unique opportunity for the implementation of a commercial demonstration in Brazil. This paper describes the idea, the scope, the technical challenges, and actual status of development of the WBP, a project which aims to demonstrate the commercial viability of the BIG-GT technology. It also highlights, the project management structure, the role of the GEF, World Bank and of the United Nations Development Program (UNDP), and the participation of the Brazilian Federal Government, through the Ministry of Science and Technology (MCT). Finally it describes the Participants (ELETROBRAS, CVRD, CIENTEC, SHELL, and CHESF), their role in the project, and how the group was formed and operates.

  13. Ultra Low Sulfur Home Heating Oil Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Batey, John E. [Energy Research Center, Inc., Easton, CT (United States); McDonald, Roger [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2015-09-30

    This Ultra Low Sulfur (ULS) Home Heating Oil Demonstration Project was funded by the New York State Energy Research and Development Authority (NYSERDA) and has successfully quantified the environmental and economic benefits of switching to ULS (15 PPM sulfur) heating oil. It advances a prior field study of Low Sulfur (500 ppm sulfur) heating oil funded by NYSERDA and laboratory research conducted by Brookhaven National Laboratory (BNL) and Canadian researchers. The sulfur oxide and particulate matter (PM) emissions are greatly reduced as are boiler cleaning costs through extending cleaning intervals. Both the sulfur oxide and PM emission rates are directly related to the fuel oil sulfur content. The sulfur oxide and PM emission rates approach near-zero levels by switching heating equipment to ULS fuel oil, and these emissions become comparable to heating equipment fired by natural gas. This demonstration project included an in-depth review and analysis of service records for both the ULS and control groups to determine any difference in the service needs for the two groups. The detailed service records for both groups were collected and analyzed and the results were entered into two spreadsheets that enabled a quantitative side-by-side comparison of equipment service for the entire duration of the ULS test project. The service frequency for the ULS and control group were very similar and did indicate increased service frequency for the ULS group. In fact, the service frequency with the ULS group was slightly less (7.5 percent) than the control group. The only exception was that three burner fuel pump required replacement for the ULS group and none were required for the control group.

  14. INNOVATIVE FOSSIL FUEL FIRED VITRIFICATION TECHNOLOGY FOR SOIL REMEDIATION. FINAL REPORT

    International Nuclear Information System (INIS)

    J. Hnat; L.M. Bartone; M. Pineda

    2001-01-01

    This Final Report summarizes the progress of Phases 3,3A and 4 of a waste technology Demonstration Project sponsored under a DOE Environmental Management Research and Development Program and administered by the U.S. Department of Energy National Energy Technology Laboratory-Morgantown (DOE-NETL) for an ''Innovative Fossil Fuel Fired Vitrification Technology for Soil Remediation''. The Summary Reports for Phases 1 and 2 of the Program were previously submitted to DOE. The total scope of Phase 3 was to have included the design, construction and demonstration of Vortec's integrated waste pretreatment and vitrification process for the treatment of low level waste (LLW), TSCA/LLW and mixed low-level waste (MLLW). Due to funding limitations and delays in the project resulting from a law suit filed by an environmental activist and the extended time for DOE to complete an Environmental Assessment for the project, the scope of the project was reduced to completing the design, construction and testing of the front end of the process which consists of the Material Handling and Waste Conditioning (MH/C) Subsystem of the vitrification plant. Activities completed under Phases 3A and 4 addressed completion of the engineering, design and documentation of the MH/C System such that final procurement of the remaining process assemblies can be completed and construction of a Limited Demonstration Project be initiated in the event DOE elects to proceed with the construction and demonstration testing of the MH/C Subsystem. Because of USEPA policies and regulations that do not require treatment of low level or low-level/PCB contaminated wastes, DOE terminated the project because there is no purported need for this technology

  15. Successful application of the strategy of blastocyst biopsy, vitrification, whole genome amplification, and thawed embryo transfer for preimplantation genetic diagnosis of neurofibromatosis type 1

    Directory of Open Access Journals (Sweden)

    Yi-Lin Chen

    2011-03-01

    Conclusion: We first demonstrate successful application of blastocyst biopsy, vitrification, WGA, and thawed embryo transfer for PGD of a monogenic disease. Vitrification of blastocysts after biopsy permits sufficient time for shipment of samples and operation of molecular diagnosis.

  16. DIMETHYL ETHER (DME)-FUELED SHUTTLE BUS DEMONSTRATION PROJECT

    Energy Technology Data Exchange (ETDEWEB)

    Elana M. Chapman; Shirish Bhide; Jennifer Stefanik; Andre L. Boehman; David Klinikowski

    2003-04-01

    The objectives of this research and demonstration program are to convert a campus shuttle bus to operation on dimethyl ether, a potential ultra-clean alternative diesel fuel. To accomplish this objective, this project includes laboratory evaluation of a fuel conversion strategy, as well as, field demonstration of the DME-fueled shuttle bus. Since DME is a fuel with no lubricity (i.e., it does not possess the lubricating quality of diesel fuel), conventional fuel delivery and fuel injection systems are not compatible with dimethyl ether. Therefore, to operate a diesel engine on DME one must develop a fuel-tolerant injection system, or find a way to provide the necessary lubricity to the DME. In this project, they have chosen the latter strategy in order to achieve the objective with minimal need to modify the engine. The strategy is to blend DME with diesel fuel, to obtain the necessary lubricity to protect the fuel injection system and to achieve low emissions. The laboratory studies have included work with a Navistar V-8 turbodiesel engine, demonstration of engine operation on DME-diesel blends and instrumentation for evaluating fuel properties. The field studies have involved performance, efficiency and emissions measurements with the Champion Motorcoach ''Defender'' shuttle bus which will be converted to DME-fueling. The results include baseline emissions, performance and combustion measurements on the Navistar engine for operation on a federal low sulfur diesel fuel (300 ppm S). Most recently, they have completed engine combustion studies on DME-diesel blends up to 30 wt% DME addition.

  17. Strengthening global health security capacity--Vietnam demonstration project, 2013.

    Science.gov (United States)

    Tran, Phu Dac; Vu, Long Ngoc; Nguyen, Hien Tran; Phan, Lan Trong; Lowe, Wayne; McConnell, Michelle S; Iademarco, Michael F; Partridge, Jeffrey M; Kile, James C; Do, Trang; Nadol, Patrick J; Bui, Hien; Vu, Diep; Bond, Kyle; Nelson, David B; Anderson, Lauren; Hunt, Kenneth V; Smith, Nicole; Giannone, Paul; Klena, John; Beauvais, Denise; Becknell, Kristi; Tappero, Jordan W; Dowell, Scott F; Rzeszotarski, Peter; Chu, May; Kinkade, Carl

    2014-01-31

    Over the past decade, Vietnam has successfully responded to global health security (GHS) challenges, including domestic elimination of severe acute respiratory syndrome (SARS) and rapid public health responses to human infections with influenza A(H5N1) virus. However, new threats such as Middle East respiratory syndrome coronavirus (MERS-CoV) and influenza A(H7N9) present continued challenges, reinforcing the need to improve the global capacity to prevent, detect, and respond to public health threats. In June 2012, Vietnam, along with many other nations, obtained a 2-year extension for meeting core surveillance and response requirements of the 2005 International Health Regulations (IHR). During March-September 2013, CDC and the Vietnamese Ministry of Health (MoH) collaborated on a GHS demonstration project to improve public health emergency detection and response capacity. The project aimed to demonstrate, in a short period, that enhancements to Vietnam's health system in surveillance and early detection of and response to diseases and outbreaks could contribute to meeting the IHR core capacities, consistent with the Asia Pacific Strategy for Emerging Diseases. Work focused on enhancements to three interrelated priority areas and included achievements in 1) establishing an emergency operations center (EOC) at the General Department of Preventive Medicine with training of personnel for public health emergency management; 2) improving the nationwide laboratory system, including enhanced testing capability for several priority pathogens (i.e., those in Vietnam most likely to contribute to public health emergencies of international concern); and 3) creating an emergency response information systems platform, including a demonstration of real-time reporting capability. Lessons learned included awareness that integrated functions within the health system for GHS require careful planning, stakeholder buy-in, and intradepartmental and interdepartmental coordination and

  18. ARSENIC REMOVAL FROM DRINKING WATER BY IRON REMOVAL. USEPA DEMONSTRATION PROJECT AT CLIMAX, MN. PROJECT SUMMARY

    Science.gov (United States)

    This document is an eight page summary of the final report on arsenic demonstration project at Climax, MN (EPA/600/R-06/152). The objectives of the project are to evaluate the effectiveness of the Kinetico iron removal system in removing arsenic to meet the new arsenic maximum co...

  19. AEP Ohio gridSMART Demonstration Project Real-Time Pricing Demonstration Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Widergren, Steven E.; Subbarao, Krishnappa; Fuller, Jason C.; Chassin, David P.; Somani, Abhishek; Marinovici, Maria C.; Hammerstrom, Janelle L.

    2014-02-01

    This report contributes initial findings from an analysis of significant aspects of the gridSMART® Real-Time Pricing (RTP) – Double Auction demonstration project. Over the course of four years, Pacific Northwest National Laboratory (PNNL) worked with American Electric Power (AEP), Ohio and Battelle Memorial Institute to design, build, and operate an innovative system to engage residential consumers and their end-use resources in a participatory approach to electric system operations, an incentive-based approach that has the promise of providing greater efficiency under normal operating conditions and greater flexibility to react under situations of system stress. The material contained in this report supplements the findings documented by AEP Ohio in the main body of the gridSMART report. It delves into three main areas: impacts on system operations, impacts on households, and observations about the sensitivity of load to price changes.

  20. Uranium soils integrated demonstration: Soil characterization project report

    International Nuclear Information System (INIS)

    Cunnane, J.C.; Gill, V.R.; Lee, S.Y.; Morris, D.E.; Nickelson, M.D.; Perry, D.L.; Tidwell, V.C.

    1993-08-01

    An Integrated Demonstration Program, hosted by the Fernald Environmental Management Project (FEMP), has been established for investigating technologies applicable to the characterization and remediation of soils contaminated with uranium. Critical to the design of relevant treatment technologies is detailed information on the chemical and physical characteristics of the uranium waste-form. To address this need a soil sampling and characterization program was initiated which makes use of a variety of standard analytical techniques coupled with state-of-the-art microscopy and spectroscopy techniques. Sample representativeness is evaluated through the development of conceptual models in an effort to identify and understand those geochemical processes governing the behavior of uranium in FEMP soils. Many of the initial results have significant implications for the design of soil treatment technologies for application at the FEMP

  1. Health risk assessment for a MWC ash utilization demonstration project

    International Nuclear Information System (INIS)

    Roffman, H.K.

    1992-01-01

    A Health Risk Assessment (HRA) was conducted for the proposed joint Hennepin County/Municipal Services Corporation (MSC) MSW Ash Utilization Demonstration Project, in which combined HERC ash was shipped to the MSC Pilot Plan near Atlanta, Georgia and used in the production of a synthetic aggregate. The synthetic aggregate, or TAP, will serve as a partial replacement for natural aggregates in a section of bituminous pavement that is proposed to be constructed on Pioneer Trail in the City of Corcoran, Minnesota. In this paper, the assessment compares the following three scenarios: a section of roadway paved using the MSC synthetic aggregate product (TAP) as a replacement for 30 percent of the natural aggregates used in bituminous pavement; a section of regular bituminous (asphalt) pavement; and a section of unpaved road currently in place at the site

  2. Electric G-Van demonstration and commercial assessment project

    Energy Technology Data Exchange (ETDEWEB)

    Braga, B.D. (Electric Power Research Inst., Palo Alto, CA (United States))

    1992-12-01

    The Electric Power Research Institute was awarded this grant to continue the joint effort initiated by EPRI, and VE International to proceed beyond the prototype phase of the electric G-Van development. The goal of EPRI and VEHMA was to develop a market for the electric G-Van, and to distribute them to commercial fleet operators. The objective of this project was to produce G-Vans in a production facility that would be comparable to the GMC Truck internal combustion engine Vandura Van produced by General Motors in quality, reliability, durability and safety. An initial market assessment/demonstration phase of sixty (60) vehicles was to be undertaken, with the ability to expand production volume quickly to meet market demands. Brief description of each task of this grant is given and the actions taken by EPRI to complete them.

  3. Uranium soils integrated demonstration: Soil characterization project report

    Energy Technology Data Exchange (ETDEWEB)

    Cunnane, J.C. [Argonne National Lab., IL (United States); Gill, V.R. [Fernald Environmental Restoration Management Corp., Cincinnati, OH (United States); Lee, S.Y. [Oak Ridge National Lab., TN (United States); Morris, D.E. [Los Alamos National Lab., NM (United States); Nickelson, M.D. [HAZWRAP, Oak Ridge, TN (United States); Perry, D.L. [Lawrence Berkeley Lab., CA (United States); Tidwell, V.C. [Sandia National Labs., Albuquerque, NM (United States)

    1993-08-01

    An Integrated Demonstration Program, hosted by the Fernald Environmental Management Project (FEMP), has been established for investigating technologies applicable to the characterization and remediation of soils contaminated with uranium. Critical to the design of relevant treatment technologies is detailed information on the chemical and physical characteristics of the uranium waste-form. To address this need a soil sampling and characterization program was initiated which makes use of a variety of standard analytical techniques coupled with state-of-the-art microscopy and spectroscopy techniques. Sample representativeness is evaluated through the development of conceptual models in an effort to identify and understand those geochemical processes governing the behavior of uranium in FEMP soils. Many of the initial results have significant implications for the design of soil treatment technologies for application at the FEMP.

  4. Project Integration Architecture: A Practical Demonstration of Information Propagation

    Science.gov (United States)

    Jones, William Henry

    2005-01-01

    One of the goals of the Project Integration Architecture (PIA) effort is to provide the ability to propagate information between disparate applications. With this ability, applications may then be formed into an application graph constituting a super-application. Such a super-application would then provide all of the analysis appropriate to a given technical system. This paper reports on a small demonstration of this concept in which a Computer Aided Design (CAD) application was connected to an inlet analysis code and geometry information automatically propagated from one to the other. The majority of the work reported involved not the technology of information propagation, but rather the conversion of propagated information into a form usable by the receiving application.

  5. Environmental monitoring annual report for the Tumulus Disposal Demonstration Project

    International Nuclear Information System (INIS)

    Yager, R.E.; Craig, P.M.

    1989-01-01

    The Fiscal Year 1988 Annual Report is the third in a series of semi-annual Tumulus Development Disposal Project data summary reports. The reporting schedule has been modified to correspond to the fiscal years and the subcontractor contract periods. This data summary spans the time from start of operations in June 1987 through the end of September 1988. The environmental data collected include run-off water quality and quantity, groundwater quality and levels, soil sampling and hydrometeorological data. This data is being used and analyzed here to demonstrate the environmental performance objectives for the TDDP as part of the overall performance assessment for the TDDP. Approximately one year of pre-operational data were collected prior to operations beginning on April 11, 1988. Comparisons are made between pre- and post-operational data. No significant environmental impacts have been found since operations have begun. 10 refs., 21 figs., 22 tabs

  6. Town of Edinburg landfill reclamation demonstration project. Final report

    International Nuclear Information System (INIS)

    1992-01-01

    A landfill reclamation demonstration project was hosted at the Town of Edinburg municipal landfill in northwest Saratoga County, with majority funding provided by the New York State Energy Research and Development Authority. The report examines various separation techniques employed at the site and appropriate uses for reclaimed materials. Specifications regarding engineered work plans, health and safety monitoring, and contingency preparedness are discussed. Major potential applications and benefits of using landfill reclamation technology at existing landfills are identified and discussed. The research and development aspect of the report also examines optimal screening technologies, site selection protocol and the results of a test burn of reclaimed waste at a waste-to-energy facility. Landfill reclamation costs are developed, and economic comparisons are made between reclamation costs and conventional landfill closure costs, with key criteria identified

  7. Texas LPG fuel cell development and demonstration project

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2004-07-26

    The State Energy Conservation Office has executed its first Fuel Cell Project which was awarded under a Department of Energy competitive grant process. The Texas LPG Fuel Processor Development and Fuel Cell Demonstration Program is a broad-based public/private partnership led by the Texas State Energy Conservation Office (SECO). Partners include the Alternative Fuels Research and Education Division (AFRED) of the Railroad Commission of Texas; Plug Power, Inc., Latham, NY, UOP/HyRadix, Des Plaines, IL; Southwest Research Institute (SwRI), San Antonio, TX; the Texas Natural Resource Conservation Commission (TNRCC), and the Texas Department of Transportation (TxDOT). The team proposes to mount a development and demonstration program to field-test and evaluate markets for HyRadix's LPG fuel processor system integrated into Plug Power's residential-scale GenSys(TM) 5C (5 kW) PEM fuel cell system in a variety of building types and conditions of service. The program's primary goal is to develop, test, and install a prototype propane-fueled residential fuel cell power system supplied by Plug Power and HyRadix in Texas. The propane industry is currently funding development of an optimized propane fuel processor by project partner UOP/HyRadix through its national checkoff program, the Propane Education and Research Council (PERC). Following integration and independent verification of performance by Southwest Research Institute, Plug Power and HyRadix will produce a production-ready prototype unit for use in a field demonstration. The demonstration unit produced during this task will be delivered and installed at the Texas Department of Transportation's TransGuide headquarters in San Antonio, Texas. Simultaneously, the team will undertake a market study aimed at identifying and quantifying early-entry customers, technical and regulatory requirements, and other challenges and opportunities that need to be addressed in planning commercialization of the units

  8. King County Metro Battery Electric Bus Demonstration: Preliminary Project Results

    Energy Technology Data Exchange (ETDEWEB)

    2017-05-22

    The U.S. Federal Transit Administration (FTA) funds a variety of research projects that support the commercialization of zero-emission bus technology. To evaluate projects funded through these programs, FTA has enlisted the help of the National Renewable Energy Laboratory (NREL) to conduct third-party evaluations of the technologies deployed under the FTA programs. NREL works with the selected agencies to evaluate the performance of the zero-emission buses compared to baseline conventional buses in similar service. The evaluation effort will advance the knowledge base of zero-emission technologies in transit bus applications and provide 'lessons learned' to aid other fleets in incrementally introducing next generation zero-emission buses into their operations. This report provides preliminary performance evaluation results from a demonstration of three zero-emission battery electric buses at King County Metro in King County, Washington. NREL developed this preliminary results report to quickly disseminate evaluation results to stakeholders. Detailed evaluation results will be published in future reports.

  9. The advanced linked extended reconnaissance and targeting technology demonstration project

    Science.gov (United States)

    Cruickshank, James; de Villers, Yves; Maheux, Jean; Edwards, Mark; Gains, David; Rea, Terry; Banbury, Simon; Gauthier, Michelle

    2007-06-01

    The Advanced Linked Extended Reconnaissance & Targeting (ALERT) Technology Demonstration (TD) project is addressing key operational needs of the future Canadian Army's Surveillance and Reconnaissance forces by fusing multi-sensor and tactical data, developing automated processes, and integrating beyond line-of-sight sensing. We discuss concepts for displaying and fusing multi-sensor and tactical data within an Enhanced Operator Control Station (EOCS). The sensor data can originate from the Coyote's own visible-band and IR cameras, laser rangefinder, and ground-surveillance radar, as well as beyond line-of-sight systems such as a mini-UAV and unattended ground sensors. The authors address technical issues associated with the use of fully digital IR and day video cameras and discuss video-rate image processing developed to assist the operator to recognize poorly visible targets. Automatic target detection and recognition algorithms processing both IR and visible-band images have been investigated to draw the operator's attention to possible targets. The machine generated information display requirements are presented with the human factors engineering aspects of the user interface in this complex environment, with a view to establishing user trust in the automation. The paper concludes with a summary of achievements to date and steps to project completion.

  10. The Japan Power Demonstration Reactor dismantling project. Radiation control

    International Nuclear Information System (INIS)

    Tomii, Hiroyuki; Seiki, Yoshihiro

    1996-01-01

    In the Japan Power Demonstration Reactor (JPDR) dismantling project, radiation control was performed properly with routine and special monitoring to keep the occupational safety and to collect data necessary for future dismantling of nuclear facilities. This report describes a summary of radiation control in the dismantling activities and some results of parametric analysis on dose equivalent evaluation, and introduces the following knowledge on radiological protection effectiveness of the dismantling systems applied in the project. a) Use of remote dismantling systems was effective in reducing equivalent workplace exposure. b) Utilization of existing facilities as radiation shield or radioactivity containment was effective in reducing workplace exposure, and also in increasing work efficiency. c) Use of underwater cutting systems was useful to minimize air contamination, and to reduce the dose equivalent rate in the working area. d) In the planning of dismantling, it is necessary to optimize the radiation protection by analyzing dismantling work procedures and evaluating radiological features of the dismantling systems applied, including additional work which the systems require brought from such activities. (author)

  11. Vitrification publication bibliography

    Energy Technology Data Exchange (ETDEWEB)

    Schmieman, E.; Johns, W.E.

    1996-02-01

    This document was compiled by a group of about 12 graduate students in the Department of Mechanical Engineering and Material Science at Washington State University and was funded by the U.S. Department of Energy. The literature search resulting in the compilation of this bibliography was designed to be an exhaustive search for research and development work involving the vitrification of mixed wastes, published by domestic and foreign researchers, primarily during 1989-1994. The search techniques were dominated by electronic methods and this bibliography is also available in electronic format, Windows Reference Manager.

  12. Vitrification publication bibliography

    International Nuclear Information System (INIS)

    Schmieman, E.; Johns, W.E.

    1996-02-01

    This document was compiled by a group of about 12 graduate students in the Department of Mechanical Engineering and Material Science at Washington State University and was funded by the U.S. Department of Energy. The literature search resulting in the compilation of this bibliography was designed to be an exhaustive search for research and development work involving the vitrification of mixed wastes, published by domestic and foreign researchers, primarily during 1989-1994. The search techniques were dominated by electronic methods and this bibliography is also available in electronic format, Windows Reference Manager

  13. Three-Dimensional Printing of Vitrification Loop Prototypes for Aquatic Species.

    Science.gov (United States)

    Tiersch, Nolan J; Childress, William M; Tiersch, Terrence R

    2018-05-16

    Vitrification is a method of cryopreservation that freezes samples rapidly, while forming an amorphous solid ("glass"), typically in small (μL) volumes. The goal of this project was to create, by three-dimensional (3D) printing, open vitrification devices based on an elliptical loop that could be efficiently used and stored. Vitrification efforts can benefit from the application of 3D printing, and to begin integration of this technology, we addressed four main variables: thermoplastic filament type, loop length, loop height, and method of loading. Our objectives were to: (1) design vitrification loops with varied dimensions; (2) print prototype loops for testing; (3) evaluate loading methods for the devices; and (4) classify vitrification responses to multiple device configurations. The various configurations were designed digitally using 3D CAD (Computer Aided Design) software, and prototype devices were produced with MakerBot ® 3D printers. The thermoplastic filaments used to produce devices were acrylonitrile butadiene styrene (ABS) and polylactic acid (PLA). Vitrification devices were characterized by the film volumes formed with different methods of loading (pipetting or submersion). Frozen films were classified to determine vitrification quality: zero (opaque, or abundant crystalline ice formation); one (translucent, or partial vitrification), or two (transparent, or substantial vitrification, glass). A published vitrification solution was used to conduct experiments. Loading by pipetting formed frozen films more reliably than by submersion, but submersion yielded fewer filling problems and was more rapid. The loop designs that yielded the highest levels of vitrification enabled rapid transfer of heat, and most often were characterized as being longer and consisting of fewer layers (height). 3D printing can assist standardization of vitrification methods and research, yet can also provide the ability to quickly design and fabricate custom devices when

  14. The ESDRED project: Engineering studies and demonstration of repository designs

    International Nuclear Information System (INIS)

    Verstricht, J.

    2009-01-01

    The construction, operation and closure of a deep geological repository for spent fuel and long-lived radioactive waste in clay involves specific technologies. The demonstration of these techniques at an industrial scale is being carried out in the frame of a technological integrated project within the sixth Framework Programme of EURATOM. The Belgian design for high level waste disposal is based on the so-called Supercontainer concept. Within this concept, the waste is encased in a carbon steel overpack, which is consequently fitted into a 70 cm thick concrete shell, in its turn enveloped by a stainless steel liner. A Supercontainer measures about 2 m in diameter. In the design of the repository, the Supercontainers will be emplaced, one after the other, in disposal galleries. The space between the Supercontainers and the gallery lining needs to be filled up with a solid material. The most essential function of this component, referred to as backfill, is to prevent a collapse of the gallery. A secondary function is to limit the presence of free oxygen, to limit corrosion. In the ESDRED project EIG EURIDICE, together with SCK-CEN and ONDRAF/NIRAS, investigates technologies to apply the backfill. After testing two techniques to apply the backfill in 2007 at limited scale (unite with granular material and grouting with backfill mortar), grouting was selected as the preferred technique. This technique then should be tested at full-scale (30 m long mock-up). First, a full-scale structure needs to built, including an extensive instrumentation programme. In addition, the logistical needs to ensure a continuous backfill operation have to be worked out. The objective is to have the almost 100 m 3 backfilled in 4 hours

  15. Technology Performance Report: Duke Energy Notrees Wind Storage Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Wehner, Jeff [Duke Energy Renewables, Charlotte, NC (United States); Mohler, David [Duke Energy Renewables, Charlotte, NC (United States); Gibson, Stuart [Duke Energy Renewables, Charlotte, NC (United States); Clanin, Jason [Duke Energy Renewables, Charlotte, NC (United States); Faris, Don [Duke Energy Renewables, Charlotte, NC (United States); Hooker, Kevin [Duke Energy Renewables, Charlotte, NC (United States); Rowand, Michael [Duke Energy Renewables, Charlotte, NC (United States)

    2015-11-01

    Duke Energy Renewables owns and operates the Notrees Wind Farm in west Texas’s Ector and Winkler counties. The wind farm, which was commissioned in April 2009, has a total capacity of 152.6 MW generated by 55 Vestas V82 turbines, one Vestas 1-V90 experimental turbine, and 40 GE 1.5-MW turbines. The Vestas V82 turbines have a generating capacity of 1.65 MW each, the Vestas V90 turbine has a generating capacity of 1.86 MW, and the GE turbines have a generating capacity of 1.5 MW each. The objective of the Notrees Wind Storage Demonstration Project is to validate that energy storage increases the value and practical application of intermittent wind generation and is commercially viable at utility scale. The project incorporates both new and existing technologies and techniques to evaluate the performance and potential of wind energy storage. In addition, it could serve as a model for others to adopt and replicate. Wind power resources are expected to play a significant part in reducing greenhouse gas emissions from electric power generation by 2030. However, the large variability and intermittent nature of wind presents a barrier to integrating it within electric markets, particularly when competing against conventional generation that is more reliable. In addition, wind power production often peaks at night or other times when demand and electricity prices are lowest. Energy storage systems can overcome those barriers and enable wind to become a valuable asset and equal competitor to conventional fossil fuel generation.

  16. Michigan Oncology Medical Home Demonstration Project: First-Year Results.

    Science.gov (United States)

    Kuntz, Gordon; Tozer, Jane; Snegosky, Jeff; Fox, John; Neumann, Kurt

    2014-03-01

    The Michigan Oncology Medical Home Demonstration Project (MOMHDP) is an innovative multipractice oncology medical home model, supported by payment reform. Sponsored by Priority Health, Physician Resource Management, and ION Solutions, MOMHDP includes four oncology practices and 29 physicians. Oncology practices used existing technologies, with MOMHDP providing evidence-based treatment guideline selection and compliance tracking, automated physician order entry, a patient portal, symptom management/standardized nurse triage, and advance care planning. To support changes in care and administrative models and to focus on quality, MOMHDP modifies provider payments. The program replaces the average sales price payment methodology with a drug acquisition reimbursement plus a care management fee, calculated to increase total drug reimbursement. Additionally, it reimburses for chemotherapy and treatment planning and advance care planning consultation. There is also a shared savings opportunity. MOMHDP will be enhanced in its second year to include a survivorship program, patient distress screening, imaging guidelines, and standardized patient satisfaction surveys. Priority Health patients receiving chemotherapy for a cancer diagnosis were recruited to the program. Results for this group were compared with a control group of patients from a prior period. In addition to the financial results, the project also accomplished the following: (1) adherence to practice-selected guidelines, (2) institution of advance care planning, (3) effective and standardized symptom management; and (4) payment reform. We have identified a number of critical success factors: strong payer/provider collaboration built on trust through transparent use and cost data; timing of clinical standardization must come from the practices, so they can effectively absorb new approaches; having comprehensive, written program documentation and consistently applied training facilitate practice understanding

  17. DIMETHYL ETHER (DME)-FUELED SHUTTLE BUS DEMONSTRATION PROJECT

    Energy Technology Data Exchange (ETDEWEB)

    Elana M. Chapman; Shirish Bhide; Jennifer Stefanik; Howard Glunt; Andre L. Boehman; Allen Homan; David Klinikowski

    2003-04-01

    The objectives of this research and demonstration program are to convert a campus shuttle bus to operation on dimethyl ether, a potential ultra-clean alternative diesel fuel. To accomplish this objective, this project includes laboratory evaluation of a fuel conversion strategy, as well as, field demonstration of the DME-fueled shuttle bus. Since DME is a fuel with no lubricity (i.e., it does not possess the lubricating quality of diesel fuel), conventional fuel delivery and fuel injection systems are not compatible with dimethylether. Therefore, to operate a diesel engine on DME one must develop a fuel-tolerant injection system, or find a way to provide the necessary lubricity to the DME. In this project, they have chosen the latter strategy in order to achieve the objective with minimal need to modify the engine. The strategy is to blend DME with diesel fuel, to obtain the necessary lubricity to protect the fuel injection system and to achieve low emissions. The bulk of the efforts over the past year were focused on the conversion of the campus shuttle bus. This process, started in August 2001, took until April 2002 to complete. The process culminated in an event to celebrate the launching of the shuttle bus on DME-diesel operation on April 19, 2002. The design of the system on the shuttle bus was patterned after the system developed in the engine laboratory, but also was subjected to a rigorous failure modes effects analysis with help from Dr. James Hansel of Air Products. The result of this FMEA was the addition of layers of redundancy and over-pressure protection to the system on the shuttle bus. The system became operation in February 2002. Preliminary emissions tests and basic operation of the shuttle bus took place at the Pennsylvania Transportation institute's test track facility near the University Park airport. After modification and optimization of the system on the bus, operation on the campus shuttle route began in early June 2002. However, the

  18. Hanford Waste Vitrification Plant capacity increase options

    International Nuclear Information System (INIS)

    Larson, D.E.

    1996-04-01

    Studies are being conducted by the Hanford Waste Vitrification Plant (HWVP) Project on ways to increase the waste processing capacity within the current Vitrification Building structural design. The Phase 1 study on remote systems concepts identification and extent of capacity increase was completed. The study concluded that the HWVP capacity could be increased to four times the current capacity with minor design adjustments to the fixed facility design, and the required design changes would not impact the current footprint of the vitrification building. A further increase in production capacity may be achievable but would require some technology development, verification testing, and a more systematic and extensive engineering evaluation. The primary changes included a single advance melter with a higher capacity, new evaporative feed tank, offgas quench collection tank, ejector venturi scrubbers, and additional inner canister closure station,a smear test station, a new close- coupled analytical facility, waste hold capacity of 400,000 gallon, the ability to concentrate out-of-plant HWVP feed to 90 g/L waste oxide concentration, and limited changes to the current base slab construction package

  19. Hanford Waste Vitrification Plant Technology Plan

    International Nuclear Information System (INIS)

    Sexton, R.A.

    1988-06-01

    The reference Hanford plan for disposal of defense high-level waste is based on waste immobilization in glass by the vitrification process and temporary vitrified waste storage at the Hanford Site until final disposal in a geologic repository. A companion document to the Hanford Waste Management Plan (HWMP) is the Draft, Interim Hanford Waste Management Technology Plan (HWMTP), which provides a description of the technology that must be developed to meet the reference waste management plan. One of the issues in the HWMTP is DST-6, Immobilization (Glass). The HWMTP includes all expense funding needed to complete the Hanford Waste Vitrification Plant (HWVP) project. A preliminary HWVP Technology Plan was prepared in 1985 as a supporting document to the HWMTP to provide a more detailed description of the technology needed to construct and operate a vitrification facility. The plan was updated and issued in 1986, and revised in 1987. This document is an annual update of the plan. The HWVP Technology Plan is limited in scope to technology that requires development or confirmation testing. Other expense-funded activities are not included. The relationship between the HWVP Technology Plan and other waste management issues addressed in the HWMTP is described in section 1.6 of this plan. 6 refs., 4 figs., 34 tabs

  20. Technical safety appraisal of the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    1989-09-01

    This report presents the results of one in a series of Technical Safety Appraisals (TSAs) being conducted of DOE nuclear operations by the Assistant Secretary for Environment, Safety, and Health Office of Safety Appraisals TSAs are one of the ititiatives announced by the Secretary of Energy on September 18, 1985, to enhance the DOE environment, safety and health program. This report presents the results of a TSA of the West Valley Demonstration Project (WVDP). The appraisal was conducted by a team of exerts assembled by the DOE Office of Safety Appraisal and was conducted during onsite visits of June 26-30 and July 10-21, 1989. West Valley, about 30 miles south of Buffalo, New York is the location of the only commercial nuclear fuel reprocessing facility operated in the United States. Nuclear Fuels Services, Inc. (NFS) operated the plant from 1966 to 1972 and processed about 640 metric tons of spent reactor fuel. The reprocessing operation generated about 560,000 gallons of high-level radioactive waste, which was transferred into underground tanks for storage. In 1972 NFS closed the plant and subsequently decided not to reopen it

  1. Staunton 1 reclamation demonstration project. Aquatic ecosystems. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Vinikour, W. S.

    1981-02-01

    To provide long-term indications of the potential water quality improvements following reclamation efforts at the Staunton 1 Reclamation Demonstration Project, macroinvertebrates were collected from three on-site ponds and from the receiving stream (Cahokia Creek) for site drainage. Implications for potential benthic community differences resulting from site runoff were disclosed, but macroinvertebrate diversity throughout Cahokia Creek was limited due to an unstable, sandy substrate. The three ponds sampled were the New Pond, which was created as part of the reclamation activities; the Shed Pond, which and the Old Pond, which, because it was an existing, nonimpacted pond free of site runoff, served as a control. Comparisons of macroinvertebrates from the ponds indicated the potential for the New Pond to develop into a productive ecosystem. Macroinvertebrates in the New Pond were generally species more tolerant of acid mine drainage conditions. However, due to the present limited faunal densities and the undesirable physical and chemical characteristics of the New Pond, the pond should not be stocked with fish at this time.

  2. Staunton 1 Reclamation Demonstration Project. Progress report II

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-07-01

    The Staunton 1 Reclamation Demonstration Project involves an evaluation of the reclamation process on a 13.8-ha abandoned deep coal mine refuse site in southwestern Illinois. The procedure included collection of preconstruction environmental data, determination of the site's final land use, and development and implementation of a detailed site development plan. Approximately 9.3 ha of refuse material was recontoured, covered with a minimum of 30 cm of soil obtained on site, and seeded with a mixture of grasses and legumes. Hydrologic investigation indicates some improvement in groundwater quality. Surface water quality also has shown improvement, but development of the aquatic ecosystem in the newly-constructed pond is slow. Revegetation has been successful, and a protective plant cover has been established on most areas of the site. Soil tests indicate that acceptable plant growth media have been constructed; however, continued application of fertilizer and limestone will probably be necessary to maintain the vegetation. The soil microbial community has achieved total numbers equal to those of old fields, but species' diversity is low. Small mammals, birds, reptiles, and amphibians have invaded and are utilizing the site. The economic value of the site and adjacent property has increased substantially, and the area's aesthetic value has been enhanced significantly. The two-year period of intensive monitoring and evaluation has been utilized to develop recommendations for improving the designs of future reclamation efforts.

  3. STATUS and DIRECTION OF THE BULK VITRIFICATION PROGRAM FOR THE SUPPLEMENTAL TREATMENT OF LOW ACTIVITY TANK WASTE AT HANFORD

    International Nuclear Information System (INIS)

    RAYMOND, R.E.

    2005-01-01

    's In-Container Vitrification(trademark) process. As an outcome of this work, the hulk vitrification process was recommended for further evaluation. In fiscal year 2004, a follow-on bulk vitrification project was initiated to design, procure, assemble and operate a full-scale bulk vitrification pilot-plant to treat low activity tank waste from Hanford tank 241-S-109 under a Research, Development and Demonstration permit. That project is referred to as the Demonstration Bulk Vitrification System (or DBVS). The DBVS project will provide a full-scale bulk vitrification demonstration facility that can be used to assess the effectiveness of the bulk vitrification process under actual operating conditions. The pilot-plant is scheduled to commence operations in late 2005. The Supplemental Treatment Program represents a major element of the ORP's strategy to complete the pretreatment and immobilization of tank wastes by 2028. This paper will provide an overview of the bulk vitrification process and the progress in establishing the pilot-plant

  4. DIMETHYL ETHER (DME)-FUELED SHUTTLE BUS DEMONSTRATION PROJECT

    Energy Technology Data Exchange (ETDEWEB)

    Elana M. Chapman; Shirish Bhide; Jennifer Stefanik; Howard Glunt; Andre L. Boehman; Allen Homan; David Klinikowski

    2003-04-01

    The objectives of this research and demonstration program are to convert a campus shuttle bus to operation on dimethyl ether, a potential ultra-clean alternative diesel fuel. To accomplish this objective, this project includes laboratory evaluation of a fuel conversion strategy, as well as, field demonstration of the DME-fueled shuttle bus. Since DME is a fuel with no lubricity (i.e., it does not possess the lubricating quality of diesel fuel), conventional fuel delivery and fuel injection systems are not compatible with dimethyl ether. Therefore, to operate a diesel engine on DME one must develop a fuel-tolerant injection system, or find a way to provide the necessary lubricity to the DME. In this project, they have chosen the latter strategy in order to achieve the objective with minimal need to modify the engine. Their strategy is to blend DME with diesel fuel, to obtain the necessary lubricity to protect the fuel injection system and to achieve low emissions. The bulk of the efforts over the past year were focused on the conversion of the campus shuttle bus. This process, started in August 2001, took until April 2002 to complete. The process culminated in an event to celebrate the launching of the shuttle bus on DME-diesel operation on April 19, 2002. The design of the system on the shuttle bus was patterned after the system developed in the engine laboratory, but also was subjected to a rigorous failure modes effects analysis (FMEA, referred to by Air Products as a ''HAZOP'' analysis) with help from Dr. James Hansel of Air Products. The result of this FMEA was the addition of layers of redundancy and over-pressure protection to the system on the shuttle bus. The system became operational in February 2002. Preliminary emissions tests and basic operation of the shuttle bus took place at the Pennsylvania Transportation Institute's test track facility near the University Park airport. After modification and optimization of the system on

  5. Successful ongoing pregnancies after vitrification of oocytes.

    Science.gov (United States)

    Lucena, Elkin; Bernal, Diana Patricia; Lucena, Carolina; Rojas, Alejandro; Moran, Abby; Lucena, Andrés

    2006-01-01

    To demonstrate the efficiency of vitrifying mature human oocytes for different clinical indications. Descriptive case series. Cryobiology laboratory, Centro Colombiano de Fertilidad y Esterilidad-CECOLFES LTDA. (Bogotá, Colombia). Oocyte vitrification was offered as an alternative management for patients undergoing infertility treatment because of ovarian hyperstimulation syndrome, premature ovarian failure, natural ovarian failure, male factor, poor response, or oocyte donation. Mature oocytes were obtained from 33 donor women and 40 patients undergoing infertility treatment. Oocytes were retrieved by ultrasound-guided transvaginal aspiration and vitrified with the Cryotops method, with 30% ethylene glycol, 30% dimethyl sulfoxide, and 0.5 mol/L sucrose. Viability was assessed 3 hours after thawing. The surviving oocytes were inseminated by intracytoplasmic sperm injection. Fertilization was evaluated after 24 hours. The zygotes were further cultured in vitro for up to 72 hours until time of embryo transfer. Recovery, viability, fertilization, and pregnancy rates. Oocyte vitrification with the Cryotop method resulted in high rates of recovery, viability, fertilization, cleavage, and ongoing pregnancy. Vitrification with the Cryotop method is an efficient, fast, and economical method for oocyte cryopreservation that offers high rates of survival, fertilization, embryo development, and ongoing normal pregnancies, providing a new alternative for the management of female infertility.

  6. Gas Dynamic Spray Technology Demonstration Project Management. Joint Test Report

    Science.gov (United States)

    Lewis, Pattie

    2011-01-01

    The standard practice for protecting metallic substrates in atmospheric environments is the use of an applied coating system. Current coating systems used across AFSPC and NASA contain volatile organic compounds (VOCs) and hazardous air pollutants (HAPs). These coatings are sUbject to environmental regulations at the Federal and State levels that limit their usage. In addition, these coatings often cannot withstand the high temperatures and exhaust that may be experienced by Air Force Space Command (AFSPC) and NASA structures. In response to these concerns, AFSPC and NASA have approved the use of thermal spray coatings (TSCs). Thermal spray coatings are extremely durable and environmentally friendly coating alternatives, but utilize large cumbersome equipment for application that make the coatings difficult and time consuming to repair. Other concerns include difficulties coating complex geometries and the cost of equipment, training, and materials. Gas Dynamic Spray (GOS) technology (also known as Cold Spray) was evaluated as a smaller, more maneuverable repair method as well as for areas where thermal spray techniques are not as effective. The technology can result in reduced maintenance and thus reduced hazardous materials/wastes associated with current processes. Thermal spray and GOS coatings also have no VOCs and are environmentally preferable coatings. The primary objective of this effort was to demonstrate GDS technology as a repair method for TSCs. The aim was that successful completion of this project would result in approval of GDS technology as a repair method for TSCs at AFSPC and NASA installations to improve corrosion protection at critical systems, facilitate easier maintenance activity, extend maintenance cycles, eliminate flight hardware contamination, and reduce the amount of hazardous waste generated.

  7. Update on the status of the West Valley demonstration project

    International Nuclear Information System (INIS)

    Greeves, J.T.; Camper, L.W.; Orlando, D.A.; Glenn, C.J.; Buckley, J.T.; Giardina, P.A.

    2002-01-01

    From 1966 to 1972, under an Atomic Energy Commission (AEC) license, Nuclear Fuel Services (NFS) reprocessed 640 metric tons of spent fuel at its West Valley, New York, facility-, the only commercial spent fuel reprocessing plant in the U.S. The facility shut down in 1972, for modifications to increase its seismic stability and to expand its capacity. In 1976, without restarting the operation, NFS withdrew from the reprocessing business and returned control of the facilities to the site owner, the New York State Energy Research and Development Authority (NYSERDA). The reprocessing activities resulted in about 2.3 million liters (600,000 gallons) of liquid high-level waste (HLW) stored below ground in tanks, other radioactive wastes, and residual radioactive contamination. The West Valley site was licensed by AEC, and then the U.S. Nuclear Regulatory Commission (NRC), until 1981, when the license was suspended to execute the 1980 West Valley Demonstration Project (WVDP) Act. The WVDP Act outlines the responsibilities of the U.S. Department of Energy (DOE), NRC, and NYSERDA at the site, including the NRC's responsibility to develop decommissioning criteria for the site. The Commission published the final policy statement on decommissioning criteria for the WVDP at the West Valley site after considering comments from interested stakeholders. In that regard, the Commission prescribed the License Termination Rule (LTR) criteria for the WVDP at the West Valley site, reflecting the fact that the applicable decommissioning goal for the entire NRC-licensed site is compliance with the requirements of the LTR. This paper will describe the history of the site, provide an update of the status of the decommissioning of the site and an overview of the technical and policy issues facing Federal and State regulators and other stakeholders as they strive to complete the remediation of the site. (author)

  8. Demonstration Project 111, ITS/CVO Technology Truck, Final Project Report

    Energy Technology Data Exchange (ETDEWEB)

    Gambrell, KP

    2002-01-11

    In 1995, the planning and building processes began to design and develop a mobile demonstration unit that could travel across the nation and be used as an effective outreach tool. In 1997, the unit was completed; and from June 1997 until December 2000, the Federal Highway Administration (FHWA)/Federal Motor Carrier Safety Administration (FMCSA) mobilized the Technology Truck, also known as Demonstration Project No. 111, ''Advanced Motor Carrier Operations and Safety Technologies.'' The project featured the latest available state-of-the-practice intelligent transportation systems (ITS) technologies designed to improve both the efficiency and safety of commercial vehicle operations (CVO). The Technology Truck was designed to inform and educate the motor carrier community and other stakeholders regarding ITS technologies, thus gaining support and buy-in for participation in the ITS program. The primary objective of the project was to demonstrate new and emerging ITS/CVO technologies and programs, showing their impact on motor carrier safety and productivity. In order to meet the objectives of the Technology Truck project, the FHWA/FMCSA formed public/private partnerships with industry and with Oak Ridge National Laboratory to demonstrate and display available ITS/CVO technologies in a cooperative effort. The mobile demonstration unit was showcased at national and regional conferences, symposiums, universities, truck shows and other venues, in an effort to reach as many potential users and decision makers as possible. By the end of the touring phase, the ITS/CVO Technology Truck had been demonstrated in 38 states, 4 Canadian provinces, 88 cities, and 114 events; been toured by 18,099 people; and traveled 115,233 miles. The market penetration for the Technology Truck exceeded 4,000,000, and the website received more than 25,000 hits. In addition to the Truck's visits, the portable ITS/CVO kiosk was demonstrated at 31 events in 23 cites in 15

  9. Environmental Management vitrification activities

    Energy Technology Data Exchange (ETDEWEB)

    Krumrine, P.H. [Waste Policy Institute, Gaithersburg, MD (United States)

    1996-05-01

    Both the Mixed Waste and Landfill Stabilization Focus Areas as part of the Office of Technology Development efforts within the Department of Energy`s (DOE) Environmental Management (EM) Division have been developing various vitrification technologies as a treatment approach for the large quantities of transuranic (TRU), TRU mixed and Mixed Low Level Wastes that are stored in either landfills or above ground storage facilities. The technologies being developed include joule heated, plasma torch, plasma arc, induction, microwave, combustion, molten metal, and in situ methods. There are related efforts going into development glass, ceramic, and slag waste form windows of opportunity for the diverse quantities of heterogeneous wastes needing treatment. These studies look at both processing parameters, and long term performance parameters as a function of composition to assure that developed technologies have the right chemistry for success.

  10. Environmental Management vitrification activities

    International Nuclear Information System (INIS)

    Krumrine, P.H.

    1996-01-01

    Both the Mixed Waste and Landfill Stabilization Focus Areas as part of the Office of Technology Development efforts within the Department of Energy's (DOE) Environmental Management (EM) Division have been developing various vitrification technologies as a treatment approach for the large quantities of transuranic (TRU), TRU mixed and Mixed Low Level Wastes that are stored in either landfills or above ground storage facilities. The technologies being developed include joule heated, plasma torch, plasma arc, induction, microwave, combustion, molten metal, and in situ methods. There are related efforts going into development glass, ceramic, and slag waste form windows of opportunity for the diverse quantities of heterogeneous wastes needing treatment. These studies look at both processing parameters, and long term performance parameters as a function of composition to assure that developed technologies have the right chemistry for success

  11. Am/Cm Vitrification Process: Vitrification Material Balance Calculations

    International Nuclear Information System (INIS)

    Smith, F.G.

    2000-01-01

    This report documents material balance calculations for the Americium/Curium vitrification process and describes the basis used to make the calculations. The material balance calculations reported here start with the solution produced by the Am/Cm pretreatment process as described in ``Material Balance Calculations for Am/Cm Pretreatment Process (U)'', SRT-AMC-99-0178 [1]. Following pretreatment, small batches of the product will be further treated with an additional oxalic acid precipitation and washing. The precipitate from each batch will then be charged to the Am/Cm melter with glass cullet and vitrified to produce the final product. The material balance calculations in this report are designed to provide projected compositions of the melter glass and off-gas streams. Except for decanted supernate collected from precipitation and precipitate washing, the flowsheet neglects side streams such as acid washes of empty tanks that would go directly to waste. Complete listings of the results of the material balance calculations are provided in the Appendices to this report

  12. Ford Plug-In Project: Bringing PHEVs to Market Demonstration and Validation Project

    Energy Technology Data Exchange (ETDEWEB)

    D' Annunzio, Julie [Ford Motor Company, Dearborn, MI (United States); Slezak, Lee [U.S. DOE Office of Energy Efficiency & Renewable Energy, Washington, DC (United States); Conley, John Jason [National Energy Technology Lab. (NETL), Albany, OR (United States)

    2014-03-26

    This project is in support of our national goal to reduce our dependence on fossil fuels. By supporting efforts that contribute toward the successful mass production of plug-in hybrid electric vehicles, our nation’s transportation-related fuel consumption can be offset with energy from the grid. Over four and a half years ago, when this project was originally initiated, plug-in electric vehicles were not readily available in the mass marketplace. Through the creation of a 21 unit plug-in hybrid vehicle fleet, this program was designed to demonstrate the feasibility of the technology and to help build cross-industry familiarity with the technology and interface of this technology with the grid. Ford Escape PHEV Demonstration Fleet 3 March 26, 2014 Since then, however, plug-in vehicles have become increasingly more commonplace in the market. Ford, itself, now offers an all-electric vehicle and two plug-in hybrid vehicles in North America and has announced a third plug-in vehicle offering for Europe. Lessons learned from this project have helped in these production vehicle launches and are mentioned throughout this report. While the technology of plugging in a vehicle to charge a high voltage battery with energy from the grid is now in production, the ability for vehicle-to-grid or bi-directional energy flow was farther away than originally expected. Several technical, regulatory and potential safety issues prevented progressing the vehicle-to-grid energy flow (V2G) demonstration and, after a review with the DOE, V2G was removed from this demonstration project. Also proving challenging were communications between a plug-in vehicle and the grid or smart meter. While this project successfully demonstrated the vehicle to smart meter interface, cross-industry and regulatory work is still needed to define the vehicle-to-grid communication interface.

  13. Habitat Demonstration Unit Project: Leadership and Management Strategies for a Rapid Prototyping Project

    Science.gov (United States)

    Kennedy, Kriss J.; Toup, Larry; Gill, Tracy; Tri, Terry; Howe, Scott; Smitherman, David

    2011-01-01

    This paper gives an overview of the National Aeronautics and Space Administration (NASA) led multi-center Habitat Demonstration Unit (HDU) project leadership and management strategies being used by the NASA HDU team for a rapid prototyping project. The HDU project team constructed and tested an analog prototype lunar surface habitat/laboratory called the Pressurized Excursion Module (PEM) during 2010. The prototype unit subsystems were integrated in a short amount of time, utilizing a tiger team rapid prototyping approach that brought together over 20 habitation-related technologies and innovations from a variety of NASA centers. This paper describes the leadership and management strategies as well as lessons learned pertaining to leading and managing a multi-center diverse team in a rapid prototype environment. The PEM configuration went from a paper design to an operational surface habitat demonstration unit in less than 12 months. The HDU project is part of the strategic plan from the Exploration Systems Mission Directorate (ESMD) Directorate Integration Office (DIO) and the Exploration Mission Systems Office (EMSO) to test destination elements in analog environments. The 2011 HDU-Deep Space Habitat (DSH) configuration will build upon the PEM work, and emphasize validity of crew operations (remote working and living), EVA operations, mission operations, logistics operations, and science operations that might be required in a deep space context for Near Earth Object (NEO) exploration mission architectures. The 2011 HDU-DSH will be field-tested during the 2011 Desert Research and Technologies Studies (DRaTS) field tests. The HDU project is a "technology-pull" project that integrates technologies and innovations from multiple NASA centers. This project will repurpose the HDU 2010 demo unit that was field tested in the 2010 DRaTS, adding habitation functionality to the prototype unit. This paper will describe the strategy of establishing a multi-center project

  14. 78 FR 78342 - Extension of Autism Services Demonstration Project for TRICARE Beneficiaries Under the Extended...

    Science.gov (United States)

    2013-12-26

    ... DEPARTMENT OF DEFENSE Office of the Secretary Extension of Autism Services Demonstration Project... (the Department) Enhanced Access to Autism Services Demonstration Project (Autism Demonstration) under the Extended Care Health Option (ECHO) for beneficiaries diagnosed with an Autism Spectrum Disorder...

  15. 76 FR 80903 - Extension of Autism Services Demonstration Project for TRICARE Beneficiaries Under the Extended...

    Science.gov (United States)

    2011-12-27

    ... DEPARTMENT OF DEFENSE Office of the Secretary Extension of Autism Services Demonstration Project... Enhanced Access to Autism Services Demonstration Project under the Extended Care Health Option for beneficiaries diagnosed with an Autism Spectrum Disorder (ASD). Under the demonstration, the Department...

  16. Northwest Open Automated Demand Response Technology Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Kiliccote, Sila; Dudley, Junqiao Han; Piette, Mary Ann

    2009-08-01

    Lawrence Berkeley National Laboratory (LBNL) and the Demand Response Research Center (DRRC) performed a technology demonstration and evaluation for Bonneville Power Administration (BPA) in Seattle City Light's (SCL) service territory. This report summarizes the process and results of deploying open automated demand response (OpenADR) in Seattle area with winter morning peaking commercial buildings. The field tests were designed to evaluate the feasibility of deploying fully automated demand response (DR) in four to six sites in the winter and the savings from various building systems. The project started in November of 2008 and lasted 6 months. The methodology for the study included site recruitment, control strategy development, automation system deployment and enhancements, and evaluation of sites participation in DR test events. LBNL subcontracted McKinstry and Akuacom for this project. McKinstry assisted with recruitment, site survey collection, strategy development and overall participant and control vendor management. Akuacom established a new server and enhanced its operations to allow for scheduling winter morning day-of and day-ahead events. Each site signed a Memorandum of Agreement with SCL. SCL offered each site $3,000 for agreeing to participate in the study and an additional $1,000 for each event they participated. Each facility and their control vendor worked with LBNL and McKinstry to select and implement control strategies for DR and developed their automation based on the existing Internet connectivity and building control system. Once the DR strategies were programmed, McKinstry commissioned them before actual test events. McKinstry worked with LBNL to identify control points that can be archived at each facility. For each site LBNL collected meter data and trend logs from the energy management and control system. The communication system allowed the sites to receive day-ahead as well as day-of DR test event signals. Measurement of DR was

  17. Waste vitrification: a historical perspective

    International Nuclear Information System (INIS)

    McElroy, J.L.; Bjorklund, W.J.; Bonner, W.F.

    1982-02-01

    The possibility of converting high-level wastes (HLW) to glass was first pursued in Canada and England at a time when other countries were evaluating many other alternatives. By 1966, the British had completed radioactive demonstrations of the FINGAL pot process, converting HLW to borosilicate glass. By this time other countries, including France and the United States, had begun using the glass waste form. Beginning in 1966, several processes, including phosphate and borosilicate glass, were demonstrated by the US in the Waste Solidification Engineering Prototypes (WSEP) program at the Pacific Northwest Laboratory (PNL). Most of the current vitrification processes are adaptations of the FINGAL pot process or the continuous metallic melter used in the WSEP program. One notable exception is the joule-heated ceramic melter, which was adapted from commercial glass technology for HLW by PNL in the mid-1970's. Both batch and continuous processes have been developed to an advanced stage of readiness. These processes are described and compared in this paper

  18. Marketing plan : Dallas Integrated Corridor Management (ICM) demonstration project.

    Science.gov (United States)

    2014-01-01

    North Central Texas is a unique region in terms of its combination of recent, current and projected size, growth rate, ethnic diversity, and transportation profile specifically in relation to congestion. This document summarizes a plan to market ...

  19. Low-cost rural surface alternatives : demonstration project.

    Science.gov (United States)

    2015-06-01

    The goals of this project were to implement several stabilization methods for preventing or mitigating freeze-thaw damage to : granular surfaced roads and identify the most effective and economical methods for the soil and climate conditions of Iowa....

  20. Soil Remediation Demonstration Project: Biodegradation of Heavy Fuel Oils

    National Research Council Canada - National Science Library

    Reynolds, Charles

    1997-01-01

    .... Low-cost treatments applicable to small-scale spills are needed. The object of this CPAR project was to examine using cost-effective, on-site bioremediation techniques for heavy-oil-contaminated soil in cold regions...

  1. Hanford low-level vitrification melter testing -- Master list of data submittals

    International Nuclear Information System (INIS)

    Hendrickson, D.W.

    1995-01-01

    The Westinghouse Hanford Company (WHC) is conducting a two-phased effort to evaluate melter system technologies for vitrification of liquid low-level radioactive waste (LLW) streams. The evaluation effort includes demonstration testing of selected glass melter technologies and technical reports regarding the applicability of the glass melter technologies to the vitrification of Hanford LLW tank waste. The scope of this document is to identify and list vendor document submittals in technology demonstration support of the Hanford Low-Level Waste Vitrification melter testing program. The scope of this document is limited to those documents responsive to the Statement of Work, accepted and issued by the LLW Vitrification Program. The purpose of such a list is to maintain configuration control of vendor supplied data and to enable ready access to, and application of, vendor supplied data in the evaluation of melter technologies for the vitrification of Hanford low-level tank wastes

  2. GATEWAY Demonstrations: Exterior LED Lighting Projects at Princeton University

    Energy Technology Data Exchange (ETDEWEB)

    Davis, Robert G. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Evans, WIlliam E. [Princeton Univ., NJ (United States); Murphy, Arthur [Princeton Univ., NJ (United States); Perrin, Tess [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-10-30

    This report focuses on four exterior solid-state lighting projects that have been completed at Princeton since 2008, when the University adopted a comprehensive sustainability plan. Through these initial projects – which include a parking garage, a pedestrian path, and two parking lot installations – the school’s facilities engineering staff learned important lessons about SSL technology and gained experience in dealing with the rapidly changing landscape of lighting manufacturers and their suppliers.

  3. In situ vitrification: A review

    International Nuclear Information System (INIS)

    Cole, L.L.; Fields, D.E.

    1989-11-01

    The in situ vitrification process (ISV) converts contaminated soils and sludges to a glass and crystalline product. The process appears to be ideally suited for on site treatment of both wet and dry wastes. Basically, the system requires four molybdenum electrodes, an electrical power system for vitrifying the soil, a hood to trap gaseous effluents, an off-gas treatment system, an off-gas cooling system, and a process control station. Mounted in three transportable trailers, the ISV process can be moved from site to site. The process has the potential for treating contaminated soils at most 13 m deep. The ISV project has won a number of outstanding achievement awards. The process has also been patented with exclusive worldwide rights being granted to Battelle Memorial Institute for nonradioactive applications. While federal applications still belong to the Department of Energy, Battelle transferred the rights of ISV for non-federal government, chemical hazardous wastes to a separate corporation in 1989 called Geosafe. This report gives a review of the process including current operational behavior and applications

  4. 34 CFR 377.1 - What is the Demonstration Projects to Increase Client Choice Program?

    Science.gov (United States)

    2010-07-01

    ... 34 Education 2 2010-07-01 2010-07-01 false What is the Demonstration Projects to Increase Client... PROJECTS TO INCREASE CLIENT CHOICE PROGRAM General § 377.1 What is the Demonstration Projects to Increase Client Choice Program? The Demonstration Projects to Increase Client Choice Program is designed to...

  5. Expedited technology demonstration project. Project baseline revision 2.2 and FY96 plan

    International Nuclear Information System (INIS)

    1996-07-01

    The Expedited Technology Demonstration Project Plan, Mixed Waste Management Facility (MWMF) current baseline. The revised plan will focus efforts specifically on the demonstration of an integrated Molten Salt Oxidation (MSO) system. In addition to the MSO primary unit, offgas, and salt recycle subsystems, the demonstrations will include feed preparation and feed delivery systems, and the generation of robust final forms from process mineral residues. A simplified process flow chart for the expedited demonstration is provided. To minimize costs and to accelerate the schedule for deployment, the integrated system will be staged in an existing facility at LLNL equipped to handle hazardous and radioactive materials. The MSO systems will be activated in fiscal year 97, followed by the activation of feed preparation and final forms in fiscal year 98

  6. 75 FR 71171 - Social Security Disability Program Demonstration Project: Benefit Offset National Demonstration...

    Science.gov (United States)

    2010-11-22

    ... project. Stage 2 Offset and Enhanced Benefits Counseling Treatment Group--We will assign approximately 3... treatment of earnings and the enhanced benefits counseling, depending on their treatment group. Alternate... Treatment Group be eligible for counseling services? A beneficiary assigned to this Stage 2 treatment group...

  7. In situ vitrification laboratory-scale test work plan

    International Nuclear Information System (INIS)

    Nagata, P.K.; Smith, N.L.

    1991-05-01

    The Buried Waste Program was established in October 1987 to accelerate the studies needed to develop a long-term management plan for the buried mixed waste at the Radioactive Waste Management Complex at Idaho Engineering Laboratory. The In Situ Vitrification Project is being conducted in a Comprehensive Environmental Response, Compensation, and Liability Act feasibility study format to identify methods for the long-term management of mixed buried waste. To support the overall feasibility study, the situ vitrification treatability investigations are proceeding along the three parallel paths: laboratory-scale tests, intermediate field tests, and field tests. Laboratory-scale tests are being performed to provide data to mathematical modeling efforts, which, in turn, will support design of the field tests and to the health and safety risk assessment. This laboratory-scale test work plan provides overall testing program direction to meet the current goals and objectives of the in situ vitrification treatability investigation. 12 refs., 1 fig., 7 tabs

  8. District Heating Demonstration project. Bydgoszcz, Poland, Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-01

    The project was finished in January 1999. The present final report outlines the activities of the pilot project. The activities of the project were: Development of a general model or a design strategy for the modernisation of group substations; Training of selected staff in updated design and latest technologies; Comparing experiences from the reconstructed heat exchanger station with alternative solutions; Investigation of potential sources of financing for the modernisation of the district heating system based on a revised feasibility study. The development of a general model for the future design of the heat exchanger station and the substations resulted in a design guideline which was used for the design of the heat exchanger station. KPEC selected the heat exchanger station CC02, located in area B1, as the object for the heat exchanger reconstruction. The station supplies 42 substations in 20 dwelling houses with a total heat demand of 11 MW. The design of the reconstruction began in the autumn of 1996. The equipment was procured during the spring of 1997 and the bulk of the installation work was finished by October 1997. The appointed design engineer participated in two study tours to Denmark. During the implementation the project was enlarged with an addendum. The addendum consisted of a modernisation of twelve building substations. The monitoring programme was enlarged accordingly and the efficiency of the two solutions were compared and evaluated through the monitoring programme. Even though some of the data are rather limited, the monitoring programme reveals a tendency towards the substation modernisation being twice as efficient as the heat exchanger modernisation. The reconstruction of the heat exchanger station has indicated a heat saving potential of 10% whereas the substation project has indicated a heat saving potential of 20%. The project further shows a huge potential for power savings in the main pumps due to the automatic control. (EHS)

  9. Advanced Flue Gas Desulfurization (AFGD) demonstration project: Volume 2, Project performance and economics. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-30

    The project objective is to demonstrate removal of 90--95% or more of the SO{sub 2} at approximately one-half the cost of conventional scrubbing technology; and to demonstrate significant reduction of space requirements. In this project, Pure Air has built a single SO{sub 2} absorber for a 528-MWe power plant. The absorber performs three functions in a single vessel: prequencher, absorber, and oxidation of sludge to gypsum. Additionally, the absorber is of a co- current design, in which the flue gas and scrubbing slurry move in the same direction and at a relatively high velocity compared to conventional scrubbers. These features all combine to yield a state- of-the-art SO{sub 2} absorber that is more compact and less expensive than conventional scrubbers. The project incorporated a number of technical features including the injection of pulverized limestone directly into the absorber, a device called an air rotary sparger located within the base of the absorber, and a novel wastewater evaporation system. The air rotary sparger combines the functions of agitation and air distribution into one piece of equipment to facilitate the oxidation of calcium sulfite to gypsum. Additionally, wastewater treatment is being demonstrated to minimize water disposal problems inherent in many high-chloride coals. Bituminous coals primarily from the Indiana, Illinois coal basin containing 2--4.5% sulfur were tested during the demonstration. The Advanced Flue Gas Desulfurization (AFGD) process has demonstrated removal of 95% or more of the SO{sub 2} while providing a commercial gypsum by-product in lieu of solid waste. A portion of the commercial gypsum is being agglomerated into a product known as PowerChip{reg_sign} gypsum which exhibits improved physical properties, easier flowability and more user friendly handling characteristics to enhance its transportation and marketability to gypsum end-users.

  10. SmartPark Technology Demonstration Project, Phase II: Final Report

    Science.gov (United States)

    2018-05-01

    The purpose of FMCSA's SmartPark project was to determine the feasibility of a technology for providing truck parking space availability information in real time to truckers on the road. SmartPark consisted of two phases. Phase I was a field operatio...

  11. OCTAVIUS: a FP7 project demonstrating CO2 capture technologies

    NARCIS (Netherlands)

    Broutin, P.; Kvamsdal, H.M.; La Marca, C.; Os, P.J. van; Robinson, L.

    2014-01-01

    The OCTAVIUS project (Optimisation of CO2 Capture Technology Allowing Verification and Implementation at Utility Scale) has started on March 1st 2012 for a period of 5 years, as part of the 7th Framework Programme of the European Commission. Gathering 15 European and 2 South African partners,

  12. Research notes : solar powered navigational lighting system demonstration project.

    Science.gov (United States)

    2011-04-01

    ODOT will be installing a solar powered navigational lighting system on the AstoriaMegler Bridge as part of a pilot project approved by the Federal Highways Administration (FHWA). The coastal bridge is the connection across the Columbia River on U.S....

  13. Urban Options Solar Greenhouse Demonstration Project. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Cipparone, L.

    1980-10-15

    The following are included: the design process, construction, thermal performance, horticulture, educational activities, and future plans. Included in appendices are: greenhouse blueprints, insulating curtain details, workshop schedules, sample data forms, summary of performance calculations on the Urban Options Solar Greenhouse, data on vegetable production, publications, news articles on th Solar Greenhouse Project, and the financial statement. (MHR)

  14. In situ vitrification large-scale operational acceptance test analysis

    International Nuclear Information System (INIS)

    Buelt, J.L.; Carter, J.G.

    1986-05-01

    A thermal treatment process is currently under study to provide possible enhancement of in-place stabilization of transuranic and chemically contaminated soil sites. The process is known as in situ vitrification (ISV). In situ vitrification is a remedial action process that destroys solid and liquid organic contaminants and incorporates radionuclides into a glass-like material that renders contaminants substantially less mobile and less likely to impact the environment. A large-scale operational acceptance test (LSOAT) was recently completed in which more than 180 t of vitrified soil were produced in each of three adjacent settings. The LSOAT demonstrated that the process conforms to the functional design criteria necessary for the large-scale radioactive test (LSRT) to be conducted following verification of the performance capabilities of the process. The energy requirements and vitrified block size, shape, and mass are sufficiently equivalent to those predicted by the ISV mathematical model to confirm its usefulness as a predictive tool. The LSOAT demonstrated an electrode replacement technique, which can be used if an electrode fails, and techniques have been identified to minimize air oxidation, thereby extending electrode life. A statistical analysis was employed during the LSOAT to identify graphite collars and an insulative surface as successful cold cap subsidence techniques. The LSOAT also showed that even under worst-case conditions, the off-gas system exceeds the flow requirements necessary to maintain a negative pressure on the hood covering the area being vitrified. The retention of simulated radionuclides and chemicals in the soil and off-gas system exceeds requirements so that projected emissions are one to two orders of magnitude below the maximum permissible concentrations of contaminants at the stack

  15. Vitrification development plan for US Department of Energy mixed wastes

    International Nuclear Information System (INIS)

    Peters, R.; Lucerna, J.; Plodinec, M.J.

    1993-10-01

    This document is a general plan for conducting vitrification development for application to mixed wastes owned by the US Department of Energy. The emphasis is a description and discussion of the data needs to proceed through various stages of development. These stages are (1) screening at a waste site to determine which streams should be vitrified, (2) waste characterization and analysis, (3) waste form development and treatability studies, (4) process engineering development, (5) flowsheet and technical specifications for treatment processes, and (6) integrated pilot-scale demonstration. Appendices provide sample test plans for various stages of the vitrification development process. This plan is directed at thermal treatments which produce waste glass. However, the study is still applicable to the broader realm of thermal treatment since it deals with issues such as off-gas characterization and waste characterization that are not necessarily specific to vitrification. The purpose is to provide those exploring or considering vitrification with information concerning the kinds of data that are needed, the way the data are obtained, and the way the data are used. This will provide guidance to those who need to prioritize data needs to fit schedules and budgets. Knowledge of data needs also permits managers and planners to estimate resource requirements for vitrification development

  16. Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification

    International Nuclear Information System (INIS)

    1993-08-01

    The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program

  17. Quality of Security Service Costing Demonstration for the MSHN Project

    National Research Council Canada - National Science Library

    Spyropoulou, Evdoxia

    2000-01-01

    .... Each service has two costs: an initialization cost and a run-time cost. The demonstration illustrates the costs incurred as network modes and security levels are changed. High level and detailed specifications are provided.

  18. Integrated System Health Management (ISHM) Technology Demonstration Project Final Report

    Science.gov (United States)

    Mackey, Ryan; Iverson, David; Pisanich, Greg; Toberman, Mike; Hicks, Ken

    2006-01-01

    Integrated System Health Management (ISHM) is an essential capability that will be required to enable upcoming explorations mission systems such as the Crew Exploration Vehicle (CEV) and Crew Launch Vehicle (CLV), as well as NASA aeronautics missions. However, the lack of flight experience and available test platforms have held back the infusion by NASA Ames Research Center (ARC) and the Jet Propulsion Laboratory (JPL) of ISHM technologies into future space and aeronautical missions. To address this problem, a pioneer project was conceived to use a high-performance aircraft as a low-cost proxy to develop, mature, and verify the effectiveness of candidate ISHM technologies. Given the similarities between spacecraft and aircraft, an F/A-18 currently stationed at Dryden Flight Research Center (DFRC) was chosen as a suitable host platform for the test bed. This report describes how the test bed was conceived, how the technologies were integrated on to the aircraft, and how these technologies were matured during the project. It also describes the lessons learned during the project and a forward path for continued work.

  19. Modeling in situ vitrification

    International Nuclear Information System (INIS)

    Mecham, D.C.; MacKinnon, R.J.; Murray, P.E.; Johnson, R.W.

    1990-01-01

    In Situ Vitrification (ISV) process is being assessed by the Idaho National Engineering Laboratory (INEL) to determine its applicability to transuranic and mixed wastes buried at INEL'S Subsurface Disposal Area (SDA). This process uses electrical resistance heating to melt waste and contaminated soil in place to produce a durable glasslike material that encapsulates and immobilizes buried wastes. This paper outlines the requirements for the model being developed at the INEL which will provide analytical support for the ISV technology assessment program. The model includes representations of the electric potential field, thermal transport with melting, gas and particulate release, vapor migration, off-gas combustion and process chemistry. The modeling objectives are to help determine the safety of the process by assessing the air and surrounding soil radionuclides and chemical pollution hazards, the nuclear criticality hazard, and the explosion and fire hazards, help determine the suitability of the ISV process for stabilizing the buried wastes involved, and help design laboratory and field tests and interpret results. 3 refs., 2 figs., 1 tab

  20. Design, operation, and evaluation of the transportable vitrification system

    International Nuclear Information System (INIS)

    Zamecnik, J.R.; Young, S.R.; Hansen, E.K.; Whitehouse, J.C.

    1997-01-01

    The Transportable Vitrification System (TVS) is a transportable melter system designed to demonstrate the treatment of low-level and mixed hazardous and radioactive wastes such as wastewater treatment sludges, contaminated soils and incinerator ash. The TVS is a large-scale, fully integrated vitrification system consisting of melter feed preparation, melter, offgas, service, and control modules. The TVS was tested with surrogate waste at the Clemson University Environmental Systems Engineering Department's (ESED) DOE/Industry Center for Vitrification Research prior to being shipped to the DOE Oak Ridge Reservation (ORR) K-25 site for treatment of mixed waste. This testing, along with additional testing at ORR, proved that the TVS would be able to successfully treat mixed waste. These surrogate tests consistently produced glass that met the EPA Toxicity Characteristic Leaching Procedure (TCLP). Performance of the system resulted in acceptable emissions of regulated metals from the offgas system. The TVS is scheduled to begin mixed waste operations at ORR in June 1997

  1. 20 CFR 416.250 - Experimental, pilot, and demonstration projects in the SSI program.

    Science.gov (United States)

    2010-04-01

    ... administration of the SSI program. These projects will test the advantages of altering certain requirements... demonstration project will have a termination date (up to 10 years from the start of the project). [48 FR 7576...

  2. Expedited technology demonstration project (Revised mixed waste management facility project) Project baseline revision 4.0 and FY98 plan

    International Nuclear Information System (INIS)

    Adamson, M. G.

    1997-01-01

    The re-baseline of the Expedited Technology Demonstration Project (Revised Mixed Waste Facility Project) is designated as Project Baseline Revision 4.0. The last approved baseline was identified as Project Baseline Revision 3.0 and was issued in October 1996. Project Baseline Revision 4.0 does not depart from the formal DOE guidance followed by, and contained in, Revision 3.0. This revised baseline document describes the MSO and Final Forms testing activities that will occur during FY98, the final year of the ETD Project. The cost estimate for work during FY98 continues to be $2.OM as published in Revision 3.0. However, the funds will be all CENRTC rather than the OPEX/CENTRC split previously anticipated. LLNL has waived overhead charges on ETD Project CENRTC funds since the beginning of project activities. By requesting the $2.OM as all CENTRC a more aggressive approach to staffing and testing can be taken. Due to a cost under- run condition during FY97 procurements were made and work was accomplished, with the knowledge of DOE, in the Feed Preparation and Final Forms areas that were not in the scope of Revision 3.0. Feed preparation activities for FY98 have been expanded to include the drum opening station/enclosure previously deleted

  3. 76 FR 56406 - Science and Technology Reinvention Laboratory Demonstration Project; Department of the Army; Army...

    Science.gov (United States)

    2011-09-13

    ... DEPARTMENT OF DEFENSE Office of the Secretary Science and Technology Reinvention Laboratory Demonstration Project; Department of the Army; Army Research, Development and Engineering Command; Tank... personnel management demonstration project for eligible TARDEC employees. Within that notice the table...

  4. 78 FR 32637 - Science and Technology Reinvention Laboratory Personnel Management Demonstration Project...

    Science.gov (United States)

    2013-05-31

    ..., Science and Technology Reinvention Laboratory Personnel Management Demonstration Project, Department of... DEPARTMENT OF DEFENSE Office of the Secretary Science and Technology Reinvention Laboratory Personnel Management Demonstration Project, Department of the Army, Army Research, Development and...

  5. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2004

    International Nuclear Information System (INIS)

    2005-01-01

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2004. The report summarizes the environmental protection program at the West Valley Demonstration Project for CY 2004

  6. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2004

    Energy Technology Data Exchange (ETDEWEB)

    West Valley Nuclear Services Company (WVNSCO) and URS Group, Inc.

    2005-09-30

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2004. The report summarizes the environmental protection program at the West Valley Demonstration Project for CY 2004.

  7. American Indian Telecommunications Satellite Demonstration Project. Summary Report.

    Science.gov (United States)

    Lyndon B. Johnson Space Center, Houston, TX.

    The technical feasibility of voice and television communication within and between tribes, between tribes and federal agencies, and between educational institutions and tribes was demonstrated by broadcasts which took place April 10, 12, and 14, 1978, with equipment located at four sites: Crow Agency, Montana; All- Indian Culture Center, New…

  8. Vitrification chemistry and nuclear waste

    International Nuclear Information System (INIS)

    Plodinec, M.J.

    1985-01-01

    The vitrification of nuclear waste offers unique challenges to the glass technologist. The waste contains 50 or 60 elements, and often varies widely in composition. Most of these elements are seldom encountered in processing commercial glasses. The melter to vitrify the waste must be able to tolerate these variations in composition, while producing a durable glass. This glass must be produced without releasing hazardous radionuclides to the environment during any step of the vitrification process. Construction of a facility to convert the nearly 30 million gallons of high-level nuclear waste at the Savannah River Plant into borosilicate glass began in late 1983. In developing the vitrification process, the Savannah River Laboratory has had to overcome all of these challenges to the glass technologist. Advances in understanding in three areas have been crucial to our success: oxidation-reduction phenomena during glass melting; the reaction between glass and natural wastes; and the causes of foaming during glass melting

  9. 78 FR 29335 - Science and Technology Reinvention Laboratory (STRL) Personnel Management Demonstration Projects

    Science.gov (United States)

    2013-05-20

    ...) Personnel Management Demonstration Projects AGENCY: Office of the Deputy Assistant Secretary of Defense... demonstration project plans. SUMMARY: Section 342(b) of the National Defense Authorization Act (NDAA) for Fiscal... 2001, authorizes the Secretary of Defense to conduct personnel demonstration projects at DoD...

  10. 77 FR 69601 - Science and Technology Reinvention Laboratory (STRL) Personnel Management Demonstration Projects

    Science.gov (United States)

    2012-11-20

    ...) Personnel Management Demonstration Projects AGENCY: Office of the Deputy Assistant Secretary of Defense... to demonstration project plans. SUMMARY: Section 342(b) of the National Defense Authorization Act... the NDAA for FY 2001, authorizes the Secretary of Defense to conduct personnel demonstration projects...

  11. 75 FR 77379 - Science and Technology Reinvention Laboratory Personnel Management Demonstration Project...

    Science.gov (United States)

    2010-12-10

    ... Personnel Management Demonstration Project, Department of Navy, Office of Naval Research; Notice #0;#0..., authorizes the Secretary of Defense (SECDEF) to conduct personnel management demonstration projects at... to execute a process and plan to employ the Department's personnel management demonstration project...

  12. SRC-I Project Baseline. [SRC-I demonstration project near Owensboro, Kentucky

    Energy Technology Data Exchange (ETDEWEB)

    None

    1982-03-01

    The Process Design Criteria Specification forms the basis for process design for the 6000-TPSD SRC-I Demonstration Plant. It sets forth: basic engineering data, e.g., type and size of plant, feedstocks, product specifications, and atmospheric emission and waste disposal limits; utility conditions; equipment design criteria and sparing philosophy; and estimating criteria for economic considerations. Previously the formal ICRC Document No. 0001-01-002 has been submitted to DOE and revised, as necessary, to be consistent with the SRC-I Project Baseline. Revision 6, dated 19 March 1982, 51 pages, was forwarded to DOE on 19 March 1982.

  13. EBR-II spent fuel treatment demonstration project

    International Nuclear Information System (INIS)

    Benedict, R.W.; Henslee, S.P.

    1997-01-01

    For approximately 10 years, Argonne National Laboratory was developed a fast reactor fuel cycle based on dry processing. When the US fast reactor program was canceled in 1994, the fuel processing technology, called the electrometallurgical technique, was adapted for treating unstable spent nuclear fuel for disposal. While this technique, which involves electrorefining fuel in a molten salt bath, is being developed for several different fuel categories, its initial application is for sodium-bonded metallic spent fuel. In June 1996, the Department of Energy (DOE) approved a radiation demonstration program in which 100 spent driver assemblies and 25 spent blanket assemblies from the Experimental Breeder Reactor-II (EBR-II) will be treated over a three-year period. This demonstrated will provide data that address issues in the National Research Council's evaluation of the technology. The planned operations will neutralize the reactive component (elemental sodium) in the fuel and produce a low enriched uranium product, a ceramic waste and a metal waste. The fission products and transuranium elements, which accumulate in the electrorefining salt, will be stabilized in the glass-bonded ceramic waste form. The stainless steel cladding hulls, noble metal fission products, and insoluble residues from the process will be stabilized in a stainless steel/zirconium alloy. Upon completion of a successful demonstration and additional environmental evaluation, the current plans are to process the remainder of the DOE sodium bonded fuel

  14. Advanced Seismic Probabilistic Risk Assessment Demonstration Project Plan

    Energy Technology Data Exchange (ETDEWEB)

    Coleman, Justin [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-09-01

    Idaho National Laboratories (INL) has an ongoing research and development (R&D) project to remove excess conservatism from seismic probabilistic risk assessments (SPRA) calculations. These risk calculations should focus on providing best estimate results, and associated insights, for evaluation and decision-making. This report presents a plan for improving our current traditional SPRA process using a seismic event recorded at a nuclear power plant site, with known outcomes, to improve the decision making process. SPRAs are intended to provide best estimates of the various combinations of structural and equipment failures that can lead to a seismic induced core damage event. However, in general this approach has been conservative, and potentially masks other important events (for instance, it was not the seismic motions that caused the Fukushima core melt events, but the tsunami ingress into the facility).

  15. Performance Analysis of XCPC Powered Solar Cooling Demonstration Project

    Science.gov (United States)

    Widyolar, Bennett K.

    A solar thermal cooling system using novel non-tracking External Compound Parabolic Concentrators (XCPC) has been built at the University of California, Merced and operated for two cooling seasons. Its performance in providing power for space cooling has been analyzed. This solar cooling system is comprised of 53.3 m2 of XCPC trough collectors which are used to power a 23 kW double effect (LiBr) absorption chiller. This is the first system that combines both XCPC and absorption chilling technologies. Performance of the system was measured in both sunny and cloudy conditions, with both clean and dirty collectors. It was found that these collectors are well suited at providing thermal power to drive absorption cooling systems and that both the coinciding of available thermal power with cooling demand and the simplicity of the XCPC collectors compared to other solar thermal collectors makes them a highly attractive candidate for cooling projects.

  16. NUCLA Circulating Atmospheric Fluidized Bed Demonstration Project. Annual report, 1988

    Energy Technology Data Exchange (ETDEWEB)

    1991-01-01

    This Annual Report on Colorado-Ute Electric Association`s NUCLA Circulating Fluidized Bed (CFB) Demonstration Program covers the period from February 1987 through December 1988. The outline for presentation in this report includes a summary of unit operations along with individual sections covering progress in study plan areas that commenced during this reporting period. These include cold-mode shakedown and calibration, plant commercial performance statistics, unit start-up (cold), coal and limestone preparation and handling, ash handling system performance and operating experience, tubular air heater, baghouse operation and performance, materials monitoring, and reliability monitoring. During this reporting period, the coal-mode shakedown and calibration plan was completed. (VC)

  17. Next Generation Luminaire (NGL) Downlight Demonstration Project, Hilton Columbus Downtown

    Energy Technology Data Exchange (ETDEWEB)

    Davis, R. G. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Perrin, T. E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2014-09-30

    At the Hilton Columbus Downtown hotel in Ohio, DOE's Better Buildings Alliance conducted a demonstration of Next Generation Luminaires-winning downlights installed in all guest rooms and suites prior to the hotel's 2012 opening. After a post-occupancy assessment, the LED downlights not only provided the aesthetic appearance and dimming functionality desired, but also provided 50% energy savings relative to a comparable CFL downlight and enabled the lighting power to be more than 20% below that allowed by code.

  18. Chloride removal from vitrification offgas

    Energy Technology Data Exchange (ETDEWEB)

    Slaathaug, E.J. [Westinghouse Hanford Co., Richland, WA (United States)

    1995-06-01

    This study identified and investigated techniques of selectively purging chlorides from the low-level waste (LLW) vitrification process with the purge stream acceptable for burial on the Hanford Site. Chlorides will be present in high concentration in several individual feeds to the LLW Vitrification Plant. The chlorides are highly volatile in combustion type melters and are readily absorbed by wet scrubbing of the melter offgas. The Tank Waste Remediation System (TWRS) process flow sheets show that the resulting chloride rich scrub solution is recycled back to the melter. The chlorides must be purged from the recycle loop to prevent the buildup of excessively high chloride concentrations.

  19. Chloride removal from vitrification offgas

    International Nuclear Information System (INIS)

    Slaathaug, E.J.

    1995-01-01

    This study identified and investigated techniques of selectively purging chlorides from the low-level waste (LLW) vitrification process with the purge stream acceptable for burial on the Hanford Site. Chlorides will be present in high concentration in several individual feeds to the LLW Vitrification Plant. The chlorides are highly volatile in combustion type melters and are readily absorbed by wet scrubbing of the melter offgas. The Tank Waste Remediation System (TWRS) process flow sheets show that the resulting chloride rich scrub solution is recycled back to the melter. The chlorides must be purged from the recycle loop to prevent the buildup of excessively high chloride concentrations

  20. Exercise Countermeasures Demonstration Project During the Lunar-Mars Life Support Test Project Phase 2A

    Science.gov (United States)

    Lee, Stuart M. C.; Guilliams, Mark E.; Moore, Alan D., Jr.; Williams, W. Jon; Greenisen, M. C.; Fortney, S. M.

    1998-01-01

    This demonstration project assessed the crew members' compliance to a portion of the exercise countermeasures planned for use onboard the International Space Station (ISS) and the outcomes of their performing these countermeasures. Although these countermeasures have been used separately in other projects and investigations, this was the first time they'd been used together for an extended period (60 days) in an investigation of this nature. Crew members exercised every day for six days, alternating every other day between aerobic and resistive exercise, and rested on the seventh day. On the aerobic exercise days, subjects exercised on an electronically braked cycle ergometer using a protocol that has been previously shown to maintain aerobic capacity in subjects exposed to a space flight analogue. On the resistive exercise days, crew members performed five major multijoint resistive exercises in a concentric mode, targeting those muscle groups and bones we believe are most severely affected by space flight. The subjects favorably tolerated both exercise protocols, with a 98% compliance to aerobic exercise prescription and a 91% adherence to the resistive exercise protocol. After 60 days, the crew members improved their peak aerobic capacity by an average 7%, and strength gains were noted in all subjects. These results suggest that these exercise protocols can be performed during ISS, lunar, and Mars missions, although we anticipate more frequent bouts with both protocols for long-duration spaceflight. Future projects should investigate the impact of increased exercise duration and frequency on subject compliance, and the efficacy of such exercise prescriptions.

  1. LIFAC sorbent injection desulfurization demonstration project. Final report, volume II: Project performance and economics

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

    This publication discusses the demonstration of the LIFAC sorbent injection technology at Richmond Power and Light`s Whitewater Valley Unit No. 2, performed under the auspices of the U.S. Department of Energy`s (DOE) Clean Coal Technology Program. LIFAC is a sorbent injection technology capable of removing 75 to 85 percent of a power plant`s SO{sub 2} emissions using limestone at calcium to sulfur molar ratios of between 2 and 2.5 to 1. The site of the demonstration is a coal-fired electric utility power plant located in Richmond, Indiana. The project is being conducted by LIFAC North America (LIFAC NA), a joint venture partnership of Tampella Power Corporation and ICF Kaiser Engineers, in cooperation with DOE, RP&L, and Research Institute (EPRI), the State of Indiana, and Black Beauty Coal Company. The purpose of Public Design Report Volume 2: Project Performance and Economics is to consolidate, for public use, the technical efficiency and economy of the LIFAC Process. The report has been prepared pursuant to the Cooperative Agreement No. DE-FC22-90PC90548 between LIFAC NA and the U.S. Department of Energy.

  2. Software for Distributed Computation on Medical Databases: A Demonstration Project

    Directory of Open Access Journals (Sweden)

    Balasubramanian Narasimhan

    2017-05-01

    Full Text Available Bringing together the information latent in distributed medical databases promises to personalize medical care by enabling reliable, stable modeling of outcomes with rich feature sets (including patient characteristics and treatments received. However, there are barriers to aggregation of medical data, due to lack of standardization of ontologies, privacy concerns, proprietary attitudes toward data, and a reluctance to give up control over end use. Aggregation of data is not always necessary for model fitting. In models based on maximizing a likelihood, the computations can be distributed, with aggregation limited to the intermediate results of calculations on local data, rather than raw data. Distributed fitting is also possible for singular value decomposition. There has been work on the technical aspects of shared computation for particular applications, but little has been published on the software needed to support the "social networking" aspect of shared computing, to reduce the barriers to collaboration. We describe a set of software tools that allow the rapid assembly of a collaborative computational project, based on the flexible and extensible R statistical software and other open source packages, that can work across a heterogeneous collection of database environments, with full transparency to allow local officials concerned with privacy protections to validate the safety of the method. We describe the principles, architecture, and successful test results for the site-stratified Cox model and rank-k singular value decomposition.

  3. Innovative technology summary report: Transportable vitrification system

    International Nuclear Information System (INIS)

    1998-09-01

    At the end of the cold war, many of the Department of Energy's (DOE's) major nuclear weapons facilities refocused their efforts on finding technically sound, economic, regulatory compliant, and stakeholder acceptable treatment solutions for the legacy of mixed wastes they had produced. In particular, an advanced stabilization process that could effectively treat the large volumes of settling pond and treatment sludges was needed. Based on this need, DOE and its contractors initiated in 1993 the EM-50 sponsored development effort required to produce a deployable mixed waste vitrification system. As a consequence, the Transportable Vitrification System (TVS) effort was undertaken with the primary requirement to develop and demonstrate the technology and associated facility to effectively vitrify, for compliant disposal, the applicable mixed waste sludges and solids across the various DOE complex sites. After 4 years of development testing with both crucible and pilot-scale melters, the TVS facility was constructed by Envitco, evaluated and demonstrated with surrogates, and then successfully transported to the ORNL ETTP site and demonstrated with actual mixed wastes in the fall of 1997. This paper describes the technology, its performance, the technology applicability and alternatives, cost, regulatory and policy issues, and lessons learned

  4. Evaluation of the uranium enrichment demonstration plant project

    International Nuclear Information System (INIS)

    Sugitsue, Noritake

    2001-01-01

    In this report, the organization system of the uranium enrichment business is evaluated, based on the operation of the uranium enrichment demonstration plant. As a result, in uranium enrichment technology development or business, it was acknowledged that maintenance of the organization which has the Trinity of a research/engineering/operation was necessary in an industrialization stage by exceptional R and D cycle. Japan Nuclear Fuel Ltd. (JNFL) set up the Rokkashomura Aomori Uranium Enrichment Research and Development Center in November 2000. As a result, the system that company directly engaged in engineering development was prepared. And results obtained in this place is expected toward certain establishment of the uranium enrichment business of Japan. (author)

  5. BACA Project: geothermal demonstration power plant. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1982-12-01

    The various activities that have been conducted by Union in the Redondo Creek area while attempting to develop the resource for a 50 MW power plant are described. The results of the geologic work, drilling activities and reservoir studies are summarized. In addition, sections discussing the historical costs for Union's involvement with the project, production engineering (for anticipated surface equipment), and environmental work are included. Nineteen geothermal wells have been drilled in the Redondo Creek area of the Valles Caldera: a prominent geologic feature of the Jemez mountains consisting of Pliocene and Pleistocene age volcanics. The Redondo Creek area is within a complex longitudinal graben on the northwest flank of the resurgent structural dome of Redondo Peak and Redondo Border. The major graben faults, with associated fracturing, are geologically plausible candidates for permeable and productive zones in the reservoir. The distribution of such permeable zones is too erratic and the locations too imprecisely known to offer an attractive drilling target. Log analysis indicates there is a preferred mean fracture strike of N31W in the upper portion of Redondo Creek wells. This is approximately perpendicular to the major structure in the area, the northeast-striking Redondo Creek graben. The geothermal fluid found in the Redondo Creek reservoir is relatively benign with low brine concentrations and moderate H/sub 2/S concentrations. Geothermometer calculations indicate that the reservoir temperature generally lies between 500/sup 0/F and 600/sup 0/F, with near wellbore flashing occurring during the majority of the wells' production.

  6. Process technology for vitrification of defense high-level waste at the Savannah River Plant

    International Nuclear Information System (INIS)

    Boersma, M.D.

    1984-01-01

    Vitrification in borosilicate glass is now the leading worldwide process for immobilizing high-level radioactive waste. Each vitrification project, however, has its unique mission and technical challenges. The Defense Waste Vitrification Facility (DWPF) now under construction at the Savannah River Plant will concentrate and vitrify a large amount of relatively low-power alkaline waste. Process research and development for the DWPF have produced significant advances in remote chemical operations, glass melting, off-gas treatment, slurry handling, decontamination, and welding. 6 references, 1 figure, 5 tables

  7. Successful vitrification and autografting of baboon (Papio anubis) ovarian tissue.

    Science.gov (United States)

    Amorim, Christiani A; Jacobs, Sophie; Devireddy, Ram V; Van Langendonckt, Anne; Vanacker, Julie; Jaeger, Jonathan; Luyckx, Valérie; Donnez, Jacques; Dolmans, Marie-Madeleine

    2013-08-01

    Can a vitrification protocol using an ethylene glycol/dimethyl sulphoxide-based solution and a cryopin successfully cryopreserve baboon ovarian tissue? Our results show that baboon ovarian tissue can be successfully cryopreserved with our vitrification protocol. Non-human primates have already been used as an animal model to test vitrification protocols for human ovarian tissue cryopreservation. Ovarian biopsies from five adult baboons were vitrified, warmed and autografted for 5 months. After grafting, follicle survival, growth and function and also the quality of stromal tissue were assessed histologically and by immunohistochemistry. The influence of the vitrification procedure on the cooling rate was evaluated by a computer model. After vitrification, warming and long-term grafting, follicles were able to grow and maintain their function, as illustrated by Ki67, anti-Müllerian hormone (AMH) and growth differentiation factor-9 (GDF-9) immunostaining. Corpora lutea were also observed, evidencing successful ovulation in all the animals. Stromal tissue quality did not appear to be negatively affected by our cryopreservation procedure, as demonstrated by vascularization and proportions of fibrotic areas, which were similar to those found in fresh ungrafted ovarian tissue. Despite our promising findings, before applying this technique in a clinical setting, we need to validate it by achieving pregnancies. In addition to encouraging results obtained with our vitrification procedure for non-human ovarian tissue, this study also showed, for the first time, expression of AMH and GDF-9 in ovarian follicles. This study was supported by grants from the Fonds National de la Recherche Scientifique de Belgique (grant Télévie No. 7.4507.10, grant 3.4.590.08 awarded to Marie-Madeleine Dolmans), Fonds Spéciaux de Recherche, Fondation St Luc, Foundation Against Cancer, and Department of Mechanical Engineering at Louisiana State University (support to Ram Devireddy), and

  8. Final report on Thermally Modified Sand demonstration project

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-23

    The use of salt and salt/sand mixtures on icy roadway surfaces has dramatically increased during the past 30 years. Despite extensive documentation on salt related damage to the roadway improvements, vehicles and the environment, road maintenance departments have continued to rely on this practice. Road maintenance departments in northern climate areas have long recognized the safety benefits for public mobility on icy roadways from the use of sand. As an abrasive material, the sand improves the surface traction that results in more drivable and less hazardous road conditions during the winter months. Stockpiles of pure sand stored during the winter months oftentimes freeze into large unworkable, monolithic piles. To maintain a free-flowing condition, it has been found to be necessary to add salt to the sand. The addition of salt in amounts ranging from 5 to 10 percent to that of sand, is usually sufficient to provide relatively free-flowing abrasive material that could be stored in stockpiles and applied to icy road surfaces with conventional sand spreading trucks. Another alternative for winter storage of pure sand to maintain a free-flowing condition is in humidity-controlled, heated buildings. As would be expected, this method has high capital and operating costs. and not cost effective for general highway maintenance use. The invention demonstrated herein is a method of thermally modifying pure sand that will remain in a free-flowing state throughout the winter season without the need for the salt additive. The thermally modified sand provides an abrasive material that when applied to icy roads does not cause environmental and corrosive damage as done by the application of sand with salt. By employing a very simple process of freezing screened sand particles by forced air convection under subfreezing conditions, the invention creates a product that has significant value in terms of economic and environmental benefits.

  9. Selecting a plutonium vitrification process

    Energy Technology Data Exchange (ETDEWEB)

    Jouan, A. [Centre d`Etudes de la Vallee du Rhone, Bagnols sur Ceze (France)

    1996-05-01

    Vitrification of plutonium is one means of mitigating its potential danger. This option is technically feasible, even if it is not the solution advocated in France. Two situations are possible, depending on whether or not the glass matrix also contains fission products; concentrations of up to 15% should be achievable for plutonium alone, whereas the upper limit is 3% in the presence of fission products. The French continuous vitrification process appears to be particularly suitable for plutonium vitrification: its capacity is compatible with the required throughout, and the compact dimensions of the process equipment prevent a criticality hazard. Preprocessing of plutonium metal, to convert it to PuO{sub 2} or to a nitric acid solution, may prove advantageous or even necessary depending on whether a dry or wet process is adopted. The process may involve a single step (vitrification of Pu or PuO{sub 2} mixed with glass frit) or may include a prior calcination step - notably if the plutonium is to be incorporated into a fission product glass. It is important to weigh the advantages and drawbacks of all the possible options in terms of feasibility, safety and cost-effectiveness.

  10. Hanford Waste Vitrification Plant hydrogen generation

    International Nuclear Information System (INIS)

    King, R.B.; King, A.D. Jr.; Bhattacharyya, N.K.

    1996-02-01

    The most promising method for the disposal of highly radioactive nuclear wastes is a vitrification process in which the wastes are incorporated into borosilicate glass logs, the logs are sealed into welded stainless steel canisters, and the canisters are buried in suitably protected burial sites for disposal. The purpose of the research supported by the Hanford Waste Vitrification Plant (HWVP) project of the Department of Energy through Battelle Pacific Northwest Laboratory (PNL) and summarized in this report was to gain a basic understanding of the hydrogen generation process and to predict the rate and amount of hydrogen generation during the treatment of HWVP feed simulants with formic acid. The objectives of the study were to determine the key feed components and process variables which enhance or inhibit the.production of hydrogen. Information on the kinetics and stoichiometry of relevant formic acid reactions were sought to provide a basis for viable mechanistic proposals. The chemical reactions were characterized through the production and consumption of the key gaseous products such as H 2 . CO 2 , N 2 0, NO, and NH 3 . For this mason this research program relied heavily on analyses of the gases produced and consumed during reactions of the HWVP feed simulants with formic acid under various conditions. Such analyses, used gas chromatographic equipment and expertise at the University of Georgia for the separation and determination of H 2 , CO, CO 2 , N 2 , N 2 O and NO

  11. Transportable Vitrification System RCRA Closure Practical Waste Disposition Saves Time And Money

    International Nuclear Information System (INIS)

    Brill, Angie; Boles, Roger; Byars, Woody

    2003-01-01

    The Transportable Vitrification System (TVS) was a large-scale vitrification system for the treatment of mixed wastes. The wastes contained both hazardous and radioactive materials in the form of sludge, soil, and ash. The TVS was developed to be moved to various United States Department of Energy (DOE) facilities to vitrify mixed waste as needed. The TVS consists of four primary modules: (1) Waste and Additive Materials Processing Module; (2) Melter Module; (3) Emissions Control Module; and (4) Control and Services Module. The TVS was demonstrated at the East Tennessee Technology Park (ETTP) during September and October of 1997. During this period, approximately 16,000 pounds of actual mixed waste was processed, producing over 17,000 pounds of glass. After the demonstration was complete it was determined that it was more expensive to use the TVS unit to treat and dispose of mixed waste than to direct bury this waste in Utah permitted facility. Thus, DOE had to perform a Resource Conservation and Recovery Act (RCRA) closure of the facility and find a reuse for as much of the equipment as possible. This paper will focus on the following items associated with this successful RCRA closure project: TVS site closure design and implementation; characterization activities focused on waste disposition; pollution prevention through reuse; waste minimization efforts to reduce mixed waste to be disposed; and lessons learned that would be integrated in future projects of this magnitude

  12. 75 FR 55199 - Science and Technology Reinvention Laboratory Personnel Management Demonstration Project...

    Science.gov (United States)

    2010-09-09

    ... customers; and 7. Workforce satisfaction. An evaluation model was developed for the Director, Defense... personnel system under an appropriate demonstration project as defined in section 342(b) of Public Law 103... satisfaction. With some modifications, this project mirrors the STRL personnel management demonstration project...

  13. 5 CFR 470.305 - Submission of proposals for demonstration projects.

    Science.gov (United States)

    2010-01-01

    ... time on submitted proposals until comparisons can be made with other existing projects or with project... projects. 470.305 Section 470.305 Administrative Personnel OFFICE OF PERSONNEL MANAGEMENT CIVIL SERVICE REGULATIONS PERSONNEL MANAGEMENT RESEARCH PROGRAMS AND DEMONSTRATIONS PROJECTS Regulatory Requirements...

  14. 75 FR 8927 - Autism Services Demonstration Project for TRICARE Beneficiaries Under the Extended Care Health...

    Science.gov (United States)

    2010-02-26

    ... DEPARTMENT OF DEFENSE Office of the Secretary Autism Services Demonstration Project for TRICARE... Access to Autism Services Demonstration Project under the Extended Care Health Option for beneficiaries diagnosed with an Autism Spectrum Disorder (ASD). Under the demonstration, the Department implemented a...

  15. Increasing seat belt use through state-level demonstration projects : a compendium of initial findings

    Science.gov (United States)

    2008-08-01

    This report summarizes the efforts and results from four of six State-level demonstration projects supported with cooperative agreements from the National Highway Traffic Safety Administration. The projects were intended to increase seat belt use sta...

  16. Vitrification of Simulated Fernald K-65 Silo Waste at Low Temperature

    International Nuclear Information System (INIS)

    Jantzen, C.M.; Pickett, J.B.

    1998-01-01

    Vitrification is the technology that has been chosen to solidify approximately 15,500 tons of geologic mill tailings at the Fernald Environmental Management Project (FEMP) in Fernald, Ohio. The geologic mill tailings are residues from the processing of pitchlende ore during 1949-1958. These waste residues are contained in silos in Operable Unit 4 (OU4) at the FEMP facility. Operable Unit 4 is one of five operable units at the FEMP. Operating Unit 4 consists of four concrete storage silos and their contents. Silos 1 and 2 contain K-65 mill tailing residues and a bentonite cap, Silo 3 contains non-radioactive metal oxides, and Silo 4 is empty. The K-65 residues contain radium, uranium, uranium daughter products, and heavy metals such as lead and barium.The K-65 waste leaches lead at greater than 100 times the allowable Environmental Protection Agency (EPA) Resource, Conservation, and Recovery Act (RCRA) concentration limits when tested by the Toxic Characteristic Leaching Procedure (TCLP). Vitrification was chosen by FEMP as the preferred technology for the Silos 1, 2, 3 wastes because the final waste form met the following criteria: controls radon emanation, eliminates the potential for hazardous or radioactive constituents to migrate to the aquifer below FEMP, controls the spread of radioactive particulates, reduces leachability of metals and radiological constituents, reduces volume of final wasteform for disposal, silo waste composition is favorable to vitrification, will meet current and proposed RCRA TCLP leaching criteria Glasses that melt at 1350 degrees C were developed by Pacific Northwest National Laboratory (PNNL) and glasses that melt between 1150-1350 degrees C were developed by the Vitreous State Laboratory (VSL) for the K-65 silo wastes. Both crucible studies and pilot scale vitrification studies were conducted by PNNL and VSL. Subsequently, a Vitrification Pilot Plant (VPP) was constructed at FEMP capable of operating at temperatures up to 1450

  17. The Treatment of Mixed Waste with GeoMelt In-Container Vitrification

    International Nuclear Information System (INIS)

    Finucane, K.G.; Campbell, B.E.

    2006-01-01

    AMEC's GeoMelt R In-Container Vitrification (ICV) TM has been used to treat diverse types of mixed low-level radioactive waste. ICV is effective in the treatment of mixed wastes containing polychlorinated biphenyls (PCBs) and other semi-volatile organic compounds, volatile organic compounds (VOCs) and heavy metals. The GeoMelt vitrification process destroys organic compounds and immobilizes metals and radionuclides in an extremely durable glass waste form. The process is flexible allowing for treatment of aqueous, oily, and solid mixed waste, including contaminated soil. In 2004, ICV was used to treat mixed radioactive waste sludge containing PCBs generated from a commercial cleanup project regulated by the Toxic Substances Control Act (TSCA), and to treat contaminated soil from Rocky Flats Environmental Technology Site. The Rocky Flats soil contained cadmium, PCBs, and depleted uranium. In 2005, AMEC completed a treatability demonstration of the ICV technology on Mock High Explosive from Sandia National Laboratories. This paper summarizes results from these mixed waste treatment projects. (authors)

  18. Vitrification of hazardous and radioactive wastes

    International Nuclear Information System (INIS)

    Bickford, D.F.; Schumacher, R.

    1995-01-01

    Vitrification offers many attractive waste stabilization options. Versatility of waste compositions, as well as the inherent durability of a glass waste form, have made vitrification the treatment of choice for high-level radioactive wastes. Adapting the technology to other hazardous and radioactive waste streams will provide an environmentally acceptable solution to many of the waste challenges that face the public today. This document reviews various types and technologies involved in vitrification

  19. Status of the French AVM vitrification facility

    International Nuclear Information System (INIS)

    Bonniaud, R.A.; Jouan, A.F.; Sombret, C.G.

    1979-01-01

    The Commission of the Marcoule Vitrification Plant (or AVM) has opened the industrial development era for the continuous vitrification process. Radioactive liquid wastes are calcinated in a rotary kiln to give a solid form, mixed with suitable raw materials in an electric furnace to make the glass. The glass is poured in containers and transferred to a disposal facility. The off gas released are processed. Design of La Hague next vitrification plant is given

  20. Glasses and nuclear waste vitrification

    International Nuclear Information System (INIS)

    Ojovan, Michael I.

    2012-01-01

    Glass is an amorphous solid material which behaves like an isotropic crystal. Atomic structure of glass lacks long-range order but possesses short and most probably medium range order. Compared to crystalline materials of the same composition glasses are metastable materials however crystallisation processes are kinetically impeded within times which typically exceed the age of universe. The physical and chemical durability of glasses combined with their high tolerance to compositional changes makes glasses irreplaceable when hazardous waste needs immobilisation for safe long-term storage, transportation and consequent disposal. Immobilisation of radioactive waste in glassy materials using vitrification has been used successfully for several decades. Nuclear waste vitrification is attractive because of its flexibility, the large number of elements which can be incorporated in the glass, its high corrosion durability and the reduced volume of the resulting wasteform. Vitrification involves melting of waste materials with glass-forming additives so that the final vitreous product incorporates the waste contaminants in its macro- and micro-structure. Hazardous waste constituents are immobilised either by direct incorporation into the glass structure or by encapsulation when the final glassy material can be in form of a glass composite material. Both borosilicate and phosphate glasses are currently used to immobilise nuclear wastes. In addition to relatively homogeneous glasses novel glass composite materials are used to immobilise problematic waste streams. (author)

  1. 78 FR 64204 - Science and Technology Reinvention Laboratory Personnel Management Demonstration Project...

    Science.gov (United States)

    2013-10-28

    ... Personnel Management Demonstration Project, Department of Navy, Office of Naval Research (ONR); Amendment... ONR Personnel Management Demonstration Project (75 FR 77380-77447, December 10, 2010). SUMMARY: On December 10, 2010 (75 FR 77380-77447), DoD published a notice of approval of a personnel management...

  2. 76 FR 12507 - Science and Technology Reinvention Laboratory Personnel Management Demonstration Project...

    Science.gov (United States)

    2011-03-07

    ... customers; and 7. Workforce satisfaction with the personnel management system. An evaluation model was... personnel system under an appropriate demonstration project as defined in section 342(b) of Public Law 103... was deleted with the actual construct of pay pools to be further defined in the Demonstration Project...

  3. Common Market measures to promote the use of solar energy - The demonstration project

    Science.gov (United States)

    Kaut, W.

    A series of solar technical projects being conducted under the auspices of the Common Market is discussed. The history and legal foundations of this demonstration project, previous proposal requests and their results, and the experiences to date and present status of the project are assessed. Twenty-six projects proposals are being funded; the only German one concerns solar heating of swimming pools. The economic and administrative aspects of these projects are detailed. Problems of the project are discussed, including the allocation of funds between older and newer aspects and financial constraints.

  4. Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification. Revision 3, Part 2

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program.

  5. Commissioning Tests of the Ulchin LLW Vitrification Facility In Korea

    International Nuclear Information System (INIS)

    Kyung-Hwa, Yang; Sang-Woon, Shin; Chan-Kook, Moon

    2009-01-01

    Since 1994, Korea Hydro and Nuclear Power Co., Ltd. (KHNP) has, together with SGN in France and Hyundai ROTEM, investigated and developed a vitrification process using a Cold Crucible Induction Melter (CCIM) to treat low-and intermediate-level radioactive waste. A commercialization project was launched in 2002 as a governmental nuclear power technology development project. The installation of the first commercial plant, Ulchin Vitrification Facility (UVF), was completed in 2007 inside Ulchin nuclear power plants no. 5 and 6. Combustible dry active waste and low-level ion exchange resin will be treated in the UVF. The UVF has a waste feeding capacity of 20 kg/h and consists of waste pretreatment and feeding systems, a cold crucible induction melter (CCIM) system, an off-gas treatment system, a dust recycling system, as well as other systems. In order to assure that systems and equipments meet their design objectives and that the UVF complies with applicable regulations, equipment tests, system functional tests and inactive performance tests were conducted. Furthermore, a long-term inactive test was carried out for 202 hours to evaluate the overall performance and stability of the facility. During the test, about 1,700 kg of surrogate waste was vitrified and 302 kg of waste glass was poured into a glass mould. As the gaseous emission from the UVF was one of the key issues for the operational license and public acceptance, 25 hazardous gases and dusts were analyzed. The compressive strength of the waste glasses was also measured. Results showed that effluent concentrations of the off-gases and the quality of the waste glass met the regulatory limits with sufficient margins. Operation procedures of the UVF were revised based on experiences gained from the tests. By demonstrating satisfactory performance of the UVF, KHNP acquired an operational license in October, 2008 as an amendment to the operational license of the Ulchin NPPs. We are planning to conduct a simulated

  6. Vitrification testing of simulated high-level radioactive waste at Hanford

    International Nuclear Information System (INIS)

    Perez, J.M. Jr.; Nakaoka, R.R.

    1986-03-01

    The Hanford Waste Vitrification Plant may apply vitrification technology, being developed at Pacific Northwest Laboratory, to solidify selected Hanford waste streams prior to disposal in a federal repository. Based on the first stage of flowsheet development and laboratory testing, a reference working glass and two candidate simulated feed slurries were recommended for vitrification testing. Over 500 hours of melter testing were performed in 1985 during prototype vitrification experiments. Testing demonstrated that the slurry compositions had acceptable processing characteristics in a ceramic melter. A pre-made glass-former frit was determined to be preferred as the method of glass-former addition. Due to a high chromium content in the waste, spinal crystal formation and settling occurred in the glass tank. The nature and extent of off-gas effluents were consistent with past experiments processing slurries containing formic acid

  7. In situ vitrification applications to hazardous wastes

    International Nuclear Information System (INIS)

    Liikala, S.

    1989-01-01

    In Situ Vitrification is a new hazardous waste remediation alternative that should be considered for contaminated soil matrices. According to the authors the advantages of using ISV include: technology demonstrated at field scale; applicable to a wide variety of soils and contaminants; pyrolyzer organics and encapsulates inorganics; product durable over geologic time period; no threat of harm to the public from exposure; and applications available for barrier walls and structural support. The use of ISV on a large scale basis has thus far been limited to the nuclear industry but has tremendous potential for widespread applications to the hazardous waste field. With the ever changing regulations for the disposal of hazardous waste in landfills, and the increasing positive analytical data of ISV, the process will become a powerful source for on-site treatment and hazardous waste management needs in the very near future

  8. Hanford Waste Vitrification Plant Quality Assurance Program description for defense high-level waste form development and qualification

    International Nuclear Information System (INIS)

    Hand, R.L.

    1992-01-01

    This document describes the quality assurance (QA) program of the Hanford Waste Vitrification Plant (HWVP) Project. The purpose of the QA program is to control project activities in such a manner as to achieve the mission of the HWVP Project in a safe and reliable manner. A major aspect of the HWVP Project QA program is the control of activities that relate to high-level waste (HLW) form development and qualification. This document describes the program and planned actions the Westinghouse Hanford Company (Westinghouse Hanford) will implement to demonstrate and ensure that the HWVP Project meets the US Department of Energy (DOE) and ASME regulations. The actions for meeting the requirements of the Waste Acceptance Preliminary Specifications (WAPS) will be implemented under the HWVP product qualification program with the objective of ensuring that the HWVP and its processes comply with the WAPS established by the federal repository

  9. ARSENIC REMOVAL FROM DRINKING WATER BY ADSORPTIVE MEDIA. U.S. EPA DEMONSTRATION PROJECT AT SPRINGFIELD, OH. PROJECT SUMMARY

    Science.gov (United States)

    This document is a eight page summary of the final report on arsenic demonstration project at the Chateau Estates Mobile Home Park in Springfield, OH. The objectives of the project are to evaluate the effectiveness of AdEdge Technologies’ AD-33 media in removing arsenic to meet t...

  10. Vitrification for stability of scrap and residue

    Energy Technology Data Exchange (ETDEWEB)

    Forsberg, C.W. [Oak Ridge National Lab., TN (United States)

    1996-05-01

    A conference breakout discussion was held on the subject of vitrification for stabilization of plutonium scrap and residue. This was one of four such sessions held within the vitrification workshop for participants to discuss specific subjects in further detail. The questions and issues were defined by the participants.

  11. Final report for the Department of Energy funded cooperative agreement ''Electronic Research Demonstration Project'' [University electronic research administration demonstration project

    Energy Technology Data Exchange (ETDEWEB)

    Rodman, John

    1998-07-31

    This is the final report for the Department of Energy (DOE) funded cooperative agreement ''Electronic Research Demonstration Project (DE-FC02-92ER35180)'' for the period August 1994-July 1998. The goal of the project, referred to as NewERA, was to demonstrate the use of open standards for electronic commerce to support research administration, otherwise referred to as Electronic Research Administration (ERA). The NewERA demonstration project provided a means to test interagency standards developed within the Federal Grant Electronic Commerce Committee, a group comprised of federal granting agencies. The NewERA program was initiated by DOE. NewERA was comprised of three separate, but related, ERA activities in preaward administration, postaward administration, and secure Internet commerce. The goal of New ERA was to demonstrate an open standard implementation of ERA using electronic data interchange, e-mail and Internet transaction security between grant applicants and DOE, along with t h e other participating agencies.

  12. Slow and steady cell shrinkage reduces osmotic stress in bovine and murine oocyte and zygote vitrification.

    Science.gov (United States)

    Lai, D; Ding, J; Smith, G W; Smith, G D; Takayama, S

    2015-01-01

    osmotic stress resulting in better morphology, higher cell quality and improved developmental competence. This microfluidic procedure resulted in murine zygotes with a significantly smoother cell surface (P rate is complementary to the prevalent osmotic stress theory in cryobiology which focuses on a minimum cell volume at which the cells shrink. The auto-microfluidic protocol described here has immediate applications for improving animal and human oocyte, zygote and embryo cryopreservation. On a fundamental level, the clear demonstration that at the same minimum cell volume, cell shrinkage rate affects sublethal damage should be broadly useful for cryobiology. This project was funded by the National Institutes of Health and the University of Michigan Reproductive Sciences Program. The authors declare no conflicts of interest. © The Author 2014. Published by Oxford University Press on behalf of the European Society of Human Reproduction and Embryology. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  13. Independent engineering review of the Hanford Waste Vitrification System

    International Nuclear Information System (INIS)

    1991-10-01

    The Hanford Waste Vitrification Plant (HWVP) was initiated in June 1987. The HWVP is an essential element of the plan to end present interim storage practices for defense wastes and to provide for permanent disposal. The project start was justified, in part, on efficient technology and design information transfer from the prototype Defense Waste Processing Facility (DWPF). Development of other serial Hanford Waste Vitrification System (HWVS) elements, such as the waste retrieval system for the double-shell tanks (DSTs), and the pretreatment system to reduce the waste volume converted into glass, also was required to accomplish permanent waste disposal. In July 1991, at the time of this review, the HWVP was in the Title 2 design phase. The objective of this technical assessment is to determine whether the status of the technology development and engineering practice is sufficient to provide reasonable assurance that the HWVP and the balance of the HWVS system will operate in an efficient and cost-effective manner. The criteria used to facilitate a judgment of potential successful operation are: vitrification of high-level radioactive waste from specified DSTs on a reasonably continuous basis; and glass produced with physical and chemical properties formally acknowledge as being acceptable for disposal in a repository for high-level radioactive waste. The criteria were proposed specifically for the Independent Engineering Review to focus that assessment effort. They are not represented as the criteria by which the Department will judge the prudence of the Project. 78 refs., 10 figs., 12 tabs

  14. Independent engineering review of the Hanford Waste Vitrification System

    Energy Technology Data Exchange (ETDEWEB)

    1991-10-01

    The Hanford Waste Vitrification Plant (HWVP) was initiated in June 1987. The HWVP is an essential element of the plan to end present interim storage practices for defense wastes and to provide for permanent disposal. The project start was justified, in part, on efficient technology and design information transfer from the prototype Defense Waste Processing Facility (DWPF). Development of other serial Hanford Waste Vitrification System (HWVS) elements, such as the waste retrieval system for the double-shell tanks (DSTs), and the pretreatment system to reduce the waste volume converted into glass, also was required to accomplish permanent waste disposal. In July 1991, at the time of this review, the HWVP was in the Title 2 design phase. The objective of this technical assessment is to determine whether the status of the technology development and engineering practice is sufficient to provide reasonable assurance that the HWVP and the balance of the HWVS system will operate in an efficient and cost-effective manner. The criteria used to facilitate a judgment of potential successful operation are: vitrification of high-level radioactive waste from specified DSTs on a reasonably continuous basis; and glass produced with physical and chemical properties formally acknowledge as being acceptable for disposal in a repository for high-level radioactive waste. The criteria were proposed specifically for the Independent Engineering Review to focus that assessment effort. They are not represented as the criteria by which the Department will judge the prudence of the Project. 78 refs., 10 figs., 12 tabs.

  15. Waddenfonds Tidal Texel Demonstration project. BlueTEC Texel Tidal Project: Environmental measurement and performance analysis

    NARCIS (Netherlands)

    Ponsoni, L.; Nauw, J.J.; Smit, M.; Ober, S.; Nichols, C.; Kenkhuis, J.; Schmidt, C.; Buatois, A.; de Haas, P.

    2016-01-01

    In the context of the BlueTEC project, this report starts by introducing theBlueTEC tidal energy platform and reviewing the patterns of circulation of theMarsdiep inlet. The energy resource assessment and the site selection for theplatform's deployment are reported. This document analyses di?erent

  16. Highway for life demonstration project : LA 511 (70th Street). Research project capsule.

    Science.gov (United States)

    2013-06-01

    The Louisiana Department of Transportation and Development (LADOTD), : has been awarded a Highways for Life (HfL) grant to be used on the LA 511 : widening project in Caddo Parish. The LA 511 corridor is one of the busiest in the : Shreveport, Louisi...

  17. Learning through a portfolio of carbon capture and storage demonstration projects

    Science.gov (United States)

    Reiner, David M.

    2016-01-01

    Carbon dioxide capture and storage (CCS) technology is considered by many to be an essential route to meet climate mitigation targets in the power and industrial sectors. Deploying CCS technologies globally will first require a portfolio of large-scale demonstration projects. These first projects should assist learning by diversity, learning by replication, de-risking the technologies and developing viable business models. From 2005 to 2009, optimism about the pace of CCS rollout led to mutually independent efforts in the European Union, North America and Australia to assemble portfolios of projects. Since 2009, only a few of these many project proposals remain viable, but the initial rationales for demonstration have not been revisited in the face of changing circumstances. Here I argue that learning is now both more difficult and more important given the slow pace of deployment. Developing a more coordinated global portfolio will facilitate learning across projects and may determine whether CCS ever emerges from the demonstration phase.

  18. A Classroom Demonstration of Potential Biases in the Subjective Interpretation of Projective Tests.

    Science.gov (United States)

    Wiederman, Michael W.

    1999-01-01

    Suggests that instructors teaching psychological assessment can use a demonstration to illustrate potential biases when subjectively interpreting response to projective stimuli. Outlines the classroom procedure, notes styles of learning involved, and presents a summary of student evaluations. (DSK)

  19. 78 FR 33051 - Non-Rock Alternatives to Shoreline Protection Demonstration Project (LA-16) Iberia, Jefferson...

    Science.gov (United States)

    2013-06-03

    ... DEPARTMENT OF AGRICULTURE Natural Resources Conservation Service Non-Rock Alternatives to...-Rock Alternatives to Shoreline Protection Demonstration Project (LA-16), Iberia, Jefferson, and... and environmental limitations preclude the use of rock structures. The shoreline protection systems...

  20. 78 FR 60887 - Expressions of Interest (EOI) for Chemical Defense Demonstration Projects

    Science.gov (United States)

    2013-10-02

    ... CDP. DATES: Submit the completed and signed DHS Form 10088 (9/12), either electronically or in hard... demonstration project will result in, among other things: (a) A review of current community preparedness...

  1. 20 CFR 404.1599 - Work incentive experiments and rehabilitation demonstration projects in the disability program.

    Science.gov (United States)

    2010-04-01

    ... the advantages and disadvantages of altering certain limitations and conditions that apply to title II... years from the start of the experiment or demonstration project). [48 FR 7575, Feb. 23, 1983, as amended...

  2. Theme II Joint Work Plan -2017 Collaboration and Knowledge Sharing on Large-scale Demonstration Projects

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Xiaoliang [World Resources Inst. (WRI), Washington, DC (United States); Stauffer, Philip H. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-09-25

    This effort is designed to expedite learnings from existing and planned large demonstration projects and their associated research through effective knowledge sharing among participants in the US and China.

  3. Rubbertown Next Generation Emission Measurement Demonstration Project Provides Innovative Approaches to Protecting Air Quality

    Science.gov (United States)

    EPA and the Louisville Metro Air Pollution Control District (LMAPCD) are working together on a research project to demonstrate NGEM approaches near facilities in the Rubbertown industrial area of Louisville, KY.

  4. System acceptance test plan : Dallas Integrated Corridor Management (ICM) demonstration project.

    Science.gov (United States)

    2013-02-01

    The Dallas Area Rapid Transit (DART) is leading the US 75 Integrated Corridor Management (ICM) : Demonstration Project for the Dallas region. Coordinated corridor operations and management is : predicated on being able to share transportation informa...

  5. A summary of the environmental restoration program retrieval demonstration project at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    McQuary, J.

    1991-02-01

    This report provides a summary of the Environmental Restoration Program's Retrieval Demonstration Project at the Idaho National Engineering Laboratory. This project developed concepts for demonstrating facilities and equipment for the retrieval of buried transuranic mixed waste at the INEL. Included is a brief assessment of the viability, cost effectiveness, and safety of retrieval based on the developed concept. Changes made in Revision 1 reflect editorial changes only. 31 refs., 1 fig

  6. 75 FR 60091 - Science and Technology Reinvention Laboratory Personnel Management Demonstration Project...

    Science.gov (United States)

    2010-09-29

    ... DEPARTMENT OF DEFENSE Office of the Secretary Science and Technology Reinvention Laboratory Personnel Management Demonstration Project, Department of the Army, Army Research, Development and... project; correction. SUMMARY: On September 9, 2010 (75 FR 55199), DoD published a notice concerning the...

  7. 42 CFR 403.308 - State systems under demonstration projects-mandatory approval.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 2 2010-10-01 2010-10-01 false State systems under demonstration projects..., DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL PROVISIONS SPECIAL PROGRAMS AND PROJECTS Recognition of State... approval of a State system are met under § 403.304 (b)(1)-(10) and § 403.304(c), and, if appropriate § 403...

  8. Evaluating a "Second Life" Problem-Based Learning (PBL) Demonstrator Project: What Can We Learn?

    Science.gov (United States)

    Beaumont, Chris; Savin-Baden, Maggi; Conradi, Emily; Poulton, Terry

    2014-01-01

    This article reports the findings of a demonstrator project to evaluate how effectively Immersive Virtual Worlds (IVWs) could support problem-based learning. The project designed, created and evaluated eight scenarios within "Second Life" (SL) for undergraduate courses in health care management and paramedic training. Evaluation was…

  9. Commercial Ion Exchange Resin Vitrification in Borosilicate Glass

    International Nuclear Information System (INIS)

    Cicero-Herman, C.A.; Workman, P.; Poole, K.; Erich, D.; Harden, J.

    1998-05-01

    Bench-scale studies were performed to determine the feasibility of vitrification treatment of six resins representative of those used in the commercial nuclear industry. Each resin was successfully immobilized using the same proprietary borosilicate glass formulation. Waste loadings varied from 38 to 70 g of resin/100 g of glass produced depending on the particular resin, with volume reductions of 28 percent to 68 percent. The bench-scale results were used to perform a melter demonstration with one of the resins at the Clemson Environmental Technologies Laboratory (CETL). The resin used was a weakly acidic meth acrylic cation exchange resin. The vitrification process utilized represented a approximately 64 percent volume reduction. Glass characterization, radionuclide retention, offgas analyses, and system compatibility results will be discussed in this paper

  10. Closed system for bovine oocyte vitrification

    Directory of Open Access Journals (Sweden)

    Helena Ševelová

    2012-01-01

    Full Text Available The aim of our study was to develop a vitrification carrier for bovine oocyte cryopreservation. The carrier was to be cheap enough, elementary in its construction and meet contemporary requirements for a safe closed system. In a closed system, a cell is prevented from direct exposure to liquid nitrogen, thus minimizing the risk of cross-contamination. Furthermore, two questions regarding the proper vitrification technique were resolved: if it is necessary to partially denude the oocytes before the vitrification process or whether intact cumulus oocyte complexes should be frozen; and if it is more advantageous to preheat the vitrification solutions to female body temperature (39 °C or to keep them at room temperature. Our results show that it is better to partially denude the oocytes prior to vitrification because cryopreserved intact cumulus oocyte complexes often proved dark, non-homogeneous or fragmented cytoplasm after warming, with many of them having visibly widened perivitelline spaces or fractured zonae pellucidae as a result of extensive damage during vitrification. Consequently, intact cumulus oocyte complexes showed significantly lower numbers of cleavage stage embryos on Day 3 compared to partially denuded oocytes (7.4% and 26%, respectively. On the other hand, the survival rate and following development of fertilized oocytes in preheated vitrification solution were equal to results reached at room temperature conditions. In conclusion, results achieved with the newly developed carrier were comparable to previously published studies and therefore they could be recommended for common use.

  11. Inventory of demonstration and trail projects in sustainable energy and transport in Scandinavia

    DEFF Research Database (Denmark)

    Andersen, Per Dannemand; Cramer-Petersen, Claus Lundgaard; Harnes, Kristian N.

    This report documents the work of work package 2 of the InnoDemo research project funded by the Research Council of Norway. Partners in the project are The Nordic Institute for Studies in Innovation, Research and Education (NIFU) (project leader), DTU Management Engineering at Technical University...... of Denmark, and CIRCLE at Lund’s University. From a state-of-the-art study in the project’s work package 1, a set of characteristics have been specified to be collected in an inventory of demonstration projects and funding programmes. This data was collected in parallel in Denmark, Norway and Sweden...

  12. Learning to make technology work - a study of learning in technology demonstration projects

    DEFF Research Database (Denmark)

    Sutherland Olsen, Dorothy; Andersen, Per Dannemand

    2014-01-01

    Building working demonstrations of new technologies within sustainable energy and transport has become an important activity in the move towards a more energy efficient society. The work involved in building these demonstrations is usually organised in a project with a variety of different partic...

  13. Project A+ Elementary Technology Demonstration Schools 1990-91. The First Year.

    Science.gov (United States)

    Marable, Paula; Frazer, Linda

    Project A+ Elementary Technology Demonstration Schools is a program made possible through grants from IBM (International Business Machines Corporation) and Apple, Inc. The primary purpose of the program is to demonstrate the educational effectiveness of technology in accelerating the learning of low achieving at-risk students and enhancing the…

  14. In-situ vitrification: pilot-scale development

    International Nuclear Information System (INIS)

    Timmerman, C.L.; Brouns, R.A.; Buelt, J.L.; Oma, K.H.

    1983-01-01

    Pacific Northwest Laboratory (PNL) is developing in-situ vitrification (ISV) as an in-place stabilization technique for buried radioactive and hazardous chemical wastes. The process melts the wastes and surrounding soil to produce a durable glass and crystalline waste form. These in situ vitrification process development testing and product evaluation studies are being conducted for the U.S. Department of Energy. This report discusses the results of four ISV pilot-scale field tests simulating radioactive and hazardous waste site conditions. The primary objectives of the field tests were to: demonstrate process scale-up from engineering-scale laboratory tests; verify equipment performance of the power system, electrodes and off-gas system; characterize the behavior of simulated wastes in the vitrified soil; identify waste losses to the off-gas system; and evaluate waste form durability. Test results have been encouraging. Process scaleup has been successfully demonstrated, with equipment and electrode performance equally as successful. The off-gas system effectively contained any volatile or entrained hazardous species. Vitrified soil analysis also indicated effective containment and a homogeneous distribution of nonradioactive radionuclide and hazardous waste simulants due to convective mixing during vitrification. Waste form leaching studies revealed that the ISV product has a durability similar to Pyrex glass

  15. Pacific Northwest GridWise™ Testbed Demonstration Projects; Part I. Olympic Peninsula Project

    Energy Technology Data Exchange (ETDEWEB)

    Hammerstrom, Donald J.; Ambrosio, Ron; Carlon, Teresa A.; DeSteese, John G.; Horst, Gale R.; Kajfasz, Robert; Kiesling, Laura L.; Michie, Preston; Pratt, Robert G.; Yao, Mark; Brous, Jerry; Chassin, David P.; Guttromson, Ross T.; Jarvegren, Olof M.; Katipamula, Srinivas; Le, N. T.; Oliver, Terry V.; Thompson, Sandra E.

    2008-01-09

    This report describes the implementation and results of a field demonstration wherein residential electric water heaters and thermostats, commercial building space conditioning, municipal water pump loads, and several distributed generators were coordinated to manage constrained feeder electrical distribution through the two-way communication of load status and electric price signals. The field demonstration took place in Washington and Oregon and was paid for by the U.S. Department of Energy and several northwest utilities. Price is found to be an effective control signal for managing transmission or distribution congestion. Real-time signals at 5-minute intervals are shown to shift controlled load in time. The behaviors of customers and their responses under fixed, time-of-use, and real-time price contracts are compared. Peak loads are effectively reduced on the experimental feeder. A novel application of portfolio theory is applied to the selection of an optimal mix of customer contract types.

  16. Demonstration and Commercialization of the Sediment Ecosystem Assessment Protocol: Project ER-201130 Environmental Restoration Project

    Science.gov (United States)

    2017-01-01

    and publication of magazine articles and white papers. Several journal articles are also now in progress. The demonstrations have also provided...manufacturer’s guidelines 2. Program SEA Ring for 29 minutes “ON” and 1 minute “OFF” with a running period of 1 week. 3. Immerse in water 4. Turn...seconds “chamber flush interval” with a running period of 10 days . 3. Immerse in water. 4. Turn control module to “Run” (counterclockwise) to start

  17. Preliminary Hanford Waste Vitrification Plan Waste Form Qualification Plan

    International Nuclear Information System (INIS)

    Nelson, J.L.

    1987-09-01

    This Waste Form Qualification Plan describes the waste form qualification activities that will be followed during the design and operation of the Hanford Waste Vitrification Plant to ensure that the vitrified Hanford defense high-level wastes will meet the acceptance requirements of the candidate geologic repositories for nuclear waste. This plan is based on the defense waste processing facility requirements. The content of this plan is based on the assumption that the Hanford Waste Vitrification Plant high-level waste form will be disposed of in one of the geologic repository projects. Proposed legislation currently under consideration by Congress may change or delay the repository site selection process. The impacts of this change will be assessed as details of the new legislation become available. The Plan describes activities, schedules, and programmatic interfaces. The Waste Form Qualification Plan is updated regularly to incorporate Hanford Waste Vitrification Plant-specific waste acceptance requirements and to serve as a controlled baseline plan from which changes in related programs can be incorporated. 10 refs., 5 figs., 5 tabs

  18. Freihoelser Forst Local Training Area Demonstration Project: Prescription development and installation

    International Nuclear Information System (INIS)

    Hinchman, R.R.; Zellmer, S.D.; Brent, J.J.

    1989-04-01

    The Freiholser Forst Local Training Area (LTA) Rehabilitation Demonstration Project is part of the Integrated Training Area Management program being developed by the US Army Corps of Engineers' Construction Engineering Research Laboratory for the Seventh Army Training Command of the US Army in Europe. The rehabilitation demonstration project was begun in 1987 to develop and demonstrate rapid, cost-effective methods to stabilize the LTA's barren, eroding maneuver areas and make training conditions more realistic. The sandy, infertile, and acidic soils at the LTA are considered the major factor limiting rehabilitation efforts there. The project involves the evaluation of three procedures to revegetate the soils, each incorporating identical methods for preparing the seedbed and a single seed mixture consisting of adapted, native species but using different soil amendments. All three treatments have satisfactorily reestablished vegetation and controlled erosion on the demonstration plots at the LTA, but their costs have varied widely

  19. Vitrification pilot plant experiences at Fernald, Ohio

    International Nuclear Information System (INIS)

    Akgunduz, N.; Gimpel, R.F.; Paine, D.; Pierce, V.H.

    1997-01-01

    A one metric ton/day Vitrification Pilot Plant (VITPP) at Fernald, Ohio, simulated the vitrification of radium and radon bearing silo residues using representative non-radioactive surrogates containing high concentrations of lead, sulfates, and phosphates. The vitrification process was carried out at temperatures of 1,150 to 1,350 C. The VITPP processed glass for seven months, until a breach of the melter containment vessel suspended operations. More than 70,000 pounds of surrogate glass were produced by the VITPP. Experiences, lessons learned, and path forward will be presented

  20. Large-scale commercial applications of the in situ vitrification remediation technology

    International Nuclear Information System (INIS)

    Campbell, B.E.; Hansen, J.E.; McElroy, J.L.; Thompson, L.E.; Timmerman, C.L.

    1994-01-01

    The first large-scale commercial application of the innovative In Situ Vitrification (ISV) remediation technology was completed at the Parsons Chemical/ETM Enterprises Superfund site in Michigan State midyear 1994. This project involved treating 4,800 tons of pesticide and mercury-contaminated soil. The project also involved performance of the USEPA SITE Program demonstration test for the ISV technology. The Parsons project involved consolidation and staging of contaminated soil from widespread locations on and nearby the site. This paper presents a brief description of the ISV technology along with case-study type information on these two sites and the performance of the ISV technology on them. The paper also reviews other remediation projects where ISV has been identified as the/a preferred remedy, and where ISV is currently planned for use. These sites include soils contaminated with pesticides, dioxin, PCP, paint wastes, and a variety of heavy metals. This review of additional sites also includes a description of a planned radioactive mixed waste remediation project in Australia that contains large amounts of plutonium, uranium, lead, beryllium, and metallic and other debris buried in limestone and dolomitic soil burial pits. Initial test work has been completed on this application, and preparations are now underway for pilot testing in Australia. This project will demonstrate the applicability of the ISV technology to the challenging application of buried mixed wastes

  1. Task 19 - Sampling, Analysis, and Vitrification Study for Thermochem's Steam Reformer Treatment Technology

    International Nuclear Information System (INIS)

    Lillemoen, C.M.; McCollor, D.P.; Qi Sun

    1998-01-01

    The overall objective of the project is to provide support to Thermochem, Inc., in the demonstration of the steam reformer treatment technology to treat LLMW. Within this program, specific objectives include the following: (1) Analyze cerium, chlorine, and fluorine concentrations in samples from the pilot-scale steam reformer tests to determine partitioning of these elements, mass balances, and changes in concentration with time. (2) Perform experimental characterization of temperature--viscosity profiles to aid in determining vitrification viability for long-term stabilization. Additionally, calculations of viscosity will be performed for several blend combinations to complement the experimentally determined values. (3) Conduct leachability tests on the vitrified slags to aid in determining if product leachability falls within EPA guidelines and to assess the suitability of the vitrified material for long-term disposal

  2. Hanford Waste Vitrification Plant quality assurance program description: Overview and applications

    International Nuclear Information System (INIS)

    Caplinger, W.H.

    1990-12-01

    This document describes the Hanford Waste Vitrification Plant Project Quality Assurance Program. This program is being implemented to ensure the acceptability of high-level radioactive canistered waste forms produced by the Hanford Waste Vitrification Plant for disposal in a licensed federal repository. The Hanford Waste Vitrification Plant Quality Assurance Program is comprised of this Quality Assurance Program Description as well as the associated contractors' quality assurance programs. The objective of this Quality Assurance Program Description is to provide the Hanford Waste Vitrification Plant Project participants with guidance and direction for program implementation while satisfying the US Department of Energy Office of Civilian Radioactive Waste Management needs in repository licensing activities with regard to canistered waste forms. To accomplish this objective, this description will be prepared in three parts: Part 1 - Overview and applications document; Part 2 - Development and qualification of the canistered waste form; Part 3 - Production of canistered waste forms. Part 1 describes the background, strategy, application, and content of the Hanford Waste Vitrification Plant Quality Assurance Program. This Quality Assurance Program Description, when complete, is designed to provide a level of confidence in the integrity of the canistered waste forms. 8 refs

  3. Reducing Plug Loads in Office Spaces: Hawaii and Guam Energy Improvement Technology Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Sheppy, M. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Metzger, I. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Cutler, D. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Holland, G. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Hanada, A. [Naval Facilities Engineering Command, Washington, DC (United States)

    2014-01-01

    As part of its overall strategy to meet its energy goals, the Naval Facilities Engineering Command (NAVFAC) partnered with the Department of Energy's National Renewable Energy Laboratory (NREL) to rapidly demonstrate and deploy cost-effective renewable energy and energy efficiency technologies. This project was one of several demonstrations of new or underutilized commercial energy technologies. The common goal was to demonstrate and measure the performance and economic benefit of the system while monitoring any ancillary impacts to related standards of service and operation and maintenance (O&M) practices. In short, demonstrations at naval facilities simultaneously evaluate the benefits and compatibility of the technology with the U.S. Department of Defense (DOD) mission, and with NAVFAC's design, construction, operations, and maintenance practices, in particular. This project demonstrated the performance of commercially available advanced power strips (APSs) for plug load energy reductions in building A4 at Joint Base Pearl Harbor-Hickam (JBPHH), Hawaii.

  4. RIMAP demonstration project. Pat. 1: Risk based life management of piping system in power plant Heilbronn

    International Nuclear Information System (INIS)

    Bareiss, J.; Puck, P.; Matschecko, B.; Jovanovic, A.; Balos, D.; Perunicic

    2003-01-01

    In the framework of EU project RIMAP [1] a new European Guideline for optimized risk based maintenance and inspection planning of industrial plants (RBLM - Risk Based Life Management) is being developed. The RIMAP project consists of the three clustered projects: development (RTD), demonstration (DEMO) and thematic network (TN). Current work and future, planned work in RIMAP demonstration project on applications of the RIMAP methodology in power plants are presented briefly in the first part of the paper. Also presented in the paper are the results of a preliminary analysis of piping system in power plant Heilbronn using the concept of risk-based monitoring as part of overall concept of risk-based life management. Shortly the following issues are discussed in the paper: identification of critical components, application of a multilevel risk analysis (..from ''screening'' to ''detailed analysis''), determination of PoF - Probability of Failure, determination of COF - Consequence of Failure and optimation of inspection and maintenance plan. (orig.)

  5. Chemical engineering problems of radioactive waste fixation by vitrification

    International Nuclear Information System (INIS)

    Taylor, R.F.

    1985-01-01

    Basic features are reviewed of the chemical engineering problems faced in the vitrification of the high-level radioactive liquid wastes resulting from the reprocessing of nuclear fuel. After an outline of glass solution properties and formation kinetics the constituent elements of the vitrification route are examined in turn: waste feed evaporation and denitration, calcination, offgas treatment, and finally melting and product quality. Plant and experimental data for each stage are discussed with comparison between process routes and with reference to the underlying principles. Attention is drawn to the future need for higher trapping efficiencies and for dealing with a wider range of species in offgas treatments as higher burnup fuels are processed after shorter cooling times from reactor. Two areas of present study where deeper insight into underlying process mechanics is needed are, firstly, the association of waste material with glass formers in the wet or sinter stages and secondly their incorporation and mixing reaction in the melt. Fuller understanding here would bring direct benefit to process performance and handling. The problems discussed are not of a nature to jeopardize the vitrification routes but if product quality does come to rely heavily on process control then demonstrable confidence in the behaviour of the central physico-chemical interactions is indispensable. (author)

  6. Stabilization of contaminated soils by in situ vitrification

    International Nuclear Information System (INIS)

    Timmerman, C.L.

    1984-01-01

    In Situ Vitrification is an emerging technology developed by Pacific Northwest Laboratory for potential in-place immobilization of radioactive wastes. The contaminated soil is stabilized and converted to an inert glass form. This conversion is accomplished by inserting electrodes in the soil and establishing an electric current between the electrodes. The electrical energy causes a joule heating effect that melts the soil during processing. Any contaminants released from the melt are collected and routed to an off-gas treatment system. A stable and durable glass block is produced which chemically and physically encapsulates any residual waste components. In situ vitrification has been developed for the potential application to radioactive wastes, specifically, contaminated soil sites; however, it could possibly be applied to hazardous chemical and buried munitions waste sites. The technology has been developed and demonstrated to date through a series of 21 engineering-scale tests [producing 50 to 1000 kg (100 to 2000 lb) blocks] and seven pilot-scale tests [producing 9000 kg (20,000 lb) blocks], the most recent of which illustrated treatment of actual radioactively contaminated soil. Testing with some organic materials has shown relatively complete thermal destruction and incineration. Further experiments have documented the insensitivity of in situ vitrification to soil characteristics such as fusion temperature, specific heat, thermal conductivity, electrical resistivity, and moisture content. Soil inclusions such as metals, cements, ceramics, and combustibles normally present only minor process limitations. Costs for hazardous waste applications are estimated to be less than $175/m 3 ($5.00/ft 3 ) of material vitrified. For many applications, in situ vitrification can provide a cost-effective alternative to other disposal options. 13 references, 4 figures, 1 table

  7. Executive summaries of reports leading to the construction of the Baca Geothermal Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Sherwood, P.B.; Newman, K.L.; Westermeier, J.F.; Giroux, H.D.; Lowe, G.D.; Nienberg, M.W.

    1980-05-01

    Executive summaries have been written for 61 reports and compilations of data which, in part, have led to the construction of the Baca 50 MW Geothermal Demonstration Project (GDP). The reports and data include environmental research, reservoir and feasibility studies, the project proposal to DOE and the Final Environmental Impact Statement. These executive summaries are intended to give the reader a general overview of each report prior to requesting the report from the GDP Data Manager.

  8. Executive summaries of reports leading to the construction of the Baca Geothermal Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Sherwood, P.B.; Newman, K.L.; Westermeier, J.F.; Giroux, H.D.; Lowe, G.D.; Nienberg, M.W.

    1980-05-01

    Executive summaries have been written for 61 reports and compilations of data which in part, have led to the construction of the Baca 50 MW Geothermal Demonstration Project (GDP). The reports and data include environmental research, reservoir and feasibility studies, the project proposal to DOE and the Final Environmental Impact Statement. These executive summaries are intended to give the reader a general overview of each report prior to requesting the report from the GDP Data Manager.

  9. TECHNICAL ASSESSMENT OF BULK VITRIFICATION PROCESS/ PRODUCT FOR TANK WASTE TREATMENT AT THE DEPARTMENT OF ENERGY HANFORD SITE

    International Nuclear Information System (INIS)

    SCHAUS, P.S.

    2006-01-01

    At the U.S. Department of Energy (DOE) Hanford Site, the Waste Treatment Plant (WTP) is being constructed to immobilize both high-level waste (IUW) for disposal in a national repository and low-activity waste (LAW) for onsite, near-surface disposal. The schedule-controlling step for the WTP Project is vitrification of the large volume of LAW, current capacity of the WTP (as planned) would require 50 years to treat the Hanford tank waste, if the entire LAW volume were to be processed through the WTP. To reduce the time and cost for treatment of Hanford Tank Waste, and as required by the Tank Waste Remediation System Environmental Impact Statement Record of Decision and the Hanford Federal Facility Consent Agreement (Tn-Party Agreement), DOE plans to supplement the LAW treatment capacity of the WTP. Since 2002, DOE, in cooperation with the Environmental Protection Agency and State of Washington Department of Ecology has been evaluating technologies that could provide safe and effective supplemental treatment of LAW. Current efforts at Hanford are intended to provide additional information to aid a joint agency decision on which technology will be used to supplement the WTP. A Research, Development and Demonstration permit has been issued by the State of Washington to build and (for a limited time) operate a Demonstration Bulk Vitrification System (DBVS) facility to provide information for the decision on a supplemental treatment technology for up to 50% of the LAW. In the Bulk Vitrification (BV) process, LAW, soil, and glass-forming chemicals are mixed, dried, and placed in a refractory-lined box, Electric current, supplied through two graphite electrodes in the box, melts the waste feed, producing a durable glass waste-form. Although recent modifications to the process have resulted in significant improvements, there are continuing technical concerns

  10. TECHNICAL ASSESSMENT OF BULK VITRIFICATION PROCESS & PRODUCT FOR TANK WASTE TREATMENT AT THE DEPARTMENT OF ENERGY HANFORD SITE

    Energy Technology Data Exchange (ETDEWEB)

    SCHAUS, P.S.

    2006-07-21

    At the U.S. Department of Energy (DOE) Hanford Site, the Waste Treatment Plant (WTP) is being constructed to immobilize both high-level waste (IUW) for disposal in a national repository and low-activity waste (LAW) for onsite, near-surface disposal. The schedule-controlling step for the WTP Project is vitrification of the large volume of LAW, current capacity of the WTP (as planned) would require 50 years to treat the Hanford tank waste, if the entire LAW volume were to be processed through the WTP. To reduce the time and cost for treatment of Hanford Tank Waste, and as required by the Tank Waste Remediation System Environmental Impact Statement Record of Decision and the Hanford Federal Facility Consent Agreement (Tn-Party Agreement), DOE plans to supplement the LAW treatment capacity of the WTP. Since 2002, DOE, in cooperation with the Environmental Protection Agency and State of Washington Department of Ecology has been evaluating technologies that could provide safe and effective supplemental treatment of LAW. Current efforts at Hanford are intended to provide additional information to aid a joint agency decision on which technology will be used to supplement the WTP. A Research, Development and Demonstration permit has been issued by the State of Washington to build and (for a limited time) operate a Demonstration Bulk Vitrification System (DBVS) facility to provide information for the decision on a supplemental treatment technology for up to 50% of the LAW. In the Bulk Vitrification (BV) process, LAW, soil, and glass-forming chemicals are mixed, dried, and placed in a refractory-lined box, Electric current, supplied through two graphite electrodes in the box, melts the waste feed, producing a durable glass waste-form. Although recent modifications to the process have resulted in significant improvements, there are continuing technical concerns.

  11. Vitrification processes for fission product solutions

    International Nuclear Information System (INIS)

    Bonniaud, R.; Jouan, A.; Moncouyoux, J.P.; Sombret, C.

    1982-10-01

    The different processes for fission product vitrification in the world are reviewed. Continuous or discontinuous processes, induction or arc heating, in can melting or casting, tests with radioactive or simulated wastes and industrial realizations are described [fr

  12. Hanford waste vitrification systems risk assessment

    International Nuclear Information System (INIS)

    Miller, W.C.; Hamilton, D.W.; Holton, L.K.; Bailey, J.W.

    1991-09-01

    A systematic Risk Assessment was performed to identify the technical, regulatory, and programmatic uncertainties and to quantify the risks to the Hanford Site double-shell tank waste vitrification program baseline (as defined in December 1990). Mitigating strategies to reduce the overall program risk were proposed. All major program elements were evaluated, including double-shell tank waste characterization, Tank Farms, retrieval, pretreatment, vitrification, and grouting. Computer-based techniques were used to quantify risks to proceeding with construction of the Hanford Waste Vitrification Plant on the present baseline schedule. Risks to the potential vitrification of single-shell tank wastes and cesium and strontium capsules were also assessed. 62 refs., 38 figs., 26 tabs

  13. Large-scale decontamination and decommissioning technology demonstration project at a former uranium metal production facility

    International Nuclear Information System (INIS)

    Martineit, R.A.; Borgman, T.D.; Peters, M.S.; Stebbins, L.L.

    1997-01-01

    The Department of Energy's (DOE) Office of Science and Technology Decontamination and Decommissioning (D ampersand D) Focus Area, led by the Federal Energy Technology Center, has been charged with improving upon baseline D ampersand D technologies with the goal of demonstrating and validating more cost-effective and safer technologies to characterize, deactivate, survey, decontaminate, dismantle, and dispose of surplus structures, buildings, and their contents at DOE sites. The D ampersand D Focus Area's approach to verifying the benefits of the improved D ampersand D technologies is to use them in large-scale technology demonstration (LSTD) projects at several DOE sites. The Fernald Environmental Management Project (FEMP) was selected to host one of the first three LSTD's awarded by the D ampersand D Focus Area. The FEMP is a DOE facility near Cincinnati, Ohio, that was formerly engaged in the production of high quality uranium metal. The FEMP is a Superfund site which has completed its RUFS process and is currently undergoing environmental restoration. With the FEMP's selection to host an LSTD, the FEMP was immediately faced with some challenges. The primary challenge was that this LSTD was to be integrated into the FEMP's Plant 1 D ampersand D Project which was an ongoing D ampersand D Project for which a firm fixed price contract had been issued to the D ampersand D Contractor. Thus, interferences with the baseline D ampersand D project could have significant financial implications. Other challenges include defining and selecting meaningful technology demonstrations, finding/selecting technology providers, and integrating the technology into the baseline D ampersand D project. To date, twelve technologies have been selected, and six have been demonstrated. The technology demonstrations have yielded a high proportion of open-quotes winners.close quotes All demonstrated, technologies will be evaluated for incorporation into the FEMP's baseline D ampersand D

  14. Stakeholder views on financing carbon capture and storage demonstration projects in China.

    Science.gov (United States)

    Reiner, David; Liang, Xi

    2012-01-17

    Chinese stakeholders (131) from 68 key institutions in 27 provinces were consulted in spring 2009 in an online survey of their perceptions of the barriers and opportunities in financing large-scale carbon dioxide capture and storage (CCS) demonstration projects in China. The online survey was supplemented by 31 follow-up face-to-face interviews. The National Development and Reform Commission (NDRC) was widely perceived as the most important institution in authorizing the first commercial-scale CCS demonstration project and authorization was viewed as more similar to that for a power project than a chemicals project. There were disagreements, however, on the appropriate size for a demonstration plant, the type of capture, and the type of storage. Most stakeholders believed that the international image of the Chinese Government could benefit from demonstrating commercial CCS and that such a project could also create advantages for Chinese companies investing in CCS technologies. In more detailed interviews with 16 financial officials, we found striking disagreements over the perceived risks of demonstrating CCS. The rate of return seen as appropriate for financing demonstration projects was split between stakeholders from development banks (who supported a rate of 5-8%) and those from commercial banks (12-20%). The divergence on rate alone could result in as much as a 40% difference in the cost of CO(2) abatement and 56% higher levelized cost of electricity based on a hypothetical case study of a typical 600-MW new build ultrasupercritical pulverized coal-fired (USCPC) power plant. To finance the extra operational costs, there were sharp divisions over which institutions should bear the brunt of financing although, overall, more than half of the support was expected to come from foreign and Chinese governments.

  15. Radioactive waste vitrification: A review

    International Nuclear Information System (INIS)

    Cole, L.L.; Fields, D.E.

    1989-08-01

    The research and development of an immobilization process for the containment of nuclear high-level liquid waste has been underway for well-over the past four decades. The method that has become the state-of-the-art is the liquid-fed ceramic melter process which converts a mixture of high-level liquid waste and glass forming frit to a borosilicate glass product. This report gives a chronological review of the various vitrification processes starting with the very first reported process in 1960. Information on the early methods of frit selection as well as information on the currently computerized method are presented. The importance of all these parameters is discussed with regard to product durability. 26 refs., 8 figs., 1 tab

  16. The Fort McMurray Demonstration Project in Social Marketing: theory, design, and evaluation.

    Science.gov (United States)

    Guidotti, T L; Ford, L; Wheeler, M

    2000-02-01

    The Fort McMurray Demonstration Project in Social Marketing is a multifaceted program that applies the techniques of social marketing to health and safety. This paper describes the origins of the project and the principles on which it was based. VENUE: Fort McMurray, in the province of Alberta, Canada, was selected because the community had several community initiatives already underway and the project had the opportunity to demonstrate "value added." The project is distinguished from others by a model that attempts to achieve mutually reinforcing effects from social marketing in the community as a whole and from workplace safety promotion in particular. Specific interventions sponsored by the project include a media campaign on cable television, public activities in local schools, a community safety audit, and media appearance by a mascot that provides visual identity to the project, a dinosaur named "Safetysaurus." The project integrated its activities with other community initiatives. The evaluation component emphasizes outcome measures. A final evaluation based on injury rates and attitudinal surveys is underway. Baseline data from the first round of surveys have been compiled and published. In 1995, Fort McMurray became the first city in North America to be given membership in the World Health Organization's Safe Community Network.

  17. Vitrification and xenografting of human ovarian tissue.

    Science.gov (United States)

    Amorim, Christiani Andrade; Dolmans, Marie-Madeleine; David, Anu; Jaeger, Jonathan; Vanacker, Julie; Camboni, Alessandra; Donnez, Jacques; Van Langendonckt, Anne

    2012-11-01

    To assess the efficiency of two vitrification protocols to cryopreserve human preantral follicles with the use of a xenografting model. Pilot study. Gynecology research unit in a university hospital. Ovarian biopsies were obtained from seven women aged 30-41 years. Ovarian tissue fragments were subjected to one of three cryopreservation protocols (slow freezing, vitrification protocol 1, and vitrification protocol 2) and xenografted for 1 week to nude mice. The number of morphologically normal follicles after cryopreservation and grafting and fibrotic surface area were determined by histologic analysis. Apoptosis was assessed by the TUNEL method. Morphometric analysis of TUNEL-positive surface area also was performed. Follicle proliferation was evaluated by immunohistochemistry. After xenografting, a difference was observed between the cryopreservation procedures applied. According to TUNEL analysis, both vitrification protocols showed better preservation of preantral follicles than the conventional freezing method. Moreover, histologic evaluation showed a significantly higher proportion of primordial follicles in vitrified (protocol 2)-warmed ovarian tissue than in frozen-thawed tissue. The proportion of growing follicles and fibrotic surface area was similar in all groups. Vitrification procedures appeared to preserve not only the morphology and survival of preantral follicles after 1 week of xenografting, but also their ability to resume folliculogenesis. In addition, vitrification protocol 2 had a positive impact on the quiescent state of primordial follicles after xenografting. Copyright © 2012 American Society for Reproductive Medicine. Published by Elsevier Inc. All rights reserved.

  18. Environmental assessment for the treatment of Class A low-level radioactive waste and mixed low-level waste generated by the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    1995-11-01

    The U.S. Department of Energy (DOE) is currently evaluating low-level radioactive waste management alternatives at the West Valley Demonstration Project (WVDP) located on the Western New York Nuclear Service Center (WNYNSC) near West Valley, New York. The WVDP's mission is to vitrify high-level radioactive waste resulting from commercial fuel reprocessing operations that took place at the WNYNSC from 1966 to 1972. During the process of high-level waste vitrification, low-level radioactive waste (LLW) and mixed low-level waste (MILLW) will result and must be properly managed. It is estimated that the WVDP's LLW storage facilities will be filled to capacity in 1996. In order to provide sufficient safe storage of LLW until disposal options become available and partially fulfill requirements under the Federal Facilities Compliance Act (FFCA), the DOE is proposing to use U.S. Nuclear Regulatory Commission-licensed and permitted commercial facilities in Oak Ridge, Tennessee; Clive, Utah; and Houston, Texas to treat (volume-reduce) a limited amount of Class A LLW and MLLW generated from the WVDP. Alternatives for ultimate disposal of the West Valley LLW are currently being evaluated in an environmental impact statement. This proposed action is for a limited quantity of waste, over a limited period of time, and for treatment only; this proposal does not include disposal. The proposed action consists of sorting, repacking, and loading waste at the WVDP; transporting the waste for commercial treatment; and returning the residual waste to the WVDP for interim storage. For the purposes of this assessment, environmental impacts were quantified for a five-year operating period (1996 - 2001). Alternatives to the proposed action include no action, construction of additional on-site storage facilities, construction of a treatment facility at the WVDP comparable to commercial treatment, and off-site disposal at a commercial or DOE facility

  19. Environmental monitoring for the DOE coolside and LIMB demonstration extension projects

    Energy Technology Data Exchange (ETDEWEB)

    White, T.; Contos, L.; Adams, L. (Radian Corp., Research Triangle Park, NC (United States). Progress Center)

    1992-02-01

    The purpose of this document is to present environmental monitoring data collected during the US DOE Limestone Injection Multistage Burner (LIMB) Demonstration Project Extension. The objective of the LIMB program is to demonstrate the sulfur dioxide (SO{sub 2}) and nitrogen oxide (NO{sub x}) emission reduction capabilities of the LIMB system. The LIMB system is a retrofit technology to be used for existing coal-fired boilers equipped with electrostatic precipitators. (VC)

  20. Milliken Clean Coal Technology Demonstration Project. Environmental monitoring report, July--September 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-05-01

    New York State Electric and Gas Corporation (NYSEG) has installed and is presently operating a high-efficiency flue gas desulfurization (FGD) system to demonstrate innovative emissions control technology and comply with the Clean Air Act Amendments of 1990. The host facility for this demonstration project is NYSEG`s Milliken Station, in the Town of Lansing, New York. The primary objective of this project is to demonstrate a retrofit of energy-efficient SO{sub 2} and NO{sub x} control systems with minimal impact on overall plant efficiency. The demonstration project has added a forced oxidation, formic acid-enhanced wet limestone FGD system, which is expected to reduce SO{sub 2} emissions by at least 90 percent. NYSEG also made combustion modifications to each boiler and plans to demonstrate selective non-catalytic reduction (SNCR) technology on unit 1, which will reduce NO{sub x} emissions. Goals of the proposed demonstration include up to 98 percent SO{sub 2} removal efficiency while burning high-sulfur coal, 30 percent NO{sub x} reductions through combustion modifications, additional NO{sub x} reductions using SNCR technology, production of marketable commercial-grade gypsum and calcium chloride by-products to minimize solid waste disposal, and zero wastewater discharge.

  1. Pacific Northwest Smart Grid Demonstration Project Technology Performance Report Volume 1: Technology Performance

    Energy Technology Data Exchange (ETDEWEB)

    Melton, Ron [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-06-01

    The Pacific Northwest Smart Grid Demonstration (PNWSGD), a $179 million project that was co-funded by the U.S. Department of Energy (DOE) in late 2009, was one of the largest and most comprehensive demonstrations of electricity grid modernization ever completed. The project was one of 16 regional smart grid demonstrations funded by the American Recovery and Reinvestment Act. It was the only demonstration that included multiple states and cooperation from multiple electric utilities, including rural electric co-ops, investor-owned, municipal, and other public utilities. No fewer than 55 unique instantiations of distinct smart grid systems were demonstrated at the projects’ sites. The local objectives for these systems included improved reliability, energy conservation, improved efficiency, and demand responsiveness. The demonstration developed and deployed an innovative transactive system, unique in the world, that coordinated many of the project’s distributed energy resources and demand-responsive components. With the transactive system, additional regional objectives were also addressed, including the mitigation of renewable energy intermittency and the flattening of system load. Using the transactive system, the project coordinated a regional response across the 11 utilities. This region-wide connection from the transmission system down to individual premises equipment was one of the major successes of the project. The project showed that this can be done and assets at the end points can respond dynamically on a wide scale. In principle, a transactive system of this type might eventually help coordinate electricity supply, transmission, distribution, and end uses by distributing mostly automated control responsibilities among the many distributed smart grid domain members and their smart devices.

  2. Rationale, Design, and Methods for Process Evaluation in the Childhood Obesity Research Demonstration Project.

    Science.gov (United States)

    Joseph, Sitara; Stevens, Andria M; Ledoux, Tracey; O'Connor, Teresia M; O'Connor, Daniel P; Thompson, Debbe

    2015-01-01

    The cross-site process evaluation plan for the Childhood Obesity Research Demonstration (CORD) project is described here. The CORD project comprises 3 unique demonstration projects designed to integrate multi-level, multi-setting health care and public health interventions over a 4-year funding period. Three different communities in California, Massachusetts, and Texas. All CORD demonstration projects targeted 2-12-year-old children whose families are eligible for benefits under Title XXI (CHIP) or Title XIX (Medicaid). The CORD projects were developed independently and consisted of evidence-based interventions that aim to prevent childhood obesity. The interventions promote healthy behaviors in children by applying strategies in 4 key settings (primary care clinics, early care and education centers, public schools, and community institutions). The CORD process evaluation outlined 3 main outcome measures: reach, dose, and fidelity, on 2 levels (researcher to provider, and provider to participant). The plan described here provides insight into the complex nature of process evaluation for consortia of independently designed multi-level, multi-setting intervention studies. The process evaluation results will provide contextual information about intervention implementation and delivery with which to interpret other aspects of the program. Copyright © 2015 Society for Nutrition Education and Behavior. All rights reserved.

  3. Americium-curium vitrification process development

    International Nuclear Information System (INIS)

    Fellinger, A.P.; Baich, M.A.; Hardy, B.J

    1999-01-01

    The successful demonstration of sequentially drying, calcining and vitrifying an oxalate slurry in the Drain Tube Test Stand (DTTS) vessel provided the process basis for testing on a larger scale in a cylindrical induction heated melter. A single processing issue, that of batch volume expansion, was encountered during the initial stage of testing. The increase in batch volume centered on a sintered frit cap and high temperature bubble formation. The formation of a sintered frit cap expansion was eliminated with the use of cullet. Volume expansions due to high temperature bubble formation (oxygen liberation from cerium reduction) were mitigated in the DTTS melter vessel through a vessel temperature profile that effectively separated the softening point of the glass cullet and the evolving oxygen from cerium reduction. An increased processing temperature of 1,470 C and a two hour hold time to find any remaining bubbles successfully reduced bubbles in the poured glass to an acceptable level. The success of the preliminary process demonstrations provided a workable process basis that was directly applicable to the newly installed Cylindrical Induction Melter (CIM) system, making the batch flowsheet the preferred option for vitrification of the americium-curium surrogate feed stream

  4. A Demonstration Project of Speech Training for the Preschool Cleft Palate Child. Final Report.

    Science.gov (United States)

    Harrison, Robert J.

    To ascertain the efficacy of a program of language and speech stimulation for the preschool cleft palate child, a research and demonstration project was conducted using 137 subjects (ages 18 to 72 months) with defects involving the soft palate. Their language and speech skills were matched with those of a noncleft peer group revealing that the…

  5. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2007

    Energy Technology Data Exchange (ETDEWEB)

    West Valley Environmental Services LLC (WVES) and URS - Washington Division

    2008-12-17

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2007. The report summarizes the calendar year (CY) 2007 environmental protection program at the WVDP. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment.

  6. Environmental monitoring for the DOE coolside and LIMB demonstration extension projects

    International Nuclear Information System (INIS)

    White, T.; Contos, L.

    1991-09-01

    The purpose of this document is to present environmental monitoring data collected during the US Department of Energy Limestone Injection Multistage Burner (DOE LIMB) Demonstration Project Extension at the Ohio Edison Edgewater Generating Station in Lorain, Ohio. These data were collected by implementing the Environmental Monitoring Plan (EMP) for the DOE LIMB Demonstration Project Extension, dated August 1988. This document is the fifth EMP status report to be published and presents the data generated during November and December 1990, and January 1991. These reports review a three or four month period and have been published since the project's start in October 1989. The DOE project is an extension of the US Environmental Protection Agency's (EPA) original LIMB Demonstration. The program is operated under DOE's Clean Coal Technology Program of ''emerging clean coal technologies'' under the categories of ''in boiler control of oxides of sulfur and nitrogen'' as well as ''post-combustion clean-up.'' The objective of the LIMB program is to demonstrate the sulfur dioxide (SO 2 ) and nitrogen oxide (NO x ) emission reduction capabilities of the LIMB system. The LIMB system is a retrofit technology to be used for existing coal-fired boilers equipped with electrostatic precipitators (ESPs). 5 figs., 12 tabs

  7. 78 FR 57623 - TRICARE Over-the-Counter Drug Demonstration Project

    Science.gov (United States)

    2013-09-19

    ... B One-Step (levonorgestrel) emergency contraceptive as an over-the-counter product ``for all women...-Counter Plan B One-Step Emergency Contraceptive (levonorgestrel). (2) OTC availability of Plan B One-Step Emergency Contraceptive (levonorgestrel) through the demonstration project will be at retail dispensing...

  8. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2006

    International Nuclear Information System (INIS)

    2007-01-01

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2006. The report summarizes calendar year (CY) 2006 environmental monitoring data so as to describe the performance of the WVDP's environmental management system (EMS), confirm compliance with standards and regulations, and highlight important programs that protect public health and safety and the environment

  9. 75 FR 55109 - Science and Technology Reinvention Laboratory Personnel Management Demonstration Project...

    Science.gov (United States)

    2010-09-09

    .... Satisfaction of customers; and 7. Workforce satisfaction with the personnel management system. An evaluation... personnel system under an appropriate demonstration project as defined in section 342(b) of Public Law 103... for the TARDEC mission, adjust the workforce for change, and improve workforce satisfaction. The...

  10. Characteristics of Young Children Exposed to Violence: The Safe Start Demonstration Project

    Science.gov (United States)

    Kaufman, Joy S.; Ortega, Sandra; Schewe, Paul A.; Kracke, Kristen

    2011-01-01

    The Safe Start demonstration projects, funded by the Office of Juvenile Justice and Delinquency Prevention (OJJDP) under the first phase of the Safe Start initiative, are primarily designed to influence change at the systems or macrolevels to reduce the incidence of and impact of exposure to violence for children aged birth to 6 years; direct…

  11. A demonstration project to test ecological restoration of a pinyon-juniper ecosystem

    Science.gov (United States)

    David W. Huffman; Michael T. Stoddard; Peter Z. Fule; W. Wallace Covington; H. B. Smith

    2008-01-01

    To test an approach for restoring historical stand densities and increasing plant species diversity of a pinyon-juniper ecosystem, we implemented a demonstration project at two sites (CR and GP) on the Grand Canyon-Parashant National Monument in northern Arizona. Historical records indicated that livestock grazing was intensive on the sites beginning in the late 1800s...

  12. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2007

    International Nuclear Information System (INIS)

    2008-01-01

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2007. The report summarizes the calendar year (CY) 2007 environmental protection program at the WVDP. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment

  13. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2005

    International Nuclear Information System (INIS)

    West Valley Nuclear Services Company WVNSCO and URS Group, Inc.

    2006-01-01

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2005. The report summarizes calendar year (CY) 2005 environmental monitoring data so as to describe the performance of the WVDP's environmental management system (EMS), confirm compliance with standards and regulations, and highlight important programs

  14. 78 FR 34655 - Science and Technology Reinvention Laboratory Personnel Management Demonstration Project...

    Science.gov (United States)

    2013-06-10

    ... CONTACT: Office of Naval Research: Ms. Margaret J. Mitchell, Director, Human Resources Office, Office of... established position management criteria, and (2) Pay Band V of the S&E Professional Career Track require... Personnel Management Demonstration Project, Department of Navy, Office of Naval Research (ONR); Proposed...

  15. Summary of the evidence file demonstrating completion of the NIF Project Completion Criteria

    Energy Technology Data Exchange (ETDEWEB)

    Haynam, C. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2014-12-04

    This document summarizes the results of performance verification tests on NIF that demonstrate it has met its performance-related Project Completion Criteria (PCC). It includes measurements made on NIF with the NIF diagnostics, the calibration of these diagnostics and the supporting analyses that verify the NIF performance criteria have been met.

  16. From demonstration projects to volume market : Market development for advanced housing renovation

    NARCIS (Netherlands)

    Mlecnik, E.; Prendergast, E.; Rodsjo, A.; Haavik, T.; Parker, P.

    2010-01-01

    How do we get from demonstration projects to a volume market for very low energy demand in advanced housing renovation? The contributors to this report have been working with this issue for many years. Some worked in both IEA SHC Task 28 Sustainable Housing (2000-2005) and in SHC Task 37 Advanced

  17. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2006

    Energy Technology Data Exchange (ETDEWEB)

    West Valley Nuclear Services Company (WVNSCO) and URS Group, Inc.

    2007-09-27

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2006. The report summarizes calendar year (CY) 2006 environmental monitoring data so as to describe the performance of the WVDP’s environmental management system (EMS), confirm compliance with standards and regulations, and highlight important programs that protect public health and safety and the environment.

  18. West Valley Demonstration Project Annual Site Environmental Report Calendard Year 2005

    Energy Technology Data Exchange (ETDEWEB)

    West Valley Nuclear Services Company (WVNSCO) and URS Group, Inc.

    2006-09-21

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2005. The report summarizes calendar year (CY) 2005 environmental monitoring data so as to describe the performance of the WVDP's environmental management system (EMS), confirm compliance with standards and regulations, and highlight important programs.

  19. The development of the human exploration demonstration project (HEDP), a planetary systems testbed

    Science.gov (United States)

    Chevers, Edward S.; Korsmeyer, David J.

    1993-01-01

    The Human Exploration Demonstration Project (HEDP) is an ongoing task at the National Aeronautics and Space Administration's Ames Research Center to address the advanced technology requirements necessary to implement an integrated working and living environment for a planetary surface habitat. The integrated environment will consist of life support systems, physiological monitoring of project crew, a virtual environment workstation, and centralized data acquisition and habitat systems health monitoring. There will be several robotic systems on a simulated planetary landscape external to the habitat environment to provide representative work loads for the crew. This paper describes the status of the HEDP after one year, the major facilities composing the HEDP, the project's role as an Ames Research Center testbed, and the types of demonstration scenarios that will be run to showcase the technologies.

  20. Environmental Assessment for the Warren Station externally fired combined cycle demonstration project

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    The proposed Penelec project is one of 5 projects for potential funding under the fifth solicitation under the Clean Coal Technology program. In Penelec, two existing boilers would be replaced at Warren Station, PA; the new unit would produce 73 MW(e) in a combined cycle mode (using both gas-fired and steam turbines). The project would fill the need for a full utility-size demonstration of externally fire combined cycle (EFCC) technology as the next step toward commercialization. This environmental assessment was prepared for compliance with NEPA; its purpose is to provide sufficient basis for determining whether to prepare an environmental impact statement or to issue a finding of no significant impact. It is divided into the sections: purpose and need for proposed action; alternatives; brief description of affected environment; environmental consequences, including discussion of commercial operation beyond the demonstration period.

  1. The optimal project position for demonstrating tricuspid annulus in angiography: an experimental study

    International Nuclear Information System (INIS)

    Bai Yuan; Zong Gongjun; Wang Hongru; Qin Yongwen; Huang Xinmiao; Jiang Haibin

    2009-01-01

    Objective: To explore the optimal project position for demonstrating tricuspid annulus angiographically in experimental goats. Methods: Eight healthy goats underwent right atrial angiography by using 6 F pig tail catheters. Under fluoroscopic monitoring the contrast media (total 110 ml, flow rate 12 ml/ s, pressure 800 psi) was injected continuously while a serious exposures were performed from RAO position to LAO position (totally 180 degree rotation). The maximum diameter of the tricuspid annulus in every picture was measured and the results were compared with that obtained from sonography. Results: The procedure was successful in all 8 experimental goats. The optimal project position to display the tricuspid annulus was at 27 degree ± 3 degree in RAO position. Conclusion: In angiography, the tricuspid annulus can be best demonstrated at the project position of 27 degree ± 3 degree in RAO. (authors)

  2. Water Use Optimization Toolset Project: Development and Demonstration Phase Draft Report

    Energy Technology Data Exchange (ETDEWEB)

    Gasper, John R. [Argonne National Laboratory; Veselka, Thomas D. [Argonne National Laboratory; Mahalik, Matthew R. [Argonne National Laboratory; Hayse, John W. [Argonne National Laboratory; Saha, Samrat [Argonne National Laboratory; Wigmosta, Mark S. [PNNL; Voisin, Nathalie [PNNL; Rakowski, Cynthia [PNNL; Coleman, Andre [PNNL; Lowry, Thomas S. [SNL

    2014-05-19

    This report summarizes the results of the development and demonstration phase of the Water Use Optimization Toolset (WUOT) project. It identifies the objective and goals that guided the project, as well as demonstrating potential benefits that could be obtained by applying the WUOT in different geo-hydrologic systems across the United States. A major challenge facing conventional hydropower plants is to operate more efficiently while dealing with an increasingly uncertain water-constrained environment and complex electricity markets. The goal of this 3-year WUOT project, which is funded by the U.S. Department of Energy (DOE), is to improve water management, resulting in more energy, revenues, and grid services from available water, and to enhance environmental benefits from improved hydropower operations and planning while maintaining institutional water delivery requirements. The long-term goal is for the WUOT to be used by environmental analysts and deployed by hydropower schedulers and operators to assist in market, dispatch, and operational decisions.

  3. In situ vitrification on buried waste

    International Nuclear Information System (INIS)

    Bates, S.O.

    1992-01-01

    In situ vitrification (ISV) is being evaluated as a remedial treatment technology for buried mixed and transuranic (TRU) wastes at the Subsurface Disposal Area (SDA) at Idaho National Engineering Laboratory (INEL) and can be related to buried wastes at other Department of Energy (DOE) sites. There are numerous locations around the DOE Complex where wastes were buried in the ground or stored for future burial. The Buried Waste Program (BWP) is conducting a comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) remedial investigation/feasibility study (RI/FS) for the Department of Energy - Field Office Idaho (DOE-ID). As part of the RI/FS, an ISV scoping study on the treatability of the SDA mixed low-level and mixed TRU waste is being performed for applicability to remediation of the waste at the Radioactive Waste Management Complex (RWMC). The ISV project being conducted at the INEL by EG ampersand G Idaho, Inc. consists of a treatability investigation to collect data to satisfy nine CERCLA criteria with regards to the SDA. This treatability investigation involves a series of experiments and related efforts to study the feasibility of ISV for remediation of mixed and TRU waste disposed of at the SDA

  4. Advanced Grid-Friendly Controls Demonstration Project for Utility-Scale PV Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Gevorgian, Vahan; O' Neill, Barbara

    2016-01-21

    A typical photovoltaic (PV) power plant consists of multiple power electronic inverters and can contribute to grid stability and reliability through sophisticated 'grid-friendly' controls. The availability and dissemination of actual test data showing the viability of advanced utility-scale PV controls among all industry stakeholders can leverage PV's value from being simply an energy resource to providing additional ancillary services that range from variability smoothing and frequency regulation to power quality. Strategically partnering with a selected utility and/or PV power plant operator is a key condition for a successful demonstration project. The U.S. Department of Energy's (DOE's) Solar Energy Technologies Office selected the National Renewable Energy Laboratory (NREL) to be a principal investigator in a two-year project with goals to (1) identify a potential partner(s), (2) develop a detailed scope of work and test plan for a field project to demonstrate the gird-friendly capabilities of utility-scale PV power plants, (3) facilitate conducting actual demonstration tests, and (4) disseminate test results among industry stakeholders via a joint NREL/DOE publication and participation in relevant technical conferences. The project implementation took place in FY 2014 and FY 2015. In FY14, NREL established collaborations with AES and First Solar Electric, LLC, to conduct demonstration testing on their utility-scale PV power plants in Puerto Rico and Texas, respectively, and developed test plans for each partner. Both Puerto Rico Electric Power Authority and the Electric Reliability Council of Texas expressed interest in this project because of the importance of such advanced controls for the reliable operation of their power systems under high penetration levels of variable renewable generation. During FY15, testing was completed on both plants, and a large amount of test data was produced and analyzed that demonstrates the ability of

  5. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2009

    Energy Technology Data Exchange (ETDEWEB)

    West Valley Environmental Services LLC (WVES) and URS Corporation

    2010-09-17

    The West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2009. The report, prepared by the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2009. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE’s effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program by the DOE ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental regulations and directives, evaluation of data collected in 2009 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  6. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2011

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2012-09-27

    The West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2011. The report, prepared for the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2011. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE’s effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental laws, regulations, and directives, evaluation of data collected in 2011 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  7. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2012

    Energy Technology Data Exchange (ETDEWEB)

    Rendall, John D. [CH2M HILL • B& amp; W West Valley, LLC (CHBWV); Steiner, Alison F. [URS Professional Solutions (URSPS); Klenk, David P. [CH2M HILL • B& amp; W West Valley, LLC (CHBWV)

    2013-09-19

    The West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2012. The report, prepared for the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2012. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE’s effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental laws, regulations, and directives, evaluation of data collected in 2012 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  8. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2010

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2011-09-28

    The West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2010. The report, prepared for the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2010. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE's effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental laws, regulations and directives, evaluation of data collected in 2010 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  9. West Valley Demonstration Project Annual Site Environmental Report (ASER) Calendar Year (2016)

    Energy Technology Data Exchange (ETDEWEB)

    Steiner, Alison F. [CH2M Hill BWXT West Valley, LLC, NY (United States); Pendl, Michael P. [CH2M Hill BWXT West Valley, LLC, NY (United States); Steiner, II, Robert E. [CH2M Hill BWXT West Valley, LLC, NY (United States); Fox, James R. [CH2M Hill BWXT West Valley, LLC, NY (United States); Hoch, Jerald J. [CH2M Hill BWXT West Valley, LLC, NY (United States); Williams, Janice D. [CH2M Hill BWXT West Valley, LLC, NY (United States); Wrotniak, Chester M. [CH2M Hill BWXT West Valley, LLC, NY (United States); Werchowski, Rebecca L. [CH2M Hill BWXT West Valley, LLC, NY (United States)

    2017-09-12

    West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2016. The report, prepared for the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2016. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE’s effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental laws, regulations, and directives, evaluation of data collected in 2016 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  10. West Valley Demonstration Project Annual Site Environmental Report (ASER) for Calendar Year 2015

    International Nuclear Information System (INIS)

    Rendall, John D.; Steiner, Alison F.; Pendl, Michael P.; Biedermann, Charles A.; Steiner II, Robert E.; Fox, James R.; Hoch, Jerald J.; Wrotniak, Chester M.; Werchowski, Rebecca L.

    2016-01-01

    West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2015. The report, prepared for the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2015. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE's effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental laws, regulations, and directives, evaluation of data collected in 2015 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  11. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2010

    International Nuclear Information System (INIS)

    2011-01-01

    The West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2010. The report, prepared for the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2010. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE's effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental laws, regulations and directives, evaluation of data collected in 2010 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  12. West Valley Demonstration Project Annual Site Environmental Report (ASER) for Calendar Year 2014

    Energy Technology Data Exchange (ETDEWEB)

    Rendall, John D. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Steiner, Alison F. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Pendl, Michael P. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Biedermann, Charles A. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Steiner, II, Robert E. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Fox, James R. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Hoch, Jerald J. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Werchowski, Rebecca L. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States)

    2015-09-15

    West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2014. The report, prepared for the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2014. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE’s effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental laws, regulations, and directives, evaluation of data collected in 2014 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  13. West Valley Demonstration Project Annual Site Environmental Report (ASER) for Calendar Year 2015

    Energy Technology Data Exchange (ETDEWEB)

    Rendall, John D. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Steiner, Alison F. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Pendl, Michael P. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Biedermann, Charles A. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Steiner, II, Robert E. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Fox, James R. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Hoch, Jerald J. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Wrotniak, Chester M. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Werchowski, Rebecca L. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States)

    2016-09-15

    West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2015. The report, prepared for the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2015. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE’s effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental laws, regulations, and directives, evaluation of data collected in 2015 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  14. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2009

    International Nuclear Information System (INIS)

    2010-01-01

    The West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2009. The report, prepared by the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2009. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE's effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program by the DOE ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental regulations and directives, evaluation of data collected in 2009 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  15. Environmental monitoring for the DOE coolside and LIMB demonstration extension projects

    Energy Technology Data Exchange (ETDEWEB)

    White, T.; Contos, L.; Adams, L. (Radian Corp., Research Triangle Park, NC (United States))

    1992-03-01

    The purpose of this document is to present environmental monitoring data collected during the US Department of Energy Limestone Injection Multistage Burner (DOE LIMB) Demonstration Project Extension at the Ohio Edison Edgewater Generating Station in Lorain, Ohio. The DOE project is an extension of the US Environmental Protection Agency's (EPA's) original LIMB Demonstration. The program is operated nuclear DOE's Clean Coal Technology Program of emerging clean coal technologies'' under the categories of in boiler control of oxides of sulfur and nitrogen'' as well as post-combustion clean-up.'' The objective of the LIMB program is to demonstrate the sulfur dioxide (SO{sub 2}) and nitrogen oxide (NO{sub x}) emission reduction capabilities of the LIMB system. The LIMB system is a retrofit technology to be used for existing coal-fired boilers equipped with electrostatic precipitators (ESPs).

  16. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2013

    Energy Technology Data Exchange (ETDEWEB)

    Rendall, John D. [CH2MHILL • B& W West Valley, LLC (CHBWV); Steiner, Alison F. [CH2MHILL • B& W West Valley, LLC (CHBWV); Pendl, Michael P. [CH2MHILL • B& W West Valley, LLC (CHBWV)

    2014-09-16

    West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2013. The report, prepared for the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2013. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE’s effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental laws, regulations, and directives, evaluation of data collected in 2013 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  17. Installation and routing of critical embedments at the Hanford Waste Vitrification Plant

    International Nuclear Information System (INIS)

    Van Katwijk, C.; Keenan, R.M.; Watts, C.

    1993-01-01

    The Hanford Waste Vitrification Plant (HWVP) is being designed by Fluor Daniel. Waste Chem Corporation is providing specialized expertise as Fluor Daniel's major subcontractor for vitrification and remote systems technologies. Westinghouse Hanford Company (Westinghouse Hanford) is the Project Integration manager and Business manager, and as the plant operator it provides technical direction to the Architect/Engineer team and constructor on behalf of the US Department of Energy, Richland Field Office. The Hot Cell portion of HWVP Vitrification Building contains very congested piping systems in the walls that penetrate in to the cells to nozzles for remote piping jumper assemblies. These nozzles require very tight tolerances to ensure a leak-tight fit to the jumpers. An approach has been developed that minimizes the time and expense of installing these nozzles in the wall to tight construction tolerances. This approach is called the Ganged Embed Plate (GEP) design

  18. Inductively coupled plasma-atomic emission spectroscopy glovebox assembly system at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Marlow, J.H.; McCarthy, K.M.; Tamul, N.R.

    1999-01-01

    The inductively coupled plasma/atomic emission spectroscopy [ICP/AES (ICP)] system for elemental analyses in support of vitrification processing was first installed in 1986. The initial instrument was a Jobin Yvon (JY) Model JY-70 ICP that consisted of sequential and simultaneous spectrometers for analysis of nonradioactive samples as radioactive surrogates. The JY-70 ICP continued supporting nonradioactive testing during the Functional and Checkout Testing of Systems (FACTS) using the full-scale melter with ''cold'' (nonradioactive) testing campaigns. As a result, the need for another system was identified to allow for the analysis of radioactive samples. The Mass Spec (Spectrometry) Lab was established for the installation of the modified ICP system for handling radioactive samples. The conceptual setup of another ICP was predicated on the use of a hood to allow ease of accessibility of the torch, nebulizer, and spray chamber, and the minimization of air flow paths. However, reconsideration of the radioactive sample dose rate and contamination levels led to the configuration of the glovebox system with a common transfer interface box for the ICP and the inductively coupled plasma-mass spectrometer (ICP-MS) glovebox assemblies. As a result, a simultaneous Model JY-50P ICP with glovebox was installed in 1990 as a first generation ICP glovebox system. This was one of the first ICP glovebox assemblies connected with an ICP-MS glovebox system. Since the economics of processing high-level radioactive waste (HLW) required the availability of an instrument to operate 24 hours a day throughout the year without any downtime, a second generation ICP glovebox assembly was designed, manufactured, and installed in 1995 using a Model JY-46P ICP. These two ICP glovebox systems continue to support vitrification of the HLW into canisters for storage. The ICP systems have been instrumental in monitoring vitrification batch processing. To date, remote sample preparation and

  19. Hydrogen fueling stations in Japan hydrogen and fuel cell demonstration project

    International Nuclear Information System (INIS)

    Koseki, K.; Tomuro, J.; Sato, H.; Maruyama, S.

    2004-01-01

    A new national demonstration project of fuel cell vehicles, which is called Japan Hydrogen and Fuel Cell Demonstration Project (JHFC Project), has started in FY2002 on a four-year plan. In this new project, ten hydrogen fueling stations have been constructed in Tokyo and Kanagawa area in FY2002-2003. The ten stations adopt the following different types of fuel and fueling methods: LPG reforming, methanol reforming, naphtha reforming, desulfurized-gasoline reforming, kerosene reforming, natural gas reforming, water electrolysis, liquid hydrogen, by-product hydrogen, and commercially available cylinder hydrogen. Approximately fifty fuel cell passenger cars and a fuel cell bus are running on public roads using these stations. In addition, two hydrogen stations will be constructed in FY2004 in Aichi prefecture where The 2005 World Exposition (EXPO 2005) will be held. The stations will service eight fuel cell buses used as pick-up buses for visitors. We, Engineering Advancement Association of Japan (ENAA), are commissioned to construct and operate a total of twelve stations by Ministry of Economy Trade and Industry (METI). We are executing to demonstrate or identify the energy-saving effect, reduction of the environmental footprint, and issues for facilitating the acceptance of hydrogen stations on the basis of the data obtained from the operation of the stations. (author)

  20. An analysis of the demonstration projects for renewable energy application buildings in China

    International Nuclear Information System (INIS)

    Liu, Xingmin; Ren, Hong; Wu, Yong; Kong, Deping

    2013-01-01

    During the 2006–2008 period, there were 386 demonstration projects for renewable energy application buildings (REAB) organised by Chinese government, with a total area of approximately 40,420,000 m 2 . By the end of 2011, the vast majority of these projects had been completed and had passed the final acceptance. This paper analyses the measures taken by the Chinese government, including economic incentive mechanisms, organising agencies, application and evaluation systems, online monitoring platforms, acceptance inspections, assessment systems, standard criteria and so forth. This paper then evaluates the policy effects. The paper shows that there has been a satisfactory effect in the development of the REAB market, mobilising the enthusiasm of the government, equipment manufacturers and scientific research institutions, and promoting energy conservation. In addition, this paper analyses the suitability of different technological types in different climatic zones, which provides further guidance for the development of the REAB. Finally, based on the analyses of the problems met in the implementation of the demonstration projects, this paper proposes some policy suggestions concerning standard criteria, technological development, project management, incentive mechanisms and so on, to promote the development of the REAB more effectively in the future in China. - Highlights: • The policy measures to promote the development of renewable energy application buildings in China. • Evaluation of the demonstration policy effects in the market development and other aspects. • Analyses of the regional applicability for renewable energy application buildings in China. • Analyses of problems met in the implementation of the demonstration projects. • Put forward some policy suggestions on standard, technology, management, etc

  1. Energy efficient ventilation based on demand humidity control. Demonstration project with 49 apartments in Soenderborg

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    The aim of the project is to demonstrate how the overall energy consumption in apartment buildings can be reduced through a combination of: 1) Energy efficient ventilation based on demand humidity control; 2) Energy efficient design of the building shell including passive solar and seasonally flexible sunspaces; 3) Use of low temperature heating system. The 3 blocks in the project, each with 16 apartments, are furnished with 3 different ventilation systems: 1) Standard exhaust system according to building codes; 2) Ventilation system with humidity control. Each room is furnished with an air inlet valve controlled by a processor, which monitors the humidity; 3) Standard ventilation system with heat recovery. (au)

  2. Demonstrating the sealing of a deep geologic repository: the RECAP project

    International Nuclear Information System (INIS)

    Kuzyk, G.W.; Dixon, D.A.; Martino, J.B.; Kozak, E.T.; Bilinsky, D.M.; Thompson, P.M.

    2006-01-01

    Atomic Energy of Canada Limited (AECL) has operated an Underground Research Laboratory (URL) for twenty-three years (1982-2005). The URL was designed and constructed to carry out in situ geotechnical R and D needed for the Canadian Nuclear Fuel Waste Management program. The facility is now being closed, the final of several phases that have included siting, site evaluation, construction and operation. The closure phase presents a unique opportunity to develop and demonstrate the methodologies needed for closure and site restoration of a deep geologic repository for used nuclear fuel. A wealth of technical background and characterization data, dating back to before the first excavation work was carried out, are available to support closure activities. A number of closure-related activities are being proposed as part of a REpository Closure And Post-closure (RECAP) project. The RECAP project is proposed to include demonstrations of shaft and borehole sealing and monitoring as well as fracture sealing (grouting), room closure and monitoring system decommissioning, all activities that would occur when closing an actual repository. In addition to the closure-related activities, the RECAP project could provide a unique opportunity to conduct intrusion-monitoring demonstrations as part of a repository safeguards demonstration. (author)

  3. Computer simulation of the off gas treatment process for the KEPCO pilot vitrification plant

    International Nuclear Information System (INIS)

    Kim, Hey Suk; Maeng, Sung Jun; Lee, Myung Chan

    1999-01-01

    Vitrification technology for treatment of low and intermediate radioactive wastes can remarkably reduce waste volume to about one twentieth of the initial volume as they are collected and converted into a very stable form. Therefore, it can minimize environmental impact when the vitrified waste is disposed of. But an off gas treatment system is necessary to apply this technology because air pollutants and radioisotopes are generated like those of other conventional incinerators during thermal oxidation process at high temperature. KEPCO designed and installed a pilot scale vitrification plant to demonstrate the feasibility of the vitrification process and then to make a conceptual design for a commercial vitrification facility. The purpose of this study was to simulate the off gas treatment system(OGTS) in order optimize the operating conditions. Mass balance and temperature profile in the off gas treatment system were simulated for different combinations of combustible wastes by computer simulation code named OGTS code and removal efficiency of each process was also calculated with change of design parameters. The OGTS code saved efforts,time and capital because scale and configuration of the system could be easily changed. The simulation result of the pilot scale off gas process as well as pilot tests will be of great use in the future for a design of the commercial vitrification facility. (author)

  4. Stability of the cytoskeleton of matured buffalo oocytes pretreated with cytochalasin B prior to vitrification.

    Science.gov (United States)

    Wang, C L; Xu, H Y; Xie, L; Lu, Y Q; Yang, X G; Lu, S S; Lu, K H

    2016-06-01

    Stabilizing the cytoskeleton system during vitrification can improve the post-thaw survival and development of vitrified oocytes. The cytoskeleton stabilizer cytochalasin B (CB) has been used in cryopreservation to improve the developmental competence of vitrified oocytes. To assess the effect of pretreating matured buffalo oocytes with CB before vitrification, we applied 0, 4, 8, or 12 μg/mL CB for 30 min. The optimum concentration of CB treatment (8 μg/mL for 30 min) was then used to evaluate the distribution of microtubules and microfilaments, the expression of the cytoskeleton proteins actin and tubulin, and the developmental potential of matured oocytes that were vitrified-warmed by the Cryotop method. Western blotting demonstrated that vitrification significantly decreased tubulin expression, but that the decrease was attenuated for oocytes pretreated with 8 μg/mL CB before vitrification. After warming and intracytoplasmic sperm injection, oocytes that were pretreated with 8 μg/mL CB before vitrification yielded significantly higher 8-cell and blastocyst rates than those that were vitrified without CB pretreatment. The values for the vitrified groups in all experiments were significantly lower (P < 0.01) than those of the control groups. In conclusion, pretreatment with 8 μg/mL CB for 30 min significantly improves the cytoskeletal structure, expression of tubulin, and development capacity of vitrified matured buffalo oocytes. Copyright © 2016 Elsevier Inc. All rights reserved.

  5. An overview of waste management systems at the West Valley demonstration project

    International Nuclear Information System (INIS)

    McIntosh, T.W.; Bixby, W.W.; Krauss, J.E.; Leap, D.R.

    1988-01-01

    In 1980, the United States Congress passed into law the West Valley Demonstration Project Act authorizing the Department of Energy (DOE) to conduct a nuclear waste management project at a former commercial nuclear fuel reprocessing facility located in West Valley, New York. The Project's main objective is to solidify approximately two million litres of high-level radioactive liquid waste into a form suitable for transport to a federal repository for final disposal. The majority of the liquid waste was produced as a by-product of the PUREX extraction process and is stored in an underground steel tank. A waste characterization program has shown that the neutralized waste has settled into two distinct layers: a clear alkaline liquid (supernatant) layer and a dense precipitate (sludge) layer. The principle radioactive elements in the waste are cesium 137 (supernatant) and strontium 90 (sludge). This paper describes the overall project strategy, the waste management systems, the present project engineering and construction status and the project schedule leading to radioactive operation

  6. Preconceptual design study for solidifying high-level waste: West Valley Demonstration Project

    International Nuclear Information System (INIS)

    1981-04-01

    This Appendix contains the preconceptual design drawings prepared by Vitro Engineering Corporation for Pacific Northwest Laboratory. The following types of drawings are included in this Appendix: process flow diagrams; process and instrumentation diagrams; hydraulic diagrams; equipment arrangement drawings; service gallery drawings; electric power one-line diagram; equipment line lists; and outline specifications. The basic purpose of these drawings was to determine the feasibility of installing the reference solidification process in existing cells at the Western New York Nuclear Service Center. Most of the process and vitrification equipment will be installed in the former Chemical Processing Cell, while the salt solidification equipment will be housed in the former Scrap Removal Room. The design utilized a remote maintenance and operation concept

  7. Vitrification and levitation of a liquid droplet on liquid nitrogen

    OpenAIRE

    Song, Young S.; Adler, Douglas; Xu, Feng; Kayaalp, Emre; Nureddin, Aida; Anchan, Raymond M.; Maas, Richard L.; Demirci, Utkan

    2010-01-01

    The vitrification of a liquid occurs when ice crystal formation is prevented in the cryogenic environment through ultrarapid cooling. In general, vitrification entails a large temperature difference between the liquid and its surrounding medium. In our droplet vitrification experiments, we observed that such vitrification events are accompanied by a Leidenfrost phenomenon, which impedes the heat transfer to cool the liquid, when the liquid droplet comes into direct contact with liquid nitroge...

  8. Hanford Waste Vitrification Plant quality assurance program description for defense high-level waste form development and qualification

    International Nuclear Information System (INIS)

    Hand, R.L.

    1990-12-01

    The US Department of Energy-Office of Civilian Radioactive Waste Management has been designated the national high-level waste repository licensee and the recipient for the canistered waste forms. The Office of Waste Operations executes overall responsibility for producing the canistered waste form. The Hanford Waste Vitrification Plant Project, as part of the waste form producer organization, consists of a vertical relationship. Overall control is provided by the US Department of Energy-Environmental Restoration and Waste Management Headquarters; with the US Department of Energy-Office of Waste Operations; the US Department of Energy- Headquarters/Vitrification Project Branch; the US Department of Energy-Richland Operations Office/Vitrification Project Office; and the Westinghouse Hanford Company, operations and engineering contractor. This document has been prepared in response to direction from the US Department of Energy-Office of Civilian Radioactive Waste Management through the US Department of Energy-Richland Operations Office for a quality assurance program that meets the requirements of the US Department of Energy. This document provides guidance and direction for implementing a quality assurance program that applies to the Hanford Waste Vitrification Plant Project. The Hanford Waste Vitrification Plant Project management commits to implementing the quality assurance program activities; reviewing the program periodically, and revising it as necessary to keep it current and effective. 12 refs., 6 figs., 1 tab

  9. The HAW project: demonstration facility for the disposal of high-level waste in salt

    International Nuclear Information System (INIS)

    Rothfuchs, T.

    1991-01-01

    This report is the so-called Synthesis report 1985-1989 of the international HAW project performed in the 800 m level of the ASSE salt mine in the Federal Republic of Germany. The major objective of this project is the pilot testing and demonstration of safe methods for the final disposal of high-level radioactive waste in geological salt-deposits. The HAW-project is carried out by the GSF-Institut fuer Tieflagerung (IFT) in cooperation with the French Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA); the Spanish Empresa Nacional de Residuos Radioactivos S.A (ENRESA) and the Netherlands Energy Research Foundation (ECN). During the years 1985 to 1989 the underground test field was excavated and after some delays in the licensing procedure, the emplacement of 30 vitrified highly radioactive canisters (containers) is now envisaged for early 1991. 32 refs; 76 figs., 11 tabs

  10. The HAW project: demonstration facility for the disposal of high-level waste in salt

    International Nuclear Information System (INIS)

    Rothfuchs, T.

    1991-01-01

    This publication is the interim report 1988-89 of the international HAW project performed in the 800 m level of the Asse salt mine in the Federal Republic of Germany. The major objective of this project is the pilot testing and demonstration of safe methods for the final disposal of high-level radioactive waste in geological salt deposits. The HAW-project is carried out by the GSF-Institut fuer Tieflagerung (IFT) in cooperation with the French Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA); the Spanish Empresa Nacional de Residuos Radiactivos S.A. (ENRESA) and the Netherlands Energy Research Foundation (ECN). After some delays in the licensing procedure the emplacement of 30 vitrified highly radioactive canisters (containers) is now envisaged for early 1991. 20 refs.; 92 figs.; 14 tabs

  11. Environmental Assessment and Finding of No Significant Impact: Kalina Geothermal Demonstration Project Steamboat Springs, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    N/A

    1999-02-22

    The Department of Energy (DOE) has prepared an Environmental Assessment (EA) to provide the DOE and other public agency decision makers with the environmental documentation required to take informed discretionary action on the proposed Kalina Geothermal Demonstration project. The EA assesses the potential environmental impacts and cumulative impacts, possible ways to minimize effects associated with partial funding of the proposed project, and discusses alternatives to DOE actions. The DOE will use this EA as a basis for their decision to provide financial assistance to Exergy, Inc. (Exergy), the project applicant. Based on the analysis in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human or physical environment, within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, the preparation of an environmental impact statement is not required and DOE is issuing this Finding of No Significant Impact (FONSI).

  12. Supplement analysis 2 of environmental impacts resulting from modifications in the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    1998-01-01

    The West Valley Demonstration Project, located in western New York, has approximately 600,000 gallons of liquid high-level radioactive waste (HLW) in storage in underground tanks. While corrosion analysis has revealed that only limited tank degradation has taken place, the failure of these tanks could release HLW to the environment. Congress requires DOE to demonstrate the technology for removal and solidification of HLW. DOE issued the Final Environmental Impact Statement (FEIS) in 1982. The purpose of this second supplement analysis is to re-assess the 1982 Final Environmental Impact Statement's continued adequacy. This report provides the necessary and appropriate data for DOE to determine whether the environmental impacts presented by the ongoing refinements in the design, process, and operations of the Project are considered sufficiently bounded within the envelope of impacts presented in the FEIS and supporting documentation

  13. Modelling and Simulation of National Electronic Product Code Network Demonstrator Project

    Science.gov (United States)

    Mo, John P. T.

    The National Electronic Product Code (EPC) Network Demonstrator Project (NDP) was the first large scale consumer goods track and trace investigation in the world using full EPC protocol system for applying RFID technology in supply chains. The NDP demonstrated the methods of sharing information securely using EPC Network, providing authentication to interacting parties, and enhancing the ability to track and trace movement of goods within the entire supply chain involving transactions among multiple enterprise. Due to project constraints, the actual run of the NDP was 3 months only and was unable to consolidate with quantitative results. This paper discusses the modelling and simulation of activities in the NDP in a discrete event simulation environment and provides an estimation of the potential benefits that can be derived from the NDP if it was continued for one whole year.

  14. Ultra-Clean Fischer-Tropsch Fuels Production and Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Steve Bergin

    2005-10-14

    The Report Abstract provides summaries of the past year's activities relating to each of the main project objectives. Some of the objectives will be expanded on in greater detail further down in the report. The following objectives have their own addition sections in the report: Dynamometer Durability Testing, the Denali Bus Fleet Demonstration, Bus Fleet Demonstrations Emissions Analysis, Impact of SFP Fuel on Engine Performance, Emissions Analysis, Feasibility Study of SFPs for Rural Alaska, and Cold Weather Testing of Ultra Clean Fuel.

  15. Vitrification of copper flotation waste

    Energy Technology Data Exchange (ETDEWEB)

    Karamanov, Alexander [Institute of Physical Chemistry, Bulgarian Academy of Science, G. Bonchev Str. Block 11, 1113 Sofia (Bulgaria)]. E-mail: karama@ing.univaq.it; Aloisi, Mirko [Department of Chemistry, Chemical Engineering and Materials, University of L' Aquila, 67040 Monteluco di Roio, L' Aquila (Italy); Pelino, Mario [Department of Chemistry, Chemical Engineering and Materials, University of L' Aquila, 67040 Monteluco di Roio, L' Aquila (Italy)

    2007-02-09

    The vitrification of an hazardous iron-rich waste (W), arising from slag flotation of copper production, was studied. Two glasses, containing 30 wt% W were melted for 30 min at 1400 deg. C. The first batch, labeled WSZ, was obtained by mixing W, blast furnace slag (S) and zeolite tuff (Z), whereas the second, labeled WG, was prepared by mixing W, glass cullet (G), sand and limestone. The glass frits showed high chemical durability, measured by the TCLP test. The crystallization of the glasses was evaluated by DTA. The crystal phases formed were identified by XRD resulting to be pyroxene and wollastonite solid solutions, magnetite and hematite. The morphology of the glass-ceramics was observed by optical and scanning electron microscopy. WSZ composition showed a high rate of bulk crystallization and resulted to be suitable for producing glass-ceramics by a short crystallization heat-treatment. WG composition showed a low crystallization rate and good sinterability; glass-ceramics were obtained by sinter-crystallization of the glass frit.

  16. Vitrification of copper flotation waste.

    Science.gov (United States)

    Karamanov, Alexander; Aloisi, Mirko; Pelino, Mario

    2007-02-09

    The vitrification of an hazardous iron-rich waste (W), arising from slag flotation of copper production, was studied. Two glasses, containing 30wt% W were melted for 30min at 1400 degrees C. The first batch, labeled WSZ, was obtained by mixing W, blast furnace slag (S) and zeolite tuff (Z), whereas the second, labeled WG, was prepared by mixing W, glass cullet (G), sand and limestone. The glass frits showed high chemical durability, measured by the TCLP test. The crystallization of the glasses was evaluated by DTA. The crystal phases formed were identified by XRD resulting to be pyroxene and wollastonite solid solutions, magnetite and hematite. The morphology of the glass-ceramics was observed by optical and scanning electron microscopy. WSZ composition showed a high rate of bulk crystallization and resulted to be suitable for producing glass-ceramics by a short crystallization heat-treatment. WG composition showed a low crystallization rate and good sinterability; glass-ceramics were obtained by sinter-crystallization of the glass frit.

  17. Vitrification of copper flotation waste

    International Nuclear Information System (INIS)

    Karamanov, Alexander; Aloisi, Mirko; Pelino, Mario

    2007-01-01

    The vitrification of an hazardous iron-rich waste (W), arising from slag flotation of copper production, was studied. Two glasses, containing 30 wt% W were melted for 30 min at 1400 deg. C. The first batch, labeled WSZ, was obtained by mixing W, blast furnace slag (S) and zeolite tuff (Z), whereas the second, labeled WG, was prepared by mixing W, glass cullet (G), sand and limestone. The glass frits showed high chemical durability, measured by the TCLP test. The crystallization of the glasses was evaluated by DTA. The crystal phases formed were identified by XRD resulting to be pyroxene and wollastonite solid solutions, magnetite and hematite. The morphology of the glass-ceramics was observed by optical and scanning electron microscopy. WSZ composition showed a high rate of bulk crystallization and resulted to be suitable for producing glass-ceramics by a short crystallization heat-treatment. WG composition showed a low crystallization rate and good sinterability; glass-ceramics were obtained by sinter-crystallization of the glass frit

  18. Vitrification development and experiences at Fernald, Ohio

    International Nuclear Information System (INIS)

    Gimpel, R.F.; Paine, D.; Roberts, J.L.; Akgunduz, N.

    1998-01-01

    Vitrification of radioactive wastes products have proven to produce an extremely stable waste form. Vitrification involves the melting of wastes with a mixture of glass-forming additives at high temperatures; when cooled, the wastes are incorporated into a glass that is analogous to obsidian. Obsidian is a volcanic glass-like rock, commonly found in nature. A one-metric ton/day Vitrification Pilot Plant (VITPP) at Fernald, Ohio, simulated the vitrification of radium and radon bearing silo residues using representative non-radioactive surrogates. These non-radioactive surrogates contained high concentrations of lead, sulfates, and phosphates. The vitrification process was carried out at temperatures of 1150 to 1350 C. Laboratory and bench-scale treatability studies were conducted before initiation of the VITPP. Development of the glass formulas, containing up to 90% waste, will be discussed in the paper. The VITPP processed glass for seven months, until a breach of the melter containment vessel suspended operations. More than 70,000 pounds of good surrogate glass were produced by the VITPP. Experiences, lessons learned, and the planned path forward will be presented

  19. A Pilot Project Demonstrating that Combat Medics Can Safely Administer Parenteral Medications in the Emergency Department.

    Science.gov (United States)

    Schauer, Steven G; Cunningham, Cord W; Fisher, Andrew D; DeLorenzo, Robert A

    2017-12-01

    Introduction Select units in the military have improved combat medic training by integrating their functions into routine clinical care activities with measurable improvements in battlefield care. This level of integration is currently limited to special operations units. It is unknown if regular Army units and combat medics can emulate these successes. The goal of this project was to determine whether US Army combat medics can be integrated into routine emergency department (ED) clinical care, specifically medication administration. Project Design This was a quality assurance project that monitored training of combat medics to administer parenteral medications and to ensure patient safety. Combat medics were provided training that included direct supervision during medication administration. Once proficiency was demonstrated, combat medics would prepare the medications under direct supervision, followed by indirect supervision during administration. As part of the quality assurance and safety processes, combat medics were required to document all medication administrations, supervising provider, and unexpected adverse events. Additional quality assurance follow-up occurred via complete chart review by the project lead. Data During the project period, the combat medics administered the following medications: ketamine (n=13), morphine (n=8), ketorolac (n=7), fentanyl (n=5), ondansetron (n=4), and other (n=6). No adverse events or patient safety events were reported by the combat medics or discovered during the quality assurance process. In this limited case series, combat medics safely administered parenteral medications under indirect provider supervision. Future research is needed to further develop this training model for both the military and civilian setting. Schauer SG , Cunningham C W, Fisher AD , DeLorenzo RA . A pilot project demonstrating that combat medics can safely administer parenteral medications in the emergency department. Prehosp Disaster Med. 2017;32(6):679-681.

  20. RM12-2703 Advanced Rooftop Unit Control Retrofit Kit Field Demonstration: Hawaii and Guam Energy Improvement Technology Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Doebber, I. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Dean, J. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Dominick, J. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Holland, G. [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2014-03-01

    As part of its overall strategy to meet its energy goals, the Naval Facilities Engineering Command (NAVFAC) partnered with U.S. Department of Energy's (DOE) National Renewable Energy Laboratory (NREL) to rapidly demonstrate and deploy cost-effective renewable energy and energy efficiency technologies. This was one of several demonstrations of new and underutilized commercial energy efficiency technologies. The consistent year-round demand for air conditioning and dehumidification in Hawaii provides an advantageous demonstration location for advanced rooftop control (ARC) retrofit kits to packaged rooftop units (RTUs). This report summarizes the field demonstration of ARCs installed on nine RTUs serving a 70,000-ft2 exchange store (large retail) and two RTUs, each serving small office buildings located on Joint Base Pearl Harbor-Hickam (JBPHH).

  1. Tumulus Disposal Demonstration Project assessment plan for potential worker exposure: Revision 1

    International Nuclear Information System (INIS)

    Styers, D.R.

    1989-03-01

    The purpose of the ''Assessment Plan for Potential Worker Exposure'' is to determine the potential radiological exposures to the workers as they dispose of low-level radioactive wastes (LLW) on the Tumulus Disposal Demonstration Project (TDDP). An evaluation of the work procedures and precautions will be made so as to maintain the exposure levels As Low As Reasonably Achievable (ALARA). 10 refs., 10 figs

  2. The integrated melter off-gas treatment systems at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Vance, R.F.

    1991-12-01

    The West Valley Demonstration project was established by an act of Congress in 1980 to solidify the high level radioactive liquid wastes produced from operation of the Western New York Nuclear Services Center from 1966 to 1972. The waste will be solidified as borosilicate glass. This report describes the functions, the controlling design criteria, and the resulting design of the melter off-gas treatment systems

  3. High temperature vitrification of surrogate Savannah River Site (SRS) mixed waste materials

    International Nuclear Information System (INIS)

    Applewhite-Ramsey, A.; Schumacher, R.F.; Spatz, T.L.; Newsom, R.A.; Circeo, L.J.; Danjaji, M.B.

    1995-01-01

    The Savannah River Technology Center (SRTC) has been funded through the DOE Office of Technology Development (DOE-OTD) to investigate high-temperature vitrification technologies for the treatment of diverse low-level and mixed wastes. High temperature vitrification is a likely candidate for processing heterogeneous solid wastes containing low levels of activity. Many SRS wastes fit into this category. Plasma torch technology is one high temperature vitrification method. A trial demonstration of plasma torch processing is being performed at the Georgia Institute of Technology on surrogate SRS wastes. This effort is in cooperation with the Engineering Research and Development Association of Georgia Universities (ERDA) program. The results of phase 1 of these plasma torch trials will be presented

  4. The PLX- α project: demonstrating the viability of spherically imploding plasma liners as an MIF driver

    Science.gov (United States)

    Hsu, S. C.; Witherspoon, F. D.; Cassibry, J. T.; Gilmore, M.; Samulyak, R.; Stoltz, P.; the PLX-α Team

    2015-11-01

    Under ARPA-E's ALPHA program, the Plasma Liner Experiment-ALPHA (PLX- α) project aims to demonstrate the viability and scalability of spherically imploding plasma liners as a standoff, high-implosion-velocity magneto-inertial-fusion (MIF) driver that is potentially compatible with both low- and high- β targets. The project has three major objectives: (a) advancing existing contoured-gap coaxial-gun technology to achieve higher operational reliability/precision and better control/reproducibility of plasma-jet properties and profiles; (2) conducting ~ π / 2 -solid-angle plasma-liner experiments with 9 guns to demonstrate (along with extrapolations from modeling) that the jet-merging process leads to Mach-number degradation and liner uniformity that are acceptable for MIF; and (3) conducting 4 π experiments with up to 60 guns to demonstrate the formation of an imploding spherical plasma liner for the first time, and to provide empirical ram-pressure and uniformity scaling data for benchmarking our codes and informing us whether the scalings justify further development beyond ALPHA. This talk will provide an overview of the PLX- α project as well as key research results to date. Supported by ARPA-E's ALPHA program; original PLX construction supported by DOE Fusion Energy Sciences.

  5. A Day in the Life of the Laser Communications Relay Demonstration Project

    Science.gov (United States)

    Edwards, Bernard; Israel, David; Caroglanian, Armen; Spero, James; Roberts, Tom; Moores, John

    2016-01-01

    This paper provides an overview of the planned concept of operations for the Laser Communications Relay Demonstration Project (LCRD), a joint project among NASA's Goddard Space Flight Center (GSFC), the Jet Propulsion Laboratory, California Institute of Technology (JPL), and the Massachusetts Institute of Technology Lincoln Laboratory (MIT/LL). LCRD will provide at least two years of bi-directional optical communications at user data rates of up to 1.244 Gbps in an operational environment. The project lays the groundwork for establishing communications architecture and protocols, and developing the communications hardware and support infrastructure, concluding in a demonstration of optical communications' potential to meet NASA's growing need for higher data rates for future science and exploration missions. A pair of flight optical communications terminals will reside on a single commercial communications satellite in geostationary orbit; the two ground optical communications terminals will be located in Southern California and Hawaii. This paper summarizes the current LCRD architecture and key systems for the demonstration, focusing on what it will take to operate an optical communications relay that can support space-to-space, space-to-air, and space-to-ground optical links.

  6. A Day in the Life of the Laser Communications Relay Demonstration (LCRD) Project.

    Science.gov (United States)

    Israel, David; Caroglanian, Armen; Edwards, Bernard; Spero, James; Roberts, Tom; Moores, John

    2016-01-01

    This presentation provides an overview of the planned concept of operations for the Laser Communications Relay Demonstration Project (LCRD), a joint project among NASA's Goddard Space Flight Center (GSFC), the Jet Propulsion Laboratory, California Institute of Technology (JPL), and the Massachusetts Institute of Technology Lincoln Laboratory (MITLL). LCRD will provide at least two years of bi-directional optical communications at user data rates of up to 1.244 Gbps in an operational environment. The project lays the ground work for establishing communications architecture and protocols, and developing the communications hardware and support infrastructure, concluding in a demonstration of optical communications potential to meet NASAs growing need for higher data rates for future science and exploration missions. A pair of flight optical communications terminals will reside on a single commercial communications satellite in geostationary orbit; the two ground optical communications terminals will be located in Southern California and Hawaii. This paper summarizes the current LCRD architecture and key systems for the demonstration, focusing on what it will take to operate an optical communications relay that can support space-to-space, space-to-air, and space-to-ground optical links.

  7. Biomethanization of tannery waste: An industrial experiment: Demonstration project. Biomethanisation de residus de tannerie: Une experience industrielle: Projet de demonstration

    Energy Technology Data Exchange (ETDEWEB)

    Aloy, M.; Mermet, R.; Sanejouand, J.

    1988-01-01

    The tanning and leather dressing industry produces large amounts of waste products including which can be placed in three categories: unrtanned waste, tanned waste, and liquid waste. Both untanned and liquid waste have a high organic content (proteins and fats) and their humidity levels are such that they are readily degraded by methanic fermentation. The results of the experiments confirm the technical feasibility of the project and indicate the economic limits of this type of plant. 14 figs.

  8. HLW vitrification in France industrial experience and glass quality

    International Nuclear Information System (INIS)

    Desvaux, J.L.; Delahaye, P.

    1994-01-01

    This paper describes the vitrification process, the technology and process improvements at the La Hague plant in R 7 and T 7 facilities. The main achievements relate to the process flexibility, the reliability of the equipment and solid waste management. The quality of the vitrified glass produced and canisters compliance with agreed specifications are demonstrated through characterization studies. Since the active start-up of R 7/T 7 facilities, canisters compliance with specifications relies upon a complete quality assurance/quality control program including process control. 1 tab., 1 fig

  9. Research, development and demonstration in the energy area in Switzerland - List of projects 2000/2001

    International Nuclear Information System (INIS)

    2002-01-01

    This report prepared by the Swiss Federal Office of Energy (SFOE) reviews research, development and demonstration projects in the energy area that were partly or wholly supported by the Swiss Federation in the years 2000/2001. A list of over 1,000 projects is presented, whereby many projects supported by the Swiss Cantons and local authorities are not included in the statistics. The report also contains figures on the efforts made by the private economy in these areas. The classification of the projects in the four main areas 'efficient use of energy', 'renewable energy sources', 'nuclear energy' and 'energy economics' is presented. This allows comparison with other publications such as the Federal Energy-Research Concept or the Overviews of the Energy-Research Programme Managers. The classification system is also compared with that used by the International Energy Agency (IEA). The Network for Information and Technology Transfer (ENET) is also presented, which has a comprehensive data base at its disposal and which maintains a systematic collection of energy-relevant publications. Details on these projects can be obtained from the appropriate heads of programmes and SFOE departmental heads, whose addresses are given in the report

  10. IEA low NOx combustion project Stage III. Low NOx combustion and sorbent injection demonstration projects. V.2

    International Nuclear Information System (INIS)

    Payne, R.

    1991-03-01

    This report summarizes the main results from an IES project concerning the demonstration of low-NO x combustion and sorbent injection as techniques for the control of NO x and SO x emissions from pulverized coal fired utility boilers. The project has built upon information generated in two previous stages of activity, where NO x and SO x control processes were evaluated at both fundamental and pilot-scales. The concept for this stage of the project was for a unique collaboration, where the participating countries (Canada, Denmark and Sweden, together with the United States) have pooled information from full scale boiler demonstrations of low-NO x burner and sorbent injection technologies, and have jointly contributed to establishing a common basis for data evaluation. Demonstration testing was successfully carried out on five wall-fired commercial boiler systems which ranged in size from a 20 MW thermal input boiler used for district heating, up to a 300 MW electric utility boiler. All of these units were fired on high-volatile bituminous coals with sulfur contents ranging from 0.6-3.2 percent. At each site the existing burners were either modified or replaced to provide for low-NO x combustion, and provisions were made to inject calcium based sorbent materials into the furnace space for SO 2 emission control. The results of sorbent injection testing showed moderate levels of SO 2 removal which ranged from approximately 15 to 55 percent at an injected calcium to sulfur molar ratio to 2.0 and with boiler operation at nominal full load. Sulfur capture was found to depend upon the combined effects of parameters such as: sorbent type and reactivity; peak sorbent temperature; coal sulfur content; and the thermal characteristics of the boilers. (8 refs., 58 figs., 6 tabs.)

  11. HyLights: Preparation of the Large-Scale Demonstration Projects on Hydrogen for Transport in Europe

    International Nuclear Information System (INIS)

    Ulrich Bunger; Volker Blandow; Volker Jaensch; Harm Jeeninga; Cristina Morte Gomez

    2006-01-01

    The strategically important project HyLights has been launched by the European Commission in preparation of the large scale demonstration projects in transition to hydrogen as a fuel and long-term renewable energy carrier. HyLights, monitors concluded/ongoing demonstration projects and assists the planning of the next demonstration project phase, putting a clear focus on hydrogen in transport. HyLights is a coordination action that comprises 5 tasks to: 1) develop an assessment framework for concluded/ongoing demonstration projects, 2) analyse individual projects and establish a project database, 3) carry out a gaps analysis and prepare a requirement profile for the next stage projects, 4) assess and identify necessary financial and legal steps in preparation of the new projects, and 5) develop a European Initiative for the Growth of Hydrogen for Transport (EIGHT). (authors)

  12. Treatment of NPP wastes using vitrification

    International Nuclear Information System (INIS)

    Sobolev, I.A.; Lifanov, F.A.; Stefanovsky, S.V.; Kobelev, A.P.; Savkin, A.E.; Kornev, V.I.

    1998-01-01

    Glass-based materials to immobilize various liquid and solid radioactive wastes generated at nuclear power plants (NPP) were designed. Glassy waste forms can be produced using electric melting including a cold crucible melting. Leach rate of cesium was found to be 10 -5 -10 -6 g/(cm 2 day) (IAEA technique). Volume reduction factor after vitrification reached 4-5. Various technologies for NPP waste vitrification were developed. Direct vitrification means feeding of source waste into the melter with formation of glassy waste form to be disposed. Joule heated ceramic melter, and cold crucible were tested. Process variables at treatment of Kursk, Chernobyl (RBMK), Kalinin, Novovoronezh (VVER) NPP wastes were determined. The most promising melter was found to be the cold crucible. Pilot plant based on the cold crucibles has been designed and constructed. Solid burnable NPP wastes are incinerated and slags are incorporated in glass. (author)

  13. In situ vitrification: Application to buried waste

    International Nuclear Information System (INIS)

    Callow, R.A.; Thompson, L.E.

    1991-01-01

    Two in situ vitrification field tests were conducted in June and July 1990 at Idaho National Engineering Laboratory. In situ vitrification is a technology for in-place conversion of contaminated soils into a durable glass and crystalline waste form and is being investigated as a potential remediation technology for buried waste. The overall objective of the two tests was to assess the general suitability of the process to remediate buried waste structures found at Idaho National Engineering Laboratory. In particular, these tests were designed as part of a treatability study to provide essential information on field performance of the process under conditions of significant combustible and metal wastes, and to test a newly developed electrode feed technology. The tests were successfully completed, and the electrode feed technology provided valuable operational control for successfully processing the high metal content waste. The results indicate that in situ vitrification is a feasible technology for application to buried waste. 2 refs., 5 figs., 2 tabs

  14. Plasma Hearth Process vitrification of DOE low-level mixed waste

    International Nuclear Information System (INIS)

    Gillins, R.L.; Geimer, R.M.

    1995-01-01

    The Plasma Hearth Process (PHP) demonstration project is one of the key technology projects in the Department of Energy (DOE) Office of Technology Development Mixed Waste Focus Area. The PHP is recognized as one of the more promising solutions to DOE's mixed waste treatment needs, with potential application in the treatment of a wide variety of DOE mixed wastes. The PHP is a high temperature vitrification process using a plasma arc torch in a stationary, refractory lined chamber that destroys organics and stabilizes the residuals in a nonleaching, vitrified waste form. This technology will be equally applicable to low-level mixed wastes generated by nuclear utilities. The final waste form will be volume reduced to the maximum extent practical, because all organics will have been destroyed and the inorganics will be in a high-density, low void-space form and little or no volume-increasing glass makers will have been added. Low volume and high integrity waste forms result in low disposal costs. This project is structured to ensure that the plasma technology can be successfully employed in radioactive service. The PHP technology will be developed into a production system through a sequence of tests on several test units, both non-radioactive and radioactive. As the final step, a prototype PHP system will be constructed for full-scale radioactive waste treatment demonstration

  15. The ORNL (Oak Ridge National Laboratory)/Y-12 sludge detoxification demonstration project

    International Nuclear Information System (INIS)

    Padgett, D.G.

    1988-01-01

    A wide variety of mixed waste streams exist at DOE facilities nation-wide. Currently, most of these wastes are being stored in permitted facilities while methodologies are being developed to handle, treat and dispose of these wastes. The purpose of this demonstration project, conducted at Martin Marietta's K-25 Facility in July and August of 1988, was to gather data on the technical and/or economic feasibility of applying an innovative, experimental technology to the treatment of a mixed waste stream. Specifically the goal of the demonstration is to treat a listed hazardous waste containing depleted uranium and other trace isotopes in such a fashion as to produce a product which could subsequently be delisted and disposed of under current burial practices. This paper describes the methodology used in conducting the demonstration and the technology which was employed

  16. Opportunities for low-cost CO2 storage demonstration projects in China

    International Nuclear Information System (INIS)

    Meng, Kyle C.; Williams, Robert H.; Celia, Michael A.

    2007-01-01

    Several CO 2 storage demonstration projects are needed in a variety of geological formations worldwide to prove the viability of CO 2 capture and storage as a major option for climate change mitigation. China has several low-cost CO 2 sources at sites that produce NH 3 from coal via gasification. At these plants, CO 2 generated in excess of the amount needed for other purposes (e.g., urea synthesis) is vented as a relatively pure stream. These CO 2 sources would potentially be economically interesting candidates for storage demonstration projects if there are suitable storage sites nearby. In this study a survey was conducted to estimate CO 2 availability at modern Chinese coal-fed ammonia plants. Results indicate that annual quantities of available, relatively pure CO 2 per site range from 0.6 to 1.1 million tonnes. The CO 2 source assessment was complemented by analysis of possible nearby opportunities for CO 2 storage. CO 2 sources were mapped in relation to China's petroliferous sedimentary basins where prospective CO 2 storage reservoirs possibly exist. Four promising pairs of sources and sinks were identified. Project costs for storage in deep saline aquifers were estimated for each pairing ranging from $15-21/t of CO 2 . Potential enhanced oil recovery and enhanced coal bed methane recovery opportunities near each prospective source were also considered

  17. Waste Energy Recovery from Natural Gas Distribution Network: CELSIUS Project Demonstrator in Genoa

    Directory of Open Access Journals (Sweden)

    Davide Borelli

    2015-12-01

    Full Text Available Increasing energy efficiency by the smart recovery of waste energy is the scope of the CELSIUS Project (Combined Efficient Large Scale Integrated Urban Systems. The CELSIUS consortium includes a world-leading partnership of outstanding research, innovation and implementation organizations, and gather competence and excellence from five European cities with complementary baseline positions regarding the sustainable use of energy: Cologne, Genoa, Gothenburg, London, and Rotterdam. Lasting four-years and coordinated by the City of Gothenburg, the project faces with an holistic approach technical, economic, administrative, social, legal and political issues concerning smart district heating and cooling, aiming to establish best practice solutions. This will be done through the implementation of twelve new high-reaching demonstration projects, which cover the most major aspects of innovative urban heating and cooling for a smart city. The Genoa demonstrator was designed in order to recover energy from the pressure drop between the main supply line and the city natural gas network. The potential mechanical energy is converted to electricity by a turboexpander/generator system, which has been integrated in a combined heat and power plant to supply a district heating network. The performed energy analysis assessed natural gas saving and greenhouse gas reduction achieved through the smart systems integration.

  18. California Food Processing Industry Wastewater Demonstration Project: Phase I Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, Glen; Atkinson, Barbara; Rhyne, Ivin

    2009-09-09

    Wastewater treatment is an energy-intensive process and electricity demand is especially high during the utilities summer peak electricity demand periods. This makes wastewater treatment facilities prime candidates for demand response programs. However, wastewater treatment is often peripheral to food processing operations and its demand response opportunities have often been overlooked. Phase I of this wastewater demonstration project monitored wastewater energy and environmental data at Bell-Carter Foods, Inc., California's largest olive processing plant. For this monitoring activity the project team used Green Energy Management System (GEMS) automated enterprise energy management (EEM) technologies. This report presents results from data collected by GEMS from September 15, 2008 through November 30, 2008, during the olive harvest season. This project established and tested a methodology for (1) gathering baseline energy and environmental data at an industrial food-processing plant and (2) using the data to analyze energy efficiency, demand response, daily peak load management, and environmental management opportunities at the plant. The Phase I goals were to demonstrate the measurement and interrelationship of electricity demand, electricity usage, and water quality metrics and to estimate the associated CO{sub 2} emissions.

  19. Demonstration project: Oxy-fuel combustion at Callide-A plant

    Energy Technology Data Exchange (ETDEWEB)

    Makino, Keiji; Misawa, Nobuhiro; Kiga, Takashi; Spero, Chris

    2007-07-01

    Oxy-fuel combustion is expected to be one of the promising systems on CO2 recovery from pulverized-coal power plant, and enable the CO2 to be captured in a more cost-effective manner compared to other CO2 recover process. An Australia-Japan consortium was established in 2004 specifically for the purpose of conducting a feasibility study on the application of oxy-fuel combustion to an existing pulverized-coal power plant that is Callide-A power plant No.4 unit at 30MWe owned by CS Energy in Australia. One of the important components in this study has been the recent comparative testing of three Australian coals under both oxy-fuel and air combustion conditions using the IHI combustion test facilities. The tests have yielded a number of important outcomes including a good comparison of normal air with oxy-fuel combustion, significant reduction in NOx mass emission rates under oxy-fuel combustion. On the basis of the feasibility study, the project under Australia-Japan consortium is now under way for applying oxy-fuel combustion to an existing plant by way of demonstration. In this project, a demonstration plant of oxy-fuel combustion will be completed by the end of 2008. This project aims at recovering CO2 from an actual power plant for storage. (auth)

  20. Building a partnership to evaluate school-linked health services: the Cincinnati School Health Demonstration Project.

    Science.gov (United States)

    Rose, Barbara L; Mansour, Mona; Kohake, Kelli

    2005-12-01

    The Cincinnati School Health Demonstration Project was a 3-year collaboration that evaluated school-linked health services in 6 urban elementary (kindergarten to eighth grade) schools. Partners from the Cincinnati Health Department, Cincinnati Public Schools, Cincinnati Children's Hospital Medical Center, and The Health Foundation of Greater Cincinnati wanted to determine if levels of school-linked care made a difference in student quality of life, school connectedness, attendance, emergency department use, and volume of referrals to health care specialists. School nurses, principals and school staff, parents and students, upper-level managers, and health service researchers worked together over a 2.5-year period to learn about and use new technology to collect information on student health, well-being, and outcome measures. Varying levels of school health care intervention models were instituted and evaluated. A standard model of care was compared with 2 models of enhanced care and service. The information collected from students, parents, nurses, and the school system provided a rich database on the health of urban children. School facilities, staffing, and computer technology, relationship building among stakeholders, extensive communication, and high student mobility were factors that influenced success and findings of the project. Funding for district-wide computerization and addition of school health staff was not secured by the end of the demonstration project; however, relationships among the partners endured and paved the way for future collaborations designed to better serve urban school children in Cincinnati.

  1. Vitrification process testing for reference HWVP waste

    International Nuclear Information System (INIS)

    Perez, J.M. Jr.; Goles, R.W.; Nakaoka, R.K.; Kruger, O.L.

    1991-01-01

    The Hanford Waste Vitrification Plant (HWVP) is being designed to vitrify high-level radioactive wastes stored on the Hanford site. The vitrification flow-sheet is being developed to assure the plant will achieve plant production requirements and the glass product will meet all waste form requirements for final geologic disposal. The first Hanford waste to be processed by the HWVP will be a neutralized waste resulting from PUREX fuel reprocessing operations. Testing is being conducted using representative nonradioactive simulants to obtain process and product data required to support design, environmental, and qualification activities. Plant/process criteria, testing requirements and approach, and results to date will be presented

  2. Task 27 -- Alaskan low-rank coal-water fuel demonstration project

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    Development of coal-water-fuel (CWF) technology has to-date been predicated on the use of high-rank bituminous coal only, and until now the high inherent moisture content of low-rank coal has precluded its use for CWF production. The unique feature of the Alaskan project is the integration of hot-water-drying (HWD) into CWF technology as a beneficiation process. Hot-water-drying is an EERC developed technology unavailable to the competition that allows the range of CWF feedstock to be extended to low-rank coals. The primary objective of the Alaskan Project, is to promote interest in the CWF marketplace by demonstrating the commercial viability of low-rank coal-water-fuel (LRCWF). While commercialization plans cannot be finalized until the implementation and results of the Alaskan LRCWF Project are known and evaluated, this report has been prepared to specifically address issues concerning business objectives for the project, and outline a market development plan for meeting those objectives.

  3. Virginia Demonstration Project Encouraging Middle School Students in Pursuing STEM Careers

    Science.gov (United States)

    Bachman, Jane T.; Kota, Dena H.; Kota, Aaron J.

    2011-01-01

    Encouraging students at all grade levels to consider pursuing a career in Science, Technology, Engineering, and Mathematics (STEM) fields i s a national focus. In 2005, the Naval Surface Warfare Center, Dahlgren Division (NSWCDD), a Department of Defense laboratory located in Da hlgren, Virginia, began work on the Virginia Demonstration Project (VDP) with the goal of increasing more student interest in STEM educatio n and pursuing STEM careers. This goal continues as the program enters its sixth year. This project has been successful through the partici pation of NSWCDD's scientists and engineers who are trained as mentor s to work in local middle school classrooms throughout the school year, As an extension of the in-class activities, several STEM summer aca demies have been conducted at NSWCDD, These academies are supported by the Navy through the VDP and the STEM Learning Module Project. These projects are part of more extensive outreach efforts offered by the National Defense Education Program (NDEP), sponsored by the Director, Defense Research and Engineering. The focus of this paper is on the types of activities conducted at the summer academy, an overview of the academy planning process, and recommendations to help support a nati onal plan of integrating modeling and simulation-based engineering and science into all grade levels. based upon the lessons learned

  4. Rural interdisciplinary mental health team building via satellite: a demonstration project.

    Science.gov (United States)

    Cornish, Peter A; Church, Elizabeth; Callanan, Terrence; Bethune, Cheri; Robbins, Carl; Miller, Robert

    2003-01-01

    This paper reports on the results of a demonstration project that examined the role of telehealth/telemedicine (hereafter referred to as telehealth) in providing interdisciplinary mental health training and support to health professionals in a rural region of Atlantic Canada. Special emphasis was placed on addressing the question of how training might affect interdisciplinary collaboration among the rural health professionals. Five urban mental health professionals from three disciplines provided training and support via video-satellite and internet, print and video resources to 34 rural health and community professionals. In order to assess the rural community's needs and the impact of the interventions, questionnaires were administered and on-site interviews were conducted before and after the project. Throughout the project, field notes were recorded and satisfaction ratings were obtained. Satisfaction with the video-satellite presentations was high and stable, with the exception of one session when signal quality was very poor. Rural participants were most satisfied with opportunities for interaction and least satisfied with the variable quality of the video transmission signal. High staff turnover among rural professionals resulted in insufficient power to permit statistical analysis. Positive reports of the project impact included expanded knowledge and heightened sensitivity to mental health issues, increased cross-disciplinary connections, and greater cohesion among professionals. The results suggest that, with some refinements, telehealth technology can be used to facilitate mental health training and promote interdisciplinary collaboration among professionals in a rural setting.

  5. Hanford Waste Vitrification Plant technical manual

    Energy Technology Data Exchange (ETDEWEB)

    Larson, D.E. [ed.; Watrous, R.A.; Kruger, O.L. [and others

    1996-03-01

    A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version.

  6. Hanford Waste Vitrification Plant technical manual

    International Nuclear Information System (INIS)

    Larson, D.E.; Watrous, R.A.; Kruger, O.L.

    1996-03-01

    A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version

  7. Technical support to the Solvent Refined Coal (SRC) demonstration projects: assessment of current research and development

    Energy Technology Data Exchange (ETDEWEB)

    Edwards, M.S.; Rodgers, B.R.; Brown, C.H.; Carlson, P.K.; Gambill, W.R.; Gilliam, T.M.; Holmes, J.M.; Krishnan, R.P.; Parsly, L.F.

    1980-12-01

    A program to demonstrate Solvent Refined Coal (SRC) technology has been initiated by the US Department of Energy (DOE) in partnership with two industrial groups. Project management responsibility has been assigned to the Oak Ridge Operations Office (ORO) of DOE. ORO requested that the Oak Ridge National Laboratory assess current research and development (R and D) activities and develop recommendations for those activities that might contribute to successful completion of the SRC demonstration plant projects. The objectives of this final report are to discuss in detail the problem areas in SRC; to discuss the current and planned R and D investigations relevant to the problems identified; and to suggest appropriate R and D activities in support of designs for the SRC demonstration plants. Four types of R and D activities are suggested: continuation of present and planned activities; coordination of activities and results, present and proposed; extension/redirection of activities not involving major equipment purchase or modifications; and new activities. Important examples of the first type of activity include continuation of fired heater, slurry rheology, and slurry mixing studies at Ft. Lewis. Among the second type of activity, coordination of data acquisition and interpretation is recommended in the areas of heat transfer, vapor/liquid equilibria, and physical properties. Principal examples of recommendations for extension/redirection include screening studies at laboratory scale on the use of carbonaceous precoat (e.g., anthracite) infiltration, and 15- to 30-day continuous tests of the Texaco gasifier at the Texaco Montebello facility (using SRC residues).

  8. Public demonstration projects and field trials: Accelerating commercialisation of sustainable technology in solar photovoltaics

    International Nuclear Information System (INIS)

    Brown, James; Hendry, Chris

    2009-01-01

    The paper considers the role of government funded demonstration projects and field trials (DTs) in accelerating the commercialisation of new energy technologies that meet a public good but do not have immediate market appeal [Sagar, A.D., van der Zwaan, B., 2006. Technological innovation in the energy sector: R and D, deployment, and learning-by-doing. Energy Policy 34, 2601-2608]. Drawing on an original database of DTs in the EU, Japan and USA from 1973 to 2004, we review the history of DTs in photovoltaic technology for electricity generation, and its subsequent take up as a commercial energy source. We find that DTs that are aimed purely at discovering suitable market opportunities are less successful in achieving diffusion than projects that target a particular application and concentrate resources on it. The former nevertheless have a vital role to play in the learning process, while a targeted focus is often dependent on national industrial and institutional factors.

  9. Explosives disposal demonstration projects. Progress report, April 12, 1995--June 30, 1995

    International Nuclear Information System (INIS)

    Charbeneau, R.

    1995-01-01

    This report contains quarterly reports on two projects. The first is undertaking the environmental restoration at the Pantex Plant. Research objectives are organized under four general tasks: field testing and produced water treatment, bioremediation of contaminated groundwater and soils, vadose zone remediation, and chromium remediation. The other project goal is to demonstrate generation of diamond by explosive compression of Carbon 60 and Carbon 70 and mixtures of these fullerenes. The intent is to exploit expertise developed by Pantex and other DOE Laboratories in the area of understanding and modeling of explosive compression for initiation of nuclear fission reactions to explosively compress carbon in the form of fullerenes with the goal of transforming the material into the diamond phase

  10. The public visits a nuclear waste site: Survey results from the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Hoffman, W.D.

    1987-01-01

    This paper discusses the results of the 1986 survey taken at the West Valley Demonstration Project Open House where a major nuclear waste cleanup is in progress. Over 1400 people were polled on what they think is most effective in educating the public on nuclear waste. A demographic analysis describes the population attending the event and their major interests in the project. Responses to attitudinal questions are examined to evaluate the importance of radioactive waste cleanup as an environmental issue and a fiscal responsibility. Additionally, nuclear power is evaluated on its public perception as an energy resource. The purpose of the study is to find out who visits a nuclear waste site and why, and to measure their attitudes on nuclear issues

  11. Training Teens to Teach Agricultural Biotechnology: A National 4-H Science Demonstration Project

    Directory of Open Access Journals (Sweden)

    Chad Ripberger

    2013-12-01

    Full Text Available This article discusses a National 4-H Science agricultural biotechnology demonstration project and the impact of the pilot programs on the teenage leaders and teachers. A total of 82 teenagers were extensively trained, who in turn, engaged 620 youth participants with agricultural biotechnology education in afterschool and summer programs in five states. This article details the national and state level trainings for these teen teachers as well as the content rich partners from agribusinesses, agricultural commodity groups, and universities who supported their involvement. The impact on the content knowledge, science process and life skills, and program development and implementation skills of the teen leaders and teachers was evaluated using multiple instruments over multiple administrations (pre-training, post-training, and post-teaching. Results indicate significant gains in most areas assessed. Project recommendations and future plans are also discussed.

  12. Bavarian liquid hydrogen bus demonstration project - safety, licensing and acceptability aspects

    Energy Technology Data Exchange (ETDEWEB)

    Wurster, R.; Knorr, H.; Pruemm, W.

    1999-07-01

    A regular 12 m city bus of the MAN SL 202 type with an internal combustion engine adapted to hydrogen operation and auxiliary gasoline operation was demonstrated in the Bavarian cities of Erlangen and Munich between April 1996 and August 1998. Three bus operators, Erlanger Stadtwerke, Stadtwerke Muenchen and Autobus Oberbayern were testing the bus in three different operating schemes. In order to be able to perform this worldwide first public demonstration of a liquid hydrogen (LH{sub 2}) city bus in regular service, several requirements with respect to safety, licensing, training and acceptability had to be fulfilled. These activities were focusing mainly on the hydrogen specific issues such as (a) integration of onboard LH{sub 2} storage vessels, piping and instrumentation, (b) implementation of storage and refueling infrastructure in the operators' yards, (c) adaptation of the maintenance garages, (d) training of operating and maintenance personnel. During phase II of the demonstration activity a poll was performed on passengers traveling onboard the hydrogen-powered city bus in order to determined the level of acceptance among the users of the bus. The bus was designed and manufactured by MAN Nutzfahrzeuge Aktiengesellschaft. The cryogenic fuel storage and the refueling equipment were designed and manufactured by Linde AG. The realization of the hardware was financially supported by the European Commission (EC) within the Euro-Quebec Hydro-Hydrogen Pilot Project. The demonstration phase was financially supported by EC and the Bavarian State Government. Ludwig-Boelkow-Systemtechnik performed project monitoring for both funding organizations. The presentation will summarize the most important results of this demonstration phase and will address the measures undertaken in order to get the bus, the refueling infrastructure and the maintenance and operating procedures approved by the relevant authorities.

  13. RIMAP demonstration project. Risk-based life management of piping system in power plant Heilbronn

    International Nuclear Information System (INIS)

    Bareiss, J.; Buck, P.; Matschecko, B.; Jovanovic, A.; Balos, D.; Perunicic, M.

    2004-01-01

    In the framework of EU project RIMAP [Risk Based Inspection and Maintenance Procedures for European Industry (2000)] a new European Guideline for optimized risk based maintenance and inspection planning of industrial plants (RBLM, Risk Based Life Management) is being developed. The RIMAP project consists of the three clustered projects: - development (RTD); - demonstration (DEMO): - thematic network (TN). Current work and future, planned work in RIMAP demonstration project on applications of the RIMAP methodology in power plants are presented briefly in the first part of the paper. Also presented in the paper are the results of a preliminary analysis of piping system in power plant Heilbronn using the concept of risk-based monitoring as part of overall concept of risk-based life management. Shortly the following issues are discussed in the paper: - identification of critical components; - application of a multilevel risk analysis (...from 'screening' to 'detailed analysis'); - determination of PoF (Probability of Failure); - determination of CoF (Consequence of Failure); - optimation of inspection and maintenance plan. From our experience with the application of the RIMAP methodology the following conclusions can be drawn: The use of risk-based methods in inspection and maintenance of piping systems in power plants gives transparency to the decision making process and gives an optimized maintenance policy based on current state of the components. The results of the work clearly show the power of the proposed method for concentration on critical items: out of 64 monitored components 5 were selected for intermediate analysis and only 1 for the detailed analysis (probabilistic high temperature fracture mechanics)

  14. Environmental assessment for the Waste Water Treatment Facility at the West Valley Demonstration Project and finding of no significant impact

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-31

    The possible environmental impacts from the construction and operation of a waste water treatment facility for the West Valley Demonstration Project are presented. The West Valley Project is a demonstration project on the solidification of high-level radioactive wastes. The need for the facility is the result of a rise in the work force needed for the project which rendered the existing sewage treatment plant incapable of meeting the nonradioactive waste water treatment needs.

  15. Environmental assessment for the Waste Water Treatment Facility at the West Valley Demonstration Project and finding of no significant impact

    International Nuclear Information System (INIS)

    1992-01-01

    The possible environmental impacts from the construction and operation of a waste water treatment facility for the West Valley Demonstration Project are presented. The West Valley Project is a demonstration project on the solidification of high-level radioactive wastes. The need for the facility is the result of a rise in the work force needed for the project which rendered the existing sewage treatment plant incapable of meeting the nonradioactive waste water treatment needs

  16. Obesity does not aggravate vitrification injury in mouse embryos: a prospective study

    Directory of Open Access Journals (Sweden)

    Ma Wenhong

    2012-08-01

    Full Text Available Abstract Background Obesity is associated with poor reproductive outcomes, but few reports have examined thawed embryo transfer in obese women. Many studies have shown that increased lipid accumulation aggravates vitrification injury in porcine and bovine embryos, but oocytes of these species have high lipid contents (63 ng and 161 ng, respectively. Almost nothing is known about lipids in human oocytes except that these cells are anecdotally known to be relatively lipid poor. In this regard, human oocytes are considered to be similar to those of the mouse, which contain approximately 4 ng total lipids/oocyte. To date, no available data show the impact of obesity on vitrification in mouse embryos. The aim of this study was to establish a murine model of maternal diet-induced obesity and to characterize the effect of obesity on vitrification by investigating the survival rate and embryo developmental competence after thawing. Methods Prospective comparisons were performed between six–eight-cell embryos from obese and normal-weight mice and between fresh and vitrified embryos. Female C57BL/6 mice were fed standard rodent chow (normal-weight group or a high-fat diet (obese group for 6 weeks. The mice were mated, zygotes were collected from oviducts and cultured for 3 days, and six–eight-cell embryos were then selected to assess lipid content in fresh embryos and to evaluate differences in apoptosis, survival, and development rates in response to vitrification. Results In fresh embryos from obese mice, the lipid content (0.044 vs 0.030, Pvs.9.3%, Pvs. 93.1%, P Conclusions This study demonstrated that differences in survival and developmental rates between embryos from obese and normal-weight mice were eliminated after vitrification. Thus, maternal obesity does not aggravate vitrification injury, but obesity alone greatly impairs pre-implantation embryo survival and development.

  17. Elder mediation in theory and practice: study results from a national caregiver mediation demonstration project.

    Science.gov (United States)

    Crampton, Alexandra

    2013-01-01

    Mediation is a process through which a third party facilitates discussion among disputing parties to help them identify interests and ideally reach an amicable solution. Elder mediation is a growing subspecialty to address conflicts involving older adults, primarily involving caregiving or finances. Mediation is theorized to empower participants but critics argue that it can exacerbate power imbalances among parties and coerce consensus. These contested claims are examined through study of a national caregiver mediation demonstration project. Study implications underscore the importance of gerontological social work expertise to ensure the empowerment of vulnerable older adults in mediation sessions.

  18. Design, construction, and operation of the contact size reduction facility at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Frank, D.E.; Reeves, S.R.; Valenti, P.J.

    1988-05-01

    This paper describes the design, construction and initial operation of the Contact-Handled Size Reduction Facility (CSRF) at the West Valley Demonstration Project. The facility was constructed to size reduce contaminated tanks, piping, and other metallic scrap and package the scrap for disposal. In addition, the CSRF has the capability to decontaminate scrap prior to disposal. The anticipated result of decontaminating the scrap is to reduce waste classified as transuranic or low-level Class B and C to Class A or release for unrestricted use as nonradioactive equipment. 10 figs., 1 tab

  19. The Role of Occupant Behavior in Achieving Net Zero Energy: A Demonstration Project at Fort Carson

    Energy Technology Data Exchange (ETDEWEB)

    Judd, Kathleen S.; Sanquist, Thomas F.; Zalesny, Mary D.; Fernandez, Nicholas

    2013-09-30

    This study, sponsored by the U.S. General Services Administration’s Office of Federal High-Performance Green Buildings, aimed to understand the potential for institutional and behavioral change to enhance the performance of buildings, through a demonstration project with the Department of Defense in five green buildings on the Fort Carson, Colorado, Army base. To approach this study, the research team identified specific occupant behaviors that had the potential to save energy in each building, defined strategies that might effectively support behavior change, and implemented a coordinated set of actions during a three-month intervention.

  20. Post Irradiation Examination Plan for High-Burnup Demonstration Project Sister Rods

    Energy Technology Data Exchange (ETDEWEB)

    Scaglione, John M [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Montgomery, Rose [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Bevard, Bruce Balkcom [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-04-01

    This test plan describes the experimental work to be implemented by the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE) to characterize high burnup (HBU) spent nuclear fuel (SNF) in conjunction with the High Burnup Dry Storage Cask Research and Development Project and serves to coordinate and integrate the multi-year experimental program to collect and develop data regarding the continued storage and eventual transport of HBU (i.e., >45 GWd/MTU) SNF. The work scope involves the development, performance, technical integration, and oversight of measurements and collection of relevant data, guided by analyses and demonstration of need.