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Sample records for barnwell fuel processing plant

  1. Barnwell Nuclear Fuels Plant applicability study. Volume III. Appendices

    International Nuclear Information System (INIS)

    Volume III suppliees supporting information to assist Congress in making a decision on the optimum utilization of the Barnwell Nuclear Fuels Plant. Included are applicable fuel cycle policies; properties of reference fuels; description and evaluation of alternative operational (flue cycle) modes; description and evaluation of safeguards systems and techniques; description and evaluation of spiking technology; waste and waste solidification evaluation; and Department of Energy programs relating to nonproliferation

  2. Study of the potential uses of the Barnwell Nuclear Fuel Plant (BNFP). Final report

    Energy Technology Data Exchange (ETDEWEB)

    1980-03-25

    The purpose of this study is to provide an evaluation of possible international and domestic uses for the Barnwell Nuclear Fuel Plant, located in South Carolina, at the conclusion of the International Nuclear Fuel Cycle Evaluation. Four generic categories of use options for the Barnwell plant have been considered: storage of spent LWR fuel; reprocessing of LWR spent fuel; safeguards development and training; and non-use. Chapters are devoted to institutional options and integrated institutional-use options.

  3. Study of the potential uses of the Barnwell Nuclear Fuel Plant (BNFP). Final report

    International Nuclear Information System (INIS)

    The purpose of this study is to provide an evaluation of possible international and domestic uses for the Barnwell Nuclear Fuel Plant, located in South Carolina, at the conclusion of the International Nuclear Fuel Cycle Evaluation. Four generic categories of use options for the Barnwell plant have been considered: storage of spent LWR fuel; reprocessing of LWR spent fuel; safeguards development and training; and non-use. Chapters are devoted to institutional options and integrated institutional-use options

  4. Spent-fuel-storage studies at the Barnwell Nuclear Fuel Plant. Studies and research concerning BNFP

    International Nuclear Information System (INIS)

    This report contains the results of various studies and demonstrations related to advanced spent-fuel-storage techniques which were performed at the Barnwell Nuclear Fuel Plant (BNFP) in 1982. The demonstrations evaluated various technical aspects of fuel disassembly and canning and dry-storage techniques. The supporting studies examined thermal limitations and criticality concerns

  5. Studies and research concerning BNFP: evaluation of spent-fuel-examination techniques for the Barnwell Nuclear Fuel Plant

    International Nuclear Information System (INIS)

    A study was made of various examinations which could be remotely performed on a production basis with spent fuel at the Barnwell Nuclear Fuel Plant (BNFP). These techniques could form an integral portion of fuel disassembly and canning operations. Their benefits accrue to either improved fuel storage, reprocessing, or both. In conjunctoin with these studies, evaluations have been made of the operational impact of receiving failed or canned fuel at the BNFP

  6. Considerations for handling failed fuel at the Barnwell Nuclear Fuel Plant

    International Nuclear Information System (INIS)

    The impact of failed fuel receipt on reprocessing operations is qualitatively described. It appears that extended storage of fuel, particularly with advanced storage techniques, will increase the quantity of failed fuel, the nature and possibly the configuration of the fuel. The receipt of failed fuel at the BNFP increases handling problems, waste volumes, and operator exposure. If it is necessary to impose special operating precautions to minimize this impact, a loss in plant throughput will result. Hence, ideally, the reprocessing plant operator would take every reasonable precaution so that no failed fuel is received. An alternative policy would be to require that failed fuel be placed in a sealed canister. In the latter case the canister must be compatible with the shipping cask and suitable for in-plant storage. A required inspection of bare fuel would be made at the reactor prior to shipping off-site. This would verify fuel integrity. These requirements are obviously idealistic. Due to the current uncertain status of reprocessing and the need to keep reactors operating, business or governmental policy may be enacted resulting in the receipt of a negotiated quantity of non-standard fuel (including failed fuel). In this situation, BNFP fuel receiving policy based soley on fuel cladding integrity would be difficult to enforce. There are certain areas where process incompatibility does exist and where a compromise would be virtually impossible, e.g., canned fuel for which material or dimensional conflicts exist. This fuel would have to be refused or the fuel would require recanning prior to shipment. In other cases, knowledge of the type and nature of the failure may be acceptable to the operator. A physical inspection of the fuel either before shipment or after the cask unloading operation would be warranted. In this manner, concerns with pool contamination can be identified and the assembly canned if deemed necessary

  7. Studies and research concerning BNFP. Nuclear transportation studies related to use of the Barnwell Nuclear Fuel Plant

    International Nuclear Information System (INIS)

    It will be necessary to transport radioactive material on a routine basis if the Barnwell Nuclear Fuel Plant (BNFP) is to be utilized. This report examines the current and projected status of transport of high-level nuclear material, with particular application directed toward the operation of the BNFP. The current domestic US status is one of comparative inactivity in the movement of utility spent fuel. Pending the successful disposition of fuel cycle options such as either Away-from-Reactor (AFR) storage or reprocessing, spent fuel transport to the BNFP will be dormant through the mid-1980's. If fuel movement is initiated, the primary areas of concern will be the maze of local, state, and federal regulations on routing, the availability of spent fuel casks, and the logistic concerns of fuel loading and unloading capability at the reactor and the BNFP. The report examines the application of overweight truck (OWT) shipments of spent fuel casks patterned on current European practice. Overweight shipments, whether by truck or intermodal movement (rail or barge combined with truck shipment), can have a significant impact on resolving logistics problems. It seems obvious from our studies that OWT casks will be utilized, along with legal weight truck and rail shipment. Water transport was also examined. It appears that this mode will only be used in the event that highway and rail problems are insuperable

  8. Spent fuel disassembly and canning programs at the Barnwell Nuclear Fuel Plant (BNFP)

    International Nuclear Information System (INIS)

    Methods of disassembling and canning spent fuel to allow more efficient storage are being investigated at the BNFP. Studies and development programs are aimed at dry disassembly of fuel to allow storage and shipment of fuel pins rather than full fuel assemblies. Results indicate that doubling existing storage capacity or tripling the carrying capacity of existing transportation equipment is achievable. Disassembly could be performed in the BNFP hot cells at rates of about 12 to 15 assemblies per day

  9. Spent fuel disassembly and canning programs at the Barnwell Nuclear Fuel Plant (BNFP)

    International Nuclear Information System (INIS)

    Methods of disassembling and canning spent fuel to allow more efficient storage are being investigated at the BNFP. Studies and development programs are aimed at dry disassembly of fuel to allow storage and shipment of fuel pins rather than complete fuel assemblies. Results indicate that doubling existing storage capacity or tripling the carrying capacity of existing transportation equipment is achievable. Disassembly could be performed in the BNFP hot cells at rates of about 12 to 15 assemblies per day

  10. Studies and research concerning BNFP. Spent fuel disassembly: increasing hot-cell storage capacity at the Barnwell Nuclear Fuel Plant

    International Nuclear Information System (INIS)

    This report presents the results of work performed at AGNS in 1979 related to production-rate fuel disassembly in the existing hot cell spaces of the BNFP. The primary advantage of the developed technique is realized at a reprocessing plant facility where suitable hot cells and connecting storage pools are available. The existing spent fuel pools are also candidates for away-from-reactor (AFR) storage space. Storage estimates based on utilization of the BNFP indicate that a major expansion from 1600 MTU up to 3000 MTU is possible. The report presents data on the results of initial process development and prototype equipment testing. Assessments were made of operational safety, licensing, and economic factors. These studies indicate that the techniques are performable and have economic merit when there is a requirement for a large increment of new storage capacity. A development program plan is presented. This plan delineates the future work required to bring the process to a point where implementation is possible

  11. Studies and research concerning BNFP: spent fuel disassembly and canning programs at the Barnwell Nuclear Fuel Plant (BNFP)

    International Nuclear Information System (INIS)

    Methods of disassembling and canning spent fuel to allow more efficient storage are being investigated at the BNFP. Studies and development programs are aimed at dry disassembly of fuel to allow storage and shipment of fuel pins rather than complete fuel assemblies. Results indicate that doubling existing storage capacity or tripling the carrying capacity of existing transportation equipment is achievable. Disassembly could be performed in the BNFP hot cells at rates of about 12 to 15 assemblies per day

  12. Final environmental statement related to the operation of the Barnwell Fuel Receiving and Storage Station (Docket No. 70-1729)

    International Nuclear Information System (INIS)

    The proposed action is to issue a materials license, pursuant to 10 CFR Parts 30, 40 and 70 of the Commission's regulations, authorizing Allied-General Nuclear Services to receive and handle fuel casks containing spent reactor fuel elements and to store spent reactor fuel at the Barnwell Nuclear Fuel Plant (BNFP), in the Barnwell Fuel Receiving and Storage Station (BFRSS). The BFRSS is a part of, and contiguous to, the BNFP-Separations Facility which is being constructed on a small portion of a 1700 acre site about six miles west of the city of Barnwell in Barnwell County, South Carolina. Construction of the BFRSS facility has been completed and the BNFP Separations Facility is more than 90% complete. A uranium Hexafluoride Facility is being constructed on the same site, and a Plutonium Product Facility is proposed to be constructed adjacent to the Separations Facility. The license that is the subject of this action will, if issued, allow lthe use of the BFRSS separate4 from the operation of the Separations Facility. Impacts resulting from the construction of the BFRSS have already occurred and mitigating measures have been and are being implemented to offset any adverse impacts. Operation of the BFRSS will not interfere with water sources, and should cause no noticeable damage to the terrestrial or aquatic environments. Operating experience at other fuel receiving and storage facilities has shown that radioactive concentrations discharged to the environs (the more significant process effluents) have been well below applicabhle state and federal limits. The small quantities to be released during operation of the BFRSS will result in negligible environmental impact. 20 figs

  13. Construction and operation of Barnwell Nuclear Fuel Plant. Draft supplement No. 1 to the final environmental statement

    International Nuclear Information System (INIS)

    This supplement treats combined impacts of all BNFP facilities, combined impacts with other facilities, and information which became available since FES publication. A total of about 80 acres of the 1706-acre site will be occupied by plant facilities; about 315 acres will be cleared. An employment peak of 2900 people is estimated, with 2000 being temporary construction personnel. The facilities will draw 4700 gpm from the Tuscaloosa aquifer and then release to Lower Three Runs Creek after holdup. Max annual total-body dose to an individual living at the site boundary is estimated 4.6 mRem, of which 4.5 mRem would be from BNFP releases; that to all people living within a 50-mile radius is 530 man-Rem (350 man-Rem from BNFP). Additional systems for reducing 85Kr, 14C, or tritium emissions is not justified

  14. Development of a computerized nuclear materials control and accounting system for a fuel reprocessing plant

    International Nuclear Information System (INIS)

    A computerized nuclear materials control and accounting system (CNMCAS) for a fuel reprocessing plant is being developed by Allied-General Nuclear Services at the Barnwell Nuclear Fuel Plant. Development work includes on-line demonstration of near real-time measurement, measurement control, accounting, and processing monitoring/process surveillance activities during test process runs using natural uranium. A technique for estimating in-process inventory is also being developed. This paper describes development work performed and planned, plus significant design features required to integrate CNMCAS into an advanced safeguards system

  15. Barnwell Nuclear Fuel Plant. License application, amendment 10

    International Nuclear Information System (INIS)

    Amendment No. 10 provides the applicant's responses to questions raised by the AEC in letters dated November 6 and December 5, 1974. Amendment No. 3, dated February 1975, to the BNFP Separations Facility Final Safety Analysis Report (FSAR) is included. The amendment consists of revision pages for volumes 1 through 5 of the FSAR along with a deletion and insertion guide. (U.S.)

  16. Barnwell Nuclear Fuel Plant. License application, FSAR, amendment 6

    International Nuclear Information System (INIS)

    FSAR Amendment No. 6 consists principally of revisions of the portions relating to: (1) facilities for the interim storage of solid waste, (2) handling of spent iodine scrubber solutions, and (3) the rise of N2O4 as an oxidizer. (LK)

  17. License restrictions at Barnwell

    Energy Technology Data Exchange (ETDEWEB)

    Autry, V.R. [S.C. Dept. of Health and Environmental Control, Columbia, SC (United States). Bureau of Radiological Health

    1991-12-31

    The State of South Carolina was delegated the authority by the US Nuclear Regulatory Commission to regulate the receipt, possession, use and disposal of radioactive material as an Agreement State. Since 1970, the state has been the principal regulatory authority for the Barnwell Low-Level Waste Disposal Facility operated by Chem-Nuclear Systems, Inc. The radioactive material license issued authorizing the receipt and disposal of low-level waste contains numerous restrictions to ensure environmental protection and compliance with shallow land disposal performance criteria. Low-level waste has evolved from minimally contaminated items to complex waste streams containing high concentrations of radionuclides and processing chemicals which necessitated these restrictions. Additionally, some waste with their specific radionuclides and concentration levels, many classified as low-level radioactive waste, are not appropriate for shallow land disposal unless additional precautions are taken. This paper will represent a number of these restrictions, the rationale for them, and how they are being dealt with at the Barnwell disposal facility.

  18. Laser-based analytical monitoring in nuclear-fuel processing plants

    Energy Technology Data Exchange (ETDEWEB)

    Hohimer, J.P.

    1978-09-01

    The use of laser-based analytical methods in nuclear-fuel processing plants is considered. The species and locations for accountability, process control, and effluent control measurements in the Coprocessing, Thorex, and reference Purex fuel processing operations are identified and the conventional analytical methods used for these measurements are summarized. The laser analytical methods based upon Raman, absorption, fluorescence, and nonlinear spectroscopy are reviewed and evaluated for their use in fuel processing plants. After a comparison of the capabilities of the laser-based and conventional analytical methods, the promising areas of application of the laser-based methods in fuel processing plants are identified.

  19. Standard format and content of license applications for plutonium processing and fuel fabrication plants

    International Nuclear Information System (INIS)

    The standard format suggested for use in applications for licenses to possess and use special nuclear materials in Pu processing and fuel fabrication plants is presented. It covers general description of the plant, summary safety assessment, site characteristics, principal design criteria, plant design, process systems, waste confinement and management, radiation protection, accident safety analysis, conduct of operations, operating controls and limits, and quality assurance

  20. Historic American Engineering Record, Idaho National Laboratory, Idaho Chemical Processing Plant, Fuel Reprocessing Complex

    Energy Technology Data Exchange (ETDEWEB)

    Susan Stacy; Julie Braun

    2006-12-01

    Just as automobiles need fuel to operate, so do nuclear reactors. When fossil fuels such as gasoline are burned to power an automobile, they are consumed immediately and nearly completely in the process. When the fuel is gone, energy production stops. Nuclear reactors are incapable of achieving this near complete burn-up because as the fuel (uranium) that powers them is burned through the process of nuclear fission, a variety of other elements are also created and become intimately associated with the uranium. Because they absorb neutrons, which energize the fission process, these accumulating fission products eventually poison the fuel by stopping the production of energy from it. The fission products may also damage the structural integrity of the fuel elements. Even though the uranium fuel is still present, sometimes in significant quantities, it is unburnable and will not power a reactor unless it is separated from the neutron-absorbing fission products by a method called fuel reprocessing. Construction of the Fuel Reprocessing Complex at the Chem Plant started in 1950 with the Bechtel Corporation serving as construction contractor and American Cyanamid Company as operating contractor. Although the Foster Wheeler Corporation assumed responsibility for the detailed working design of the overall plant, scientists at Oak Ridge designed all of the equipment that would be employed in the uranium separations process. After three years of construction activity and extensive testing, the plant was ready to handle its first load of irradiated fuel.

  1. INNOVATIVE FRESH WATER PRODUCTION PROCESS FOR FOSSIL FUEL PLANTS

    Energy Technology Data Exchange (ETDEWEB)

    James F. Klausner; Renwei Mei; Yi Li; Mohamed Darwish; Diego Acevedo; Jessica Knight

    2003-09-01

    This report describes the annual progress made in the development and analysis of a Diffusion Driven Desalination (DDD) system, which is powered by the waste heat from low pressure condensing steam in power plants. The desalination is driven by water vapor saturating dry air flowing through a diffusion tower. Liquid water is condensed out of the air/vapor mixture in a direct contact condenser. A thermodynamic analysis demonstrates that the DDD process can yield a fresh water production efficiency of 4.5% based on a feed water inlet temperature of only 50 C. An example is discussed in which the DDD process utilizes waste heat from a 100 MW steam power plant to produce 1.51 million gallons of fresh water per day. The main focus of the initial development of the desalination process has been on the diffusion tower. A detailed mathematical model for the diffusion tower has been described, and its numerical implementation has been used to characterize its performance and provide guidance for design. The analysis has been used to design a laboratory scale diffusion tower, which has been thoroughly instrumented to allow detailed measurements of heat and mass transfer coefficient, as well as fresh water production efficiency. The experimental facility has been described in detail.

  2. INNOVATIVE FRESH WATER PRODUCTION PROCESS FOR FOSSIL FUEL PLANTS

    Energy Technology Data Exchange (ETDEWEB)

    James F. Klausner; Renwei Mei; Yi Li; Jessica Knight

    2004-09-01

    An innovative Diffusion Driven Desalination (DDD) process was recently described where evaporation of mineralized water is driven by diffusion within a packed bed. The energy source to drive the process is derived from low pressure condensing steam within the main condenser of a steam power generating plant. Since waste heat is used to drive the process, the main cost of fresh water production is attributed to the energy cost of pumping air and water through the packed bed. This report describes the annual progress made in the development and analysis of a Diffusion Driven Desalination (DDD) system. A combined thermodynamic and dynamic analysis demonstrates that the DDD process can yield a fresh water production of 1.03 million gallon/day by utilizing waste heat from a 100 MW steam power plant based on a condensing steam pressure of only 3'' Hg. Throughout the past year, the main focus of the desalination process has been on the diffusion tower and direct contact condenser. Detailed heat and mass transfer analyses required to size and analyze these heat and mass transfer devices are described. An experimental DDD facility has been fabricated, and temperature and humidity data have been collected over a range of flow and thermal conditions. The analyses agree quite well with the current data and the information available in the literature. Direct contact condensers with and without packing have been investigated. It has been experimentally observed that the fresh water production rate is significantly enhanced when packing is added to the direct contact condensers.

  3. Innovative Fresh Water Production Process for Fossil Fuel Plants

    Energy Technology Data Exchange (ETDEWEB)

    James F. Klausner; Renwei Mei; Yi Li; Jessica Knight; Venugopal Jogi

    2005-09-01

    This project concerns a diffusion driven desalination (DDD) process where warm water is evaporated into a low humidity air stream, and the vapor is condensed out to produce distilled water. Although the process has a low fresh water to feed water conversion efficiency, it has been demonstrated that this process can potentially produce low cost distilled water when driven by low grade waste heat. This report describes the annual progress made in the development and analysis of a Diffusion Driven Desalination (DDD) system. A dynamic analysis of heat and mass transfer demonstrates that the DDD process can yield a fresh water production of 1.03 million gallon/day by utilizing waste heat from a 100 MW steam power plant based on a condensing steam pressure of only 3 Hg. The optimum operating condition for the DDD process with a high temperature of 50 C and sink temperature of 25 C has an air mass flux of 1.5 kg/m{sup 2}-s, air to feed water mass flow ratio of 1 in the diffusion tower, and a fresh water to air mass flow ratio of 2 in the condenser. Operating at these conditions yields a fresh water production efficiency (m{sub fW}/m{sub L}) of 0.031 and electric energy consumption rate of 0.0023 kW-hr/kg{sub fW}. Throughout the past year, the main focus of the desalination process has been on the direct contact condenser. Detailed heat and mass transfer analyses required to size and analyze these heat and mass transfer devices are described. The analyses agree quite well with the current data. Recently, it has been recognized that the fresh water production efficiency can be significantly enhanced with air heating. This type of configuration is well suited for power plants utilizing air-cooled condensers. The experimental DDD facility has been modified with an air heating section, and temperature and humidity data have been collected over a range of flow and thermal conditions. It has been experimentally observed that the fresh water production rate is enhanced when air

  4. Distillate fuel-oil processing for phosphoric acid fuel-cell power plants

    Energy Technology Data Exchange (ETDEWEB)

    Ushiba, K. K.

    1980-02-01

    The current efforts to develop distillate oil-steam reforming processes are reviewed, and the applicability of these processes for integration with the fuel cell are discussed. The development efforts can be grouped into the following processing approaches: high-temperature steam reforming (HTSR); autothermal reforming (ATR); autothermal gasification (AG); and ultra desulfurization followed by steam reforming. Sulfur in the feed is a key problem in the process development. A majority of the developers consider sulfur as an unavoidable contaminant of distillate fuel and are aiming to cope with it by making the process sulfur-tolerant. In the HTSR development, the calcium aluminate catalyst developed by Toyo Engineering represents the state of the art. United Technology (UTC), Engelhard, and Jet Propulsion Laboratory (JPL) are also involved in the HTSR research. The ATR of distillate fuel is investigated by UTC and JPL. The autothermal gasification (AG) of distillate fuel is being investigated by Engelhard and Siemens AG. As in the ATR, the fuel is catalytically gasified utilizing the heat generated by in situ partial combustion of feed, however, the goal of the AG is to accomplish the initial breakdown of the feed into light gases and not to achieve complete conversion to CO and H/sub 2/. For the fuel-cell integration, a secondary reforming of the light gases from the AG step is required. Engelhard is currently testing a system in which the effluent from the AG section enters the steam-reforming section, all housed in a single vessel. (WHK)

  5. Activity of fuel batches processed through Hanford separations plants, 1944 through 1989

    Energy Technology Data Exchange (ETDEWEB)

    Watrous, R.A.; Wootan, D.W.

    1997-07-29

    This document provides a printout of the ``Fuel Activity Database`` (version U6) generated by the Hanford DKPRO code and transmitted to the Los Alamos National Laboratory for input to their ``Hanford Defined Waste`` model of waste tank inventories. This fuel activity file consists of 1,276 records--each record representing the activity associated with a batch of spent reactor fuel processed by month (or shorter period) through individual Hanford separations plants between 1944 and 1989. Each record gives the curies for 46 key radionuclides, decayed to a common reference date of January 1, 1994.

  6. Design of process cell equipment layout and its associated piping in typical nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Nuclear fuel reprocessing plant processes spent nuclear fuel discharged from the nuclear reactor to separate chemically the uranium and plutonium. Spent nuclear fuel emits radiation due to the presence of fission products, actinides and activation products. The major operation steps in reprocessing plant are dismantling of spent fuel subassemblies, chopping of fuel pins and dissolution in concentrated nitric acid. Subsequently, this solution containing uranium and plutonium, fission products and actinides is subjected to solvent extraction with tributyl phosphate in diluent as solvent for separating uranium and plutonium from fission products and other actinides. In the design of a fuel reprocessing plant, apart from problems associated with conventional chemical process industries such as corrosion, materials handling, industrial and fire safety and economy, specific considerations such as health hazards from radioactivity (radiological safety) and damage to material by radiation are considered. This necessitates the processing of spent fuel inside the shielded process cells (concrete and lead cells) with remote operation and maintenance philosophy to prevent the contamination as well as radiation exposure to the operators and prevention of criticality in process tanks and equipments. Reprocessing plant consists of number of shielded process cells depending on the processing capacity and type of spent fuel handled. Concrete cells and lead cells houses various type of storage tanks, equipments, liquid transfer devices, etc with interconnecting small bore pipe lines for liquid transfer and supply of services, which runs in multiple layers, forming a high density piping inside the cells. In addition to this, cells have remote handling systems and gadgets for remote operation and maintenance wherever required. This paper highlights the design of process cells, its equipment layout and piping in typical reprocessing plant; the suitable material of construction

  7. Innovative Fresh Water Production Process for Fossil Fuel Plants

    Energy Technology Data Exchange (ETDEWEB)

    James F. Klausner; Renwei Mei; Yi Li; Jessica Knight

    2006-09-29

    This project concerns a diffusion driven desalination (DDD) process where warm water is evaporated into a low humidity air stream, and the vapor is condensed out to produce distilled water. Although the process has a low fresh water to feed water conversion efficiency, it has been demonstrated that this process can potentially produce low cost distilled water when driven by low grade waste heat. This report summarizes the progress made in the development and analysis of a Diffusion Driven Desalination (DDD) system. Detailed heat and mass transfer analyses required to size and analyze the diffusion tower using a heated water input are described. The analyses agree quite well with the current data and the information available in the literature. The direct contact condenser has also been thoroughly analyzed and the system performance at optimal operating conditions has been considered using a heated water/ambient air input to the diffusion tower. The diffusion tower has also been analyzed using a heated air input. The DDD laboratory facility has successfully been modified to include an air heating section. Experiments have been conducted over a range of parameters for two different cases: heated air/heated water and heated air/ambient water. A theoretical heat and mass transfer model has been examined for both of these cases and agreement between the experimental and theoretical data is good. A parametric study reveals that for every liquid mass flux there is an air mass flux value where the diffusion tower energy consumption is minimal and an air mass flux where the fresh water production flux is maximized. A study was also performed to compare the DDD process with different inlet operating conditions as well as different packing. It is shown that the heated air/heated water case is more capable of greater fresh water production with the same energy consumption than the ambient air/heated water process at high liquid mass flux. It is also shown that there can be

  8. Modeling of the filling and cooling processes of hot fuel mains in Liquid Fuel Rocket Power Plant (LFRPP)

    Science.gov (United States)

    Prisnyakov, V. F.; Pokrishkin, V. V.; Serebryansky, V. N.

    A mathematical model of heat and mass exchange processes during filling and cooling of hot fuel mains of the Liquid Fuel Rocket Power Plant (LFRPP), which allows to define a mass consumption and distribution of two-phase flow parameters by the length of pipeline. Results of calculations are compared with experimental data, taken during filling of the main with a supply of liquid oxygen from the tank into the combustion chamber. Also, the results of modeling of hydrogen main dynamic characteristics of LFRPP in the same conditions are given.

  9. Fuel-Flexible Combustion System for Refinery and Chemical Plant Process Heaters

    Energy Technology Data Exchange (ETDEWEB)

    Benson, Charles; Wilson, Robert

    2014-04-30

    This project culminated in the demonstration of a full-scale industrial burner which allows a broad range of “opportunity” gaseous fuels to be cost-effectively and efficiently utilized while generating minimal emissions of criteria air pollutants. The burner is capable of maintaining a stable flame when the fuel composition changes rapidly. This enhanced stability will contribute significantly to improving the safety and reliability of burner operation in manufacturing sites. Process heating in the refining and chemicals sectors is the primary application for this burner. The refining and chemical sectors account for more than 40% of total industrial natural gas use. Prior to the completion of this project, an enabling technology did not exist that would allow these energy-intensive industries to take full advantage of opportunity fuels and thereby reduce their natural gas consumption. Opportunity gaseous fuels include biogas (from animal and agricultural wastes, wastewater plants, and landfills) as well as syngas (from the gasification of biomass, municipal solid wastes, construction wastes, and refinery residuals). The primary challenge to using gaseous opportunity fuels is that their composition and combustion performance differ significantly from those of conventional fuels such as natural gas and refinery fuel gas. An effective fuel-flexible burner must accept fuels that range widely in quality and change in composition over time, often rapidly. In Phase 1 of this project, the team applied computational fluid dynamics analysis to optimize the prototype burner’s aerodynamic, combustion, heat transfer, and emissions performance. In Phase 2, full-scale testing and refinement of two prototype burners were conducted in test furnaces at Zeeco’s offices in Broken Arrow, OK. These tests demonstrated that the full range of conventional and opportunity fuels could be utilized by the project’s burner while achieving robust flame stability and very low levels of

  10. Recent studies related to head-end fuel processing at the Hanford PUREX plant

    Energy Technology Data Exchange (ETDEWEB)

    Swanson, J.L.

    1988-08-01

    This report presents the results of studies addressing several problems in the head-end processing (decladding, metathesis, and core dissolution) of N Reactor fuel elements in the Hanford PUREX plant. These studies were conducted over 2 years: FY 1986 and FY 1987. The studies were divided into three major areas: 1) differences in head-end behavior of fuels having different histories, 2) suppression of /sup 106/Ru volatilization when the ammonia scrubber solution resulting from decladding is decontaminated by distillation prior to being discharged, and 3) suitability of flocculating agents for lowering the amount of transuranic (TRU) element-containing solids that accompany the decladding solution to waste. 16 refs., 43 figs.

  11. Krypton-85 health risk assessment for a nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    The risks involved in the routine release of 85Kr from nuclear fuel reprocessing operations to the environment were compared to those resulting from the capture and storage of 85Kr. Instead of releasing the 85Kr to the environment when fuel is reprocessed, it can be captured, immobilized and stored. Two alternative methods of capturing 85Kr (cryogenic distillation and fluorocarbon absorption) and one method of immobilizing the captured gas (ion implantation/sputtering) were theoretically incorporated into a representative fuel reprocessing plant, the Barnwell Nuclear Fuel Plant, even though there are no known plans to start up this facility. Given the uncertainties in the models used to generate lifetime risk numbers (0.02 to 0.027 radiation induced fatal cancers expected in the occupational workforce and 0.017 fatal cancers in the general population), the differences in total risks for the three situations, (i.e., no-capture and two-capture alternatives) cannot be considered meaningful. It is possible that no risks would occur from any of the three situations. There is certainly no reason to conclude that risks from 85Kr routinely released to the environment are greater than those that would result from the other two situations considered. Present regulations mandate recovery and disposal of 85Kr from the off gases of a facility reprocessing spent fuel from commercial sources. Because of the lack of a clear-cut indication that recovery woud be beneficial, it does not seem prudent to burden the facilities with a requirement for 85Kr recovery, at least until operating experience demonstrates the incentive. The probable high aging of the early fuel to be processed and the higher dose resulting from the release of the unregulated 3H and 14C also encourage delaying implementation of the 85Kr recovery in the early plants

  12. Processing of radioactive wastes from long-term fuel store of A-1 nuclear power plant

    International Nuclear Information System (INIS)

    A solidification system was designed for the very special composition of radioactive wastes of non-standard type generated in the A-1 nuclear power plant. The system was tested on laboratory scale and tests under pilot plant conditions have just started. The chemical composition of the intermediate-level wastes is not accurately known but in the routine fuel cycle of nuclear power plants it certainly does not occur. The designed system is based on vitrification, attention mainly being centred on the development of suitable glasses. A detailed presentation is made of the results of the development of lead glasses and glasses with a high titanium content. Tests were made with radioactive samples of wastes and with selected types of glass. An experimental melting facility was built which allows to process a model, i.e., non-radioactive, waste of the A-1 type to a scale of 1:1. Pilot plant experiments on the facility will be followed by the design and construction of a fully operational facility. (Z.M.)

  13. Criticality accident in uranium fuel processing plant. Questionnaires from Research Committee of Nuclear Safety

    International Nuclear Information System (INIS)

    The Research Committee of Nuclear Safety carried out a research on criticality accident at the JCO plant according to statement of president of the Japan Atomic Energy Society on October 8, 1999, of which results are planned to be summarized by the constitutions shown as follows, for a report on the 'Questionnaires of criticality accident in the Uranium Fuel Processing Plant of the JCO, Inc.': general criticality safety, fuel cycle and the JCO, Inc.; elucidation on progress and fact of accident; cause analysis and problem picking-up; proposals on improvement; and duty of the Society. Among them, on last two items, because of a conclusion to be required for members of the Society at discussions of the Committee, some questionnaires were send to more than 1800 of them on April 5, 2000 with name of chairman of the Committee. As results of the questionnaires contained proposals and opinions on a great numbers of fields, some key-words like words were found on a shape of repeating in most questionnaires. As they were thought to be very important nuclei in these two items, they were further largely classified to use for summarizing proposals and opinions on the questionnaires. This questionnaire had a big characteristic on the duty of the Society in comparison with those in the other organizations. (G.K.)

  14. Technology, safety, and costs of decommissioning a reference nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Safety and cost information were developed for the conceptual decommissioning of a fuel reprocessing plant with characteristics similar to the Barnwell Nuclear Fuel Plant. The main process building, spent fuel receiving and storage station, liquid radioactive waste storage tank system, and a conceptual high-level waste-solidification facility were postulated to be decommissioned. The plant was conceptually decommissioned to three decommissioning states or modes; layaway, protective storage, and dismantlement. Assuming favorable work performance, the elapsed time required to perform the decommissioning work in each mode following plant shutdown was estimated to be 2.4 years for layaway, 2.7 years for protective storage, and 5.2 years for dismantlement. In addition to these times, approximately 2 years of planning and preparation are required before plant shutdown. Costs, in constant 1975 dollars, for decommissioning were estimated to be $18 million for layaway, $19 million for protective storage and $58 million for dismantlement. Maintenance and surveillance costs were estimated to be $680,000 per year after layaway and $140,000 per year after protective storage. The combination mode of protective storage followed by dismantlement deferred for 10, 30, and 100 years was estimated to cost $64 million, $67 million and $77 million, respectively, in nondiscounted total 1975 dollars. Present values of these costs give reduced costs as dismantlement is deferred. Safety analyses indicate that radiological and nonradiological safety impacts from decommissioning activities should be small. The 50-year radiation dose commitment to the members of the public from airborne releases from normal decommissioning activities were estimated to be less than 11 man-rem

  15. Technology, safety, and costs of decommissioning a reference nuclear fuel reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, K.J.; Jenkins, C.E.; Rhoads, R.E.

    1977-09-01

    Safety and cost information were developed for the conceptual decommissioning of a fuel reprocessing plant with characteristics similar to the Barnwell Nuclear Fuel Plant. The main process building, spent fuel receiving and storage station, liquid radioactive waste storage tank system, and a conceptual high-level waste-solidification facility were postulated to be decommissioned. The plant was conceptually decommissioned to three decommissioning states or modes; layaway, protective storage, and dismantlement. Assuming favorable work performance, the elapsed time required to perform the decommissioning work in each mode following plant shutdown was estimated to be 2.4 years for layaway, 2.7 years for protective storage, and 5.2 years for dismantlement. In addition to these times, approximately 2 years of planning and preparation are required before plant shutdown. Costs, in constant 1975 dollars, for decommissioning were estimated to be $18 million for layaway, $19 million for protective storage and $58 million for dismantlement. Maintenance and surveillance costs were estimated to be $680,000 per year after layaway and $140,000 per year after protective storage. The combination mode of protective storage followed by dismantlement deferred for 10, 30, and 100 years was estimated to cost $64 million, $67 million and $77 million, respectively, in nondiscounted total 1975 dollars. Present values of these costs give reduced costs as dismantlement is deferred. Safety analyses indicate that radiological and nonradiological safety impacts from decommissioning activities should be small. The 50-year radiation dose commitment to the members of the public from airborne releases from normal decommissioning activities were estimated to be less than 11 man-rem.

  16. Nuclear fuel reprocessing deactivation plan for the Idaho Chemical Processing Plant, Revision 1

    International Nuclear Information System (INIS)

    The decision was announced on April 28, 1992 to cease all United States Department of Energy (DOE) reprocessing of nuclear fuels. This decision leads to the deactivation of all fuels dissolution, solvent extraction, krypton gas recovery operations, and product denitration at the Idaho Chemical Processing Plant (ICPP). The reprocessing facilities will be converted to a safe and stable shutdown condition awaiting future alternate uses or decontamination and decommissioning (D ampersand D). This ICPP Deactivation Plan includes the scope of work, schedule, costs, and associated staffing levels necessary to achieve a safe and orderly deactivation of reprocessing activities and the Waste Calcining Facility (WCF). Deactivation activities primarily involve shutdown of operating systems and buildings, fissile and hazardous material removal, and related activities. A minimum required level of continued surveillance and maintenance is planned for each facility/process system to ensure necessary environmental, health, and safety margins are maintained and to support ongoing operations for ICPP facilities that are not being deactivated. Management of the ICPP was transferred from Westinghouse Idaho Nuclear Company, Inc. (WINCO) to Lockheed Idaho Technologies Company (LITCO) on October 1, 1994 as part of the INEL consolidated contract. This revision of the deactivation plan (formerly the Nuclear Fuel Reprocessing Phaseout Plan for the ICPP) is being published during the consolidation of the INEL site-wide contract and the information presented here is current as of October 31, 1994. LITCO has adopted the existing plans for the deactivation of ICPP reprocessing facilities and the plans developed under WINCO are still being actively pursued, although the change in management may result in changes which have not yet been identified. Accordingly, the contents of this plan are subject to revision

  17. Idaho Chemical Processing Plant Spent Fuel and Waste Management Technology Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-09-01

    The Department of Energy (DOE) has received spent nuclear fuel (SNF) at the Idaho Chemical Processing Plant (ICPP) for interim storage and reprocessing since 1953. Reprocessing of SNF has resulted in an existing inventory of 1.5 million gallons of radioactive sodium-bearing liquid waste and 3800 cubic meters (m{sup 3}) of calcine, in addition to the 768 metric tons (MT) of SNF and various other fuel materials in inventory. To date, the major activity of the ICPP has been the reprocessing of SNF to recover fissile uranium; however, recent changes in world events have diminished the demand to recover and recycle this material. As a result, DOE has discontinued reprocessing SNF for uranium recovery, making the need to properly manage and dispose of these and future materials a high priority. In accordance with the Nuclear Waste Policy Act (NWPA) of 1982, as amended, disposal of SNF and high-level waste (HLW) is planned for a geological repository. Preparation of SNF, HLW, and other radioactive wastes for disposal may include mechanical, physical, and/or chemical processes. This plan outlines the program strategy of the ICPP Spent Fuel and Waste Management Technology Development Program (SF&WMTDP) to develop and demonstrate the technology required to ensure that SNF and radioactive waste will properly stored and prepared for final disposal. Program elements in support of acceptable interim storage and waste minimization include: developing and implementing improved radioactive waste treatment technologies; identifying and implementing enhanced decontamination and decommissioning techniques; developing radioactive scrap metal (RSM) recycle capabilities; and developing and implementing improved technologies for the interim storage of SNF.

  18. Idaho Chemical Processing Plant spent fuel and waste management technology development program plan: 1994 Update

    International Nuclear Information System (INIS)

    The Department of Energy has received spent nuclear fuel (SNF) at the Idaho Chemical Processing Plant (ICPP) for interim storage since 1951 and reprocessing since 1953. Until April 1992, the major activity of the ICPP was the reprocessing of SNF to recover fissile uranium and the management of the resulting high-level wastes (HLW). In 1992, DOE chose to discontinue reprocessing SNF for uranium recovery and shifted its focus toward the continued safe management and disposition of SNF and radioactive wastes accumulated through reprocessing activities. Currently, 1.8 million gallons of radioactive liquid wastes (1.5 million gallons of radioactive sodium-bearing liquid wastes and 0.3 million gallons of high-level liquid waste), 3,800 cubic meters of calcine waste, and 289 metric tons heavy metal of SNF are in inventory at the ICPP. Disposal of SNF and high-level waste (HLW) is planned for a repository. Preparation of SNF, HLW, and other radioactive wastes for disposal may include mechanical, physical, and/or chemical processes. This plan outlines the program strategy of the ICPP spent Fuel and Waste Management Technology Development Program (SF ampersand WMTDP) to develop and demonstrate the technology required to ensure that SNF and radioactive waste will be properly stored and prepared for final disposal in accordance with regulatory drivers. This Plan presents a brief summary of each of the major elements of the SF ampersand WMTDP; identifies key program assumptions and their bases; and outlines the key activities and decisions that must be completed to identify, develop, demonstrate, and implement a process(es) that will properly prepare the SNF and radioactive wastes stored at the ICPP for safe and efficient interim storage and final disposal

  19. Process analysis of an oxygen lean oxy-fuel power plant with co-production of synthesis gas

    International Nuclear Information System (INIS)

    This paper investigates new possibilities and synergy effects for an oxy-fuel fired polygeneration scheme (transportation fuel and electricity) with carbon capture and co-firing of biomass. The proposed process has the potential to make the oxy-fuel process more effective through a sub-stoichiometric combustion in-between normal combustion and gasification, which lowers the need for oxygen within the process. The sub-stoichiometric combustion yields production of synthesis gas, which is utilised in an integrated synthesis to dimethyl ether (DME). The process is kept CO2 neutral through co-combustion of biomass in the process. The proposed scheme is simulated with a computer model with a previous study of an oxy-fuel power plant as a reference process. The degree of sub-stoichiometric combustion, or amount of synthesis gas produced, is optimised with respect to the overall efficiency. The maximal efficiency was found at a stoichiometric ratio just below 0.6 with the efficiency for the electricity producing oxy-fuel process of 0.35 and a DME process efficiency of 0.63. It can be concluded that the proposed oxygen lean combustion process constitutes a way to improve the oxy-fuel carbon capture processes with an efficient production of DME in a polygeneration process

  20. Studies and research concerning BNFP: converting reprocessing plant's fuel receiving and storage area to an away-from-reactor (AFR) storage facility. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, Jim E.; Shallo, Frank A.; Musselwhite, E Larry; Wiedemann, George F.; Young, Moylen

    1979-09-01

    Converting a reprocessing plant's fuel receiving and storage station into an Away-From-Reactor storage facility is evaluated in this report. An engineering analysis is developed which includes (1) equipment modifications to the facility including the physical protection system, (2) planning schedules for licensing-related activities, and (3) cost estimates for implementing such a facility conversion. Storage capacities are evaluated using the presently available pools of the existing Barnwell Nuclear Fuel Plant-Fuel Receiving and Storage Station (BNFP-FRSS) as a model.

  1. Studies and research concerning BNFP: converting reprocessing plant's fuel receiving and storage area to an away-from-reactor (AFR) storage facility. Final report

    International Nuclear Information System (INIS)

    Converting a reprocessing plant's fuel receiving and storage station into an Away-From-Reactor storage facility is evaluated in this report. An engineering analysis is developed which includes (1) equipment modifications to the facility including the physical protection system, (2) planning schedules for licensing-related activities, and (3) cost estimates for implementing such a facility conversion. Storage capacities are evaluated using the presently available pools of the existing Barnwell Nuclear Fuel Plant-Fuel Receiving and Storage Station (BNFP-FRSS) as a model

  2. 10 CFR 140.13a - Amount of financial protection required for plutonium processing and fuel fabrication plants.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Amount of financial protection required for plutonium... of financial protection required for plutonium processing and fuel fabrication plants. (a) Each holder of a license issued pursuant to part 70 of this chapter to possess and use plutonium at...

  3. Conversion of cotton plant and cotton gin residues to fuels by the extruder-feeder liquefaction process

    Energy Technology Data Exchange (ETDEWEB)

    White, D.H. [Arizona Univ., Tucson, AZ (United States). Dept. of Chemical and Environmental Engineering; Coates, W.E. [Arizona Univ., Tucson, AZ (United States). Bioresources Research Facility; Wolf, D. [Ben-Gurion Univ. of the Negev, Beersheba (Israel). Dept. of Chemical Engineering

    1996-04-01

    Cotton is planted on a large scale in the USA, and is a major crop in Arizona. A large amount of cotton plant residue and cotton gin waste is produced annually, and these present a disposal problem. This material is comprised of cotton stalks, along with the upper portion of the taproot, and cotton gin trash. Cotton plant residues are a greater problem in the warmer regions of the USA as they serve as an over-wintering site for insect pests, and thus must be destroyed. Presently they are buried. Most field operations used to bury the residue are high energy consumers, and tend to destroy soil structure, thereby increasing the potential for erosion. This burial process is considered to be detrimental to the soil. One option to change the negative value of this biomass to a positive one is to harvest the cotton plants and combine them with other cotton wastes to produce a feedstock for liquefaction purposes. A process for harvesting and transporting the roots and stalks is being developed at the University of Arizona. In this paper we propose a combined harvesting/liquefaction system. This system would harvest and liquefy cotton wastes into oil and densified solid fuels with higher economic values. The extruder-feeder liquefaction process was developed at the University of Arizona in the 1980s under the sponsorship of the U.S. Department of Energy, with the goal to convert wood to a clean, 16000 btu/lb liquid fuel. The process has been redirected to other organic wastes using additional processing to yield ``value-added`` byproducts. Cotton wastes are good candidates for this process. By combining the harvesting and fuel processing operations, a negative value biomass would become a positive value biomass by (a) solving a disposal problem, and (b) producing high value fuels. (Author)

  4. Richard Barnwell honored with emeritus status

    OpenAIRE

    Crumbley, Liz

    2006-01-01

    Richard W. Barnwell of Newport News, Va., professor of aerospace and ocean engineering and engineering science and mechanics in the College of Engineering at Virginia Tech, was conferred with the title,"professor emeritus" by the Virginia Tech Board of Visitors during the board's quarterly meeting August 28.

  5. Initial evaluation of dry storage issues for spent nuclear fuels in wet storage at the Idaho Chemical Processing Plant

    Energy Technology Data Exchange (ETDEWEB)

    Guenther, R J; Johnson, Jr, A B; Lund, A L; Gilbert, E R [and others

    1996-07-01

    The Pacific Northwest Laboratory has evaluated the basis for moving selected spent nuclear fuels in the CPP-603 and CPP-666 storage pools at the Idaho Chemical Processing Plant from wet to dry interim storage. This work is being conducted for the Lockheed Idaho Technologies Company as part of the effort to determine appropriate conditioning and dry storage requirements for these fuels. These spent fuels are from 22 test reactors and include elements clad with aluminum or stainless steel and a wide variety of fuel materials: UAl{sub x}, UAl{sub x}-Al and U{sub 3}O{sub 8}-Al cermets, U-5% fissium, UMo, UZrH{sub x}, UErZrH, UO{sub 2}-stainless steel cermet, and U{sub 3}O{sub 8}-stainless steel cermet. The study also included declad uranium-zirconium hydride spent fuel stored in the CPP-603 storage pools. The current condition and potential failure mechanisms for these spent fuels were evaluated to determine the impact on conditioning and dry storage requirements. Initial recommendations for conditioning and dry storage requirements are made based on the potential degradation mechanisms and their impacts on moving the spent fuel from wet to dry storage. Areas needing further evaluation are identified.

  6. Initial evaluation of dry storage issues for spent nuclear fuels in wet storage at the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    The Pacific Northwest Laboratory has evaluated the basis for moving selected spent nuclear fuels in the CPP-603 and CPP-666 storage pools at the Idaho Chemical Processing Plant from wet to dry interim storage. This work is being conducted for the Lockheed Idaho Technologies Company as part of the effort to determine appropriate conditioning and dry storage requirements for these fuels. These spent fuels are from 22 test reactors and include elements clad with aluminum or stainless steel and a wide variety of fuel materials: UAlx, UAlx-Al and U3O8-Al cermets, U-5% fissium, UMo, UZrHx, UErZrH, UO2-stainless steel cermet, and U3O8-stainless steel cermet. The study also included declad uranium-zirconium hydride spent fuel stored in the CPP-603 storage pools. The current condition and potential failure mechanisms for these spent fuels were evaluated to determine the impact on conditioning and dry storage requirements. Initial recommendations for conditioning and dry storage requirements are made based on the potential degradation mechanisms and their impacts on moving the spent fuel from wet to dry storage. Areas needing further evaluation are identified

  7. Analysis of cumulative energy consumption in an oxy-fuel combustion power plant integrated with a CO2 processing unit

    International Nuclear Information System (INIS)

    Highlights: • Oxy-fuel combustion is promising CCS technology. • Sum of direct and indirect energy consumption ought to be consider. • This sum is expressed by cumulative energy consumption. • Input–output analysis is adequate method of CCS modeling. - Abstract: A balance of direct energy consumption is not a sufficient tool for an energy analysis of an oxy-fuel combustion power plant because of the indirect consumption of energy in preceding processes in the energy-technological set of interconnections. The sum of direct and indirect consumption expresses cumulative energy consumption. Based on the “input–output” model of direct energy consumption the mathematical model of cumulative energy consumption concerning an integrated oxy-fuel combustion power plant has been developed. Three groups of energy carriers or materials are to be distinguished, viz. main products, by-products and external supplies not supplementing the main production. The mathematical model of the balance of cumulative energy consumption based on the assumption that the indices of cumulative energy consumption of external supplies (mainly fuels and raw materials) are known a’priori. It results from weak connections between domestic economy and an integrated oxy-fuel combustion power plant. The paper presents both examples of the balances of direct and cumulative energy consumption. The results of calculations of indices of cumulative energy consumption concerning main products are presented. A comparison of direct and cumulative energy effects between three variants has been worked out. Calculations of the indices of cumulative energy consumption were also subjected to sensitive analysis. The influence of the indices of cumulative energy consumption of external supplies (input data), as well as the assumption concerning the utilization of solid by-products of the combustion process have been investigated

  8. Nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    The present invention concerns an improvement for corrosion resistance of the welded portion of materials which constitutes a reprocessing plant of spent nuclear fuels. That is, Mo-added austenite stainless steel is used for a plant member at the portion in contact with a nitric acid solution. Then, laser beams are irradiated to the welded portion of the plant member and the surface layer is heated to higher than 1,000degC. If such a heat treatment is applied, the degradation of corrosion resistance of the welded portion can be eliminated at the surface. Further, since laser beams are utilized, heating can be limited only to the surface. Accordingly, undesired thermal deformation of the plant members can be prevented. As a result, the plant member having high pit corrosion resistance against a dissolution solution for spent fuels containing sludges comprising insoluble residue and having resistance to nitric acid solution also in the welded portion substantially equal to that of the matrix can be attained. (I.S.)

  9. Studies and research concerning BNFP: LWR spent fuel storage

    International Nuclear Information System (INIS)

    This report describes potential spent fuel storage expansion programs using the Barnwell Nuclear Fuel Plant--Fuel Receiving and Storage Station (BNFP-FRSS) as a model. Three basic storage arrangements are evaluated with cost and schedule estimates being provided for each configuration. A general description of the existing facility is included with emphasis on the technical and equipment requirements which would be necessary to achieve increased spent fuel storage capacity at BNFP-FRSS

  10. Towards Multi Fuel SOFC Plant

    DEFF Research Database (Denmark)

    Rokni, Masoud; Clausen, Lasse Røngaard; Bang-Møller, Christian

    2011-01-01

    Complete Solid Oxide Fuel Cell (SOFC) plants fed by several different fuels are suggested and analyzed. The plants sizes are about 10 kW which is suitable for single family house with needs for both electricity and heat. Alternative fuels such as, methanol, DME (Di-Methyl Ether) and ethanol...... are also considered and the results will be compared with the base plant fed by Natural Gas (NG). A single plant design will be suggested that can be fed with methanol, DME and ethanol whenever these fuels are available. It will be shown that the plant fed by ethanol will have slightly higher electrical...... efficiency compared with other fuels. A methanator will be suggested to be included into the plants design in order to produce methane from the fuel before entering the anode side of the SOFC stacks. Increasing methane content will decrease the needed compressor effect and thereby increase the plant power....

  11. Fuels Processing Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — NETL’s Fuels Processing Laboratory in Morgantown, WV, provides researchers with the equipment they need to thoroughly explore the catalytic issues associated with...

  12. Energy Conversion Alternatives Study (ECAS), General Electric Phase 1. Volume 3: Energy conversion subsystems and components. Part 3: Gasification, process fuels, and balance of plant

    Science.gov (United States)

    Boothe, W. A.; Corman, J. C.; Johnson, G. G.; Cassel, T. A. V.

    1976-01-01

    Results are presented of an investigation of gasification and clean fuels from coal. Factors discussed include: coal and coal transportation costs; clean liquid and gas fuel process efficiencies and costs; and cost, performance, and environmental intrusion elements of the integrated low-Btu coal gasification system. Cost estimates for the balance-of-plant requirements associated with advanced energy conversion systems utilizing coal or coal-derived fuels are included.

  13. Towards Multi Fuel SOFC Plant

    OpenAIRE

    Rokni, Masoud; Clausen, Lasse Røngaard; Bang-Møller, Christian

    2011-01-01

    Complete Solid Oxide Fuel Cell (SOFC) plants fed by several different fuels are suggested and analyzed. The plants sizes are about 10 kW which is suitable for single family house with needs for both electricity and heat. Alternative fuels such as, methanol, DME (Di-Methyl Ether) and ethanol are also considered and the results will be compared with the base plant fed by Natural Gas (NG). A single plant design will be suggested that can be fed with methanol, DME and ethanol whenever these fuels...

  14. Purex process improvements for the UP3 spent fuel reprocessing plant at La Hague, France

    International Nuclear Information System (INIS)

    The UP3 reprocessing plant commissioned for active operation in November 1989 features numerous innovations both for the process flowsheet and the associated equipment. These innovations yielded positive results following initial active testing and are of considerable interest for solvent extraction specialists. This paper describes the main improvements introduced for the extraction cycles used to separate and purify uranium and plutonium. Specifically, these improvements include: adaptation of the first extraction cycle flowsheet for technetium decontamination and tritium confinement; solvent purification process based on distillation, a key element in the solvent system; flowsheets adapted for maximum recycling of liquid organic and mineral streams (solvent or nitric acid); use of annular or cylindrical pulsed columns with high-efficiency packing

  15. Design Fuels Corporation (DFC)-Apache, Inc. coal reclamation system for the plant of the future for processing clean coal

    International Nuclear Information System (INIS)

    The mechanical washing processing and drying portion of the DFC process offers an efficient method for cleaning of pyritic sulfur bearing compounds which represents 25% sulfur reduction from original run-of-mine coal quality. This reduction can be augmented with the use of calcium and sodium based compounds to reduce the sulfur in many coals to produce compliance quality coal. The use of mechanical/physical methods for the removal of the pyritic material found in coal is used by the DFC process as a first step to the final application of a complete coal refuse clean-up technology based on site specific conditions of the parent coal. The paper discusses the use of the DFC process to remediate slurry ponds and tailings piles and to improve coal cleaning by gravity separation methods, flotation, hydrocyclones and spiral separators, dense media separation, water only cyclones, and oil/solvent agglomeration. A typical DFC Project is the Rosa Coal Reclamation Project which involves the development of a bituminous coal waste impoundment reclamation and washery system. The plant would be located adjacent to a coal fines pond or tailings pond and refuse pile or gob pile at a former coal strip mine in Oneonta, Alabama. Design Fuels would provide a development program by which coal waste at the Rosa Mine could be reclaimed, cleaned and sold profitably. This feedstock could be furnished from recovered coal for direct use in blast furnaces, or as feedstock for coke ovens at 250,000 tons per year at an attractive price on a 10-year contract basis. The site has an old coal washing facility on the property that will be dismantled. Some equipment salvage has been considered; and removal of the existing plant would be the responsibility of Design Fuels. The paper briefly discusses the market potential of the process

  16. Container concept for the PBMR fuel plant

    Energy Technology Data Exchange (ETDEWEB)

    Braehler, G.; Kelly, M.; Sauer, L.; Welbers, P. [NUKEM Technologies GmbH (Germany)

    2009-07-01

    This presentation describes the types and the characteristics of the containers uniquely designed for and used in the PBMR Fuel Plant in Pelindaba, South Africa. The PBMR Fuel Plant is designed to manufacture so called Fuel Spheres for the High Temperature Reactor which shall be built in Koeberg near Cape Town. The PBMR fuel is based on a proven, high quality German fuel design consisting of 10% enriched Uranium triple-coated isotropic (LEU-TRISO) particles contained in a moulded graphite sphere. A coated particle comprises a kernel of Uranium dioxide surrounded by different layers. A fuel sphere consists of 9 g of Uranium (some 15 000 particles) and has a diameter of 60 mm; the total mass of a fuel sphere is 210 g. During normal operation the PBMR core contains a load of 456,000 fuel spheres. The PBMR Fuel plant is designed to produce 270,000 fuel spheres a year with the option to doubling the throughput. Two basic types of containers are foreseen for the plant, i.e. the Safe Geometry Containers for transportation and storage of Uranium bearing material and Containers in non restricted geometry for solid raw and auxiliary materials required by the different processes. Unlike other concepts in fuel element plants, the Safe Geometry Containers are allowed to be stored, from a criticality point of view, everywhere in the plant. Special identification measures, physical and IT based, prevent wrong material being processed. The sub-critical configuration is still maintained after the specified fire scenario for the PBMR Fuel Plant. (orig.)

  17. Effects of fuel processing methods on industrial scale biogas-fuelled solid oxide fuel cell system for operating in wastewater treatment plants

    Science.gov (United States)

    Farhad, Siamak; Yoo, Yeong; Hamdullahpur, Feridun

    The performance of three solid oxide fuel cell (SOFC) systems, fuelled by biogas produced through anaerobic digestion (AD) process, for heat and electricity generation in wastewater treatment plants (WWTPs) is studied. Each system has a different fuel processing method to prevent carbon deposition over the anode catalyst under biogas fuelling. Anode gas recirculation (AGR), steam reforming (SR), and partial oxidation (POX) are the methods employed in systems I-III, respectively. A planar SOFC stack used in these systems is based on the anode-supported cells with Ni-YSZ anode, YSZ electrolyte and YSZ-LSM cathode, operated at 800 °C. A computer code has been developed for the simulation of the planar SOFC in cell, stack and system levels and applied for the performance prediction of the SOFC systems. The key operational parameters affecting the performance of the SOFC systems are identified. The effect of these parameters on the electrical and CHP efficiencies, the generated electricity and heat, the total exergy destruction, and the number of cells in SOFC stack of the systems are studied. The results show that among the SOFC systems investigated in this study, the AGR and SR fuel processor-based systems with electrical efficiency of 45.1% and 43%, respectively, are suitable to be applied in WWTPs. If the entire biogas produced in a WWTP is used in the AGR or SR fuel processor-based SOFC system, the electricity and heat required to operate the WWTP can be completely self-supplied and the extra electricity generated can be sold to the electrical grid.

  18. Preparation of LWBR [Light Water Breeder Reactor] spent fuel for shipment to ICPP [Idaho Chemical Processing Plant] for long term storage (LWBR Development Program)

    International Nuclear Information System (INIS)

    After successfully operating for 29,047 effective full power hours, the Light Water Breeder Reactor (LWBR) core was defueled prior to total decommissioning of the Shippingport facility. All nuclear fuel and much of the reactor internal hardware was removed from the reactor vessel. Non-fuel components were prepared for shipment to disposal sites, and the fuel assemblies were partially disassembled and shipped to the Expended Core Facility (ECF) in Idaho. At ECF, the fuel modules underwent further disassembly to provide fuel rods for nondestructive testing to establish the core's breeding efficiency and to provide core components for examinations to assess their performance characteristics. This report presents a basic description of the processes and equipment used to prepare and to ship all LWBR nuclear fuel to the Idaho Chemical Processing Plant (ICPP) for long-term storage. Preparation processes included the underwater loading of LWBR fuel into storage liners, the sealing, dewatering and drying of the storage liners, and the final pressurization of the storage liners with inert neon gas. Shipping operations included the underwater installation of the fuel loaded storage liner into the Peach Bottom shipping cask, cask removal from the waterpit, cask preparations for shipping, and cask shipment by tractor trailer to the ICPP facility for long-term storage. The ICPP facility preparations for LWBR fuel storage and the ICPP process for discharge of the fuel into underground silos are presented. 10 refs., 42 figs

  19. Concept of the plant for the BN-800 fast reactor fuel recycling with application of pyro-process and vibro-packing technology

    Energy Technology Data Exchange (ETDEWEB)

    Bychkov, A.V.; Skiba, O.V.; Mayorshin, A.A.; Demidova, L.S.; Kormilitzyna, L.A.; Ishunin, V.S

    2000-07-01

    The conception of Plant was developed for MOX-fuel recycle at two BN-800 type fast reactors by pyrochemical reprocessing of irradiated nuclear fuel (INF) and production of vibro-pac fuel pins and SA. INF production process and stages of pyrochemical reprocessing were analyzed. Starting materials were chosen. Characteristics of irradiated SA and requirements for finished products were defined. Volumes of production were estimated. Procedure of waste management was defined. The following description was made: (1) general flow sheet of fuel recycling and partial schemes of single reprocessing; (2) composition of production process equipment; (3) arrangement of production process equipment; (4) lay out of Plant building and engineering communications. Principle economical assessments were made for production under design. (authors)

  20. Fuel Gas Demonstration Plant Program. Volume I. Demonstration plant

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

    The objective of this project is for Babcock Contractors Inc. (BCI) to provide process designs, and gasifier retort design for a fuel gas demonstration plant for Erie Mining Company at Hoyt Lake, Minnesota. The fuel gas produced will be used to supplement natural gas and fuel oil for iron ore pellet induration. The fuel gas demonstration plant will consist of five stirred, two-stage fixed-bed gasifier retorts capable of handling caking and non-caking coals, and provisions for the installation of a sixth retort. The process and unit design has been based on operation with caking coals; however, the retorts have been designed for easy conversion to handle non-caking coals. The demonstration unit has been designed to provide for expansion to a commercial plant (described in Commercial Plant Package) in an economical manner.

  1. Melvin Calvin: Fuels from Plants

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, S.E.; Otvos, J.W.

    1998-11-24

    A logical extension of his early work on the path of carbon during photosynthesis, Calvin's studies on the production of hydrocarbons by plants introduced many in the scientific and agricultural worlds to the potential of renewable fuel and chemical feedstocks. He and his co-workers identified numerous candidate compounds from plants found in tropical and temperate climates from around the world. His travels and lectures concerning the development of alternative fuel supplies inspired laboratories worldwide to take up the investigation of plant-derived energy sources as an alternative to fossil fuels.

  2. Energy and exergy analysis and optimal design of the hybrid molten carbonate fuel cell power plant and carbon dioxide capturing process

    International Nuclear Information System (INIS)

    Highlights: • An hybrid molten carbonate fuel cell systems is analyzed. • Power generation and carbon dioxide capturing is done in a process. • Advanced exergy analysis is applied on a fuel cell system. - Abstract: A hybrid molten carbonate fuel cell power plant and carbon dioxide capturing process is investigated through the exergy and advanced exergy analysis. The results show that the greatest exergy destruction (181 MW) occurs in the combustion chamber. It is because of irreversibility of the chemical reactions in the combustion process. Also the lowest exergy efficiency is related to the fuel cell. Advanced exergy analysis shows that the most portion of the exergy destruction is avoidable (more than 65%). Optimal design of the process is done by adjusting the effective operating conditions for reducing the power consumption and carbon dioxide emission of the process. Results of the optimization shows that the power consumption in the compressors can be reduced up to 33%

  3. On-Line Monitoring for Process Control and Safeguarding of Radiochemical Streams at Spent Fuel Reprocessing Plants

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA) has established international safe- guards standards for fissionable material at spent nuclear fuel reprocessing plants to ensure that significant quantities of weapons-grade nuclear material are not diverted from these facilities. Currently, methods to verify material control and accountancy (MC&A) at these facilities require time-consuming and resource-intensive destructive assay (DA). Leveraging new on-line non-destructive assay (NDA) techniques in conjunction with the traditional and highly precise DA methods may provide a more timely, cost-effective and resource-efficient means for MC&A verification at such facilities. Pacific Northwest National Laboratory (PNNL) is developing on-line NDA process monitoring technologies, including a spectroscopy-based monitoring system, to potentially reduce the time and re- source burden associated with current techniques. The spectroscopic monitor continuously measures chemical compositions of the process streams including actinide metal ions (U, Pu, Np), selected fission products, and major cold flowsheet chemicals using ultra-violet and visible, near infrared and Raman spectroscopy. This paper will provide an overview of the methods and report our on-going efforts to develop and demonstrate the technologies. Our ability to identify material intentionally diverted from a liquid-liquid solvent extraction contactor system was successfully tested using on-line process monitoring as a means to detect the amount of material diverted. A chemical diversion, and detection of that diversion, from a solvent extraction scheme was demonstrated using a centrifugal contactor system operating with the PUREX flowsheet. A portion of the feed from a counter-current extraction system was diverted while a continuous extraction experiment was underway. The amount observed to be diverted by on-line spectroscopic process monitoring was in excellent agreement with values based from the known mass of

  4. Biomass-fueled power plants in Finland

    Energy Technology Data Exchange (ETDEWEB)

    Raiko, M. [IVO Power Engineering Ltd., Vantaa (Finland); Hulkkonen, S. [Imatran Voima Oy, Vantaa (Finland)

    1997-07-01

    Combined heat and power production (CHP) from biomass is a commercially viable alternative when district heat or process steam is needed in small towns or in a process industry. The high nominal investment cost of a small power plant that uses local biomass fuels is compensated by the revenues from the heat. The price of the district heat or the steam generated in the CHP-plant can be valued at the same price level as the heat from a mere steam boiler. Also, the price of heat produced by a small-generation-capacity plant is local and higher, whereas electricity has a more general market price. A typical small Finnish CHP-plant consists of a bubbling fluidized bed boiler and a simplified steam turbine cycle generating 4 to 10 MW of electricity and 10 to 30 MW of district heat or process steam. There are about 10 power plants of this type in commercial operation in Finland. As a whole, biomass, which is used in more than 200 plants, provides about 20% of the primary energy consumption in Finland. Roughly half of these produce only heat but the rest are combined heat and power plants. The majority of the plants is in pulp and paper industry applications. Imatran Voima Oy (IVO) is the biggest energy producer in Finland. IVO builds, owns and operates several biomass-fired power plants and carries out active R and D work to further develop the biomass-fueled small power plant. This paper discusses the experiences of the biomass-fueled power plants. (author)

  5. The development of in-process inventory walk-through examination system in the process at borrowing inspection between LEU fuel fabrication plants

    International Nuclear Information System (INIS)

    Since the Nuclear Material Control Center (NMCC) was designed the safeguards inspection organization by Ministry of Education, Culture, Sports, Science and Technology (MEXT) in December 1999, the NMCC has been performing safeguards inspection for the Nuclear Facilities in Japan. The NMCC has carried out the safeguards inspections to LEU Fuel Fabrication Plants (FFPs) and the NMCC has improved the method of safeguards inspection as it has changed over to the integrated safeguards from the year of 2005. Concerning the Borrowing inspection between LEU FFPs, which is the precondition to change over to the integrated safeguards, it is needed to estimate the entire inventory in the facility within the limited time. Therefore, the NMCC has developed the system called IWES (In-process inventory Walk-through Examination System) to examine the inventory in process smoothly, quickly and correctly at borrowing inspection, check the entire inventory quantity and evaluate them. This report describes how IWES aiming at effective/efficient confirmation of in-process inventory has been developed and how it is applied to the borrowing inspection activities. (author)

  6. Research and development projects, new processes binded at the stop of a fuel fabrication plant (Nukem-A)

    International Nuclear Information System (INIS)

    This research work is aimed at the assessment of new procedures in the framework of the decommissioning of the NUKEM-A facility, a plant used for over 30 years for the fabrication of Material Test Reactor (MTR) and Thorium High Temperature Reactor (THTR) fuel elements. Important issues in this work are the preparation of detailed uranium and thorium contamination distribution maps in walls and floors, the execution of various dismantling and decontamination operations under health physics control, the large-scale treatment of arising primary waste and the minimization of secondary waste

  7. Analysis of causes of criticality accidents at nuclear fuel processing facilities in foreign countries. Similarities to the criticality accident at JCO's uranium processing plant

    International Nuclear Information System (INIS)

    On September 30, 1999, a criticality accident occurred at the JCO's uranium processing plant, which resulted in the first nuclear accident involving a fatality, in Japan, and forced the residents in the vicinity of the site to be evacuated and be sheltered indoors. Before the JCO accident, 21 criticality accidents have been reported at nuclear fuel processing facilities in foreign countries. The present paper describes the overall trends observed in the 21 accidents and discusses the sequences and causes of the accidents analyzed in terms of similarities to the JCO accident. Almost all of them occurred with the uranium or plutonium solution and in vessels/tanks with unfavorable geometry. In some cases, the problems similar to those observed in the JCO accident were identified: violations of procedures and/or technical specifications for improving work efficiencies, procedural changes without any application to and permission from the regulatory body, lack of understanding of criticality hazards, and complacency that a criticality accident would not occur. (author)

  8. Manufacturing technology and process for BWR fuel

    International Nuclear Information System (INIS)

    Following recent advanced technologies, processes and requests of the design changes of BWR fuel, Nuclear Fuel Industries, Ltd. (NFI) has upgraded the manufacturing technology and honed its own skills to complete its brand-new automated facility in Tokai in the latter half of 1980's. The plant uses various forms of automation throughout the manufacturing process: the acceptance of uranium dioxide powder, pelletizing, fuel rod assembling, fuel bundle assembling and shipment. All processes are well computerized and linked together to establish the integrated control system with three levels of Production and Quality Control, Process Control and Process Automation. This multi-level system plays an important role in the quality assurance system which generates the highest quality of fuels and other benefits. (author)

  9. Final report, Task 3: possible uses of the Nuclear Fuel Services, Inc. reprocessing plant at West Valley, New York

    International Nuclear Information System (INIS)

    The West Valley Plant could readily be used for work on reprocessing of alternative fuels, spiking, coprocessing (including CIVEX), waste solidification, and the recovery of radioactive gases. The plant could be easily modified for any scale between small-scale experimental work to production-scale demonstration, involving virtually any combination of fissile/fertile fuel materials that might be used in the future. The use of this plant for the contemplated experimental work would involve lower capital costs than the use of other facilities at DOE sites, except possibly for spiking of recovered products; the operating costs would be no greater than at other sites. The work on reprocessing of alternative fuels and coprocessing could commence within about one year; on recovery of radioactive gases, in 3 to 5 years; on spiking, in 4 years; and on waste solidification demonstration, in about 5 years. The contemplated work could be begun at this plant at least as early as at Barnwell, although work on spiking of recovered products could probably be started in existing hot cells earlier than at West Valley

  10. Direct FuelCell/Turbine Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Hossein Ghezel-Ayagh

    2008-09-30

    This report summarizes the progress made in development of Direct FuelCell/Turbine (DFC/T{reg_sign}) power plants for generation of clean power at very high efficiencies. The DFC/T system employs an indirectly heated Turbine Generator to supplement fuel cell generated power. The concept extends the high efficiency of the fuel cell by utilizing the fuel cell's byproduct heat in a Brayton cycle. Features of the DFC/T system include: electrical efficiencies of up to 75% on natural gas, minimal emissions, reduced carbon dioxide release to the environment, simplicity in design, direct reforming internal to the fuel cell, and potential cost competitiveness with existing combined cycle power plants. Proof-of-concept tests using a sub-MW-class DFC/T power plant at FuelCell Energy's (FCE) Danbury facility were conducted to validate the feasibility of the concept and to measure its potential for electric power production. A 400 kW-class power plant test facility was designed and retrofitted to conduct the tests. The initial series of tests involved integration of a full-size (250 kW) Direct FuelCell stack with a 30 kW Capstone microturbine. The operational aspects of the hybrid system in relation to the integration of the microturbine with the fuel cell, process flow and thermal balances, and control strategies for power cycling of the system, were investigated. A subsequent series of tests included operation of the sub-MW Direct FuelCell/Turbine power plant with a Capstone C60 microturbine. The C60 microturbine extended the range of operation of the hybrid power plant to higher current densities (higher power) than achieved in initial tests using the 30kW microturbine. The proof-of-concept test results confirmed the stability and controllability of operating a fullsize (250 kW) fuel cell stack in combination with a microturbine. Thermal management of the system was confirmed and power plant operation, using the microturbine as the only source of fresh air supply

  11. Equipment specifications for an electrochemical fuel reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Hemphill, Kevin P [Los Alamos National Laboratory

    2010-01-01

    Electrochemical reprocessing is a technique used to chemically separate and dissolve the components of spent nuclear fuel, in order to produce new metal fuel. There are several different variations to electrochemical reprocessing. These variations are accounted for by both the production of different types of spent nuclear fuel, as well as different states and organizations doing research in the field. For this electrochemical reprocessing plant, the spent fuel will be in the metallurgical form, a product of fast breeder reactors, which are used in many nuclear power plants. The equipment line for this process is divided into two main categories, the fuel refining equipment and the fuel fabrication equipment. The fuel refining equipment is responsible for separating out the plutonium and uranium together, while getting rid of the minor transuranic elements and fission products. The fuel fabrication equipment will then convert this plutonium and uranium mixture into readily usable metal fuel.

  12. Direct FuelCell/Turbine Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Hossein Ghezel-Ayagh

    2008-09-30

    This report summarizes the progress made in development of Direct FuelCell/Turbine (DFC/T{reg_sign}) power plants for generation of clean power at very high efficiencies. The DFC/T system employs an indirectly heated Turbine Generator to supplement fuel cell generated power. The concept extends the high efficiency of the fuel cell by utilizing the fuel cell's byproduct heat in a Brayton cycle. Features of the DFC/T system include: electrical efficiencies of up to 75% on natural gas, minimal emissions, reduced carbon dioxide release to the environment, simplicity in design, direct reforming internal to the fuel cell, and potential cost competitiveness with existing combined cycle power plants. Proof-of-concept tests using a sub-MW-class DFC/T power plant at FuelCell Energy's (FCE) Danbury facility were conducted to validate the feasibility of the concept and to measure its potential for electric power production. A 400 kW-class power plant test facility was designed and retrofitted to conduct the tests. The initial series of tests involved integration of a full-size (250 kW) Direct FuelCell stack with a 30 kW Capstone microturbine. The operational aspects of the hybrid system in relation to the integration of the microturbine with the fuel cell, process flow and thermal balances, and control strategies for power cycling of the system, were investigated. A subsequent series of tests included operation of the sub-MW Direct FuelCell/Turbine power plant with a Capstone C60 microturbine. The C60 microturbine extended the range of operation of the hybrid power plant to higher current densities (higher power) than achieved in initial tests using the 30kW microturbine. The proof-of-concept test results confirmed the stability and controllability of operating a fullsize (250 kW) fuel cell stack in combination with a microturbine. Thermal management of the system was confirmed and power plant operation, using the microturbine as the only source of fresh air supply

  13. System Studies of Fuel Cell Power Plants

    OpenAIRE

    Kivisaari, Timo

    2001-01-01

    This thesis concerns system studies of power plants wheredifferent types of fuel cells accomplish most of the energyconversion. Ever since William Grove observed the fuel cell effect inthe late 1830s fuel cells have been the subject or more or lessintense research and development. Especially in the USA theseactivities intensified during the second part of the 1950s,resulting in the development of the fuel cells used in theApollo-program. Swedish fuel cell activities started in themid-1960s, w...

  14. Environmental impacts of fossil-fuel and nuclear power plants

    International Nuclear Information System (INIS)

    Large power plants burning fossil fuels generate emissions with a high content of sulphur dioxide and a content of noxious aerosols and radioisotopes whose radioactivity exceeds the limits set for nuclear power plants. The main problem of nuclear power plants is to secure radiation safety namely in case of an accident even though the probability of such an event is very small. The most complicated problems are related to the treatment of spent fuel, its transport, processing and storage. (B.H.)

  15. Application of Reactor Physics Calculation Methods to Criticality Control of Non-Inherently Safe Systems in Fuel Processing Plants

    International Nuclear Information System (INIS)

    The economics of fuel processing operations involving the handling of large quantities of fissionable materials can be significantly improved by utilizing somewhat detailed reactor physics calculation methods to establish criticality safe process parameters. These calculation techniques serve as an extension of critical experiment data to systems not specifically covered by such data and may be used to establish the safety of larger mass limits and process equipment dimensions than could be justified by conservative extrapolation of the available experimental data. This paper describes some of the calculation techniques used for this purpose at United Nuclear Corporation. Both hand calculation techniques and computerized techniques are discussed in connection with highly enriched uranium alloy water systems, poison-wrapped cylinders, fixed poison sheets in unsafe geometry tanks, and safety arrays of unmoderated uranium materials; and generally useful data obtained with these methods are presented. Comparison of these calculation methods against experimental data, and the assumptions made in applying these methods to criticality safety work, are also discussed. (author)

  16. Preparation for commissioning of nuclear plant with reference to British Nuclear Fuels Plc fuel handling plant project

    International Nuclear Information System (INIS)

    The new Fuel Handing Plant at British Nuclear Fuels Sellafield is part of a Pound 550M complex which provides facilities for the receipt, storage and mechanical preparation of both magnox and A.G.R. fuel. The plant is very large and complex with considerable use of computer based process control systems, providing for physical and nuclear safety. The preparation of such plant for ''active'' commissioning necessitates a great many physical checks and technical evaluations in support of its safety case. This paper describes arrangements for plant commissioning checks, against the regulatory framework and explains the physical preparations necessary for their timely accomplishment. (author)

  17. Methodology for estimating reprocessing costs for nuclear fuels

    International Nuclear Information System (INIS)

    A technological and economic evaluation of reprocessing requirements for alternate fuel cycles requires a common assessment method and a common basis to which various cycles can be related. A methodology is described for the assessment of alternate fuel cycles utilizing a side-by-side comparison of functional flow diagrams of major areas of the reprocessing plant with corresponding diagrams of the well-developed Purex process as installed in the Barnwell Nuclear Fuel Plant (BNFP). The BNFP treats 1500 metric tons of uranium per year (MTU/yr). Complexity and capacity factors are determined for adjusting the estimated facility and equipment costs of BNFP to determine the corresponding costs for the alternate fuel cycle. Costs of capacities other than the reference 1500 MT of heavy metal per year are estimated by the use of scaling factors. Unit costs of reprocessed fuel are calculated using a discounted cash flow analysis for three economic bases to show the effect of low-risk, typical, and high-risk financing methods

  18. Criticality accident in uranium fuel processing plant. Emergency medical care and dose estimation for the severely overexposed patients

    Energy Technology Data Exchange (ETDEWEB)

    Akashi, Makoto; Ishigure, Nobuhito [National Inst. of Radiological Sciences, Chiba (Japan)

    2000-08-01

    A criticality accident occurred in JCO, a plant for nuclear fuel production in 1999 and three workers were exposed to extremely high-level radiation (neutron and {gamma}-ray). This report describes outlines of the clinical courses and the medical cares for the patients of this accident and the emergent medical system for radiation accident in Japan. One (A) of the three workers of JCO had vomiting and diarrhea within several minutes after the accident and another one (B) had also vomiting within one hour after. Based on these evidences, the exposure dose of A and B were estimated to be more than 8 and 4 GyEq, respectively. Generally, acute radiation syndrome (ARS) is assigned into three phases; prodromal phase, critical or manifestation phase and recovery phase or death. In the prodromal phase, anorexia, nausea, vomiting and diarrhea often develop, whereas the second phase is asymptotic. In the third phase, various syndromes including infection, hemorrhage, dehydration shock and neurotic syndromes are apt to occur. It is known that radiation exposure at 1 Gy or more might induce such acute radiation syndromes. Based on the clinical findings of Chernobyl accident, it has been thought that exposure at 0.5 Gy or more causes a lowering of lymphocyte level and a decrease in immunological activities within 48 hours. Lymphocyte count is available as an indicator for the evaluation of exposure dose in early phase, but not in later phase The three workers of JCO underwent chemical analysis of blood components, chromosomal analysis and analysis of blood {sup 24}Na immediately after the arrival at National Institute of Radiological Sciences via National Mito Hospital specified as the third and the second facility for the emergency medical care system in Japan, respectively. (M.N.)

  19. Evaluation of gasification and gas cleanup processes for use in molten carbonate fuel cell power plants. Final report. [Contains lists and evaluations of coal gasification and fuel gas desulfurization processes

    Energy Technology Data Exchange (ETDEWEB)

    Jablonski, G.; Hamm, J.R.; Alvin, M.A.; Wenglarz, R.A.; Patel, P.

    1982-01-01

    This report satisfies the requirements for DOE Contract AC21-81MC16220 to: List coal gasifiers and gas cleanup systems suitable for supplying fuel to molten carbonate fuel cells (MCFC) in industrial and utility power plants; extensively characterize those coal gas cleanup systems rejected by DOE's MCFC contractors for their power plant systems by virtue of the resources required for those systems to be commercially developed; develop an analytical model to predict MCFC tolerance for particulates on the anode (fuel gas) side of the MCFC; develop an analytical model to predict MCFC anode side tolerance for chemical species, including sulfides, halogens, and trace heavy metals; choose from the candidate gasifier/cleanup systems those most suitable for MCFC-based power plants; choose a reference wet cleanup system; provide parametric analyses of the coal gasifiers and gas cleanup systems when integrated into a power plant incorporating MCFC units with suitable gas expansion turbines, steam turbines, heat exchangers, and heat recovery steam generators, using the Westinghouse proprietary AHEAD computer model; provide efficiency, investment, cost of electricity, operability, and environmental effect rankings of the system; and provide a final report incorporating the results of all of the above tasks. Section 7 of this final report provides general conclusions.

  20. Recent advances in fuel product and manufacturing process development

    International Nuclear Information System (INIS)

    This paper discusses advancements in commercial nuclear fuel products and manufacturing made by the Westinghouse Electric Corporation in response to the commercial nuclear fuel industry's demand for high reliability, increased plant availability and improved operating flexibility. The features and benefits of Westinghouse's most advanced fuel products--VANTAGE 5 for PWR plants and QUAD+ for BWR plants--are described, as well as high performance fuel concepts now under development for delivery in the late 1980s. The paper also discusses the importance of in-process quality control throughout manufacturing towards reducing product variability and improving fuel reliability

  1. Recent advances in fuel product and manufacturing process development

    International Nuclear Information System (INIS)

    This paper discusses advancements in commercial nuclear fuel products and manufacturing made by the Westinghouse Electric Corporation in response to the commercial nuclear fuel industry's demand for high reliability, increased plant availability and improved operating flexibility. The features and benefits of Westinghouse's most advanced fuel products--VANTAGE 5 for PWR plants and QUAD+ for BWR plants--are described, as well as 'high performance' fuel concepts now under development for delivery in the late 1980s. The paper also disusses the importance of in-process quality control throughout manufacturing towards reducing product variability and improving fuel reliability. (author)

  2. The biogenic content of process streams from mechanical-biological treatment plants producing solid recovered fuel. Do the manual sorting and selective dissolution determination methods correlate?

    Science.gov (United States)

    Séverin, Mélanie; Velis, Costas A; Longhurst, Phil J; Pollard, Simon J T

    2010-07-01

    The carbon emissions trading market has created a need for standard methods for the determination of biogenic content (chi(B)) in solid recovered fuels (SRF). We compare the manual sorting (MSM) and selective dissolution methods (SDM), as amended by recent research, for a range of process streams from a mechanical-biological treatment (MBT) plant. The two methods provide statistically different biogenic content values, as expressed on a dry mass basis, uncorrected for ash content. However, they correlate well (r(2)>0.9) and the relative difference between them was <5% for chi(B) between 21% (w)/w(d) and 72% (w)/w(d) (uncorrected for ash content). This range includes the average SRF biogenic content of ca. 68% (w)/w(d). Methodological improvements are discussed in light of recent studies. The repeatability of the SDM is characterised by relative standard deviations on triplicates of <2.5% for the studied population. PMID:20116991

  3. Alternative Fuel for Portland Cement Processing

    Energy Technology Data Exchange (ETDEWEB)

    Schindler, Anton K; Duke, Steve R; Burch, Thomas E; Davis, Edward W; Zee, Ralph H; Bransby, David I; Hopkins, Carla; Thompson, Rutherford L; Duan, Jingran; ; Venkatasubramanian, Vignesh; Stephen, Giles

    2012-06-30

    The production of cement involves a combination of numerous raw materials, strictly monitored system processes, and temperatures on the order of 1500 °C. Immense quantities of fuel are required for the production of cement. Traditionally, energy from fossil fuels was solely relied upon for the production of cement. The overarching project objective is to evaluate the use of alternative fuels to lessen the dependence on non-renewable resources to produce portland cement. The key objective of using alternative fuels is to continue to produce high-quality cement while decreasing the use of non-renewable fuels and minimizing the impact on the environment. Burn characteristics and thermodynamic parameters were evaluated with a laboratory burn simulator under conditions that mimic those in the preheater where the fuels are brought into a cement plant. A drop-tube furnace and visualization method were developed that show potential for evaluating time- and space-resolved temperature distributions for fuel solid particles and liquid droplets undergoing combustion in various combustion atmospheres. Downdraft gasification has been explored as a means to extract chemical energy from poultry litter while limiting the throughput of potentially deleterious components with regards to use in firing a cement kiln. Results have shown that the clinkering is temperature independent, at least within the controllable temperature range. Limestone also had only a slight effect on the fusion when used to coat the pellets. However, limestone addition did display some promise in regards to chlorine capture, as ash analyses showed chlorine concentrations of more than four times greater in the limestone infused ash as compared to raw poultry litter. A reliable and convenient sampling procedure was developed to estimate the combustion quality of broiler litter that is the best compromise between convenience and reliability by means of statistical analysis. Multi-day trial burns were conducted

  4. Alternative Fuel for Portland Cement Processing

    Energy Technology Data Exchange (ETDEWEB)

    Anton K. Schindler; Steve R. Duke; Thomas E. Burch; Edward W. Davis; Ralph H. Zee; David I. Bransby; Carla Hopkins; Rutherford L. Thompson; Jingran Duan; Vignesh Venkatasubramanian; Stephen Giles.

    2012-06-30

    The production of cement involves a combination of numerous raw materials, strictly monitored system processes, and temperatures on the order of 1500 °C. Immense quantities of fuel are required for the production of cement. Traditionally, energy from fossil fuels was solely relied upon for the production of cement. The overarching project objective is to evaluate the use of alternative fuels to lessen the dependence on non-renewable resources to produce portland cement. The key objective of using alternative fuels is to continue to produce high-quality cement while decreasing the use of non-renewable fuels and minimizing the impact on the environment. Burn characteristics and thermodynamic parameters were evaluated with a laboratory burn simulator under conditions that mimic those in the preheater where the fuels are brought into a cement plant. A drop-tube furnace and visualization method were developed that show potential for evaluating time- and space-resolved temperature distributions for fuel solid particles and liquid droplets undergoing combustion in various combustion atmospheres. Downdraft gasification has been explored as a means to extract chemical energy from poultry litter while limiting the throughput of potentially deleterious components with regards to use in firing a cement kiln. Results have shown that the clinkering is temperature independent, at least within the controllable temperature range. Limestone also had only a slight effect on the fusion when used to coat the pellets. However, limestone addition did display some promise in regards to chlorine capture, as ash analyses showed chlorine concentrations of more than four times greater in the limestone infused ash as compared to raw poultry litter. A reliable and convenient sampling procedure was developed to estimate the combustion quality of broiler litter that is the best compromise between convenience and reliability by means of statistical analysis. Multi-day trial burns were conducted

  5. Power plant process computer

    International Nuclear Information System (INIS)

    The concept of instrumentation and control in nuclear power plants incorporates the use of process computers for tasks which are on-line in respect to real-time requirements but not closed-loop in respect to closed-loop control. The general scope of tasks is: - alarm annunciation on CRT's - data logging - data recording for post trip reviews and plant behaviour analysis - nuclear data computation - graphic displays. Process computers are used additionally for dedicated tasks such as the aeroball measuring system, the turbine stress evaluator. Further applications are personal dose supervision and access monitoring. (orig.)

  6. Spent fuel disposal impact on plant decommissioning

    International Nuclear Information System (INIS)

    Regardless of the decommissioning option selected (DECON, SAFSTOR, or ENTOMB), a 10 CFR 50 license cannot be terminated until the spent fuel is either removed from the site or stored in a separately 10 CFR 72 licensed Independent Spent Fuel Storage Installation (ISFSI). Humboldt Bay is an example of a plant which has selected the SAFSTOR option. Its spent fuel is currently in wet storage in the plant's spent fuel pool. When it completes its dormant period and proceeds with dismantlement, it will have to dispose of its fuel or license an ISFSI. Shoreham is an example of a plant which has selected the DECON option. Fuel disposal is currently critical path for license termination. In the event an ISFSI is proposed to resolve the spent fuel removal issue, whether wet or dry, utilities need to properly determine the installation, maintenance, and decommissioning costs for such a facility. In considering alternatives for spent fuel removal, it is important for a utility to properly account for ISFSI decommissioning costs. A brief discussion is presented on one method for estimating ISFSI decommissioning costs

  7. Criticality accident in uranium fuel processing plant. Influence of the critical accident seen to consciousness investigation of the public

    International Nuclear Information System (INIS)

    Here was introduced a consciousness investigation result carried out at Fukui prefecture and Osaka city after about two months of the JCO criticality accident. Peoples were disturbed by the accident, and not a little changed their individual estimations on items relating to energy. However, peoples lived in Fukui prefecture did not increase rate of opposition against nuclear energy promotion and nuclear power plant construction to their living area on comparison with a year before the accident. This reason might be understood by that the accident was not an accident of a nuclear power plant directly, and that their living area was much distant from place of the accident and was not suffered any danger. On the other hand, public opinion in Osaka city made worse on comparison with that before a year, and if such worse public opinion was thought to be due to the accident, its effect could be said to be different in each area even with no direct relation to the accident to shown a result dependent upon its various conditions. As a rough tendency on psychological disturbance due to the accident, it could be said that peoples became to have feelings of avoiding hard nuclear energy technology at a chance of the accident and to direct thoughts of soft natural energy and environment respect. (G.K.)

  8. Uranium Fuel Plant. Applicants environmental report

    International Nuclear Information System (INIS)

    The Uranium Fuel Plant, located at the Cimarron Facility, was constructed in 1964 with operations commencing in 1965 in accordance with License No. SNM-928, Docket No. 70-925. The plant has been in continuous operation since the issuance of the initial license and currently possesses contracts extending through 1978, for the production of nuclear fuels. The Uranium Plant is operated in conjunction with the Plutonium Facility, each sharing common utilities and sanitary wastes disposal systems. The operation has had little or no detrimental ecological impact on the area. For the operation of the Uranium Fuel Fabrication Plant, initial equipment provided for the production of UO2, UF4, uranium metal and recovery of scrap materials. In 1968, the plant was expanded by increasing the UO2 and pellet facilities by the installation of another complete production line for the production of fuel pellets. In 1969, fabrication facilities were added for the production of fuel elements. Equipment initially installed for the recovery of fully enriched scrap has not been used since the last work was done in 1970. Economically, the plant has benefited the Logan County area, with approximately 104 new jobs with an annual payroll of approximately $1.3 million. In addition, $142,000 is annually paid in taxes to state, local and federal governments, and local purchases amount to approximately $1.3 million. This was all in land that was previously used for pasture land, with a maximum value of approximately 37,000 dollars. Environmental effects of plant operation have been minimal. A monitoring and measurement program is maintained in order to ensure that the ecology of the immediate area is not affected by plant operations

  9. Idaho Chemical Processing Plant Site Development Plan

    International Nuclear Information System (INIS)

    The Idaho Chemical Processing Plant (ICPP) mission is to receive and store spent nuclear fuels and radioactive wastes for disposition for Department of Energy (DOE) in a cost-effective manner that protects the safety of Idaho National Engineering Laboratory (INEL) employees, the public, and the environment by: Developing advanced technologies to process spent nuclear fuel for permanent offsite disposition and to achieve waste minimization. Receiving and storing Navy and other DOE assigned spent nuclear fuels. Managing all wastes in compliance with applicable laws and regulations. Identifying and conducting site remediation consistent with facility transition activities. Seeking out and implementing private sector technology transfer and cooperative development agreements. Prior to April 1992, the ICPP mission included fuel reprocessing. With the recent phaseout of fuel reprocessing, some parts of the ICPP mission have changed. Others have remained the same or increased in scope

  10. Microbial fuel cell treatment of fuel process wastewater

    Science.gov (United States)

    Borole, Abhijeet P; Tsouris, Constantino

    2013-12-03

    The present invention is directed to a method for cleansing fuel processing effluent containing carbonaceous compounds and inorganic salts, the method comprising contacting the fuel processing effluent with an anode of a microbial fuel ell, the anode containing microbes thereon which oxidatively degrade one or more of the carbonaceous compounds while producing electrical energy from the oxidative degradation, and directing the produced electrical energy to drive an electrosorption mechanism that operates to reduce the concentration of one or more inorganic salts in the fuel processing effluent, wherein the anode is in electrical communication with a cathode of the microbial fuel cell. The invention is also directed to an apparatus for practicing the method.

  11. Description of Finnish spent fuel encapsulation plant and encapsulation process. Phase I Interim report on Task FIN A 1184 of the Finnish support program to IAEA Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Honkamaa, T. [Radiation and Nuclear Safety Authority, Helsinki (Finland); Kukkola, T. [Fortum Engineering Ltd, Vantaa (Finland)

    1999-10-01

    This report presents a preliminary, detailed design of the encapsulation plant envisaged in the final disposal programme of spent fuel of Posiva ltd. The design information gives good basis for design information verification. Possible diversion scenarios can be identified and guidelines for initial safeguards approach can be suggested. Reviewing the design with present IAEA requirements for conditioning facility and existing experience of IAEA and EURATOM will give valuable information for further improvements. (orig.)

  12. Holdup measurement for nuclear fuel manufacturing plants

    Energy Technology Data Exchange (ETDEWEB)

    Zucker, M.S.; Degen, M.; Cohen, I.; Gody, A.; Summers, R.; Bisset, P.; Shaub, E.; Holody, D.

    1981-07-13

    The assay of nuclear material holdup in fuel manufacturing plants is a laborious but often necessary part of completing the material balance. A range of instruments, standards, and a methodology for assaying holdup has been developed. The objectives of holdup measurement are ascertaining the amount, distribution, and how firmly fixed the SNM is. The purposes are reconciliation of material unbalance during or after a manufacturing campaign or plant decommissioning, to decide security requirements, or whether further recovery efforts are justified.

  13. Advanced coal gasifier-fuel cell power plant systems design

    Science.gov (United States)

    Heller, M. E.

    1983-01-01

    Two advanced, high efficiency coal-fired power plants were designed, one utilizing a phosphoric acid fuel cell and one utilizing a molten carbonate fuel cell. Both incorporate a TRW Catalytic Hydrogen Process gasifier and regenerator. Both plants operate without an oxygen plant and without requiring water feed; they, instead, require makeup dolomite. Neither plant requires a shift converter; neither plant has heat exchangers operating above 1250 F. Both plants have attractive efficiencies and costs. While the molten carbonate version has a higher (52%) efficiency than the phosphoric acid version (48%), it also has a higher ($0.078/kWh versus $0.072/kWh) ten-year levelized cost of electricity. The phosphoric acid fuel cell power plant is probably feasible to build in the near term: questions about the TRW process need to be answered experimentally, such as weather it can operate on caking coals, and how effective the catalyzed carbon-dioxide acceptor will be at pilot scale, both in removing carbon dioxide and in removing sulfur from the gasifier.

  14. Plant microbial fuel cell applied in wetlands

    NARCIS (Netherlands)

    Wetser, Koen; Liu, Jia; Buisman, Cees; Strik, David

    2015-01-01

    The plant microbial fuel cell (PMFC) has to be applied in wetlands to be able to generate electricity on a large scale. The objective of this PMFC application research is to clarify the differences in electricity generation between a Spartina anglica salt marsh and Phragmites australis peat soil

  15. Complex plasmochemical processing of solid fuel

    Directory of Open Access Journals (Sweden)

    Vladimir Messerle

    2012-12-01

    Full Text Available Technology of complex plasmaochemical processing of solid fuel by Ecibastuz bituminous and Turgay brown coals is presented. Thermodynamic and experimental study of the technology was fulfilled. Use of this technology allows producing of synthesis gas from organic mass of coal and valuable components (technical silicon, ferrosilicon, aluminum and silicon carbide and microelements of rare metals: uranium, molybdenum, vanadium etc. from mineral mass of coal. Produced a high-calorific synthesis gas can be used for methanol synthesis, as high-grade reducing gas instead of coke, as well as energy gas in thermal power plants.

  16. The element technology of clean fuel alcohol plant construction

    Energy Technology Data Exchange (ETDEWEB)

    Lee, D.S; Lee, D.S. [Sam-Sung Engineering Technical Institute (Korea, Republic of); Choi, C.Y [Seoul National University, Seoul (Korea, Republic of)] [and others

    1996-02-01

    The fuel alcohol has been highlighted as a clean energy among new renewable energy sources. However, the production of the fuel alcohol has following problems; (i)bulk distillate remains is generated and (ii) benzene to be used as a entertainer in the azeotropic distillation causes the environmental problem. Thus, we started this research on the ground of preserving the cleanness in the production of fuel alcohol, a clean energy. We examined the schemes of replacing the azotropic distillation column which causes the problems with MSDP(Molecular Sieve Dehydration Process) system using adsorption technology and of treating the bulk distillate remains to be generated as by-products. In addition, we need to develop the continuous yea station technology for the continuous operation of fuel alcohol plant as a side goal. Thus, we try to develop a continuous ethanol fermentation process by high-density cell culture from tapioca, a industrial substrate, using cohesive yeast. For this purpose, we intend to examine the problem of tapioca, a industrial substrate, where a solid is existed and develop a new process which can solve the problem. Ultimately, the object of this project is to develop each element technology for the construction of fuel alcohol plant and obtain the ability to design the whole plant. (author) 54 refs., 143 figs., 34 tabs.

  17. Design of MOX fuel fabrication plant for Indian PFBR

    International Nuclear Information System (INIS)

    The energy demand is expected to grow rapidly in the coming decades. Fast reactors are expected to be major contributors in sufficing this demand to a great extent. Fast reactors with a co-located fuel cycle facility extend self sufficiency and closing of fuel cycle by recycling of discharged fuel i.e. Plutonium and Uranium. Fuel fabrication facility has a crucial role to play because of limited time period to meet the recurring reload requirements of the reactor. Conventional powder pellet route comprising of various powder metallurgical unit operations is employed for fabrication of fuel. These unit operations are carried out in glove boxes. Automation schemes for handling and transfer of material in the glove box train has been developed. The plant has been analysed for various hazard because of natural and man-made events. Consequence analysis of various postulated events/accidents like criticality, fire, loss of confinement has been carried out. A process layout with branching (hybrid layout) of the glove box train for optimal utilisation of equipment's has been considered. Highly imbalanced time period of different unit operation process necessitates time cycle analysis. Additionally radioactive material inventory limits due to criticality and dose considerations have also been taken into account in the analysis. A code has been developed to simulate this material movement through the optimized process layout. This paper discusses various issues mentioned above for design of a MOX fuel fabrication plant

  18. Modeling of advanced fossil fuel power plants

    Science.gov (United States)

    Zabihian, Farshid

    The first part of this thesis deals with greenhouse gas (GHG) emissions from fossil fuel-fired power stations. The GHG emission estimation from fossil fuel power generation industry signifies that emissions from this industry can be significantly reduced by fuel switching and adaption of advanced power generation technologies. In the second part of the thesis, steady-state models of some of the advanced fossil fuel power generation technologies are presented. The impacts of various parameters on the solid oxide fuel cell (SOFC) overpotentials and outputs are investigated. The detail analyses of operation of the hybrid SOFC-gas turbine (GT) cycle when fuelled with methane and syngas demonstrate that the efficiencies of the cycles with and without anode exhaust recirculation are close, but the specific power of the former is much higher. The parametric analysis of the performance of the hybrid SOFC-GT cycle indicates that increasing the system operating pressure and SOFC operating temperature and fuel utilization factor improves cycle efficiency, but the effects of the increasing SOFC current density and turbine inlet temperature are not favourable. The analysis of the operation of the system when fuelled with a wide range of fuel types demonstrates that the hybrid SOFC-GT cycle efficiency can be between 59% and 75%, depending on the inlet fuel type. Then, the system performance is investigated when methane as a reference fuel is replaced with various species that can be found in the fuel, i.e., H2, CO2, CO, and N 2. The results point out that influence of various species can be significant and different for each case. The experimental and numerical analyses of a biodiesel fuelled micro gas turbine indicate that fuel switching from petrodiesel to biodiesel can influence operational parameters of the system. The modeling results of gas turbine-based power plants signify that relatively simple models can predict plant performance with acceptable accuracy. The unique

  19. Dry Process Fuel Performance Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Myung Seung; Song, K. C.; Moon, J. S. and others

    2005-04-15

    The objective of the project is to establish the performance evaluation system of DUPIC fuel during the Phase II R and D. In order to fulfil this objectives, irradiation test of DUPIC fuel was carried out in HANARO using the non-instrumented and SPND-instrumented rig. Also, the analysis on the in-reactor behavior analysis of DUPIC fuel, out-pile test using simulated DUPIC fuel as well as performance and integrity assessment in a commercial reactor were performed during this Phase. The R and D results of the Phase II are summarized as follows : - Performance evaluation of DUPIC fuel via irradiation test in HANARO - Post irradiation examination of irradiated fuel and performance analysis - Development of DUPIC fuel performance code (modified ELESTRES) considering material properties of DUPIC fuel - Irradiation behavior and integrity assessment under the design power envelope of DUPIC fuel - Foundamental technology development of thermal/mechanical performance evaluation using ANSYS (FEM package)

  20. Solid oxide fuel cell power plant having a bootstrap start-up system

    Energy Technology Data Exchange (ETDEWEB)

    Lines, Michael T

    2016-10-04

    The bootstrap start-up system (42) achieves an efficient start-up of the power plant (10) that minimizes formation of soot within a reformed hydrogen rich fuel. A burner (48) receives un-reformed fuel directly from the fuel supply (30) and combusts the fuel to heat cathode air which then heats an electrolyte (24) within the fuel cell (12). A dilute hydrogen forming gas (68) cycles through a sealed heat-cycling loop (66) to transfer heat and generated steam from an anode side (32) of the electrolyte (24) through fuel processing system (36) components (38, 40) and back to an anode flow field (26) until fuel processing system components (38, 40) achieve predetermined optimal temperatures and steam content. Then, the heat-cycling loop (66) is unsealed and the un-reformed fuel is admitted into the fuel processing system (36) and anode flow (26) field to commence ordinary operation of the power plant (10).

  1. Dry process fuel performance technology development

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Kweon Ho; Kim, K. W.; Kim, B. K. (and others)

    2006-06-15

    The objective of the project is to establish the performance evaluation system of DUPIC fuel during the Phase III R and D. In order to fulfil this objectives, property model development of DUPIC fuel and irradiation test was carried out in Hanaro using the instrumented rig. Also, the analysis on the in-reactor behavior analysis of DUPIC fuel, out-pile test using simulated DUPIC fuel as well as performance and integrity assessment in a commercial reactor were performed during this Phase. The R and D results of the Phase III are summarized as follows: Fabrication process establishment of simulated DUPIC fuel for property measurement, Property model development for the DUPIC fuel, Performance evaluation of DUPIC fuel via irradiation test in Hanaro, Post irradiation examination of irradiated fuel and performance analysis, Development of DUPIC fuel performance code (KAOS)

  2. Fuel corrosion processes under waste disposal conditions

    International Nuclear Information System (INIS)

    The release of the majority of radionuclides from spent nuclear fuel under permanent disposal conditions will be controlled by the rate of dissolution of the UO2 fuel matrix. In this manuscript the mechanism of the coupled anodic (fuel dissolution) and cathodic (oxidant reduction) reactions which constitute the overall fuel corrosion process is reviewed, and the many published observations on fuel corrosion under disposal conditions discussed. The primary emphasis is on summarizing the overall mechanistic behaviour and establishing the primary factors likely to control fuel corrosion. Included are discussions on the influence of various oxidants including radiolytic ones, pH, temperature, groundwater composition, and the formation of corrosion product deposits. The relevance of the data recorded on unirradiated UO2 to the interpretation of spent fuel behaviour is included. Based on the review, the data used to develop fuel corrosion models under the conditions anticipated in Yucca Mountain (NV, USA) are evaluated

  3. Fuel breaks affect nonnative species abundance in Californian plant communities

    Science.gov (United States)

    Merriam, K.E.; Keeley, J.E.; Beyers, J.L.

    2006-01-01

    We evaluated the abundance of nonnative plants on fuel breaks and in adjacent untreated areas to determine if fuel treatments promote the invasion of nonnative plant species. Understanding the relationship between fuel treatments and nonnative plants is becoming increasingly important as federal and state agencies are currently implementing large fuel treatment programs throughout the United States to reduce the threat of wildland fire. Our study included 24 fuel breaks located across the State of California. We found that nonnative plant abundance was over 200% higher on fuel breaks than in adjacent wildland areas. Relative nonnative cover was greater on fuel breaks constructed by bulldozers (28%) than on fuel breaks constructed by other methods (7%). Canopy cover, litter cover, and duff depth also were significantly lower on fuel breaks constructed by bulldozers, and these fuel breaks had significantly more exposed bare ground than other types of fuel breaks. There was a significant decline in relative nonnative cover with increasing distance from the fuel break, particularly in areas that had experienced more numerous fires during the past 50 years, and in areas that had been grazed. These data suggest that fuel breaks could provide establishment sites for nonnative plants, and that nonnatives may invade surrounding areas, especially after disturbances such as fire or grazing. Fuel break construction and maintenance methods that leave some overstory canopy and minimize exposure of bare ground may be less likely to promote nonnative plants. ?? 2006 by the Ecological Society of America.

  4. The Effect of Wood Fuels on Power Plant Availability

    Energy Technology Data Exchange (ETDEWEB)

    Orjala, Markku (Markku.Orjala@vtt.fi); Kaerki, Janne; Vainikka, Pasi [VTT Processes, Jyvaeskylae (Finland)

    2003-11-01

    There is a growing international interest in utilising renewable fuels, also in multifuel applications. Main reasons for this are the objective to reduce CO{sub 2} emissions and meet emission limits for NO{sub x} and SO{sub 2}. On one hand cofiring, defined as simultaneous combustion of different fuels in the same boiler, provides an alternative to achieve emission reductions. This is not only accomplished by replacing fossil fuel with biomass, but also as a result of the interaction of fuel reactants of different origin (e.g. biomass vs. coal). On the other hand, utilisation of solid biofuels and wastes sets new demands for process control and boiler design, as well as for combustion technologies, fuel blend control and fuel handling systems. In the case of wood-based fuels this is because of their high reactivity, high moisture content and combustion residues' high alkaline metal content. Combustion and cofiring properties of fuels have been studied both in VTT Processes' test facilities and in industrial-scale power plant boilers. The formation of alkaline and chlorine compounds in biomass combustion and their effect on boiler fouling and corrosion have been monitored by temperature controlled deposit formation and material monitoring probes. Deposit formation monitoring at full-scale boilers provides unique information on the rate of deposit formation, the effect of sootblowing and consequent changes in heat transfer. Additionally, the data from deposit formation monitoring has been shown to correlate with boiler performance, which gives basis for studying the interrelation of: fuel blend characteristics; deposit formation; boiler performance. If biomass fuels are blended with coal or peat, following implications may be expected: increased rate of deposit formation, shorter sootblowing interval, cleaning of heat transfer surfaces in revisions may be required, bed material agglomeration (in fluidised beds), increased risk of corrosion, higher in

  5. Dynamic simulation of a direct carbonate fuel cell power plant

    Energy Technology Data Exchange (ETDEWEB)

    Ernest, J.B. [Fluor Daniel, Inc., Irvine, CA (United States); Ghezel-Ayagh, H.; Kush, A.K. [Fuel Cell Engineering, Danbury, CT (United States)

    1996-12-31

    Fuel Cell Engineering Corporation (FCE) is commercializing a 2.85 MW Direct carbonate Fuel Cell (DFC) power plant. The commercialization sequence has already progressed through construction and operation of the first commercial-scale DFC power plant on a U.S. electric utility, the 2 MW Santa Clara Demonstration Project (SCDP), and the completion of the early phases of a Commercial Plant design. A 400 kW fuel cell stack Test Facility is being built at Energy Research Corporation (ERC), FCE`s parent company, which will be capable of testing commercial-sized fuel cell stacks in an integrated plant configuration. Fluor Daniel, Inc. provided engineering, procurement, and construction services for SCDP and has jointly developed the Commercial Plant design with FCE, focusing on the balance-of-plant (BOP) equipment outside of the fuel cell modules. This paper provides a brief orientation to the dynamic simulation of a fuel cell power plant and the benefits offered.

  6. UNIFRAME interim design report. [Fuel element size reduction plant

    Energy Technology Data Exchange (ETDEWEB)

    Strand, J.B.; Baer, J.W.; Cook, E.J.

    1977-12-01

    A fuel element size reduction system has been designed for the ''cold'' pilot-scale plant for an HTGR Fuel Reference Recycle Facility. This report describes in detail the present design.

  7. Radiation protection training at uranium hexafluoride and fuel fabrication plants

    International Nuclear Information System (INIS)

    This report provides general information and references useful for establishing or operating radiation safety training programs in plants that manufacture nuclear fuels, or process uranium compounds that are used in the manufacture of nuclear fuels. In addition to a brief summary of the principles of effective management of radiation safety training, the report also contains an appendix that provides a comprehensive checklist of scientific, safety, and management topics, from which appropriate topics may be selected in preparing training outlines for various job categories or tasks pertaining to the uranium nuclear fuels industry. The report is designed for use by radiation safety training professionals who have the experience to utilize the report to not only select the appropriate topics, but also to tailor the specific details and depth of coverage of each training session to match both employee and management needs of a particular industrial operation. 26 refs., 3 tabs

  8. ATRIUMTM Fuel - Continuous Upgrading for High Duty BWR Plants

    International Nuclear Information System (INIS)

    AREVA NP is a supplier of nuclear fuel assemblies and associated core components to Boiling Water Reactors worldwide, representing today more than 60 000 fuel assemblies. Since first delivered in 1992, ATRIUMTM10 fuel assemblies have now been supplied to a total of 32 BWR plants in the US, Europe, and Asia resulting in an operating experience over 20 000 fuel assemblies. Among them, the latest versions are ATRIUMTM 10XP and ATRIUMTM 10XM fuel assemblies which have been delivered to several utilities worldwide. During six years of operation experience reaching a maximum fuel assembly burnup of 66 MWd/kgU, no fuel failure of ATRIUMTM 10XP/XM occurred. Regular upgrading of the fuel assemblies' reliability and performance has been made possible thanks to AREVA NP's continuous improvement process and the 'Zero tolerance for failure' program. In this frame, the in-core behavior follow-up, manufacturing experience feedback and customer expectations are the bases for setting improvement management objectives. As an example, most fuel rod failures observed in the past years resulted from debris fretting and Pellet Cladding Interaction (PCI) generally caused by Missing Pellet Surface. To address these issues, the development of the Improved FUELGUARDTM debris filter was initiated and completed while implementation of chamfered pellets and Cr doped fuel will address PCI aspects. In the case of fuel channel bow issue, efforts to ensure dimensional stability at high burnup levels and under challenging corrosion environments have been done resulting in material recommendations and process developments. All the described solutions will strongly support the INPO goal of 'Zero fuel failures by 2010'. In a longer perspective, the significant trend in nuclear fuel operation is to increase further the discharge burnup and/or to increase the reactor power output. In the majority of nuclear power plants worldwide, strong efforts in power up-rating were made and are still ongoing. Most

  9. Integrated international safeguards concepts for fuel reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Hakkila, E.A.; Gutmacher, R.G.; Markin, J.T.; Shipley, J.P.; Whitty, W.J.; Camp, A.L.; Cameron, C.P.; Bleck, M.E.; Ellwein, L.B.

    1981-12-01

    This report is the fourth in a series of efforts by the Los Alamos National Laboratory and Sandia National Laboratories, Albuquerque, to identify problems and propose solutions for international safeguarding of light-water reactor spent-fuel reprocessing plants. Problem areas for international safeguards were identified in a previous Problem Statement (LA-7551-MS/SAND79-0108). Accounting concepts that could be verified internationally were presented in a subsequent study (LA-8042). Concepts for containment/surveillance were presented, conceptual designs were developed, and the effectiveness of these designs was evaluated in a companion study (SAND80-0160). The report discusses the coordination of nuclear materials accounting and containment/surveillance concepts in an effort to define an effective integrated safeguards system. The Allied-General Nuclear Services fuels reprocessing plant at Barnwell, South Carolina, was used as the reference facility.

  10. Integrated international safeguards concepts for fuel reprocessing

    International Nuclear Information System (INIS)

    This report is the fourth in a series of efforts by the Los Alamos National Laboratory and Sandia National Laboratories, Albuquerque, to identify problems and propose solutions for international safeguarding of light-water reactor spent-fuel reprocessing plants. Problem areas for international safeguards were identified in a previous Problem Statement (LA-7551-MS/SAND79-0108). Accounting concepts that could be verified internationally were presented in a subsequent study (LA-8042). Concepts for containment/surveillance were presented, conceptual designs were developed, and the effectiveness of these designs was evaluated in a companion study (SAND80-0160). The report discusses the coordination of nuclear materials accounting and containment/surveillance concepts in an effort to define an effective integrated safeguards system. The Allied-General Nuclear Services fuels reprocessing plant at Barnwell, South Carolina, was used as the reference facility

  11. Mathematical modeling of biomass fuels formation process.

    Science.gov (United States)

    Gaska, Krzysztof; Wandrasz, Andrzej J

    2008-01-01

    The increasing demand for thermal and electric energy in many branches of industry and municipal management accounts for a drastic diminishing of natural resources (fossil fuels). Meanwhile, in numerous technical processes, a huge mass of wastes is produced. A segregated and converted combustible fraction of the wastes, with relatively high calorific value, may be used as a component of formed fuels. The utilization of the formed fuel components from segregated groups of waste in associated processes of co-combustion with conventional fuels causes significant savings resulting from partial replacement of fossil fuels, and reduction of environmental pollution resulting directly from the limitation of waste migration to the environment (soil, atmospheric air, surface and underground water). The realization of technological processes with the utilization of formed fuel in associated thermal systems should be qualified by technical criteria, which means that elementary processes as well as factors of sustainable development, from a global viewpoint, must not be disturbed. The utilization of post-process waste should be preceded by detailed technical, ecological and economic analyses. In order to optimize the mixing process of fuel components, a mathematical model of the forming process was created. The model is defined as a group of data structures which uniquely identify a real process and conversion of this data in algorithms based on a problem of linear programming. The paper also presents the optimization of parameters in the process of forming fuels using a modified simplex algorithm with a polynomial worktime. This model is a datum-point in the numerical modeling of real processes, allowing a precise determination of the optimal elementary composition of formed fuels components, with assumed constraints and decision variables of the task.

  12. Environmental monitoring at the Barnwell low level radioactive waste disposal site

    Energy Technology Data Exchange (ETDEWEB)

    Ragan, F.A. [South Carolina Dept. of Health and Environmental Control, Columbia, SC (United States)

    1989-11-01

    The Barnwell site has undergone an evolution to achieve the technology which is utilized today. A historical background will be presented along with an overview of present day operations. This paper will emphasize the environmental monitoring program: the types of samples taken, the methods of compiling and analyzing data, modeling, and resulting actions.

  13. Forecast of environment influence of the Ukrainian nuclear fuel plant

    International Nuclear Information System (INIS)

    Problem of site selection for the Ukrainian nuclear fuel plant is considered. Ecological influence of the site and possible contamination levels are calculated for normal and emergency situations in plant operation

  14. Process control in biogas plants

    DEFF Research Database (Denmark)

    Holm-Nielsen, Jens Bo; Oleskowicz-Popiel, Piotr

    2013-01-01

    Efficient monitoring and control of anaerobic digestion (AD) processes are necessary in order to enhance biogas plant performance. The aim of monitoring and controlling the biological processes is to stabilise and optimise the production of biogas. The principles of process analytical technology...

  15. Multispectral Image Processing for Plants

    Science.gov (United States)

    Miles, Gaines E.

    1991-01-01

    The development of a machine vision system to monitor plant growth and health is one of three essential steps towards establishing an intelligent system capable of accurately assessing the state of a controlled ecological life support system for long-term space travel. Besides a network of sensors, simulators are needed to predict plant features, and artificial intelligence algorithms are needed to determine the state of a plant based life support system. Multispectral machine vision and image processing can be used to sense plant features, including health and nutritional status.

  16. Structural Materials and Fuels for Space Power Plants

    Science.gov (United States)

    Bowman, Cheryl; Busby, Jeremy; Porter, Douglas

    2008-01-01

    A fission reactor combined with Stirling convertor power generation is one promising candidate in on-going Fission Surface Power (FSP) studies for future lunar and Martian bases. There are many challenges for designing and qualifying space-rated nuclear power plants. In order to have an affordable and sustainable program, NASA and DOE designers want to build upon the extensive foundation in nuclear fuels and structural materials. This talk will outline the current Fission Surface Power program and outline baseline design options for a lunar power plant with an emphasis on materials challenges. NASA first organized an Affordable Fission Surface Power System Study Team to establish a reference design that could be scrutinized for technical and fiscal feasibility. Previous papers and presentations have discussed this study process in detail. Considerations for the reference design included that no significant nuclear technology, fuels, or material development were required for near term use. The desire was to build upon terrestrial-derived reactor technology including conventional fuels and materials. Here we will present an overview of the reference design, Figure 1, and examine the materials choices. The system definition included analysis and recommendations for power level and life, plant configuration, shielding approach, reactor type, and power conversion type. It is important to note that this is just one concept undergoing refinement. The design team, however, understands that materials selection and improvement must be an integral part of the system development.

  17. Analysis of gas turbine integrated cogeneration plant: Process integration approach

    International Nuclear Information System (INIS)

    Cogeneration is defined as generation of two forms of energy viz. heat and work using single primary fuel. Cogeneration or combined heat and power (CHP) is important in improving energy efficiency of the overall plant and in reducing environmental pollution. A methodology, based on pinch analysis, is proposed in this paper to integrate gas turbine and regenerator with a process plant to minimize fuel consumption. Thermodynamic analysis of gas turbine integrated CHP plant is presented on gas turbine pressure ratio versus power to heat ratio diagram. On this novel diagram, limits of integration are identified and various regions of integration are represented. Additionally, contour plots of energy utilization factors and fuel energy saving ratios are represented on this diagram for optimal integration of gas turbine with a process plant. It is interesting to note that though the contour plots of energy utilization factors and fuel energy saving ratios differ significantly, loci of the maximal energy utilization factor and the maximal fuel energy saving ratio are identical. Optimum sizing of gas turbine integrated cogeneration plant for grassroots design and retrofitting are performed based on these diagrams. - Highlights: • Methodology for direct integration of gas turbine, regenerator, and process plant. • Integrated system analysis plotted on turbine pressure ratio vs. power to heat ratio. • Regions of integration are identified on this new diagram. • Variations of energy utilization factor and fuel energy saving ratio are indicated. • Optimal sizing of integrated gas turbine for retrofitting and grassroots design

  18. Exergy-based Comparative Assessment of “Zero CO2 Emission” Coal Gasification Processes Feeding H2 –Fueled Power Plants

    Directory of Open Access Journals (Sweden)

    Paolo Fiorini

    2006-03-01

    Full Text Available A modular Process Simulator, CAMEL®, developed by the University of Roma 1, has been applied to analyse a series of “zero emissions” high efficiency cycles. This paper compares three different cycles integrated with CO2 separation technologies based on chemical or physical absorption upstream of the combustion process: pure hydrogen is burnt in presence of pure oxygen to produce superheated steam. All solutions are based on nonconventional plant configurations: two of them are H2/O2 cycles and the third one is the so called ZECOTECH® cycle. The main features of all three configurations are presented and their thermodynamic cycles are simulated in order to perform an exergy analysis.

  19. High burnup fast reactor fuel: processing and waste management experiences

    International Nuclear Information System (INIS)

    The routine processing of mixed Plutonium/Uranium oxide fuels from the Prototype Fast Reactor (PFR) at Dounreay began in September 1980 and the design features of the modified Dounreay Fast Reactor (DFR) reprocessing plant and experience of the first active campaign were described in a paper to the British Nuclear Engineering Society in November 1981 (1). Since then progress in processing the fuel discharged from PFR has been covered briefly in a number of papers to international conferences and the Public Inquiry held in 1986 into the outline planning application for the proposed European Demonstration Reprocessing Plant. During this decade considerable experience in the operation of fast reactors and associated fuel plants has been accumulated providing confidence in the system before entering the next development phase - that of its commercial demonstration. Confidence in the UK draws on the successful operation of the PFR and the associated Dounreay fuel reprocessing and BNF Sellafield fabrication plants. Of equal importance is public confidence in safe operation and in the management of wastes generated by a fast reactor system. The present paper is a review of fast reactor reprocessing and waste management at the Dounreay Nuclear Establishment (DNE) as a contribution to the present status of the fast reactor system

  20. Process and plant safety

    CERN Document Server

    Hauptmanns, Ulrich

    2015-01-01

    Accidents in technical installations are random events. Hence they cannot be totally avoided. Only the probability of their occurrence may be reduced and their consequences be mitigated. The book proceeds from hazards caused by materials and process conditions to indicating technical and organizational measures for achieving the objectives of reduction and mitigation. Qualitative methods for identifying weaknesses of design and increasing safety as well as models for assessing accident consequences are presented. The quantitative assessment of the effectiveness of safety measures is explained. The treatment of uncertainties plays a role there. They stem from the random character of the accident and from lacks of knowledge on some of the phenomena to be addressed. The reader is acquainted with the simulation of accidents, safety and risk analyses and learns how to judge the potential and limitations of mathematical modelling. Risk analysis is applied amongst others to “functional safety” and the determinat...

  1. Assessment and comparison of 100-MW coal gasification phosphoric acid fuel cell power plants

    Science.gov (United States)

    Lu, Cheng-Yi

    1988-01-01

    One of the advantages of fuel cell (FC) power plants is fuel versatility. With changes only in the fuel processor, the power plant will be able to accept a variety of fuels. This study was performed to design process diagrams, evaluate performance, and to estimate cost of 100 MW coal gasifier (CG)/phosphoric acid fuel cell (PAFC) power plant systems utilizing coal, which is the largest single potential source of alternate hydrocarbon liquids and gases in the United States, as the fuel. Results of this study will identify the most promising integrated CG/PAFC design and its near-optimal operating conditions. The comparison is based on the performance and cost of electricity which is calculated under consistent financial assumptions.

  2. Mass Customization of process plants

    DEFF Research Database (Denmark)

    Hvam, Lars

    2006-01-01

    This case study describes how F.L.Smidth A/S, a manufacturer of large processing plants for cement production, has applied the principles of mass customisation in the area of highly complex, custom engineered products. The company has based its sales process on a configuration system to achieve...

  3. Fuel handling and storage systems in nuclear power plants

    International Nuclear Information System (INIS)

    The scope of this Guide includes the design of handling and storage facilities for fuel assemblies from the receipt of fuel into the nuclear power plant until the fuel departs from that plant. The unirradiated fuel considered in this Guide is assumed not to exhibit any significant level of radiation so that it can be handled without shielding or cooling. This Guide also gives limited consideration to the handling and storage of certain core components. While the general design and safety principles are discussed in Section 2 of this Guide, more specific design requirements for the handling and storage of fuel are given in detailed sections which follow the general design and safety principles. Further useful information is to be found in the IAEA Technical Reports Series No. 189 ''Storage, Handling and Movement of Fuel and Related Components at Nuclear Power Plants'' and No. 198 ''Guide to the Safe Handling of Radioactive Wastes at Nuclear Power Plants''. However, the scope of the Guide does not include consideration of the following: (1) The various reactor physics questions associated with fuel and absorber loading and unloading into the core; (2) The design aspects of preparation of the reactor for fuel loading (such as the removal of the pressure vessel head for a light water reactor) and restoration after loading; (3) The design of shipping casks; (4) Fuel storage of a long-term nature exceeding the design lifetime of the nuclear power plant; (5) Unirradiated fuel containing plutonium

  4. Fuel ethanol production using nuclear-plant steam

    International Nuclear Information System (INIS)

    In the United States, the production of fuel ethanol from corn for cars and light trucks has increased from about 6 billion liters per year in 2000 to 19 billion liters per year in 2006. A third of the world's liquid fuel demands could ultimately be obtained from biomass. The production of fuel ethanol from biomass requires large quantities of steam. For a large ethanol plant producing 380 million liters of fuel ethanol from corn per year, about 80 MW(t) of 1-MPa (∼180 deg. C) steam is required. Within several decades, the steam demand for ethanol plants in the United States is projected to be tens of gigawatts, with the worldwide demand being several times larger. This market may become the largest market for cogeneration of steam from nuclear electric power plants. There are strong incentives to use steam from nuclear power plants to meet this requirement. The cost of low-pressure steam from nuclear power plants is less than that of natural gas, which is now used to make steam in corn-to-ethanol plants. Steam from nuclear power plants reduces greenhouse gases compared with steam produced from fossil fuels. While ethanol is now produced from sugarcane and corn, the next-generation ethanol plants will use more abundant cellulose feedstocks. It is planned that these plants will burn the lignin in the cellulosic feedstocks to provide the required steam. Lignin is the primary non-sugar-based component in cellulosic biomass that can not be converted to ethanol. Low-cost steam from nuclear plants creates the option of converting the lignin to other liquid fuels and thus increase the liquid fuel production per unit of biomass. Because liquid fuel production from biomass is ultimately limited by the availability of biomass, steam from nuclear plants can ultimately increase the total liquid fuels produced from biomass. (author)

  5. 78 FR 66986 - Notice of Opportunity for Public Comment on Surplus Property Release at Barnwell County Airport...

    Science.gov (United States)

    2013-11-07

    ... Airport be used for aeronautical purposes. Currently, ownership of the property provides for protection of... location. SUPPLEMENTARY INFORMATION: The FAA is reviewing a request by the County of Barnwell to release...

  6. Biomass conversion processes for energy and fuels

    Science.gov (United States)

    Sofer, S. S.; Zaborsky, O. R.

    The book treats biomass sources, promising processes for the conversion of biomass into energy and fuels, and the technical and economic considerations in biomass conversion. Sources of biomass examined include crop residues and municipal, animal and industrial wastes, agricultural and forestry residues, aquatic biomass, marine biomass and silvicultural energy farms. Processes for biomass energy and fuel conversion by direct combustion (the Andco-Torrax system), thermochemical conversion (flash pyrolysis, carboxylolysis, pyrolysis, Purox process, gasification and syngas recycling) and biochemical conversion (anaerobic digestion, methanogenesis and ethanol fermentation) are discussed, and mass and energy balances are presented for each system.

  7. Decommissioning of B and W's fuel conversion plant

    International Nuclear Information System (INIS)

    B and W is managing an ongoing $65 million Project involving the site characterization, decontamination, and deconstruction of its former nuclear fuel fabrication plant in Apollo, Pennsylvania. This 90,000 ft facility was used from the late 1950's until the early 1980's for the conversion of uranium hexafluoride to various fuel forms, including uranium dioxide powder and pellets. Both high- and low-enriched uranium as well as thorium were processed in the facility. Upon discontinuing fuel manufacturing operations, the chemical processing equipment was decontaminated, removed, packaged, and shipped to a licensed low-level radioactive waste (LLRW) burial site. As a result of plant operations, uranium contamination existed within the building and in the soils on the plant site. A detailed site characterization program was completed to establish the extent of contamination and to plan the subsequent soil remediation and building deconstruction efforts. As a result of several factors, B and W made the decision in 1990 to accelerate the final decommissioning of the Apollo site. These factors also became constraints on the completion of the project: Rapidly escalating waste disposal costs, with LLRW burial site surcharges scheduled to increase from $40 to $120 per cubic foot in January 1992; Increasing regulatory confusion on the criteria for the residual radioactivity contamination levels that can remain on an NRC-licensed site being remediated for unlicensed, unrestricted use; The probable loss of burial site alternatives in January 1993 due to the provisions of the Low-Level Radioactive Waste Policy Amendments Act of 1985; Delays in the siting and construction of the Appalachian Compact's burial site which is projected to have a capacity insufficient to handle the large volume of waste produced by a major decommissioning project. This paper presents an overview of this decontamination and decommissioning project with emphasis on the key business issues which

  8. Progress and prospects for phosphoric acid fuel cell power plants

    Energy Technology Data Exchange (ETDEWEB)

    Bonville, L.J.; Scheffler, G.W.; Smith, M.J. [International Fuel Cells Corp., South Windsor, CT (United States)

    1996-12-31

    International Fuel Cells (IFC) has developed the fuel cell power plant as a new, on-site power generation source. IFC`s commercial fuel cell product is the 200-kW PC25{trademark} power plant. To date over 100 PC25 units have been manufactured. Fleet operating time is in excess of one million hours. Individual units of the initial power plant model, the PC25 A, have operated for more than 30,000 hours. The first model {open_quotes}C{close_quotes} power plant has over 10,000 hours of operation. The manufacturing, application and operation of this power plant fleet has established a firm base for design and technology development in terms of a clear understanding of the requirements for power plant reliability and durability. This fleet provides the benchmark against which power plant improvements must be measured.

  9. Optimal sizes and siting of nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    The expansion of a nuclear economy entails the development of fuel process and reprocessing plant programmes. The model proposed makes it possible to select the size, the site and the start-up schedule of the plants in such a way as to minimize the total freight and reprocessing costs. As an illustration, we have approached the problem of burnt natural uranium processing plants related to natural uranium-graphite as nuclear power stations. The sites and annual output of the reactors, the possible plant sites and cost functions (freight and reprocessing) are supposed to be known. The method consists in first approaching the process plant problem as a Dynamic Programming problem, increasing programme slices (total reactor output) being explored sequentially. When the quantities of burnt natural uranium to be reprocessed are fixed, the minimization of the transport cost is then also carried out as a dynamic programming problem. The neighbourhood of the optimum process cost is explored in order to find the minimum summation of a suboptimal processing cost and corresponding optimal transport cost. As the reprocessing problem can be represented on a sequential graph, in order to compute the sub-optima, we developed and used a 'reflexion algorithm'. The method can be interpreted as a general mechanism for determining the optimum when to a sequential dynamic problem (for example an equipment programme) is added a complementary problem (transport, for instance). It also makes it possible to estimate the economic losses which result from the choice of a non optimal policy for other than economic reasons. (author)

  10. Flowsheet for shear/leach processing of N Reactor fuel at PUREX

    International Nuclear Information System (INIS)

    This document was originally prepared to support the restart of the PUREX plant using a new Shear/Leach head end process. However, the PUREX facility was shutdown and processing of the remaining N Reactor fuel is no longer considered an alternative for fuel disposition. This document is being issued for reference only to document the activities which were investigated to incorporate the shear/leach process in the PUREX plant

  11. Flowsheet for shear/leach processing of N Reactor fuel at PUREX

    Energy Technology Data Exchange (ETDEWEB)

    Enghusen, M.B.

    1995-04-13

    This document was originally prepared to support the restart of the PUREX plant using a new Shear/Leach head end process. However, the PUREX facility was shutdown and processing of the remaining N Reactor fuel is no longer considered an alternative for fuel disposition. This document is being issued for reference only to document the activities which were investigated to incorporate the shear/leach process in the PUREX plant.

  12. Intermediate-sized natural gas fueled carbonate fuel cell power plants

    Science.gov (United States)

    Sudhoff, Frederick A.; Fleming, Donald K.

    1994-04-01

    This executive summary of the report describes the accomplishments of the joint US Department of Energy's (DOE) Morgantown Energy Technology Center (METC) and M-C POWER Corporation's Cooperative Research and Development Agreement (CRADA) No. 93-013. This study addresses the intermediate power plant size between 2 megawatt (MW) and 200 MW. A 25 MW natural-gas, fueled-carbonate fuel cell power plant was chosen for this purpose. In keeping with recent designs, the fuel cell will operate under approximately three atmospheres of pressure. An expander/alternator is utilized to expand exhaust gas to atmospheric conditions and generate additional power. A steam-bottoming cycle is not included in this study because it is not believed to be cost effective for this system size. This study also addresses the simplicity and accuracy of a spreadsheet-based simulation with that of a full Advanced System for Process Engineering (ASPEN) simulation. The personal computer can fully utilize the simple spreadsheet model simulation. This model can be made available to all users and is particularly advantageous to the small business user.

  13. Thermodynamic optimization of solid oxide fuel cell based combined cycle cogeneration plant

    Energy Technology Data Exchange (ETDEWEB)

    Odukoya, A.; Reddy, B.V. [University of Ontario Inst. of Technology, Oshawa, ON (Canada). Dept. of Mechanical Engineering; Carretero, J.A. [New Brunswick Univ., Fredericton, NB (Canada). Dept. of Mechanical Engineering

    2010-07-01

    Although coal has the highest greenhouse gas emission of all fossil fuels it is the most abundant of all the fuels. Optimization of new and existing power plant designs will help increase the operational efficiency of power generation. In particular, there is a need to optimize the design and operating parameters of power plants using integrated gasification combined cycle cogeneration technology. This study investigated the optimal operating condition of a co-fired combined cycle cogeneration power plant with solid oxide fuel cell (SOFC) combination fuelled with coal and natural gas. It examined the macroscopic detail of the plant while optimizing the operating parameters of individual components such as the gasifier, the consumption of methane and carbon monoxide in the fuel cell and the consumption of fuel in the combustion chamber of the gas turbine. The optimization of the entire plant was used to determine the best mode of operating the plant for a set of conditions within suggested limits. The study also found efficient ways to perform iterative processes to find exit conditions from the gasifier, fuel cell, gas turbine combustion chamber and exit condition from the gas turbine. The maximum fuel cell net work output, combined cycle net work output, combined cycle thermal efficiency and cogeneration efficiency were determined. The optimal pressure ratio, temperature of operation of the SOFC and, gas turbine inlet temperature were determined using a sequential quadratic program solver based on the Quasi-Newton algorithm. 18 refs., 5 tabs., 2 figs.

  14. Radiation protection aspects in decommissioning of a fuel reprocessing plant

    International Nuclear Information System (INIS)

    The decontamination of a fuel reprocessing plant which underwent partial decommissioning is described. The following radiation protection aspects of the work are discussed: dismantling and removal of process vessels, columns and process off-gas filters; decontamination of various process areas; and management of liquid and solid wastes. The work was completed safely by using personnel protective equipment such as plastic suits and respirators (gas, particulate and fresh air). Total dose commitment for this work was around 3000 man-rems, including dose received by staff for certain jobs related to the operation of a section of the plant. The external dose was kept below the annual limit of 5000 mrems for any individual. No internal contamination incident occurred which caused a dose commitment in excess of 10% of the annual limit. The fact that all the work was completed by the staff normally associated with the operation of the plant contributed significantly to the management and control of personnel exposures. (H.K.)

  15. Idaho Chemical Processing Plant Process Efficiency improvements

    Energy Technology Data Exchange (ETDEWEB)

    Griebenow, B.

    1996-03-01

    In response to decreasing funding levels available to support activities at the Idaho Chemical Processing Plant (ICPP) and a desire to be cost competitive, the Department of Energy Idaho Operations Office (DOE-ID) and Lockheed Idaho Technologies Company have increased their emphasis on cost-saving measures. The ICPP Effectiveness Improvement Initiative involves many activities to improve cost effectiveness and competitiveness. This report documents the methodology and results of one of those cost cutting measures, the Process Efficiency Improvement Activity. The Process Efficiency Improvement Activity performed a systematic review of major work processes at the ICPP to increase productivity and to identify nonvalue-added requirements. A two-phase approach was selected for the activity to allow for near-term implementation of relatively easy process modifications in the first phase while obtaining long-term continuous improvement in the second phase and beyond. Phase I of the initiative included a concentrated review of processes that had a high potential for cost savings with the intent of realizing savings in Fiscal Year 1996 (FY-96.) Phase II consists of implementing long-term strategies too complex for Phase I implementation and evaluation of processes not targeted for Phase I review. The Phase II effort is targeted for realizing cost savings in FY-97 and beyond.

  16. Idaho Chemical Processing Plant Process Efficiency improvements

    International Nuclear Information System (INIS)

    In response to decreasing funding levels available to support activities at the Idaho Chemical Processing Plant (ICPP) and a desire to be cost competitive, the Department of Energy Idaho Operations Office (DOE-ID) and Lockheed Idaho Technologies Company have increased their emphasis on cost-saving measures. The ICPP Effectiveness Improvement Initiative involves many activities to improve cost effectiveness and competitiveness. This report documents the methodology and results of one of those cost cutting measures, the Process Efficiency Improvement Activity. The Process Efficiency Improvement Activity performed a systematic review of major work processes at the ICPP to increase productivity and to identify nonvalue-added requirements. A two-phase approach was selected for the activity to allow for near-term implementation of relatively easy process modifications in the first phase while obtaining long-term continuous improvement in the second phase and beyond. Phase I of the initiative included a concentrated review of processes that had a high potential for cost savings with the intent of realizing savings in Fiscal Year 1996 (FY-96.) Phase II consists of implementing long-term strategies too complex for Phase I implementation and evaluation of processes not targeted for Phase I review. The Phase II effort is targeted for realizing cost savings in FY-97 and beyond

  17. Spent fuel reprocessing system availability definition by process simulation

    International Nuclear Information System (INIS)

    To examine nuclear fuel reprocessing plant operating parameters such as maintainability, reliability, availability, equipment redundancy, and surge storage requirements and their effect on plant throughput, a computer simulation model of integrated HTGR fuel reprocessing plant operations is being developed at General Atomic Company (GA). The simulation methodology and the status of the computer programming completed on reprocessing head end systems is reported

  18. Cost and quality of fuels for electric plants 1993

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    The Cost and Quality of Fuels for Electric Utility Plants (C&Q) presents an annual summary of statistics at the national, Census division, State, electric utility, and plant levels regarding the quantity, quality, and cost of fossil fuels used to produce electricity. The purpose of this publication is to provide energy decision-makers with accurate and timely information that may be used in forming various perspectives on issues regarding electric power.

  19. Water processing in power plants

    International Nuclear Information System (INIS)

    Surface water can be treated to a high degree of efficiency by means of new compact processes. The quantity of chemicals to be dosed can easily be adjusted to the raw water composition by intentional energy supply via agitators. In-line coagulations is a new filtration process for reducing organic substances as well as colloids present in surface water. The content of organic substances can be monitored by measuring the plugging index. Advanced ion-exchanger processes (fluidised-bed, compound fluidised-bed and continuously operating ion exchanger plants) allow the required quantity of chemicals as well as the plant's own water consumption to be reduced, thus minimising the adverse effect on the environment. The reverse-osmosis process is becoming more and more significant due to the low adverse effect on the environment and the given possibilities of automation. As not only ionogenic substances but also organic matter are removed by reverse osmosis, this process is particularly suited for treating surface water to be used as boiler feed water. The process of vacuum degassing has become significant for the cold removal of oxygen. (orig.)

  20. Microbial transformations of radionuclides released from nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    Microorganisms can affect the stability and mobility of the actinides U, Pu, Cm, Am, Np, and the fission products Tc, I, Cs, Sr, released from nuclear fuel reprocessing plants. Under appropriate conditions, microorganisms can alter the chemical speciation, solubility and sorption properties and thus could increase or decrease the concentrations of radionuclides in solution and the bioavailability. Dissolution or immobilization of radionuclides is brought about by direct enzymatic action or indirect non-enzymatic action of microorganisms. Although the physical, chemical, and geochemical processes affecting dissolution, precipitation, and mobilization of radionuclides have been investigated, we have only limited information on the effects of microbial processes. The mechanisms of microbial transformations of the major and minor actinides and the fission products under aerobic and anaerobic conditions in the presence of electron donors and acceptors are reviewed. (author)

  1. MICROBIAL TRANSFORMATIONS OF RADIONUCLIDES RELEASED FROM NUCLEAR FUEL REPROCESSING PLANTS.

    Energy Technology Data Exchange (ETDEWEB)

    FRANCIS,A.J.

    2006-10-18

    Microorganisms can affect the stability and mobility of the actinides U, Pu, Cm, Am, Np, and the fission products Tc, I, Cs, Sr, released from nuclear fuel reprocessing plants. Under appropriate conditions, microorganisms can alter the chemical speciation, solubility and sorption properties and thus could increase or decrease the concentrations of radionuclides in solution and the bioavailability. Dissolution or immobilization of radionuclides is brought about by direct enzymatic action or indirect non-enzymatic action of microorganisms. Although the physical, chemical, and geochemical processes affecting dissolution, precipitation, and mobilization of radionuclides have been investigated, we have only limited information on the effects of microbial processes. The mechanisms of microbial transformations of the major and minor actinides and the fission products under aerobic and anaerobic conditions in the presence of electron donors and acceptors are reviewed.

  2. Hydrogen Separation Membranes for Vision 21 Fossil Fuel Plants

    Energy Technology Data Exchange (ETDEWEB)

    Roark, Shane E.; Mackay, Richard; Sammells, Anthony F.

    2001-11-06

    Eltron Research and team members CoorsTek, McDermott Technology, Sued Chemie, Argonne National Laboratory, and Oak Ridge National Laboratory are developing an environmentally benign, inexpensive, and efficient method for separating hydrogen from gas mixtures produced during industrial processes, such as coal gasification. This objective is being pursued using dense membranes based in part on Eltron-patented ceramic materials with a demonstrated ability for proton and electron conduction. The technical goals are being addressed by modifying single-phase and composite membrane composition and microstructure to maximize proton and electron conductivity without loss of material stability. Ultimately, these materials must enable hydrogen separation at practical rates under ambient and high-pressure conditions, without deactivation in the presence of feedstream components such as carbon dioxide, water, and sulfur. This project was motivated by the Department of Energy (DOE) National Energy Technology Laboratory (NETL) Vision 21 initiative which seeks to economically eliminate environmental concerns associated with the use of fossil fuels. The proposed technology addresses the DOE Vision 21 initiative in two ways. First, this process offers a relatively inexpensive solution for pure hydrogen separation that can be easily incorporated into Vision 21 fossil fuel plants. Second, this process could reduce the cost of hydrogen, which is a clean burning fuel under increasing demand as supporting technologies are developed for hydrogen utilization and storage. Additional motivation for this project arises from the potential of this technology for other applications. By appropriately changing the catalysts coupled with the membrane, essentially the same system can be used to facilitate alkane dehydrogenation and coupling, aromatics processing, and hydrogen sulfide decomposition.

  3. Plant-scale anodic dissolution of unirradiated N-Reactor fuel

    International Nuclear Information System (INIS)

    Anodic dissolution tests were made with unirradiated N-Reactor fuel to determine the fuel segment length, diameter, and shape required for high throughput electrorefiner treatment for ultimate disposal in a geologic repository. Based on these tests, a conceptual design was produced of an electrorefiner for a full-scale plant to process N-Reactor spent fuel. In this design, the diameter of an electrode assembly is about 0.6 m (25 in.). Eight of these assemblies in an electrorefiner would accommodate a 1.333-metric-ton batch of N-Reactor fuel. Electrorefining would proceed at a rate of 40 kg uranium per hour

  4. Process optimization of DUPIC fuel pellet fabrication

    International Nuclear Information System (INIS)

    DUPIC pellets are remotely fabricated by using DUPIC powder prepared by the OREOX treatment of spent fuel pellets. DUPIC pellets were successfully fabricated using spent PWR fuel material with an average discharge burn-up of 27,300 MWd/tU. Sintered density, grain size and surface roughness of the DUPIC pellets were investigated on the basis of CANDU fuel criteria. In order to optimize the DUPIC pellet manufacturing processes, 3 series of experiments for the pre-qualification and 3 series for the qualification were performed. In these experiments, the sintered densities of the pellets ranged from 10.35 g/cm3(95.7 % of T.D.) to 10.43 g/cm3(96.4 % of T.D.) and the average grain size ranged from 14.6 to 14.9 μm. Based on these results, the optimum manufacturing processes of DUPIC pellets have been established. Then, under the control of the QA program developed with the assistance of AECL, 8 series of production runs have been performed to make DUPIC pellets in a batch size of 1 kg. The sintered densities of the fabricated pellets ranged from 10.26 g/cm3 to 10.43 g/cm3. The surface roughness of the ground pellets was less than Ra 0.8 μm by the dry grinding process. As the results of the production runs, DUPIC fuel pellets meeting the standard CANDU fuel specifications were successfully fabricated by the established processes. (author)

  5. Fuel performance of licensed nuclear power plants through 1974

    International Nuclear Information System (INIS)

    General aspects of fuel element design and specific design data for typical Pressurized and Boiling Water Reactors are presented. Based on a literature search, failure modes and specific failures incurred through December 31, 1974 are described, together with a discussion of those problems which have had a significant impact upon plant operation. The relationship between fuel element failures and the resultant coolant activity/radioactive gaseous effluents upon radiation exposure, plant availability and capacity factors, economic impact, and waste management, are discussed. An assessment was made regarding the generation, availability, and use of fuel performance data

  6. Legal, institutional, and political issues in transportation of nuclear materials at the back end of the LWR nuclear fuel cycle

    International Nuclear Information System (INIS)

    A study was conducted to identify major legal and institutional problems and issues in the transportation of spent fuel and associated processing wastes at the back end of the LWR nuclear fuel cycle. (Most of the discussion centers on the transportation of spent fuel, since this activity will involve virtually all of the legal and institutional problems likely to be encountered in moving waste materials, as well.) Actions or approaches that might be pursued to resolve the problems identified in the analysis are suggested. Two scenarios for the industrial-scale transportation of spent fuel and radioactive wastes, taken together, high-light most of the major problems and issues of a legal and institutional nature that are likely to arise: (1) utilizing the Allied General Nuclear Services (AGNS) facility at Barnwell, SC, as a temporary storage facility for spent fuel; and (2) utilizing AGNS for full-scale commercial reprocessing of spent LWR fuel

  7. Legal, institutional, and political issues in transportation of nuclear materials at the back end of the LWR nuclear fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Lippek, H.E.; Schuller, C.R.

    1979-03-01

    A study was conducted to identify major legal and institutional problems and issues in the transportation of spent fuel and associated processing wastes at the back end of the LWR nuclear fuel cycle. (Most of the discussion centers on the transportation of spent fuel, since this activity will involve virtually all of the legal and institutional problems likely to be encountered in moving waste materials, as well.) Actions or approaches that might be pursued to resolve the problems identified in the analysis are suggested. Two scenarios for the industrial-scale transportation of spent fuel and radioactive wastes, taken together, high-light most of the major problems and issues of a legal and institutional nature that are likely to arise: (1) utilizing the Allied General Nuclear Services (AGNS) facility at Barnwell, SC, as a temporary storage facility for spent fuel; and (2) utilizing AGNS for full-scale commercial reprocessing of spent LWR fuel.

  8. The market for utility-scale fuel cell plants

    Science.gov (United States)

    Watanabe, Yasuo; Matsumoto, Masaru; Takasu, Kazuhiko

    This paper is devoted to a survey of the current technology and future market for utility-scale fuel cell plants. The phosphoric acid fuel cell (PAFC) is entering into the stage where it is practically available for use with natural gas. Large capacity plants such as 11, 5 and 1 MW have been installed and operated in Italy and Japan. Their efficiency ranges from 36 to 42%. The molten carbonate fuel cell (MCFC) is in the demonstrating stage, both the fuel cell and the balance-of-plant (BOP) for natural gas. Demonstration plants of 2 and 1 MW have been under construction in the USA and Japan. Their efficiency will range from 40 to 50%. The solid oxide fuel cell (SOFC) is in the experimental stage around 100 kW for co-generation. Its conceptual system design has been conducted for both centralized and dispersed power plant in a cooperation with Westinghouse and NEDO. A market survey is now considered on the basis that future fuel cells will run for around 40 000 h in a stable manner with competitive performance. The market for fuel cells will be roughly at 2000 MW in Japan by the year 2010. Half of them will be installed for electric companies on the utility scale. The market will be shared between PAFC and MCFC by 10 and 90%, respectively. Current technologies have not reached the stage to precisely forecast when fuel cells will be entering into the market on a utility scale. At the present time, it is worthwhile to consider how the technological and economic requirements will be definitely achieved. After achieving these requirements, fuel cells will be positively introduced and socially accepted as the best energy converting option to save energy and environmental impact. Further efforts will be devoted to meeting the market from the technological and economic aspects.

  9. Automation of remote handling in uranium and mixed oxide fuel element fabrication plants

    International Nuclear Information System (INIS)

    The subject of the analyses are plants for the fabrication or uranium oxide and uranium-plutonium mixed oxide fuel elements. The reference basis of the paper is an overview of the state-of-the-art of manufacturing technologies with regard to automation and remote handling during fuel element fabrication in national and foreign plants, and in comparabel sectors of conventional technologies. Proceeding from ambient dose rates, residence times, and technical conditions or individual doses at typical work-places during fuel element fabrication, work processes are pointed out which, taking into account technical possibilities, should be given priority when automating, and technical solutions for it are sought. Advantages and disadvantages of such measures are outlined, and reduction of radiation exposure is shown (example: mixed oxide fuel fabrication plant at Hanau). (orig./HP)

  10. Arid lands plants as feedstocks for fuels and chemicals

    Energy Technology Data Exchange (ETDEWEB)

    Hoffmann, J.J.

    1983-01-01

    The purpose of this paper is to review the recent research on arid-adapted plants that have potential as producers of fuels or chemicals. The major focus will be on plant species that appear to have commercial value. Research on guayule (Parthenium argentatum) and jojoba (Simmondsia chinensis) will be mentioned only briefly, since these plants have been discussed extensively in the literature, and excellent reviews are already in existence. In this review the literature on arid-adapted plants that have potential uses for solid fuels, liquid fuels, and chemical feedstocks is summarized, followed by an overview of the research directions and types of development that are needed in order for bio-energy production systems to reach the commercial stage. 127 references.

  11. Hydrogen Gas Production from Nuclear Power Plant in Relation to Hydrogen Fuel Cell Technologies Nowadays

    Science.gov (United States)

    Yusibani, Elin; Kamil, Insan; Suud, Zaki

    2010-06-01

    Recently, world has been confused by issues of energy resourcing, including fossil fuel use, global warming, and sustainable energy generation. Hydrogen may become the choice for future fuel of combustion engine. Hydrogen is an environmentally clean source of energy to end-users, particularly in transportation applications because without release of pollutants at the point of end use. Hydrogen may be produced from water using the process of electrolysis. One of the GEN-IV reactors nuclear projects (HTGRs, HTR, VHTR) is also can produce hydrogen from the process. In the present study, hydrogen gas production from nuclear power plant is reviewed in relation to commercialization of hydrogen fuel cell technologies nowadays.

  12. Interrelationships among plant biomass, plant surface area and the interception of particulate deposition by grasses

    International Nuclear Information System (INIS)

    The interrelationships among plant biomass, plant surface area and interception fraction were determined for the interception by corn of 238Pu-bearing particles released to the atmosphere from the H-Area nuclear fuels chemical separations facility on the U.S. Department of Energy's Savannah River Plant in Barnwell County, South Carolina. The relationship between interception fraction and corn biomass was accurately approximated by a filtration model with an absorption coefficient of 3.60 m2 kg-1. A filtration model with an absorption coefficient of 2.91 m2 kg-1 accurately approximated the relationship between biomass and interception fraction for data compiled from the literature for a variety of grass species. A linear regression model accurately approximated the relationship between interception fraction and surface area, but was not a better predictor of interception fraction than the filtration model for biomass

  13. Used nuclear fuel separations process simulation and testing

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, C.; Krebs, J.F.; Copple, J.M.; Frey, K.E.; Maggos, L.E.; Figueroa, J.; Willit, J.L.; Papadias, D.D. [Argonne National Laboratory: 9700 South Cass Avenue, Argonne, IL 60439 (United States)

    2013-07-01

    Recent efforts in separations process simulation at Argonne have expanded from the traditional focus on solvent extraction flowsheet design in order to capture process dynamics and to simulate other components, processing and systems of a used nuclear fuel reprocessing plant. For example, the Argonne Model for Universal Solvent Extraction (AMUSE) code has been enhanced to make it both more portable and more readily extensible. Moving away from a spreadsheet environment makes the addition of new species and processes simpler for the expert user, which should enable more rapid implementation of chemical models that simulate evolving processes. The dyAMUSE (dynamic AMUSE) version allows the simulation of transient behavior across an extractor. Electrochemical separations have now been modeled using spreadsheet codes that simulate the electrochemical recycle of fast reactor fuel. The user can follow the evolution of the salt, products, and waste compositions in the electro-refiner, cathode processors, and drawdown as a function of fuel batches treated. To further expand capabilities in integrating multiple unit operations, a platform for linking mathematical models representing the different operations that comprise a reprocessing facility was adapted to enable systems-level analysis and optimization of facility functions. (authors)

  14. A technique to measure fuel oil viscosity in a fuel power plant.

    Science.gov (United States)

    Delgadillo, Miguel Angel; Ibargüengoytia, Pablo H; García, Uriel A

    2016-01-01

    The viscosity measurement and control of fuel oil in power plants is very important for a proper combustion. However, the conventional viscometers are only reliable for a short period of time. This paper proposes an on-line analytic viscosity evaluation based on energy balance applied to a piece of tube entering the fuel oil main heater and a new control strategy for temperature control. This analytic evaluation utilizes a set of temperature versus viscosity graphs were defined during years of analysis of fuel oil in Mexican power plants. Also the temperature set-point for the fuel oil main heater output is obtained by interpolating in the corresponding graph. Validation tests of the proposed analytic equations were carried out in the Tuxpan power plant in Veracruz, Mexico.

  15. Decommissioning alternatives for the West Valley, New York, Fuel Reprocessing Plant

    Energy Technology Data Exchange (ETDEWEB)

    Munson, L F; Nemec, J F; Koochi, A K

    1978-06-01

    The methodology and numerical values of NUREG-0278 were applied to four decommissioning alternatives for the West Valley Fuel Reprocessing Plant. The cost and impacts of the following four alternatives for the process building, fuel receiving and storage, waste tank farm, and auxiliary facilities were assessed: (1) layaway, (2) protective storage, (3) preparation for alternate nuclear use, and (4) dismantlement. The estimated costs are 5.7, 11, 19, and 31 million dollars, respectively. (DLC)

  16. Decommissioning alternatives for the West Valley, New York, Fuel Reprocessing Plant

    International Nuclear Information System (INIS)

    The methodology and numerical values of NUREG-0278 were applied to four decommissioning alternatives for the West Valley Fuel Reprocessing Plant. The cost and impacts of the following four alternatives for the process building, fuel receiving and storage, waste tank farm, and auxiliary facilities were assessed: (1) layaway, (2) protective storage, (3) preparation for alternate nuclear use, and (4) dismantlement. The estimated costs are 5.7, 11, 19, and 31 million dollars, respectively

  17. Total energy analysis of nuclear and fossil fueled power plants

    International Nuclear Information System (INIS)

    The overall thermal efficiencies of electrical power generation were determined for Liquid Metal Fast Breeder, High Temperature Gas Cooled, Boiling Water, and Pressurized Water Reactors and for coal-, oil-, and gas-fired systems. All important energy consuming steps from mining through processing, transporting, and reprocessing the fuels were included in the energy balance along with electrical transmission and thermal losses and energy expenditures for pollution abatement. The results of these studies show that the overall fuel cycle efficiency of the light water nuclear fueled reactors is less than the efficiency of modern fossil fuel cycles. However, the nuclear fuel cycle based on the fast breeder reactors should produce power more efficiently than the most modern supercritical fossil fuel cycles. The high temperature gas cooled reactor has a cycle efficiency comparable to the supercritical coal fuel cycle

  18. CO2 capture from oxy-fuel combustion power plants

    OpenAIRE

    Hu, Yukun

    2011-01-01

    To mitigate the global greenhouse gases (GHGs) emissions, carbon dioxide (CO2) capture and storage (CCS) has the potential to play a significant role for reaching mitigation target. Oxy-fuel combustion is a promising technology for CO2 capture in power plants. Advantages compared to CCS with the conventional combustion technology are: high combustion efficiency, flue gas volume reduction, low fuel consumption, near zero CO2 emission, and less nitrogen oxides (NOx) formation can be reached sim...

  19. Dry Process Fuel Core Characteristics Assessment Technology Development

    International Nuclear Information System (INIS)

    Major research activities of the Phase I study are the analysis of the dry process fuel irradiation test in HANARO research reactor, review of the DUPIC fuel compatibility analysis results and supplementary calculations, and the feasibility study of the dry process technology for the application to the future fuel cycle. The irradiation test of the dry process fuel was successfully performed in the HANARO research reactor. For the compatibility analysis of the DUPIC fuel, the mechanical integrity and safety of the DUPIC fuel were analyzed. Especially the radiation source term of the DUPIC fuel core was re-evaluated so that the credibility of the radiation effect calculation is improved. In order to assess the applicability of the dry process technology, a fuel cycle analysis code DYMOND was imported and a DUPIC fuel cycle model was developed to be implemented in the DYMOND code. The fuel cycle analyses were performed for the criticality of the dry process, fast reactor cycle, thorium fuel cycle and the light water reactor cycle. The fuel cycle analysis showed that the dry process should be appropriately introduced into the fuel cycle in the time domain. However the recycle analysis also showed that the fission products should be effectively removed from the spent fuel in order to establish the fuel cycle and, therefore, it is recommended to perform theoretical and experimental analyses in the Phase II study

  20. Studies and research concerning BNFP. Nuclear spent fuel transportation studies

    International Nuclear Information System (INIS)

    Currently, there are a number of institutional problems associated with the shipment of spent fuel assemblies from commercial nuclear power plants: new and conflicting regulations, embargoing of certain routes, imposition of transport safeguards, physical security in-transit, and a lack of definition of when and where the fuel will be moved. This report presents a summary of these types and kinds of problems. It represents the results of evaluations performed relative to fuel receipt at the Barnwell Nuclear Fuel Plant. Case studies were made which address existing reactor sites with near-term spent fuel transportation needs. Shipment by either highway, rail, water, or intermodal water-rail was considered. The report identifies the impact of new regulations and uncertainty caused by indeterminate regulatory policy and lack of action on spent fuel acceptance and storage. This stagnant situation has made it impossible for industry to determine realistic transportation scenarios for business planning and financial risk analysis. A current lack of private investment in nuclear transportation equipment is expected to further prolong the problems associated with nuclear spent fuel and waste disposition. These problems are expected to intensify in the 1980's and in certain cases will make continuing reactor plant operation difficult or impossible

  1. DOE small scale fuel alcohol plant design

    Energy Technology Data Exchange (ETDEWEB)

    LaRue, D.M.; Richardson, J.G.

    1980-01-01

    The Department of Energy, in an effort to facilitate the deployment of rural-based ethanol production capability, has undertaken this effort to develop a basic small-scale plant design capable of producing anhydrous ethanol. The design, when completed, will contain all necessary specifications and diagrams sufficient for the construction of a plant. The design concept is modular; that is, sections of the plant can stand alone or be integrated into other designs with comparable throughput rates. The plant design will be easily scaled up or down from the designed flow rate of 25 gallons of ethanol per hour. Conversion factors will be provided with the final design package to explain scale-up and scale-down procedures. The intent of this program is to provide potential small-scale producers with sound information about the size, engineering requirements, costs and level of effort in building such a system.

  2. HIGH ENERGY LIQUID FUELS FROM PLANTS

    Energy Technology Data Exchange (ETDEWEB)

    Nemethy, E. K.; Otvos, J. W.; Calvin, M.

    1980-10-01

    The heptane extract of Euphorbia lathyris has a low oxygen content and a heat valve of 42 MJ/kg which is comparable to that of crude oil (44 MJ/kg). These qualities indicate a potential for use as fuel or chemical feedstock material. Therefore we have investigated the chemical composition of this fraction in some detail. Since the amoun of the methanol fraction is quite substantial we have also identified the major components of this fraction.

  3. Thorium fuel cycle studies: fuel fabrication process and cost estimation

    International Nuclear Information System (INIS)

    Early in 1976 a study was made to assess the relative economics and fuel utilization of thorium and uranium fuel cycles in various types of reactors. It was to be completed in approximately two months, so all component parts had to be developed in a short time with a high degree of dependence on existing information. One of the components required for the study was a consistent set of relatively accurate fuel fabrication costs for the various reactor-fuel combinations. A report documents the rationale used in generating these cost estimates and presents in some detail the basis and methodology employed. Since three types of thermal flux reactors (LWR, HWR, and HTGR) and two types of fast flux reactors (liquid metal and gas cooled) together with three fuel forms (oxides, carbides, and metal) were included in the study with various combinations of the fissionable metals U, Th, and Pu, it was necessary to define a methodology that would permit a rapid relative estimate for each case. Existing cost studies were chosen for a Light-Water Reactor with low-enriched uranium fuel and for a High-Temperature Gas-Cooled Reactor with highly enriched uranium and thorium fuel as the reference cases which could be compared with other reactor-fuel combinations

  4. Cost and availability of gadolinium for nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    Gadolinium is currently planned for use as a soluble neutron poison in nuclear fuel reprocessing plants to prevent criticality of solutions of spent fuel. Gadolinium is relatively rare and expensive. The present study was undertaken therefore to estimate whether this material is likely to be available in quantities sufficient for fuel reprocessing and at reasonable prices. It was found that gadolinium, one of 16 rare earth elements, appears in the marketplace as a by-product and that its present supply is a function of the production rate of other more prevalent rare earths. The potential demand for gadolinium in a fuel reprocessing facility serving a future fast reactor industry amounts to only a small fraction of the supply. At the present rate of consumption, domestic supplies of rare earths containing gadolinium are adequate to meet national needs (including fuel reprocessing) for over 100 years. With access to foreign sources, US demands can be met well beyond the 21st century. It is concluded therefore that the supply of gadolinium will quite likely be more than adequate for reprocessing spent fuel for the early generation of fast reactors. The current price of 99.99% pure gadolinium oxide lies in the range $50/lb to $65/lb (1984 dollars). By the year 2020, in time for reprocessing spent fuel from an early generation of large fast reactors, the corresponding values are expected to lie in the $60/lb to $75/lb (1984 dollars) price range. This increase is modest and its economic impact on nuclear fuel reprocessing would be minor. The economic potential for recovering gadolinium from the wastes of nuclear fuel reprocessing plants (which use gadolinium neutron poison) was also investigated. The cost of recycled gadolinium was estimated at over twelve times the cost of fresh gadolinium, and thus recycle using current recovery technology is not economical. 15 refs., 4 figs., 11 tabs

  5. Design considerations for an integrated safeguards system for fuel-reprocessng plants

    International Nuclear Information System (INIS)

    This report presents design ideas for safeguards systems in nuclear fuels reprocessing plants. The report summarizes general safeguards requirements and describes a safeguards system concept being developed and tested at the Idaho Chemical Processing Plant. The report gives some general concepts intended for design consideration and a checklist of specific problems that should be considered. The report is intended as an aid for the safeguards system designer and as a source of useful information

  6. Arizona Public Service - Alternative Fuel (Hydrogen) Pilot Plant Design Report

    Energy Technology Data Exchange (ETDEWEB)

    James E. Francfort

    2003-12-01

    Hydrogen has promise to be the fuel of the future. Its use as a chemical reagent and as a rocket propellant has grown to over eight million metric tons per year in the United States. Although use of hydrogen is abundant, it has not been used extensively as a transportation fuel. To assess the viability of hydrogen as a transportation fuel and the viability of producing hydrogen using off-peak electric energy, Pinnacle West Capital Corporation (PNW) and its electric utility subsidiary, Arizona Public Service (APS) designed, constructed, and operates a hydrogen and compressed natural gas fueling station—the APS Alternative Fuel Pilot Plant. This report summarizes the design of the APS Alternative Fuel Pilot Plant and presents lessons learned from its design and construction. Electric Transportation Applications prepared this report under contract to the U.S. Department of Energy’s Advanced Vehicle Testing Activity. The Idaho National Engineering and Environmental Laboratory manages these activities for the Advanced Vehicle Testing Activity.

  7. Standard model for safety analysis report of fuel reprocessing plants

    International Nuclear Information System (INIS)

    A standard model for a safety analysis report of fuel reprocessing plants is established. This model shows the presentation format, the origin, and the details of the minimal information required by CNEN (Comissao Nacional de Energia Nuclear) aiming to evaluate the requests of construction permits and operation licenses made according to the legislation in force. (E.G.)

  8. China's First Orimulsion-Fueled Power Plant Constructed in Zhanjiang

    Institute of Scientific and Technical Information of China (English)

    Xing Jianxiao

    2003-01-01

    @@ A ceremony commencement of Orimulsion-fueled electric power generation project was held in Zhanjiang City,Guangdong Province, on November 26. Vice Governor of Guangdong Province You Ningfeng, Vice President of PetroChina and other officials from the related departments attended the foundation-laying ceremony for the power plant.

  9. Cost and quality of fuels for electric utility plants, 1992

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-02

    This publication presents an annual summary of statistics at the national, Census division, State, electric utility, and plant levels regarding the quantity, quality, and cost of fossil fuels used to produce electricity. The purpose of this publication is to provide energy decision-makers with accurate and timely information that may be used in forming various perspectives on issues regarding electric power.

  10. Standard model for safety analysis report of fuel fabrication plants

    International Nuclear Information System (INIS)

    A standard model for a safety analysis report of fuel fabrication plants is established. This model shows the presentation format, the origin, and the details of the minimal information required by CNEN (Comissao Nacional de Energia Nuclear) aiming to evaluate the requests of construction permits and operation licenses made according to the legislation in force. (E.G.)

  11. Cost and quality of fuels for electric utility plants, 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-14

    This document presents an annual summary of statistics at the national, Census division, State, electric utility, and plant levels regarding the quantity, quality, and cost of fossil fuels used to produce electricity. Purpose of this publication is to provide energy decision-makers with accurate, timely information that may be used in forming various perspectives on issues regarding electric power.

  12. Integrating fuel cell power systems into building physical plants

    Energy Technology Data Exchange (ETDEWEB)

    Carson, J. [KCI Technologies, Inc., Hunt Valley, MD (United States)

    1996-12-31

    This paper discusses the integration of fuel cell power plants and absorption chillers to cogenerate chilled water or hot water/steam for all weather air conditioning as one possible approach to building system applications. Absorption chillers utilize thermal energy in an absorption based cycle to chill water. It is feasible to use waste heat from fuel cells to provide hydronic heating and cooling. Performance regimes will vary as a function of the supply and quality of waste heat. Respective performance characteristics of fuel cells, absorption chillers and air conditioning systems will define relationships between thermal and electrical load capacities for the combined systems. Specifically, this paper develops thermodynamic relationships between bulk electrical power and cooling/heating capacities for combined fuel cell and absorption chiller system in building applications.

  13. Fuel Quality/Processing Study. Volume II. Appendix, Task I, literature survey

    Energy Technology Data Exchange (ETDEWEB)

    O' Hara, J B; Bela, A; Jentz, N E; Klumpe, H W; Kessler, R E; Kotzot, H T; Loran, B I

    1981-04-01

    This activity was begun with the assembly of information from Parsons' files and from contacts in the development and commercial fields. A further more extensive literature search was carried out using the Energy Data Base and the American Petroleum Institute Data Base. These are part of the DOE/RECON system. Approximately 6000 references and abstracts were obtained from the EDB search. These were reviewed and the especially pertinent documents, approximately 300, were acquired in the form of paper copy or microfiche. A Fuel Properties form was developed for listing information pertinent to gas turbine liquid fuel properties specifications. Fuel properties data for liquid fuels from selected synfuel processes, deemed to be successful candidates for near future commercial plants were tabulated on the forms. The processes selected consisted of H-Coal, SRC-II and Exxon Donor Solvent (EDS) coal liquefaction processes plus Paraho and Tosco shale oil processes. Fuel properties analyses for crude and distillate syncrude process products are contained in Section 2. Analyses representing synthetic fuels given refinery treatments, mostly bench scale hydrotreating, are contained in Section 3. Section 4 discusses gas turbine fuel specifications based on petroleum source fuels as developed by the major gas turbine manufacturers. Section 5 presents the on-site gas turbine fuel treatments applicable to petroleum base fuels impurities content in order to prevent adverse contaminant effects. Section 7 relates the environmental aspects of gas turbine fuel usage and combustion performance. It appears that the near future stationary industrial gas turbine fuel market will require that some of the synthetic fuels be refined to the point that they resemble petroleum based fuels.

  14. Development of Advanced Spent Fuel Management Process

    International Nuclear Information System (INIS)

    As a part of research efforts to develop an advanced spent fuel management process, this project focused on the electrochemical reduction technology which can replace the original Li reduction technology of ANL, and we have successfully built a 20 kgHM/batch scale demonstration system. The performance tests of the system in the ACPF hot cell showed more than a 99% reduction yield of SIMFUEL, a current density of 100 mA/cm2 and a current efficiency of 80%. For an optimization of the process, the prevention of a voltage drop in an integrated cathode, a minimization of the anodic effect and an improvement of the hot cell operability by a modulation and simplization of the unit apparatuses were achieved. Basic research using a bench-scale system was also carried out by focusing on a measurement of the electrochemical reduction rate of the surrogates, an elucidation of the reaction mechanism, collecting data on the partition coefficients of the major nuclides, quantitative measurement of mass transfer rates and diffusion coefficients of oxygen and metal ions in molten salts. When compared to the PYROX process of INL, the electrochemical reduction system developed in this project has comparative advantages in its application of a flexible reaction mechanism, relatively short reaction times and increased process yields

  15. Development of Advanced Spent Fuel Management Process

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Chung Seok; Choi, I. K.; Kwon, S. G. (and others)

    2007-06-15

    As a part of research efforts to develop an advanced spent fuel management process, this project focused on the electrochemical reduction technology which can replace the original Li reduction technology of ANL, and we have successfully built a 20 kgHM/batch scale demonstration system. The performance tests of the system in the ACPF hot cell showed more than a 99% reduction yield of SIMFUEL, a current density of 100 mA/cm{sup 2} and a current efficiency of 80%. For an optimization of the process, the prevention of a voltage drop in an integrated cathode, a minimization of the anodic effect and an improvement of the hot cell operability by a modulation and simplization of the unit apparatuses were achieved. Basic research using a bench-scale system was also carried out by focusing on a measurement of the electrochemical reduction rate of the surrogates, an elucidation of the reaction mechanism, collecting data on the partition coefficients of the major nuclides, quantitative measurement of mass transfer rates and diffusion coefficients of oxygen and metal ions in molten salts. When compared to the PYROX process of INL, the electrochemical reduction system developed in this project has comparative advantages in its application of a flexible reaction mechanism, relatively short reaction times and increased process yields.

  16. Fuel staging tests at the Kymijaervi power plant

    International Nuclear Information System (INIS)

    The aim of this study was to measure nitrogen oxide (NOx) emissions and find the methods to reduce them in plants using coal and natural gas as fuel. The tests involved were made at the Kymijaervi Power Plant, Lahti, Finland. Coal and natural gas was used alone or mixed. With natural gas when using flue gas recirculation, the NOx emission level dropped from 330 mg/m3 down to 60 mg/m3. A negative side effect was that the flue gas temperature increased. At coal combustion and staged combustion, the flue gas recirculation had no significant effect on the NOx emission level. At coal combustion, the staging of combustion air halved the NOx emission but the combustibles increased strongly. With fuel staging, using coal as main fuel and gas as staging fuel, the NOx emission level was decreased from 340 mg/m3 to 170 mg/m3. At the same time the combustibles increased 2 %- units. Also the flue gas temperature increased a little. At the tests, the proportion of natural gas was rather high, one third of the fuel energy input, but it could not be decreased, because the gas flow ratio was already too low to ensure good mixing

  17. Effect of processing plant on pork quality

    NARCIS (Netherlands)

    Hambrecht, E.; Eissen, J.J.; Verstegen, M.W.A.

    2003-01-01

    The impact of processing plant on pork quality was studied by assessing pork quality in three commercial plants (A, B, Q. Plants differed in the layout of the races, stunning systems (A and B: electrical, C: CO2 stunning) and chilling systems (A: rapid chilling, B and C: conventional). Factors not r

  18. Plant-based remediation processes

    Energy Technology Data Exchange (ETDEWEB)

    Gupta, Dharmendra Kumar (ed.) [Belgian Nuclear Research Centre (SCK.CEN), Mol (Belgium). Radiological Impact and Performance Assessment Division

    2013-11-01

    A valuable source of information for scientists in the field of environmental pollution and remediation. Describes the latest biotechnological methods for the treatment of contaminated soils. Includes case studies and protocols. Phytoremediation is an emerging technology that employs higher plants for the clean-up of contaminated environments. Basic and applied research have unequivocally demonstrated that selected plant species possess the genetic potential to accumulate, degrade, metabolize and immobilize a wide range of contaminants. The main focus of this volume is on the recent advances of technologies using green plants for remediation of various metals and metalloids. Topics include biomonitoring of heavy metal pollution, amendments of higher uptake of toxic metals, transport of heavy metals in plants, and toxicity mechanisms. Further chapters discuss agro-technological methods for minimizing pollution while improving soil quality, transgenic approaches to heavy metal remediation and present protocols for metal remediation via in vitro root cultures.

  19. Design and fabrication of stainless steel components for long life of spent fuel reprocessing plants

    International Nuclear Information System (INIS)

    Reprocessing of spent nuclear fuels based on the PUREX process is the proven process with many commercial plants operating satisfactorily worldwide. The process medium being nitric acid, austenitic stainless steel is the material of construction as it is the best commercially available material for meeting the conditions in the reprocessing plants. Because of the high radiation fields, contact maintenance of equipment and systems of these plants are very time consuming and costly unlike other chemical process plants. Though the plants constructed in the early years required extensive shut downs for replacement of equipment and systems within the first fifteen years of operation itself, development in the field of stainless steel metallurgy and fabrication techniques have made it possible to design the present day plants for an operating life period of forty years. A review of the operational experience of the PUREX process based aqueous reprocessing plants has been made in this paper and reveals that life limiting failures of equipment and systems are mainly due to corrosion while a few are due to stresses. Presently there are no standards for design specification of materials and fabrication of reprocessing plants like the nuclear power plants, where well laid down ASTM and ASME codes and standards are available which are based on the large scale operational feedbacks on pressure vessels for conventional and nuclear industries. (author)

  20. Selection of Fuel by Using Analytical Hierarchy Process

    Directory of Open Access Journals (Sweden)

    Asilata M. Damle,

    2015-04-01

    Full Text Available Selection of fuel is a very important and critical decision one has to make. Various criteria are to be considered while selecting a fuel. Some of important criteria are Fuel Economy, Availability of fuel, Pollution from vehicle, Maintenance of the vehicle. Selection of best fuel is a complex situation. It needs a multi-criteria analysis. Earlier, the solution to the problem were found by applying classical numerical methods which took into account only technical and economic merits of the various alternatives. By applying multi-criteria tools, it is possible to obtain more realistic results. This paper gives a systematic analysis for selection of fuel by using Analytical Hierarchy Process (AHP. This is a multi-criteria decision making process. By using AHP we can select the fuel by comparing various factors in a mathematical model. This is a scientific method to find out the best fuel by making pairwise comparisons.

  1. Correction and supplement of the first report 'On fire and explosion accidents in asphalt solidification processing facility of fuel reprocessing plant in Tokai Works, Power Reactor and Nuclear Fuel Development Corporation'

    International Nuclear Information System (INIS)

    The report of the accidents by the Corporation to the Director of Science and Technology Agency dated April 30, 1997 was made in the form of the tables of comparison of the points of correction and supplement with the modified first report. The reason is the correction of the time of the accidents and the correct description of the activities at the time of the accidents. The modified first report is attached as the material for reference. In the first report, it was described that fire occurred on March 11, 1997 in the asphalt solidification processing facility, and it seemed to be extinguished, explosion occurred in the same facility about 10 hours later, the activities of environmental monitoring and the preparation for restoration were carried out, the state of radiation exposure dose equivalent, the cause and countermeasures. The materials on the main circumstances just after the accidents, the asphalt solidification processing facility and its state of operation on the day of accidents, the building and cell ventilation system, the state of damage, environmental monitoring and the countermeasures after the explosion are attached. (K.I.)

  2. MEDIUM PRESSURE HYDROUPGRADING PROCESS (MHUG) AND PRODUCTION OF CLEAN FUELS

    Institute of Scientific and Technical Information of China (English)

    2001-01-01

    The medium pressure hydroupgrading process (MHUG) unit with an 800 kt/a processing capacity of Jinzhou Petrochemical Company is used to hydroupgrade the mixture of FCC LCO fuel and straight-run diesel fuel in the presence of RN/RT series catalysts for improvement of the quality of the diesel fuel. Meanwhile, catalytic reforming feedstock is also obtained. The sulfur, nitrogen and aromatics contained in the hydroupgraded diesel fuel products can be minimized and the cetane number can be heightened. The produced clean fuels can meet the requirements of environmental protection.

  3. Process for tightly sealing nuclear reactor fuel rods

    International Nuclear Information System (INIS)

    This invention refers to a process for pressurising and tightly sealing fuel rods used in nuclear reactors. The fuel rods utilised in commercial nuclear reactors are usually composed of a zircaloy tubular cladding of around 15 mm in diameter and up to 5 m long, filled with fuel pellets maintained in place by end plugs sealed on each end of the cladding. The main purpose of the invention is to promote a process using laser beam welding equipment to seal the end plugs on the fuel rods, drill a pressurising hole in one of the end plugs and hermetically seal the hole after the fuel rod has been placed under pressure

  4. Fuel Cell Stations Automate Processes, Catalyst Testing

    Science.gov (United States)

    2010-01-01

    Glenn Research Center looks for ways to improve fuel cells, which are an important source of power for space missions, as well as the equipment used to test fuel cells. With Small Business Innovation Research (SBIR) awards from Glenn, Lynntech Inc., of College Station, Texas, addressed a major limitation of fuel cell testing equipment. Five years later, the company obtained a patent and provided the equipment to the commercial world. Now offered through TesSol Inc., of Battle Ground, Washington, the technology is used for fuel cell work, catalyst testing, sensor testing, gas blending, and other applications. It can be found at universities, national laboratories, and businesses around the world.

  5. Commissioning of the fuel reprocessing plant of Rokkasho-Mura; Demarrage de l'usine de retraitement nucleaire de Rokkasho-Mura

    Energy Technology Data Exchange (ETDEWEB)

    Anon

    2006-03-15

    The first Japanese plant dedicated to the separation of uranium and plutonium from spent fuel was commissioned on march 2006 after a 12 year long construction on the Rokkasho-Mura site. This plant, that has been built from the model of the UP3 plant at La-Hague, will enable Japan to process its spent fuel and to produce MOX fuel. A technology transfer agreement was signed in 1987 between Areva and the Japan nuclear fuel company (JNFL). This plant will be on test till mid 2007 when its industrial use is scheduled to begin. (A.C.)

  6. Energy analysis of nuclear power plants and their fuel cycle

    International Nuclear Information System (INIS)

    Energy analysis has become an increasingly feasible and practical additional method for evaluating the engineering, economic and environmental aspects of power-producing systems. It compares total direct and indirect energy investment into construction and operation of power plants with their lifetime energy output. This method was applied to nuclear power-producing systems and their fuel cycles. Results were adapted to countries with various levels of industrialization and resources. With dynamic energy analysis different scenarios were investigated. For comparison purposes fossil-fuelled and solar power plants were analysed. The global results of static evaluation analysis were specifically modified according to the economic situations of countries with various levels of industrialization. The influence of energy imports upon energy analysis is also discussed. By dynamic energy analyses the cumulative energy requirements for specific power plant construction programmes have been compared with their total energy output. Investigations of this sort are extremely valuable not only for economic reasons, but especially for their usefulness in showing the advantages and disadvantages of a specific power programme with respect to its alternatives. Naturally the impact of these investigations on the fuel requirements is of importance, especially because of the frequently cited ''valuable cumulated fossil fuel savings''. (author)

  7. Renewable hydrogen production for fossil fuel processing

    Energy Technology Data Exchange (ETDEWEB)

    Greenbaum, E.; Lee, J.W.; Tevault, C.V. [and others

    1995-06-01

    In the fundamental biological process of photosynthesis, atmospheric carbon dioxide is reduced to carbohydrate using water as the source of electrons with simultaneous evolution of molecular oxygen: H{sub 2}O + CO{sub 2} + light {yields} O{sub 2} + (CH{sub 2}O). It is well established that two light reactions, Photosystems I and II (PSI and PSII) working in series, are required to perform oxygenic photosynthesis. Experimental data supporting the two-light reaction model are based on the quantum requirement for complete photosynthesis, spectroscopy, and direct biochemical analysis. Some algae also have the capability to evolve molecular hydrogen in a reaction energized by the light reactions of photosynthesis. This process, now known as biophotolysis, can use water as the electron donor and lead to simultaneous evolution of molecular hydrogen and oxygen. In green algae, hydrogen evolution requires prior incubation under anaerobic conditions. Atmospheric oxygen inhibits hydrogen evolution and also represses the synthesis of hydrogenase enzyme. CO{sub 2} fixation competes with proton reduction for electrons relased from the photosystems. Interest in biophotolysis arises from both the questions that it raises concerning photosynthesis and its potential practical application as a process for converting solar energy to a non-carbon-based fuel. Prior data supported the requirement for both Photosystem I and Photosystem II in spanning the energy gap necessary for biophotolysis of water to oxygen and hydrogen. In this paper we report the at PSII alone is capable of driving sustained simultaneous photoevolution of molecular hydrogen and oxygen in an anaerobically adapted PSI-deficient strain of Chlamydomonas reinhardtii, mutant B4, and that CO{sub 2} competes as an electron acceptor.

  8. Hermetic seal process for nuclear fuel element

    International Nuclear Information System (INIS)

    The welding of the end plug onto the sheath of the fuel rod is made inside an enclosure filled with inert gas under the same pressure at that needed inside the fuel rod. The welding can be a tungsten arc welding, a laser welding or a micro plasma welding

  9. Handbook on process and chemistry on nuclear fuel reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Atsuyuki (ed.) [Tokyo Univ., Tokyo (Japan); Asakura, Toshihide; Adachi, Takeo (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

    2001-12-01

    'Wet-type' nuclear fuel reprocessing technology, based on PUREX technology, has wide applicability as the principal reprocessing technology of the first generation, and relating technologies, waste management for example, are highly developed, too. It is quite important to establish a database summarizing fundamental information about the process and the chemistry of 'wet-type' reprocessing, because it contributes to establish and develop fuel reprocessing process and nuclear fuel cycle treating high burn-up UO{sub 2} fuel and spent MOX fuel, and to utilize 'wet-type' reprocessing technology much widely. This handbook summarizes the fundamental data on process and chemistry, which was collected and examined by 'Editing Committee of Handbook on Process and Chemistry of Nuclear Fuel Reprocessing', from FY 1993 until FY 2000. (author)

  10. Need for higher fuel burnup at the Hatch Plant

    Energy Technology Data Exchange (ETDEWEB)

    Beckhman, J.T. [Georgia Power Co., Birmingham, AL (United States)

    1996-03-01

    Hatch is a BWR 4 and has been in operation for some time. The first unit became commercial about 1975. Obtaining higher burnups, or higher average discharge exposures, is nothing new at Hatch. Since we have started, the discharge exposure of the plant has increased. Now, of course, we are not approaching the numbers currently being discussed but, the average discharge exposure has increased from around 20,000 MWD/MTU in the early to mid-1980s to 34,000 MWD/MTU in 1994, I am talking about batch average values. There are also peak bundle and peak rod values. You will have to make the conversions if you think in one way or the other because I am talking in batch averages. During Hatch`s operating history we have had some problems with fuel failure. Higher burnup fuel raises a concern about how much fuel failure you are going to have. Fuel failure is, of course, an economic issue with us. Back in the early 1980s, we had a problem with crud-induced localized corrosion, known as CILC. We have gotten over that, but we had some times when it was up around 27 fuel failures a year. That is not a pleasant time to live through because it is not what you want from an economic viewpoint or any other. We have gotten that down. We have had some fuel failures recently, but they have not been related to fuel burnup or to corrosion. In fact, the number of failures has decreased from the early 1980s to the 90s even though burnup increased during that time. The fuel failures are more debris-related-type failures. In addition to increasing burnups, utilities are actively evaluating or have already incorporated power uprate and longer fuel cycles (e.g., 2-year cycles). The goal is to balance out the higher power density, longer cycles, higher burnup, and to have no leakers. Why do we as an industry want to have higher burnup fuel? That is what I want to tell you a little bit about.

  11. Technical Report Cellulosic Based Black Liquor Gasification and Fuels Plant Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Fornetti, Micheal [Escanaba Paper Company, MI (United States); Freeman, Douglas [Escanaba Paper Company, MI (United States)

    2012-10-31

    The Cellulosic Based Black Liquor Gasification and Fuels Plant Project was developed to construct a black liquor to Methanol biorefinery in Escanaba, Michigan. The biorefinery was to be co-located at the existing pulp and paper mill, NewPage’s Escanaba Paper Mill and when in full operation would: • Generate renewable energy for Escanaba Paper Mill • Produce Methanol for transportation fuel of further refinement to Dimethyl Ether • Convert black liquor to white liquor for pulping. Black liquor is a byproduct of the pulping process and as such is generated from abundant and renewable lignocellulosic biomass. The biorefinery would serve to validate the thermochemical pathway and economic models for black liquor gasification. It was a project goal to create a compelling new business model for the pulp and paper industry, and support the nation’s goal for increasing renewable fuels production and reducing its dependence on foreign oil. NewPage Corporation planned to replicate this facility at other NewPage Corporation mills after this first demonstration scale plant was operational and had proven technical and economic feasibility. An overview of the process begins with black liquor being generated in a traditional Kraft pulping process. The black liquor would then be gasified to produce synthesis gas, sodium carbonate and hydrogen sulfide. The synthesis gas is then cleaned with hydrogen sulfide and carbon dioxide removed, and fed into a Methanol reactor where the liquid product is made. The hydrogen sulfide is converted into polysulfide for use in the Kraft pulping process. Polysulfide is a known additive to the Kraft process that increases pulp yield. The sodium carbonate salts are converted to caustic soda in a traditional recausticizing process. The caustic soda is then part of the white liquor that is used in the Kraft pulping process. Cellulosic Based Black Liquor Gasification and Fuels Plant project set out to prove that black liquor gasification could

  12. Artificial intelligence methods in process plant layout

    OpenAIRE

    McBrien, Andrew

    1994-01-01

    The thesis describes "Plant Layout System" or PLS, an Expert System which automates all aspects of conceptual layout of chemical process plant, from sizing equipment using process data to deriving the equipment items' elevation and plan positions. PLS has been applied to a test process of typical size and complexity and which encompasses a wide range of layout issues and problems. The thesis presents the results of the tests to show that PLS generates layouts that are entirely satisfactory an...

  13. Cost and quality of fuels for electric utility plants 1991

    International Nuclear Information System (INIS)

    Data for 1991 and 1990 receipts and costs for fossil fuels discussed in the Executive Summary are displayed in Tables ES1 through ES7. These data are for electric generating plants with a total steam-electric and combined-cycle nameplate capacity of 50 or more megawatts. Data presented in the Executive Summary on generation, consumption, and stocks of fossil fuels at electric utilities are based on data collected on the Energy Information Administration, Form EIA-759, ''Monthly Power Plant Report.'' These data cover all electric generating plants. The average delivered cost of coal, petroleum, and gas each decreased in 1991 from 1990 levels. Overall, the average annual cost of fossil fuels delivered to electric utilities in 1991 was $1.60 per million Btu, a decrease of $0.09 per million Btu from 1990. This was the lowest average annual cost since 1978 and was the result of the abundant supply of coal, petroleum, and gas available to electric utilities. US net generation of electricity by all electric utilities in 1991 increased by less than I percent--the smallest increase since the decline that occurred in 1982.3 Coal and gas-fired steam net generation, each, decreased by less than I percent and petroleum-fired steam net generation by nearly 5 percent. Nuclear-powered net generation, however, increased by 6 percent. Fossil fuels accounted for 68 percent of all generation; nuclear, 22 percent; and hydroelectric, 10 percent. Sales of electricity to ultimate consumers in 1991 were 2 percent higher than during 1990

  14. Bio-oil fueled diesel power plant; Biooeljyllae toimiva dieselvoimala

    Energy Technology Data Exchange (ETDEWEB)

    Vuorinen, A. [Modigen Oy, Helsinki (Finland)

    1995-12-31

    The project mission is to develop a diesel power plant which is capable of using liquid bio-oils as the main fuel of the power plant. The applicable bio-oils are rape seed oils and pyrolysis oils. The project was started in 1994 by installing a 1.5 MW Vasa 4L32 engine in VTT Energy laboratory in Otaniemi. During 1995 the first tests with the rape seed oils were made. The tests show that the rape seed oil can be used in Vasa 32 engines without difficulties. In the second phase of the project during 1996 and 1997 pyrolysis oil made of wood will be tested. Finally a diesel power plant concept with integrated pyrolysis oil, electricity and heat production will be developed

  15. Multivariable Robust Control of a Simulated Hybrid Solid Oxide Fuel Cell Gas Turbine Plant

    Energy Technology Data Exchange (ETDEWEB)

    Tsai A, Banta L, Tucker D

    2010-08-01

    This work presents a systematic approach to the multivariable robust control of a hybrid fuel cell gas turbine plant. The hybrid configuration under investigation built by the National Energy Technology Laboratory comprises a physical simulation of a 300kW fuel cell coupled to a 120kW auxiliary power unit single spool gas turbine. The public facility provides for the testing and simulation of different fuel cell models that in turn help identify the key difficulties encountered in the transient operation of such systems. An empirical model of the built facility comprising a simulated fuel cell cathode volume and balance of plant components is derived via frequency response data. Through the modulation of various airflow bypass valves within the hybrid configuration, Bode plots are used to derive key input/output interactions in transfer function format. A multivariate system is then built from individual transfer functions, creating a matrix that serves as the nominal plant in an H{sub {infinity}} robust control algorithm. The controller’s main objective is to track and maintain hybrid operational constraints in the fuel cell’s cathode airflow, and the turbo machinery states of temperature and speed, under transient disturbances. This algorithm is then tested on a Simulink/MatLab platform for various perturbations of load and fuel cell heat effluence. As a complementary tool to the aforementioned empirical plant, a nonlinear analytical model faithful to the existing process and instrumentation arrangement is evaluated and designed in the Simulink environment. This parallel task intends to serve as a building block to scalable hybrid configurations that might require a more detailed nonlinear representation for a wide variety of controller schemes and hardware implementations.

  16. Dry Process Fuel Core Characteristics Assessment Technology Development

    International Nuclear Information System (INIS)

    For the normal operating condition of a dry-process fuel CANDU reactor, the fuel integrity was assessed using the fuel design curves. Sensitivity calculations were performed to improve the fuel performance and the results showed that the plenum volume had a dominant effect. When an additional plenum volume of 0.5 mm3/K was applied, the internal pressure and the sheath plastic strain satisfied the design values of the natural uranium fuel. Benchmark calculations of the WIMS-DRAGON-RFSP was performed using the Phase-B measurement data of Wolsong-2/3/4. The benchmark calculation showed that the critical boron concentration, reactivity device worth and the flux distribution were predicted within the uncertainty level of the measurement. Sensitivity calculations also showed that the use of a 2-energy group is mandatory to obtain reliable physics calculation results. A feasibility study was performed for the oxide fuel recycling in a sodium-cooled fast reactor (SFR). If fission products are removed by more than 70% during the dry process, the spent fuel can be recycled in the core without using fissile material feed. If carbon is mixed with the recycled fuel, the physics performance of the core can also be improved. Fuel cycle analyses were performed by the DYMOND code for the DUPIC, thorium-DUPIC, SFR and an accelerator driven system (ADS) cycles, and the results showed that the spent fuel inventory was reduced by more than 90% in the fast reactor cycle when compared to the once-through fuel cycle. However the fuel cycle cost was 2.5 and 1.3 times higher for the fast reactor and CANDU reactor recycle, respectively, when compared to the once-through fuel cycle. Also the radiation and decay heat data of the spent fuel were generated to establish the fuel cycle analysis system

  17. Development of spent fuel storage process equipment

    International Nuclear Information System (INIS)

    The scope of the research and development project covers the development of various remote operation technologies which are important assets for the repairment and maintenance of spent fuel handling facilities as well as the actual handling of spent fuels. As a key technology pertaining to such an objective, an anti-swing overhead crane system is developed. The anti-swing crane system is designed to provide oscillation free transportation of heavy equipments and materials such as spent fuel casks in nuclear facilities, therefore, an increased level of safety may be achieved. Also a teleoperated robotic impact wrench system is developed by adopting multi-sensor integration and suitably designed impact wrench module. The performance of the impact wrench system is tested by opening the spent fuel cask lid. Other related efforts in technological innovations are also made in the development of fuzzy logic controller for a tele-visual surveillance system and the design of a three-dimensional range finder. (Author)

  18. DUPIC nuclear fuel manufacturing and process technology development

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Myung Seung; Park, J. J.; Lee, J. W. [and others

    2000-05-01

    In this study, DUPIC fuel fabrication technology and the active fuel laboratory were developed for the study of spent nuclear fuel. A new nuclear fuel using highly radioactive nuclear materials can be studied at the active fuel laboratory. Detailed DUPIC fuel fabrication process flow was developed considering the manufacturing flow, quality control process and material accountability. The equipment layout of about twenty DUPIC equipment at IMEF M6 hot cell was established for the minimization of the contamination during DUPIC processes. The characteristics of the SIMFUEL powder and pellets was studied in terms of milling conditions. The characteristics of DUPIC powder and pellet was studied by using 1 kg of spent PWR fuel at PIEF nr.9405 hot cell. The results were used as reference process conditions for following DUPIC fuel fabrication at IMEF M6. Based on the reference fabrication process conditions, the main DUPIC pellet fabrication campaign has been started at IMEF M6 using 2 kg of spent PWR fuel since 2000 January. As of March 2000, about thirty DUPIC pellets were successfully fabricated.

  19. Direct fuel cell power plants: the final steps to commercialization

    Science.gov (United States)

    Glenn, Donald R.

    Since the last paper presented at the Second Grove Fuel Cell Symposium, the Energy Research Corporation (ERC) has established two commercial subsidiaries, become a publically-held firm, expanded its facilities and has moved the direct fuel cell (DFC) technology and systems significantly closer to commercial readiness. The subsidiaries, the Fuel Cell Engineering Corporation (FCE) and Fuel Cell Manufacturing Corporation (FCMC) are perfecting their respective roles in the company's strategy to commercialize its DFC technology. FCE is the prime contractor for the Santa Clara Demonstration and is establishing the needed marketing, sales, engineering, and servicing functions. FCMC in addition to producing the stacks and stack modules for the Santa Clara demonstration plant is now upgrading its production capability and product yields, and retooling for the final stack scale-up for the commercial unit. ERC has built and operated the tallest and largest capacities-to-date carbonate fuel cell stacks as well as numerous short stacks. While most of these units were tested at ERC's Danbury, Connecticut (USA) R&D Center, others have been evaluated at other domestic and overseas facilities using a variety of fuels. ERC has supplied stacks to Elkraft and MTU for tests with natural gas, and RWE in Germany where coal-derived gas were used. Additional stack test activities have been performed by MELCO and Sanyo in Japan. Information from some of these activities is protected by ERC's license arrangements with these firms. However, permission for limited data releases will be requested to provide the Grove Conference with up-to-date results. Arguably the most dramatic demonstration of carbonate fuel cells in the utility-scale, 2 MW power plant demonstration unit, located in the City of Santa Clara, California. Construction of the unit's balance-of-plant (BOP) has been completed and the installed equipment has been operationally checked. Two of the four DFC stack sub-modules, each

  20. Notes on breeding sharp-shinned hawks and Cooper’s hawks in Barnwell County, South Carolina.

    Energy Technology Data Exchange (ETDEWEB)

    Vukovich, Mark; Kilgo, John, C.

    2009-07-01

    Abstract - Breeding records of Accipiter striatus (Sharp-shinned Hawks) in the southeastern US are scattered and isolated. We documented a Sharp-shinned Hawk and Accipiter cooperii (Cooper’s Hawk) nest while conducting a telemetry study on Melanerpes erythrocephalus (Red-headed Woodpeckers) in Barnwell County, SC in 2006 and 2007. We report the first known nest of a Sharp-shinned Hawk in Barnwell County, SC and the first report of Sharp-shinned Hawks preying upon Red-headed Woodpeckers. Thirteen of 93 (13.9 %) woodpeckers were killed by accipiters in the summers of 2006 and 2007. Large, contiguous forests managed for Picoides borealis (Red-cockaded Woodpeckers) may be used by breeding Sharp-shinned Hawks. The bright plumage, loud calls, and behavior of Red-headed Woodpeckers, particularly during the nestling stage, may make them conspicuous prey for accipiters.

  1. Ferrous Metal Processing Plants - Direct Download

    Data.gov (United States)

    U.S. Geological Survey, Department of the Interior — This map layer includes ferrous metal processing plants in the United States. The data represent commodities covered by the Minerals Information Team (MIT) of the...

  2. Nonferrous Metal Processing Plants - Direct Download

    Data.gov (United States)

    U.S. Geological Survey, Department of the Interior — This map layer includes nonferrous metal processing plants in the United States. The data represent commodities covered by the Minerals Information Team (MIT) of...

  3. Plant Characteristics of an Integrated Solid Oxide Fuel Cell Cycle and a Steam Cycle

    DEFF Research Database (Denmark)

    Rokni, Masoud

    2010-01-01

    Plant characteristics of a system containing a solid oxide fuel cell (SOFC) cycle on the top of a Rankine cycle were investigated. Natural gas (NG) was used as the fuel for the plant. A desulfurization reactor removes the sulfur content in the fuel, while a pre-reformer broke down the heavier hyd...

  4. Effect of processing plant on pork quality.

    Science.gov (United States)

    Hambrecht, E; Eissen, J J; Verstegen, M W A

    2003-06-01

    The impact of processing plant on pork quality was studied by assessing pork quality in three commercial plants (A, B, C). Plants differed in the layout of the races, stunning systems (A and B: electrical, C: CO(2) stunning) and chilling systems (A: rapid chilling, B and C: conventional). Factors not related to the processing plants (e.g. genetic background of animals, transport, lairage) were standardized. In total, nine batches of about 150 pigs each were processed. Each batch was purchased at a commercial farm and randomly divided into three groups for delivery to the three processing plants. Meat quality was evaluated by measuring early post-mortem muscle pH and temperature as well as ultimate pH, meat colour (Minolta Chroma Meter and Japanese colour scale), filter paper score (FPS), electrical conductivity (EC) and drip loss. Plant C produced an inferior quality compared to plants A and B: meat was paler (C: 2.8 vs. A: 2.9 and B: 3.0 on the Japanese colour scale) and had higher drip losses (C: 5.2 vs. A: 4.8 and B: 4.9%). Meat colour hardly differed between plants A and B but waterholding properties were best at plant A as indicated by FPS (A: 2.4 vs. B: 2.8 vs. C: 3.3) and EC (A: 5.4 vs. B: 6.4 vs. C: 7.4 mS). It is concluded that processing plant may influence meat quality. Correlations between early post-mortem measurements and meat quality traits were low. Nevertheless, high carcass temperatures and low pH values early post-mortem were shown to lead to inferior meat quality.

  5. General principles of the criticality safety for handling, processing and transportation of spent fuel in the USSR

    International Nuclear Information System (INIS)

    The paper describes the general principles of nuclear criticality safety for handling, processing, transportation and spent fuel storing. Measures to limit the consequences of critical accidents are discussed for the fuel reprocessing plant and spent fuel storage. The system of scientific and technical measures on nuclear safety as well as the system of control and state supervision based on the rules, limits and requirements are described. The nuclear safety aspects for various stages of handling nuclear materials are considered. The paper gives description of the methods and approaches for critical risk assessments for the reprocessing plant and spent fuel storages. (author)

  6. Process flow model of solid oxide fuel cell system supplied with sewage biogas

    OpenAIRE

    Van herle, Jan; Favrat, Daniel; Maréchal, François; Bucheli, Olivier; Leuenberger, Sacha; Membrez, Yves

    2004-01-01

    A model for a 1000 kW class solid oxide fuel cell (SOFC) system running on biogas from a sewage sludge digestion plant was implemented in a process flow scheme using external steam reforming. The model stack consisted of planar anode supported cells operated at 800 degreesC displaying state-of- the-art electrochemical performance (0.15 W/cm(2) at 80% fuel utilisation). Real annual data from an existing sewage plant were used as input to the model. From the input of 43 m(3)/h biogas (63% ...

  7. Process plant equipment operation, control, and reliability

    CERN Document Server

    Holloway, Michael D; Onyewuenyi, Oliver A

    2012-01-01

    "Process Plant Equipment Book is another great publication from Wiley as a reference book for final year students as well as those who will work or are working in chemical production plants and refinery…" -Associate Prof. Dr. Ramli Mat, Deputy Dean (Academic), Faculty of Chemical Engineering, Universiti Teknologi Malaysia "…give[s] readers access to both fundamental information on process plant equipment and to practical ideas, best practices and experiences of highly successful engineers from around the world… The book is illustrated throughout with numerous black & white p

  8. Adjustment of machine equipment in heating plants to facilitate addition of straw fuel; Anpassning av vaermeverksutrustning till halminblandning

    Energy Technology Data Exchange (ETDEWEB)

    Stridsberg, Sven [BIOSYD (Sweden)

    1999-10-01

    The ground of the project is a development work, carried out by BIOSYD according combustion of straw in heating plants. First we have handled combustion experiments with addition of straw in some plants working with wood fuels, mainly with good results. In the next step we have worked with new techniques for handling and delivery of straw to the plants, also including experiments with chopping of the straw on the field, storing it in outdoor uncovered piles and consequently delivered in the shape of 'chips' to the heating plant. The whole cycle from cutting to combustion has been checked. The results indicate a possible price of the straw at the heating plant of approx 85 SEK/MWh, which can easily compete with wood fuels. The present project will describe which adjustments of the machine equipment are needed to allow a 25 % addition of straw in the fuel mix, how much these adjustments will cost and if they should be profitable in competition with wood fuels for 110 SEK/MWh. In total 37 heating plants from Skaane up to Uppland have been visited and the process from fuel reception to combustion analyzed. The costs of adjustments needed have been calculated from similar examples. The main impression from the studies is that the fuel reception has too small volumes to allow more numerous kinds of fuel and specially make it possible to give a good mix. This is often not critical for wood fuels but for straw we must guarantee a good mix to get a good combustion. Other critical points are crossings between conveyors, for example dips and feeding out devices, which often have to be adjusted. In the combustion there is a risk for sintering as well as coatings on tubes and walls. These functions must be avoided by air distribution, feed back of fuel gas and better carbon removing. In our analyses we would have judged on results from practical tests, but as this would have been too extensive, we must trust in former experiences, transferred to respective plants. Our

  9. Determining the fate of virginiamycin in the fuel ethanol production process

    Science.gov (United States)

    Antibiotics are frequently used to prevent and treat bacterial contamination at commercial fuel ethanol facilities. A study to evaluate the fate of the antibiotic virginiamycin during the ethanol production process was conducted in the pilot plant facilities at the National Corn to Ethanol Research...

  10. Membrane-integrated oxy-fuel combustion of coal: Process design and simulation

    NARCIS (Netherlands)

    Chen, Wei; Ham, van der A.G.J.; Nijmeijer, A.; Winnubst, A.J.A.

    2015-01-01

    A membrane-integrated oxy-fuel combustion process is designed and simulated in UniSim Design®. The results of the simulation indicate that a net efficiency of 31.8% is obtained for a coal-fired power plant of 182 MWth (assuming only carbon in the coal), including the compression of CO2 to 100 bar. T

  11. Fabrication Process of a Nuclear Fuel Test Rig in HANARO

    International Nuclear Information System (INIS)

    To evaluate the performance of newly developed PWR nuclear fuels, an adequate test rig installed in a pressure vessel of IPS, as a part of FTL (Fuel Test Loop) should be fabricated to meet the irradiation purposes. Generally, a nuclear fuel test rig is designed to measure the central temperature of a nuclear fuel pellet and the internal pressure of a fuel rod during an irradiation test. In special cases, it is also designed to measure the swelling or elongation of the fuel rod. The fabrication process of a nuclear fuel test rig that includes a detachable fuel rod assembly has been introduced in this study. Key techniques to fabricate a nuclear fuel test rig have been developed and used in fabricating a test rig mockup. Therefore, to fabricate a new test rig, the tooling of the components and making sub-assemblies that do not include nuclear fuels are out sourced, and the key assembly and sealing processes are carried out in the controlled area using the developed techniques

  12. Fabrication Process of a Nuclear Fuel Test Rig in HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Jintae; Joung, Chang-Young; Ahn, Sung-Ho; Heo, Sung-Ho; Kim, Jin-Joo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    To evaluate the performance of newly developed PWR nuclear fuels, an adequate test rig installed in a pressure vessel of IPS, as a part of FTL (Fuel Test Loop) should be fabricated to meet the irradiation purposes. Generally, a nuclear fuel test rig is designed to measure the central temperature of a nuclear fuel pellet and the internal pressure of a fuel rod during an irradiation test. In special cases, it is also designed to measure the swelling or elongation of the fuel rod. The fabrication process of a nuclear fuel test rig that includes a detachable fuel rod assembly has been introduced in this study. Key techniques to fabricate a nuclear fuel test rig have been developed and used in fabricating a test rig mockup. Therefore, to fabricate a new test rig, the tooling of the components and making sub-assemblies that do not include nuclear fuels are out sourced, and the key assembly and sealing processes are carried out in the controlled area using the developed techniques.

  13. ERC product improvement activities for direct fuel cell power plants

    Energy Technology Data Exchange (ETDEWEB)

    Bentley, C.; Carlson, G.; Doyon, J. [and others

    1995-08-01

    This program is designed to advance the carbonate fuel cell technology from the current power plant demonstration status to the commercial design in an approximately five-year period. The specific objectives which will allow attainment of the overall program goal are: (1) Define market-responsive power plant requirements and specifications, (2) Establish the design for a multifuel, low-cost, modular, market-responsive power plant, (3) Resolve power plant manufacturing issues and define the design for the commercial manufacturing facility, (4) Define the stack and BOP equipment packaging arrangement and define module designs, (5) Acquire capability to support developmental testing of stacks and BOP equipment as required to prepare for commercial design, and (6) Resolve stack and BOP equipment technology issues and design, build, and field test a modular commercial prototype power plant to demonstrate readiness for commercial entry. A seven-task program, dedicated to attaining objective(s) in the areas noted above, was initiated in December 1994. Accomplishments of the first six months are discussed in this paper.

  14. Welding process optimization of nuclear fuel rod using TIG technique for fuel irradiation tests

    International Nuclear Information System (INIS)

    The irradiation test of fuel elements was planned for the evaluation of nuclear fuel performance. To establish fabrication process satisfying the requirements of irradiation test, orbital-TIG welding system for fuel elements was developed, and preliminary welding experiments for optimizing process conditions of fuel element was performed. Fuel elements with 9.5mm diameter and 0.6mm wall thickness of cladding tubes and end caps have been used and optimum conditions of endcap welding have been selected. In this study, the qualification test was performed by tensile tests, helium leak inspections, and metallography examinations to qualify the end cap welding procedure. The soundness of the welds quality of nuclear fuel elements has been confirmed by mechanical tests and microstructural examinations

  15. Fuel-Flexible Combustion System for Co-production Plant Applications

    Energy Technology Data Exchange (ETDEWEB)

    Joel Haynes; Justin Brumberg; Venkatraman Iyer; Jonathan Janssen; Ben Lacy; Matt Mosbacher; Craig Russell; Ertan Yilmaz; Williams York; Willy Ziminsky; Tim Lieuwen; Suresh Menon; Jerry Seitzman; Ashok Anand; Patrick May

    2008-12-31

    Future high-efficiency, low-emission generation plants that produce electric power, transportation fuels, and/or chemicals from fossil fuel feed stocks require a new class of fuel-flexible combustors. In this program, a validated combustor approach was developed which enables single-digit NO{sub x} operation for a future generation plants with low-Btu off gas and allows the flexibility of process-independent backup with natural gas. This combustion technology overcomes the limitations of current syngas gas turbine combustion systems, which are designed on a site-by-site basis, and enable improved future co-generation plant designs. In this capacity, the fuel-flexible combustor enhances the efficiency and productivity of future co-production plants. In task 2, a summary of market requested fuel gas compositions was created and the syngas fuel space was characterized. Additionally, a technology matrix and chemical kinetic models were used to evaluate various combustion technologies and to select two combustor concepts. In task 4 systems analysis of a co-production plant in conjunction with chemical kinetic analysis was performed to determine the desired combustor operating conditions for the burner concepts. Task 5 discusses the experimental evaluation of three syngas capable combustor designs. The hybrid combustor, Prototype-1 utilized a diffusion flame approach for syngas fuels with a lean premixed swirl concept for natural gas fuels for both syngas and natural gas fuels at FA+e gas turbine conditions. The hybrid nozzle was sized to accommodate syngas fuels ranging from {approx}100 to 280 btu/scf and with a diffusion tip geometry optimized for Early Entry Co-generation Plant (EECP) fuel compositions. The swozzle concept utilized existing GE DLN design methodologies to eliminate flow separation and enhance fuel-air mixing. With changing business priorities, a fully premixed natural gas & syngas nozzle, Protoytpe-1N, was also developed later in the program. It did

  16. Feasibility study: comparison of coal- and nuclear-fueled alternatives for process steam and by product electrical power generation for the PPG Industries, Incorporated Plant Site, Lake Charles, Louisiana

    Energy Technology Data Exchange (ETDEWEB)

    1978-07-01

    The purpose of the study was to evaluate the technical and economic feasibility of a small, (365 MWt) nuclear reactor for supplying process steam and electricity as a replacement for energy sources using increasingly scarce natural gas or oil. The PPG Industries, Incorporated Plant Site at Lake Charles, Louisiana, was chosen as representative of industrial installations that require sizeable amounts of process steam and electricity. For comparison purposes conventional coal-fired boilers were also evaluated. It was determined that both nuclear- and coal-based process energy supply systems are technically feasible. For the specific steam/electricity demands at the reference site, the coal-fired plant proved to be economically more attractive than the nuclear units. For an application requiring a base-loaded supply of saturated steam, utilizing full reactor capacity, the nuclear option appears competitive for coal costing $40/ton in 1978 dollars.

  17. Dose Assurance in Radiation Processing Plants

    DEFF Research Database (Denmark)

    Miller, Arne; Chadwick, K.H.; Nam, J.W.

    1983-01-01

    Radiation processing relies to a large extent on dosimetry as control of proper operation. This applies in particular to radiation sterilization of medical products and food treatment, but also during development of any other process. The assurance that proper dosimetry is performed at the...... radiation processing plant can be obtained through the mediation of an international organization, and the IAEA is now implementing a dose assurance service for industrial radiation processing....

  18. Dose assurance in radiation processing plants

    International Nuclear Information System (INIS)

    Radiation processing relies to a large extent on dosimetry as control of proper operation. This applies in particular to radiation sterilization of medical products and food treatment, but also during development of any other process. The assurance that proper dosimetry is performed at the radiation processing plant can be obtained through the mediation of an international organization, and the IAEA is now implementing a dose assurance service for industrial radiation processing. (author)

  19. Dose assurance in radiation processing plants

    Science.gov (United States)

    Miller, A.; Chadwick, K. H.; Nam, J. W.

    Radiation processing relies to a large extent on dosimetry as control of proper operation. This applies in particular to radiation sterilization of medical products and food treatment, but also during development of any other process. The assurance that proper dosimetry is performed at the radiation processing plant can be obtained through the mediation of an international organization, and the IAEA is now implementing a dose assurance service for industrial radiation processing.

  20. Process calculations for a moderator detritiation plant

    International Nuclear Information System (INIS)

    The Savannah River Plant is currently analyzing processes for the removal of tritium from the heavy water used as a moderator in SRP's nuclear reactors. An accompanying paper describes the background and need for this process. A computer-aided design program was used to simulate the distillation section of the detritiation process flowsheet. Simplified calculation techniques were performed to optimize the process parameters. Results obtained are being used to evaluate proposals from various vendors

  1. Durability testing modified compression ignition engines fueled with straight plant oil

    Energy Technology Data Exchange (ETDEWEB)

    Basinger, M.; Lackner, K.S. [Earth and Environmental Engineering, Columbia University, New York City 10027 (United States); Reding, T. [Mechanical Engineering, Manhattan College, New York City (United States); Rodriguez-Sanchez, F.S. [Mali Biocarburant, Bamako (Mali); Modi, V. [Mechanical Engineering, Columbia University, New York City 10027 (United States)

    2010-08-15

    Many short-run studies point to the potential for direct fueling of compression ignition engines with plant oil fuels. There is a much smaller body of work that examines the potential for these fuels in long-run tests that illuminate engine endurance and longevity issues. Generally, longevity studies involving direct fueling of engines with straight plant oils have shown significant impact to the life of the engine, though test results vary widely depending on the oil, engine type, test conditions, and measurement approach. This study utilizes a previously designed modification kit to investigate the longevity implications of directly fueling straight plant oil in an indirect injection (IDI) listeroid type, slow speed stationary engine common in agro-processing applications in developing countries. Specifically this study focuses on the lubrication oil by developing a model to characterize the engine wear and estimate lube oil change frequency. The model is extended to an analysis of the piston rings. Cylinder liner wear, emissions, engine performance, and a visual investigation of several critical engine components are also studied. The 500 hour test with waste vegetable oil fuel resulted in several important findings. The engine break-in period was identified as taking between 200 and 300 h. Emissions analysis supported the break-in definition as smoke opacity and carbon monoxide values fell from 9% and 600 ppm (respectively) during the first few hundred hours, to 5% and 400 ppm in the final 200 h. Lubrication oil viscosity was found to be the limiting degradation factor in the lube oil, requiring oil to be changed every 110 h. Piston ring mass loss was found to correlate very closely with chromium buildup in the lubrication oil and the mathematical model that was developed was used to estimate that piston ring inspection and replacement should occur after 1000 h. Cylinder ovalisation was found to be most sever at top dead center (TDC) at 53 microns of averaged

  2. Long-term performance of a plant microbial fuel cell with Spartina anglica

    NARCIS (Netherlands)

    Timmers, R.A.; Strik, D.P.B.T.B.; Hamelers, H.V.M.; Buisman, C.J.N.

    2010-01-01

    The plant microbial fuel cell is a sustainable and renewable way of electricity production. The plant is integrated in the anode of the microbial fuel cell which consists of a bed of graphite granules. In the anode, organic compounds deposited by plant roots are oxidized by electrochemically active

  3. Studies on production planning of IPEN fuel-element plant in order to meet RMB demand

    Energy Technology Data Exchange (ETDEWEB)

    Negro, Miguel L.M.; Saliba-Silva, Adonis M.; Durazzo, Michelangelo, E-mail: mlnegro@ipen.br, E-mail: saliba@ipen.br, E-mail: mdurazzo@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    The plant of the Nuclear Fuel Center (CCN) will have to change its current laboratorial production level to an industrial level in order to meet the fuel demand of RMB and of IEA-R1. CCN's production process is based on the hydrolysis of UF6, which is not a frequent production route for nuclear fuel. The optimization of the production capacity of such a production route is a new field of studies. Two different approaches from the area of Operations Research (OR) were used in this paper. The first one was the PERT/CPM technique and the second one was the creation of a mathematical linear model for minimization of the production time. PERT/CPM's results reflect the current situation and disclose which production activities may not be critical. The results of the second approach show a new average time of 3.57 days to produce one Fuel Element and set the need of inventory. The mathematical model is dynamic, so that it issues better results if performed monthly. CCN's management team will therefore have a clearer view of the process times and production and inventory levels. That may help to shape the decisions that need to be taken for the enlargement of the plant's production capacity. (author)

  4. Environmental benchmarking of the largest fossil-fueled electricity generating plants in the U.S

    Science.gov (United States)

    Sarkis, Joseph

    2004-02-01

    Environmental management, to be effective, requires performance evaluation and process improvement. This is especially the case in fossil-fueled electricity generating plants. Although eco-efficient management of these types of organizations are critical to local, national and global environmental issues, few studies have focused on performance measurement and eco-efficiency improvements in this industry. This study evaluates the eco-efficiencies of the top 100 major U.S. fossil-fueled electricity generating plants from 1998 data. Using a multi-criteria non-parametric productivity model (data envelopment analysis) efficiency scores are determined. These efficiency scores are treated by a clustering method in identifying benchmarks for improving poorly performing plants. Efficiency measures are based on three resource input measures including boiler generating capacity, total fuel heat used, and total generator capacity, and four output measures including actual energy generated, SO2, NOx, and CO2 emissions. The purpose of this paper is two-fold, to introduce the methodology"s application to eco-efficiency performance measurement and show some characteristics of the benchmarked plants and groups.

  5. 77 FR 823 - Guidance for Fuel Cycle Facility Change Processes

    Science.gov (United States)

    2012-01-06

    ... possess greater than a critical mass of special nuclear material and that are engaged in enriched uranium processing, fabrication of uranium fuel or fuel assemblies, uranium enrichment, enriched uranium hexafluoride... Information DG-3037 was published in the Federal Register on July 14, 2011 (76 FR 41527). The public...

  6. Thermochemical production of liquid fuels from biomass: Thermo-economic modeling, process design and process integration analysis

    Energy Technology Data Exchange (ETDEWEB)

    Tock, Laurence; Gassner, Martin; Marechal, Francois [Industrial Energy Systems Laboratory, Ecole Polytechnique Federale de Lausanne, Station postale 9, CH-1015 Lausanne (Switzerland)

    2010-12-15

    A detailed thermo-economic model combining thermodynamics with economic analysis and considering different technological alternatives for the thermochemical production of liquid fuels from lignocellulosic biomass is presented. Energetic and economic models for the production of Fischer-Tropsch fuel (FT), methanol (MeOH) and dimethyl ether (DME) by means of biomass drying with steam or flue gas, directly or indirectly heated fluidized bed or entrained flow gasification, hot or cold gas cleaning, fuel synthesis and upgrading are reviewed and developed. The process is integrated and the optimal utility system is computed. The competitiveness of the different process options is compared systematically with regard to energetic, economic and environmental considerations. At several examples, it is highlighted that process integration is a key element that allows for considerably increasing the performance by optimal utility integration and energy conversion. The performance computations of some exemplary technology scenarios of integrated plants yield overall energy efficiencies of 59.8% (crude FT-fuel), 52.5% (MeOH) and 53.5% (DME), and production costs of 89, 128 and 113 EURMWh{sup -1} on fuel basis. The applied process design approach allows to evaluate the economic competitiveness compared to fossil fuels, to study the influence of the biomass and electricity price and to project for different plant capacities. Process integration reveals in particular potential energy savings and waste heat valorization. Based on this work, the most promising options for the polygeneration of fuel, power and heat will be determined in a future thermo-economic optimization. (author)

  7. Development of Glovebox Unattended Assay and Monitoring system for JNFL MOX fuel fabrication plant

    International Nuclear Information System (INIS)

    In the Mixed Oxide (MOX) Fuel Fabrication Plant of Japan Nuclear Fuel Limited (JNFL), a glove box unattended assay and monitoring system (GUAM) has been developed. The setting-up process of the main components, a 3He(7.5 atm pressure) neutron detector with an organic moderator (6-cm thick polyethylene) and a data acquisition system on a computer, with optimization procedure for their performance is reported in this paper. Dependence of the detection efficiency on the position of 240Pu (10 and 110 g) situated in GUAM, especially in relation with the glove box wall, was examined using 252Cf-neutron source as a simulator. It is concluded that the overall error of the measurement in GUAM amounts to 7.7% before installing the equipments needed to handle presumed MOX fuels. (S.Ohno)

  8. Impact of plant transient response on fuel management strategy at Virginia Power

    International Nuclear Information System (INIS)

    Virginia Power has been performing in-house reload core design and safety analysis for several years. These analyses have been in support of North Anna units 1 and 2 and Surry units 1 and 2, all of which are three-loop pressurized water reactor plants designed and built by Westinghouse. Historically, Virginia Power first developed the capability to design and optimize its own core loading patterns in the early 1970's. This development effort was driven by the need to establish in-house control of the fuel management process, thereby ensuring that energy generation requirements are met in an economically optimum fashion. It soon became obvious that reload design and safety analysis processes are so integrally coupled that in order to perform the fuel management function in an effective manner, in-house capability in both areas needed to be developed. After reviewing the spectrum of economic, safety and operational constraints which affect the reload design and analysis process, an integrated model of the process is presented in flow chart format. This is followed by several specific examples which illustrate the interplay between sound fuel management practice and the assurance of plant safety using in-house analysis techniques

  9. Disposal of spent fuel from German nuclear power plants - 16028

    International Nuclear Information System (INIS)

    to this, the feasibility of the direct disposal of transport and storage casks, the so-called 'DIREGT concept', is being investigated. The implementation of this concept would avoid the necessity to separate fuel rods from structural parts and to procure custom-made final disposal casks. All investigations and studies performed so far support the feasibility of direct disposal of spent fuel in multipurpose casks as today used for transport and storage. Both additional concepts, BSK 3 and DIREGT, are expected to simplify disposal processes and to reduce operational risk without any compromise in long-term radiological safety aspects. (authors)

  10. Emergency water supply systems for fuel reprocessing plants

    International Nuclear Information System (INIS)

    Sources of emergency water acceptable to the NRC staff are described and bases for the design of systems that furnish emergency water to the fuel storage pool, high-level radioactive waste storage, fire protection system, certain process vessels, and any other safety-related equipment or system requiring a supply of water to perform the design safety function, directly or indirectly, are presented. (LK)

  11. States and compacts: Issues and events affecting facility development efforts, including the Barnwell opening

    Energy Technology Data Exchange (ETDEWEB)

    Larson, G.S.

    1995-12-31

    Ten years have passed since the first regional low-level radioactive waste compacts received Congressional consent and initiated their efforts to develop new disposal capacity. During these 10 years, both significant achievements and serious setbacks have marked our efforts and affect our current outlook. Recent events in the waste marketplace, particularly in the operating status of the Barnwell disposal facility, have now raised legitimate questions about the continued rationale for the regional framework that grew out of the original legislation enacted by Congress in 1980. At the same time, licensing activities for new regional disposal facilities are under way in three states, and a fourth awaits the final go-ahead to begin construction. Uncertainty over the meaning and reliability of the marketplace events makes it difficult to gauge long-term implications. In addition, differences in the status of individual state and compact facility development efforts lead to varying assessments of the influence these events will, or should, have on such efforts.

  12. Coordinated safeguards for materials management in a fuel reprocessing plant. Volume I

    International Nuclear Information System (INIS)

    A materials management system is described for safeguarding special nuclear materials in a fuel-reprocessing plant. Recently developed nondestructive-analysis techniques and process-monitoring devices are combined with conventional chemical analyses and process-control instrumentation for improved materials accounting data. Unit-process accounting based on dynamic material balances permits localization of diversion in time and space, and the application of advanced statistical methods supported by decision-analysis theory ensures optimum use of accounting information for detecting diversion. This coordinated safeguards system provides maximum effectiveness consistent with modest cost and minimum process interference. Modeling and simulation techniques are used to evaluate the sensitivity of the system to single and multiple thefts and to compare various safeguards options. The study identifies design criteria that would improve the safeguardability of future plants

  13. Integrated coke, asphalt and jet fuel production process and apparatus

    Science.gov (United States)

    Shang, Jer Y.

    1991-01-01

    A process and apparatus for the production of coke, asphalt and jet fuel m a feed of fossil fuels containing volatile carbon compounds therein is disclosed. The process includes the steps of pyrolyzing the feed in an entrained bed pyrolyzing means, separating the volatile pyrolysis products from the solid pyrolysis products removing at least one coke from the solid pyrolysis products, fractionating the volatile pyrolysis products to produce an overhead stream and a bottom stream which is useful as asphalt for road pavement, condensing the overhead stream to produce a condensed liquid fraction and a noncondensable, gaseous fraction, and removing water from the condensed liquid fraction to produce a jet fuel-containing product. The disclosed apparatus is useful for practicing the foregoing process. the process provides a useful method of mass producing and jet fuels from materials such as coal, oil shale and tar sands.

  14. Processes assessment in binary mixture plant

    Directory of Open Access Journals (Sweden)

    N. Shankar Ganesh, T. Srinivas

    2013-01-01

    Full Text Available Binary fluid system has an efficient system of heat recovery compared to a single fluid system due to a better temperature match between hot and cold fluids. There are many applications with binary fluid system i.e. Kalina power generation, vapor absorption refrigeration, combined power and cooling etc. Due to involvement of three properties (pressure, temperature and concentration in the processes evaluation, the solution is complicated compared to a pure substance. The current work simplifies this complex nature of solution and analyzes the basic processes to understand the processes behavior in power generation as well as cooling plants. Kalina power plant consists of regenerator, heat recovery vapor generator, condenser, mixture, separator, turbine, pump and throttling device. In addition to some of these components, the cooling plant consists of absorber which is similar in operation of condenser. The amount of vapor at the separator decreases with an increase in its pressure and temperature.

  15. Electrochemical fluorination for processing of used nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Garcia-Diaz, Brenda L.; Martinez-Rodriguez, Michael J.; Gray, Joshua R.; Olson, Luke C.

    2016-07-05

    A galvanic cell and methods of using the galvanic cell is described for the recovery of uranium from used nuclear fuel according to an electrofluorination process. The galvanic cell requires no input energy and can utilize relatively benign gaseous fluorinating agents. Uranium can be recovered from used nuclear fuel in the form of gaseous uranium compound such as uranium hexafluoride, which can then be converted to metallic uranium or UO.sub.2 and processed according to known methodology to form a useful product, e.g., fuel pellets for use in a commercial energy production system.

  16. Using polymer electrolyte membrane fuel cells in a hybrid surface ship propulsion plant to increase fuel efficiency

    OpenAIRE

    Kroll, Douglas M.

    2010-01-01

    CIVINS Approved for public release; distribution is unlimited An increasingly mobile US Navy surface fleet and oil price uncertainty contrast with the Navy's desire to lower the amount of money spent purchasing fuel. Operational restrictions limiting fuel use are temporary and cannot be dependably relied upon. Long term technical research toward improving fuel efficiency is ongoing and includes advanced gas turbines and integrated electric propulsion plants, but these will not be implem...

  17. Contribution to the study of the degradation of the solvent used in a nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    The degradation of a mixed solvent (tributylphosphate - hydrocarbons) in a fuel reprocessing plant (UP2 at La Hague, France) is studied in this thesis. Laboratory studies on degradation mechanisms, decomposition products and regeneration processes are reviewed in a bibliographic synthesis. Solvent degradation is investigated on a real solvent from a reprocessing plant. Influence of degradation on solvent performance is shown and regeneration processes should be improved. Many regeneration processes are tested on solvent from the plant and results are discussed. Separation and analysis of degradation products show the polyfunctional structure of compounds formed

  18. Nuclear fuels technologies fiscal year 1998 fuel fabrication process development feed materials baseline development summary report

    International Nuclear Information System (INIS)

    This document summarizes a portion of the work performed for the fuel fabrication process development task for the fiscal year 1998 (FY98) research and development (R and D) activities at Los Alamos National Laboratory (LANL). It was determined through previous efforts that development work is necessary when new feed materials are introduced into an established fabrication process. The FMD Program decided to select a new UO2 source in FY98 for use in fuel fabrication R and D activities. The new source identified was UO2 powder derived from the Ammonium Uranyl Carbonate (AUC) process. Fuel fabrication activities to date have used Cameco UO2 obtained from Canada. The properties of Cameco UO2 differ significantly from those of AUC-derived UO2. Although the AUC-derived UO2 material was used previously to fabricate the majority of the European reactor-grade mixed oxide (MOX) fuel, it is important to establish how it will interact with weapons-grade plutonium in terms of fuel fabricability. Furthermore, plutonium feed materials can be quite different (from a ceramics perspective) depending on the conversion process and processing parameters, and it is important to quantify the effects these differences may have on the fuel fabrication process. There were two main tasks included in this effort: (1) Develop baseline MOX fuel fabrication processing parameters for the AUC-derived source of UO2 feed material, using both surrogate CeO2 and prototypic PuO2 powders. (2) Fabricate MOX fuel using the baseline fabrication processing parameters, the new source of UO2 feed material, and an alternative source of PuO2 feed material. The experiments performed and results obtained from these Feed Materials Baseline Development activities are described

  19. Systems Analysis of an Advanced Nuclear Fuel Cycle Based on a Modified UREX+3c Process

    Energy Technology Data Exchange (ETDEWEB)

    E. R. Johnson; R. E. Best

    2009-12-28

    The research described in this report was performed under a grant from the U.S. Department of Energy (DOE) to describe and compare the merits of two advanced alternative nuclear fuel cycles -- named by this study as the “UREX+3c fuel cycle” and the “Alternative Fuel Cycle” (AFC). Both fuel cycles were assumed to support 100 1,000 MWe light water reactor (LWR) nuclear power plants operating over the period 2020 through 2100, and the fast reactors (FRs) necessary to burn the plutonium and minor actinides generated by the LWRs. Reprocessing in both fuel cycles is assumed to be based on the UREX+3c process reported in earlier work by the DOE. Conceptually, the UREX+3c process provides nearly complete separation of the various components of spent nuclear fuel in order to enable recycle of reusable nuclear materials, and the storage, conversion, transmutation and/or disposal of other recovered components. Output of the process contains substantially all of the plutonium, which is recovered as a 5:1 uranium/plutonium mixture, in order to discourage plutonium diversion. Mixed oxide (MOX) fuel for recycle in LWRs is made using this 5:1 U/Pu mixture plus appropriate makeup uranium. A second process output contains all of the recovered uranium except the uranium in the 5:1 U/Pu mixture. The several other process outputs are various waste streams, including a stream of minor actinides that are stored until they are consumed in future FRs. For this study, the UREX+3c fuel cycle is assumed to recycle only the 5:1 U/Pu mixture to be used in LWR MOX fuel and to use depleted uranium (tails) for the makeup uranium. This fuel cycle is assumed not to use the recovered uranium output stream but to discard it instead. On the other hand, the AFC is assumed to recycle both the 5:1 U/Pu mixture and all of the recovered uranium. In this case, the recovered uranium is reenriched with the level of enrichment being determined by the amount of recovered plutonium and the combined amount

  20. Systems Analysis of an Advanced Nuclear Fuel Cycle Based on a Modified UREX+3c Process

    International Nuclear Information System (INIS)

    The research described in this report was performed under a grant from the U.S. Department of Energy (DOE) to describe and compare the merits of two advanced alternative nuclear fuel cycles -- named by this study as the 'UREX+3c fuel cycle' and the 'Alternative Fuel Cycle' (AFC). Both fuel cycles were assumed to support 100 1,000 MWe light water reactor (LWR) nuclear power plants operating over the period 2020 through 2100, and the fast reactors (FRs) necessary to burn the plutonium and minor actinides generated by the LWRs. Reprocessing in both fuel cycles is assumed to be based on the UREX+3c process reported in earlier work by the DOE. Conceptually, the UREX+3c process provides nearly complete separation of the various components of spent nuclear fuel in order to enable recycle of reusable nuclear materials, and the storage, conversion, transmutation and/or disposal of other recovered components. Output of the process contains substantially all of the plutonium, which is recovered as a 5:1 uranium/plutonium mixture, in order to discourage plutonium diversion. Mixed oxide (MOX) fuel for recycle in LWRs is made using this 5:1 U/Pu mixture plus appropriate makeup uranium. A second process output contains all of the recovered uranium except the uranium in the 5:1 U/Pu mixture. The several other process outputs are various waste streams, including a stream of minor actinides that are stored until they are consumed in future FRs. For this study, the UREX+3c fuel cycle is assumed to recycle only the 5:1 U/Pu mixture to be used in LWR MOX fuel and to use depleted uranium (tails) for the makeup uranium. This fuel cycle is assumed not to use the recovered uranium output stream but to discard it instead. On the other hand, the AFC is assumed to recycle both the 5:1 U/Pu mixture and all of the recovered uranium. In this case, the recovered uranium is reenriched with the level of enrichment being determined by the amount of recovered plutonium and the combined amount of the

  1. Repository for spent nuclear fuel. Plant description layout D - Forsmark

    International Nuclear Information System (INIS)

    This document describes the final repository for spent nuclear fuel, SFK, which is located at Forsmark, in Oesthammar. The bedrock at the site is part of a so-called tectonic lens, in which the rock composition is relatively homogeneous and less deformed than outside the lens. The bedrock consists mainly of granite with high quartz content and good thermal conductivity. The central parts above ground are grouped in an operations area, located at the Soederviken on the south side of the intake duct for cooling water for nuclear power plant. Operating area is divided into an internal, secured portion, where the canisters of fuel are handled and there are links to the underground part, and a outer part, where the buffer, backfill and sealing used in the repository's barriers are produced. The above-ground part of the plant and also include storage of excavated rock, ventilation stations, and supplies of bentonite. The underground portion consists of a central area and a storage area. Caverns of the central area contain features for the underground operation. It communicates with the internal operating range above ground via a spiral ramp and several shafts. The ramp used to transport capsules of spent fuel and other heavy or bulky transport. The shafts are used to transport rock, buffer, backfill and staff, as well as for ventilation. The largest part of the space below ground is the repository where the canisters with the spent fuel are disposed. The capsules are deposited in vertical holes in the tunnels. When the deposit in a tunnel is complete, the tunnel is re-filled. The two main activities underground is rock work and disposal work, which are conducted separately from each other. Rock works covers all steps required to excavate tunnels and drill deposition holes, as well as to make temporary installations in the tunnels. To the landfill works count, besides the deposit of the capsule, the placement of the bentonite buffer in the deposition hole and backfilling

  2. Multi-fuel multi-product operation of IGCC power plants with carbon capture and storage (CCS)

    International Nuclear Information System (INIS)

    This paper investigates multi-fuel multi-product operation of IGCC plants with carbon capture and storage (CCS). The investigated plant designs co-process coal with different sorts of biomass (e.g. sawdust) and solid wastes, through gasification, leading to different decarbonised energy vectors (power, hydrogen, heat, substitute natural gas etc.) simultaneous with carbon capture. Co-gasification of coal with different renewable energy sources coupled with carbon capture will pave the way towards zero emissions power plants. The energy conversions investigated in the paper were simulated using commercial process flow modelling package (ChemCAD) in order to produce mass and energy balances necessary for the proposed evaluation. As illustrative cases, hydrogen and power co-generation and Fischer–Tropsch fuel synthesis (both with carbon capture), were presented. The case studies investigated in the paper produce a flexible ratio between power and hydrogen (in the range of 400–600 MW net electricity and 0–200 MWth hydrogen considering the lower heating value) with at least 90% carbon capture rate. Special emphasis were given to fuel selection criteria for optimisation of gasification performances (fuel blending), to the selection criteria for gasification reactor in a multi-fuel multi-product operation scenario, modelling and simulation of whole process, to thermal and power integration of processes, flexibility analysis of the energy conversion processes, in-depth techno-economic and environmental assessment etc. - Highlights: • Assessment of IGCC-based energy vectors poly-generation systems with CCS. • Optimisation of gasification performances and CO2 emissions by fuel blending. • Multi-fuel multi-product operation of gasification plants

  3. Revaluation on measured burnup values of fuel assemblies by post-irradiation experiments at BWR plants

    International Nuclear Information System (INIS)

    Fuel composition data for 8x8 UO2, Tsuruga MOX and 9x9-A type UO2 fuel assemblies irradiated in BWR plants were measured. Burnup values for measured fuels based on Nd-148 method were revaluated. In this report, Nd-148 fission yield and energy per fission obtained by burnup analyses for measured fuels were applied and fuel composition data for the measured fuel assemblies were revised. Furthermore, the adequacies of revaluated burnup values were verified through the comparison with burnup values calculated by the burnup analyses for the measured fuel assemblies. (author)

  4. Advanced fuel cycle on the basis of pyroelectrochemical process for irradiated fuel reprocessing and vibropacking technology

    International Nuclear Information System (INIS)

    For advanced nuclear fuel cycle in SSC RIAR there is developed the pyroelectrochemical process to reprocess irradiated fuel and produce granulated oxide fuel UO2, PuO2 or (U,Pu)O2 from chloride melts. The basic technological stage is the extraction of oxides as a crystal product with the methods either of the electrolysis (UO2 and UO2-PuO2) or of the precipitating crystalIization (PuO2). After treating the granulated fuel is ready for direct use to manufacture vibropacking fuel pins. Electrochemical model for (U,Pu)O2 coprecipitation is described. There are new processes being developed: electroprecipitation of mixed oxides - (U,Np)O2, (U,Pu,Np)O2, (U,Am)O2 and (U,Pu,Am)O2. Pyroelectrochemical production of mixed actinide oxides is used both for reprocessing spent fuel and for producing actinide fuel. Both the efficiency of pyroelectrochemical methods application for reprocessing nuclear fuel and of vibropac technology for plutonium recovery are estimated. (author)

  5. 1000kW phosphoric acid fuel cell power plant. Outline of the plant

    Energy Technology Data Exchange (ETDEWEB)

    Shinobe, Kenji; Suzuki, Kazuo; Kaneko, Hideo

    1988-02-10

    The outline of the 1000KW phosphoric acid fuel cell power plant, developed as part of the Moonlight plan, was described. The plant was composed of 4 stacks of 260KW DC output. They were devided into two train with 680V and 765A. The generation efficiency of the plant was 40% and more. Steam reforming of natural gas was used. As the fuel, fuel cell exhaust gas was used in composition with the natural gas. The DC-AC inverter had an efficiency of 96%. The capacity of hot water generator and demineralized water plant for cell cooling were 2t/h and 1.6t/h, respectively, and air-system was incorporated. In September of 1987, the plant has succeeded in 1000KW power generation, and put in operation now. Under the 100% loaded condition, each cell had a voltage of 0.7V with little variation, and the current was 200mA/cm/sup 2/. No problems were found in cooling conditions and in the control of interpole differential pressure. The reformer has been operated for 1200h scince its commisioning, and had experiences of 100 times on start up-shut down operations, the reformer also indicated good performances in the gas compositions. The starting time of 8h and the load follow-up rate 10%/min remain as the subjects for shortening. DC-AC conversion was good. The concentration of NOx and the noise level satisfied the target values. (12 figs, 1 tab)

  6. Modern power station practice mechanical boilers, fuel-, and ash-handling plant

    CERN Document Server

    Sherry, A; Cruddace, AE

    2014-01-01

    Modern Power Station Practice, Second Edition, Volume 2: Mechanical (Boilers, Fuel-, and Ash-Handling Plant) focuses on the design, manufacture and operation of boiler units and fuel-and ash-handling plants.This book is organized into five main topics-furnace and combustion equipment, steam and water circuits, ancillary plant and fittings, dust extraction and draught plant, and fuel-and ash-handling plant.In these topics, this text specifically discusses the influence of nature of coal on choice of firing equipment; oil-burner arrangements, ignition and control; disposition of the heating surf

  7. Investigation of Thermal Processes at Dry Storage of Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    For good safety dry storage of the spent nuclear fuel of the Zaporizhska nuclear power plant (Ukraine) investigations of thermal processes are carried out. Researches were carried out by the solution of the conjugate problems of heat exchange. The free convection of ventilating air and helium into basket of storage, and radiative heat exchange in the container was considered. As a result temperature fields of the container and air in windless day and temperature fields of the spent fuel assemblies with identical and various energy-release inside the container of a storage are obtained. Results of investigations can be used for construction of safety nearstations dry storages in other atomic power plants of Ukraine or at open dry storages of the spent nuclear fuel in other countries. (author)

  8. A comparative study among fossil fuel power plants in PJM and California ISO by DEA environmental assessment

    International Nuclear Information System (INIS)

    This study compares among fossil fuel power plants in PJM and California ISO by their unified (operational and environmental) performance. DEA (Data Envelopment Analysis) is used as a methodology. For comparative analysis, DEA incorporates strategic concepts such as natural and managerial disposability into the computational process. This study explores both how to measure Returns to Scale (RTS) under natural disposability and how to measure Damages to Scale (DTS) under managerial disposability. This empirical study obtains two implications on US energy policy. One of the two policy implications is that California ISO outperforms PJM in terms of the three unified efficiency measures. The result implies that strict regulation on undesirable outputs, as found in California, is important in enhancing the performance of US fossil fuel power plants. Thus, it is necessary for federal and local governments to regulate the fossil fuel power plants under the strict implementation of environmental protection. Under such a policy direction, it is possible for US fossil fuel power plants to attain economic prosperity (by enhancing their operational efficiencies) and to satisfy environmental regulation (by enhancing their environmental efficiencies). The other policy implication is that coal-fired and gas-fired power plants in PJM and California ISO need to reduce their operational sizes or introduce technology innovation on desirable and undesirable outputs and/or new management for environmental protection within their operations. Meanwhile, oil-fired power plants may increase their operational sizes if they can introduce technology innovation and new management on undesirable outputs. - Highlights: • This study compares fossil fuel power plants in PJM and California ISO. • California ISO outperforms PJM in terms of their unified efficiency measures. • Regulation by Clean Air Act is important for environmental protection. • Fossil fuel power plants need technology

  9. Fate of virginiamycin through the fuel ethanol production process.

    Science.gov (United States)

    Bischoff, Kenneth M; Zhang, Yanhong; Rich, Joseph O

    2016-05-01

    Antibiotics are frequently used to prevent and treat bacterial contamination of commercial fuel ethanol fermentations, but there is concern that antibiotic residues may persist in the distillers grains coproducts. A study to evaluate the fate of virginiamycin during the ethanol production process was conducted in the pilot plant facilities at the National Corn to Ethanol Research Center, Edwardsville, IL. Three 15,000-liter fermentor runs were performed: one with no antibiotic (F1), one dosed with 2 parts per million (ppm) of a commercial virginiamycin product (F2), and one dosed at 20 ppm of virginiamycin product (F3). Fermentor samples, distillers dried grains with solubles (DDGS), and process intermediates (whole stillage, thin stillage, syrup, and wet cake) were collected from each run and analyzed for virginiamycin M and virginiamycin S using a liquid chromatography-mass spectrometry method. Virginiamycin M was detected in all process intermediates of the F3 run. On a dry-weight basis, virginiamycin M concentrations decreased approximately 97 %, from 41 μg/g in the fermentor to 1.4 μg/g in the DDGS. Using a disc plate bioassay, antibiotic activity was detected in DDGS from both the F2 and F3 runs, with values of 0.69 μg virginiamycin equivalent/g sample and 8.9 μg/g, respectively. No antibiotic activity (process intermediate samples from the F2 run. These results demonstrate that low concentrations of biologically active antibiotic may persist in distillers grains coproducts produced from fermentations treated with virginiamycin.

  10. Springfield Processing Plant (SPP) Facility Information

    Energy Technology Data Exchange (ETDEWEB)

    Leach, Janice; Torres, Teresa M.

    2012-10-01

    The Springfield Processing Plant is a hypothetical facility. It has been constructed for use in training workshops. Information is provided about the facility and its surroundings, particularly security-related aspects such as target identification, threat data, entry control, and response force data.

  11. Plant for producing an oxygen-containing additive as an ecologically beneficial component for liquid motor fuels

    Science.gov (United States)

    Siryk, Yury Paul; Balytski, Ivan Peter; Korolyov, Volodymyr George; Klishyn, Olexiy Nick; Lnianiy, Vitaly Nick; Lyakh, Yury Alex; Rogulin, Victor Valery

    2013-04-30

    A plant for producing an oxygen-containing additive for liquid motor fuels comprises an anaerobic fermentation vessel, a gasholder, a system for removal of sulphuretted hydrogen, and a hotwell. The plant further comprises an aerobic fermentation vessel, a device for liquid substance pumping, a device for liquid aeration with an oxygen-containing gas, a removal system of solid mass residue after fermentation, a gas distribution device; a device for heavy gases utilization; a device for ammonia adsorption by water; a liquid-gas mixer; a cavity mixer, a system that serves superficial active and dispersant matters and a cooler; all of these being connected to each other by pipelines. The technical result being the implementation of a process for producing an oxygen containing additive, which after being added to liquid motor fuels, provides an ecologically beneficial component for motor fuels by ensuring the stability of composition fuel properties during long-term storage.

  12. Development of Voloxidation Process for Treatment of LWR Spent Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. J.; Jung, I. H.; Shin, J. M. (and others)

    2007-08-15

    The objective of the project is to develop a process which provides a means to recover fuel from the cladding, and to simplify downstream processes by recovering volatile fission products. This work focuses on the process development in three areas ; the measurement and assessment of the release behavior for the volatile and semi-volatile fission products from the voloxidation process, the assessment of techniques to trap and recover gaseous fission products, and the development of process cycles to optimize fuel cladding separation and fuel particle size. High temperature adsorption method of KAERI was adopted in the co-design of OTS for hot experiment in INL. KAERI supplied 6 sets of filter for hot experiment. Three hot experiment in INL hot cell from the 25th of November for two weeks with attaching 4 KAERI staffs had been carried out. The results were promising. For example, trapping efficiency of Cs was 95% and that of I was 99%, etc.

  13. International guidelines for fire protection at nuclear installations including nuclear fuel plants, nuclear fuel stores, teaching reactors, research establishments

    International Nuclear Information System (INIS)

    The guidelines are recommended to designers, constructors, operators and insurers of nuclear fuel plants and other facilities using significant quantities of radioactive materials including research and teaching reactor installations where the reactors generally operate at less than approximately 10 MW(th). Recommendations for elementary precautions against fire risk at nuclear installations are followed by appendices on more specific topics. These cover: fire protection management and organization; precautions against loss during construction alterations and maintenance; basic fire protection for nuclear fuel plants; storage and nuclear fuel; and basic fire protection for research and training establishments. There are numerous illustrations of facilities referred to in the text. (U.K.)

  14. GT-MHR spent fuel storage disposal without processing

    International Nuclear Information System (INIS)

    Possibility of GT-MHR spent fuel storage during long time without additional processing is discussed in this paper. Spent fuel elements discharged from this reactor type are ideal waste forms for permanent disposal in a geologic repository. The graphite fuel elements and the ceramic coatings on the fuel particles are as-manufactured engineered barriers that provide excellent near field containment of radionuclides and minimize reliance on the waste package and surrounding geologic media for long-term containment. Because of the high level of plutonium destruction and degradation achieved by GT-MHR, the isotopic composition of residual plutonium in spent fuel elements would not be practical for use in nuclear weapons and for energy production. Dilution of plutonium within the relatively large volume of GT-MHR fuel elements provides excellent resistance to diversion throughout the fuel cycle. This is accomplished without adversely impacting repository land requirements, since repository loading is determined by decay heat load and not by physical volume. These conditions of safe fuel storage: criticality conditions, conditions of decay heat removing and radiation doses are discussed as well. (author)

  15. Removal plan for Shippingport pressurized water reactor core 2 blanket fuel assemblies form T plant to the canister storage building

    Energy Technology Data Exchange (ETDEWEB)

    Lata

    1996-09-26

    This document presents the current strategy and path forward for removal of the Shippingport Pressurized Water Reactor Core 2 blanket fuel assemblies from their existing storage configuration (wet storage within the T Plant canyon) and transport to the Canister Storage Building (designed and managed by the Spent Nuclear Fuel. Division). The removal plan identifies all processes, equipment, facility interfaces, and documentation (safety, permitting, procedures, etc.) required to facilitate the PWR Core 2 assembly removal (from T Plant), transport (to the Canister storage Building), and storage to the Canister Storage Building. The plan also provides schedules, associated milestones, and cost estimates for all handling activities.

  16. 75 FR 60147 - Calvert Cliffs Nuclear Power Plant, LLC; Independent Spent Fuel Storage Installation; Notice of...

    Science.gov (United States)

    2010-09-29

    ... COMMISSION Calvert Cliffs Nuclear Power Plant, LLC; Independent Spent Fuel Storage Installation; Notice of... Branch, Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and... Independent Spent Fuel Storage Installation (ISFSI) Technical Specifications (TS) be revised as follows: 1....

  17. 76 FR 22935 - Calvert Cliffs Nuclear Power Plant, LLC Independent Spent Fuel Storage Installation; Notice of...

    Science.gov (United States)

    2011-04-25

    ... Class C (GTCC) waste and other radioactive materials associated with spent fuel storage at the CCNPP... granted, the renewed license will authorize the applicant to continue to store spent fuel in a dry cask... COMMISSION Calvert Cliffs Nuclear Power Plant, LLC Independent Spent Fuel Storage Installation; Notice...

  18. Green electricity production with living plants and bacteria in a fuel cell

    NARCIS (Netherlands)

    Strik, D.P.B.T.B.; Hamelers, H.V.M.; Snel, J.F.H.; Buisman, C.J.N.

    2008-01-01

    The world needs sustainable, efficient, and renewable energy production. We present the plant microbial fuel cell (plant-MFC), a concept that exploits a bioenergy source in situ. In the plant-MFC, plants and bacteria were present to convert solar energy into green electricity. The principal idea is

  19. Development of a 200kW multi-fuel type PAFC power plant

    Energy Technology Data Exchange (ETDEWEB)

    Take, Tetsuo; Kuwata, Yutaka; Adachi, Masahito; Ogata, Tsutomu [NTT Integrated Information & Energy System Labs., Tokyo (Japan)

    1996-12-31

    Nippon Telegraph and Telephone Corporation (NFT) has been developing a 200 kW multi-fuel type PAFC power plant which can generate AC 200 kW of constant power by switching fuel from pipeline town gas to liquefied propane gas (LPG) and vice versa. This paper describes the outline of the demonstration test plant and test results of its fundamental characteristics.

  20. Use of Pilot Plants for Developing Used Nuclear Fuel Recycling Facilities

    International Nuclear Information System (INIS)

    EnergySolutions and its teaming partners are working with the US Department of Energy (DOE) to develop processes, equipment and facilities for recycling used nuclear fuel (UNF). Recycling significantly reduces the volume of wastes that ultimately will be consigned to the National Geologic Repository, enables the re-use in new fuel of the valuable uranium and plutonium in the UNF, and allows the long-lived minor actinides to be treated separately so they do not become long term heat emitters in the Repository. A major requirement of any new UNF recycling facility is that pure plutonium is not separated anywhere in the process, so as to reduce the nuclear proliferation attractiveness of the facility. EnergySolutions and its team partner the UK National Nuclear Laboratory (NNL) have developed the NUEX process to achieve this and to handle appropriately the treatment of other species such as krypton, tritium, neptunium and technetium. NUEX is based on existing successful commercial UNF recycling processes deployed in the UK, France and imminently in Japan, but with a range of modifications to the flowsheet to keep some uranium with the plutonium at all times and to minimize aerial and liquid radioactive discharges. NNL's long-term experience in developing the recycling and associated facilities at the Sellafield site in the UK, and its current duties to support technically the operation of the Thermal Oxide Reprocessing Plant (THORP) at Sellafield provides essential input to the design of the US NUEX-based facility. Development work for THORP and other first-of-kind nuclear plants employed miniature scale fully radioactive through large scale inactive pilot plants. The sequence of development work that we have found most successful is to (i) perform initial process development at small (typically 1/5000) scale in gloveboxes using trace active materials, (ii) demonstrate the processes at the same small scale with actual irradiated fuel in hot cells and (iii) demonstrate

  1. Advantages in energy, fuel, and investment savings by melt-type granulation processes

    Energy Technology Data Exchange (ETDEWEB)

    Young, R.D.; Lee, R.G.

    1975-01-01

    Melt-type processes developed by TVA, in which wet-process phosphoric acid provides all or most of the P/sub 2/O/sub 5/ in granular fertilizers, show promise in decreasing fuel, total energy, investment, and operating cost. The analyses and estimates were based on pilot-plant studies and demonstration-plant experience at TVA's National Fertilizer Development Center, Muscle Shoals, Alabama. It is shown that elimination of fuel for drying and substantially decreased horsepower requirements (particularly in a new plant) would decrease energy requirement in the granulation plant by about 1,000,000 Btu's per metric ton of P/sub 2/O%. When coupled with lower operating costs that are based on investment factors, the savings for the granulation plant is indicated to be about $6 per metric ton of P/sub 2/O/sub 5/ for a melt-type ammonium phosphate plant. As explained in the text, there would be just about a tradeoff in energy required for drying in a conventional ammonium phosphate granulation plant (where wet-process acid also is produced) against the equivalent steam that would be needed to concentrate the feed acid from 40% P/sub 2/O/sub 5/ to 52 to 54% P/sub 2/O/sub 5/ for use in melt-type granulation. This would decrease the overall estimated savings for a melt-type ammonium phosphate granulation plant to about $3.65 per metric ton P/sub 2/O/sub 5/. In the case of NPK granulation plants using 52 to 54% P/sub 2/O/sub 5/ acid shipped in, the full indicated savings of about $5.10 per metric ton nutrient should be realized. Savings in existing and new plants are indicated.

  2. Sensitivity analysis of technological, economic and sustainability evaluation of power plants using the analytic hierarchy process

    International Nuclear Information System (INIS)

    Technological, economic and sustainability evaluation of power plants by use of the analytic hierarchy process and nine end node criteria for a reference scenario based on subjective criteria weighting has been presented in a previous paper by authors. However, criteria weight variations may substantially modify overall evaluations and rankings of power plants. The current paper presents a sensitivity analysis with four alternative scenarios (sets of criteria weights) compared with the reference scenario. The results show that priority to 'technology and sustainability' favors renewable energy power plants, while priority to 'economic' criteria favors mainly nuclear power plants and less the four types of fossil fuel power plant

  3. Sensitivity analysis of technological, economic and sustainability evaluation of power plants using the analytic hierarchy process

    International Nuclear Information System (INIS)

    Technological, economic and sustainability evaluation of power plants by use of the analytic hierarchy process and nine end node criteria for a reference scenario based on subjective criteria weighting has been presented in a previous paper by authors. However, criteria weight variations may substantially modify overall evaluations and rankings of power plants. The current paper presents a sensitivity analysis with four alternative scenarios (sets of criteria weights) compared with the reference scenario. The results show that priority to 'technology and sustainability' favors renewable energy power plants, while priority to 'economic' criteria favors mainly nuclear power plants and less the four types of fossil fuel power plant. (author)

  4. Microwave Processing of Simulated Advanced Nuclear Fuel Pellets

    International Nuclear Information System (INIS)

    Throughout the three-year project funded by the Department of Energy (DOE) and lead by Virginia Tech (VT), project tasks were modified by consensus to fit the changing needs of the DOE with respect to developing new inert matrix fuel processing techniques. The focus throughout the project was on the use of microwave energy to sinter fully stabilized zirconia pellets using microwave energy and to evaluate the effectiveness of techniques that were developed. Additionally, the research team was to propose fundamental concepts as to processing radioactive fuels based on the effectiveness of the microwave process in sintering the simulated matrix material.

  5. Microwave Processing of Simulated Advanced Nuclear Fuel Pellets

    Energy Technology Data Exchange (ETDEWEB)

    D.E. Clark; D.C. Folz

    2010-08-29

    Throughout the three-year project funded by the Department of Energy (DOE) and lead by Virginia Tech (VT), project tasks were modified by consensus to fit the changing needs of the DOE with respect to developing new inert matrix fuel processing techniques. The focus throughout the project was on the use of microwave energy to sinter fully stabilized zirconia pellets using microwave energy and to evaluate the effectiveness of techniques that were developed. Additionally, the research team was to propose fundamental concepts as to processing radioactive fuels based on the effectiveness of the microwave process in sintering the simulated matrix material.

  6. Potential safety-related incidents with possible applicability to a nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    The occurrence of certain potential events in nuclear fuel reprocessing plants could lead to significant consequences involving risk to operating personnel or to the general public. This document is a compilation of such potential initiating events in nuclear fuel reprocessing plants. Possible general incidents and incidents specific to key operations in fuel reprocessing are considered, including possible causes, consequences, and safety features designed to prevent, detect, or mitigate such incidents

  7. Potential safety-related incidents with possible applicability to a nuclear fuel reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Perkins, W.C.; Durant, W.S.; Dexter, A.H.

    1980-12-01

    The occurrence of certain potential events in nuclear fuel reprocessing plants could lead to significant consequences involving risk to operating personnel or to the general public. This document is a compilation of such potential initiating events in nuclear fuel reprocessing plants. Possible general incidents and incidents specific to key operations in fuel reprocessing are considered, including possible causes, consequences, and safety features designed to prevent, detect, or mitigate such incidents.

  8. Industrial Fuel Gas Demonstration Plant Program: environmental permit compliance plan

    Energy Technology Data Exchange (ETDEWEB)

    Bodamer, Jr., James W.; Bocchino, Robert M.

    1979-11-01

    This Environmental Permit Compliance Plan is intended to assist the Memphis Light, Gas and Water Division in acquiring the necessary environmental permits for their proposed Industrial Fuel Gas Demonstration Plant in a time frame consistent with the construction schedule. Permits included are those required for installation and/or operation of gaseous, liquid and solid waste sources and disposal areas. Only those permits presently established by final regulations are described. The compliance plan describes procedures for obtaining each permit from identified federal, state and local agencies. The information needed for the permit application is presented, and the stepwise procedure to follow when filing the permit application is described. Information given in this plan was obtained by reviewing applicable laws and regulations and from telephone conversations with agency personnel on the federal, state and local levels. This Plan also presents a recommended schedule for beginning the work necessary to obtain the required environmental permits in order to begin dredging operations in October, 1980 and construction of the plant in September, 1981. Activity for several key permits should begin as soon as possible.

  9. Fluidized-bed gasification under pressure of fuel element graphite in an industrial-scale reprocessing plant for HTR fuel elements

    International Nuclear Information System (INIS)

    In the head end of nuclear fuel reprocessing, the graphite cladding of spent HTR fuel elements is separated from the fissible material. Fluidized-bed combustion has some advantages over fixed-bed combustion. It is the method of choice in the design of a large-scale plant of 50.000 MWe HTR power. By means of an excess pressure of about 5 bar, a threefold increase in efficiency of a fluidized-bed ractor can be achieved. For an optimum layout of a prototype combustion plant, jacket cooling and internal heat exchangers are required. For an assessment of fluidized-bed combustion under pressure as a process step in the head end of a reprocessing plant, the author presents heat transfer calculations on the basis of a varying specific combustion load and investigations of the necessary peripheral equipment (reactor vessel, dust removal systems, gas supply and distribution, etc.) in several model set-ups. (RB)

  10. Method to process irradiated nuclear fuel

    International Nuclear Information System (INIS)

    The process is based on the Purex process and does not require chemical reducing agents, which decreases the waste volume. The saturation of the solvent with uranium is maintained at over 90% throughout the entire washing section of the reflux column. The nitric acid is simultaneously removed in the first stages of the washing section, so that the uranium accumulates on the tributyl phosphate decomposition products. Hence a higher decontamination factor can be achieved. (DG)

  11. Workshop on instrumentation and analyses for a nuclear fuel reprocessing hot pilot plant

    International Nuclear Information System (INIS)

    In order to assist in the study of instrumentation and analytical needs for reprocessing plants, a workshop addressing these needs was held at Oak Ridge National Laboratory from May 5 to 7, 1980. The purpose of the workshop was to incorporate the knowledge of chemistry and of advanced measurement techniques held by the nuclear and radiochemical community into ideas for improved and new plant designs for both process control and inventory and safeguards measurements. The workshop was athended by experts in nuclear and radiochemistry, in fuel recycle plant design, and in instrumentation and analysis. ORNL was a particularly appropriate place to hold the workshop since the Consolidated Fuel Reprocessing Program (CFRP) is centered there. Requirements for safeguarding the special nuclear materials involved in reprocessing, and for their timely measurement within the process, within the reprocessing facility, and at the facility boundaries are being studied. Because these requirements are becoming more numerous and stringent, attention is also being paid to the analytical requirements for these special nuclear materials and to methods for measuring the physical parameters of the systems containing them. In order to provide a focus for the consideration of the workshop participants, the Hot Experimental Facility (HEF) being designed conceptually by the CFRP was used as a basis for consideration and discussions

  12. Parallel processing of neutron transport in fuel assembly calculation

    International Nuclear Information System (INIS)

    Group constants, which are used for reactor analyses by nodal method, are generated by fuel assembly calculations based on the neutron transport theory, since one or a quarter of the fuel assembly corresponds to a unit mesh in the current nodal calculation. The group constant calculation for a fuel assembly is performed through spectrum calculations, a two-dimensional fuel assembly calculation, and depletion calculations. The purpose of this study is to develop a parallel algorithm to be used in a parallel processor for the fuel assembly calculation and the depletion calculations of the group constant generation. A serial program, which solves the neutron integral transport equation using the transmission probability method and the linear depletion equation, was prepared and verified by a benchmark calculation. Small changes from the serial program was enough to parallelize the depletion calculation which has inherent parallel characteristics. In the fuel assembly calculation, however, efficient parallelization is not simple and easy because of the many coupling parameters in the calculation and data communications among CPU's. In this study, the group distribution method is introduced for the parallel processing of the fuel assembly calculation to minimize the data communications. The parallel processing was performed on Quadputer with 4 CPU's operating in NURAD Lab. at KAIST. Efficiencies of 54.3 % and 78.0 % were obtained in the fuel assembly calculation and depletion calculation, respectively, which lead to the overall speedup of about 2.5. As a result, it is concluded that the computing time consumed for the group constant generation can be easily reduced by parallel processing on the parallel computer with small size CPU's

  13. DEVELOPMENT OF METHODS IMPROVING INDUSTRIAL SAFETY OF TECHNOLOGICAL PROCESSES IN ASPHALT-CONCRETE PLANT MIXERS

    Directory of Open Access Journals (Sweden)

    I. A. Ivanova

    2010-05-01

    Full Text Available Problem statement. The problem of improvement of industrial safety of technol-ogical processes in mixers of asphalt-concrete plants is considered on the basis of analysis of organic impurities content in incomplete combustion products, and es-timation of efficiency of purification of asphalt-concrete plant emissions in the presence of “wet” flue gas purification system is given.Results and conclusions. It has been found that the efficiency of hydrocarbon fuel burning affects the amount of hydrophobic dust thrown into the atmosphere, and burning of heavy fuel oil is attended by significant incompleteness of fuel combustion, and this is connected with the processes of fuel dispersion and evapo-ration. The optimal measures for efficient combustion and cleaning of hydrophob-ic dust are described.

  14. Pinellas Plant facts. [Products, processes, laboratory facilities

    Energy Technology Data Exchange (ETDEWEB)

    1986-09-01

    This plant was built in 1956 in response to a need for the manufacture of neutron generators, a principal component in nuclear weapons. The neutron generators consist of a miniaturized linear ion accelerator assembled with the pulsed electrical power supplies required for its operation. The ion accelerator, or neutron tube, requires ultra clean, high vacuum technology: hermetic seals between glass, ceramic, glass-ceramic, and metal materials: plus high voltage generation and measurement technology. The existence of these capabilities at the Pinellas Plant has led directly to the assignment of the lightning arrester connector, specialty capacitor, vacuum switch, and crystal resonator. Active and reserve batteries and the radioisotopically-powered thermoelectric generator draw on the materials measurement and controls technologies which are required to ensure neutron generator life. A product development and production capability in alumina ceramics, cermet (electrical) feedthroughs, and glass ceramics has become a specialty of the plant; the laboratories monitor the materials and processes used by the plant's commercial suppliers of ferroelectric ceramics. In addition to the manufacturing facility, a production development capability is maintained at the Pinellas Plant.

  15. Environmental analysis of a Concentrated Solar Power (CSP) plant hybridised with different fossil and renewable fuels

    OpenAIRE

    Corona Bellostas, Blanca; San Miguel Alfaro, Guillermo

    2014-01-01

    The environmental performance of a 50 MW parabolic trough Concentrated Solar Power (CSP) plant hybridised with different fuels was determined using a Life Cycle Assessment methodology. Six different scenarios were investigated, half of which involved hybridisation with fossil fuels (natural gas, coal and fuel oil), and the other three involved hybridisation with renewable fuels (wheat straw, wood pellets and biogas). Each scenario was compared to a solar-only operation. Nine different environ...

  16. Preliminary concepts: coordinated safeguards for materials management in a thorium--uranium fuel reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Hakkila, E.A.; Barnes, J.W.; Dayem, H.A.; Dietz, R.J.; Shipley, J.P.

    1978-10-01

    This report addresses preliminary concepts for coordinated safeguards materials management in a typical generic thorium--uranium-fueled light-water reactor (LWR) fuels reprocessing plant. The reference facility is designed to recover thorium and uranium from first-generation (denatured /sup 235/U) startup fuels, first-recycle and equilibrium (denatured /sup 233/U) thorium--uranium LWR fuels, and to recover the plutonium generated in the /sup 238/U denaturant as well. 12 figures, 3 tables.

  17. Solid recovered fuel: materials flow analysis and fuel property development during the mechanical processing of biodried waste.

    Science.gov (United States)

    Velis, Costas A; Wagland, Stuart; Longhurst, Phil; Robson, Bryce; Sinfield, Keith; Wise, Stephen; Pollard, Simon

    2013-03-19

    Material flows and their contributions to fuel properties are balanced for the mechanical section of a mechanical-biological treatment (MBT) plant producing solid recovered fuel (SRF) for the UK market. Insights for this and similar plants were secured through a program of sampling, manual sorting, statistics, analytical property determination, and material flow analysis (MFA) with error propagation and data reconciliation. Approximately three-quarters of the net calorific value (Q(net,p,ar)) present in the combustible fraction of the biodried flow is incorporated into the SRF (73.2 ± 8.6%), with the important contributors being plastic film (30.7 MJ kg(ar)(-1)), other packaging plastic (26.1 MJ kg(ar)(-1)), and paper/card (13.0 MJ kg(ar)(-1)). Nearly 80% w/w of the chlorine load in the biodried flow is incorporated into SRF (78.9 ± 26.2%), determined by the operation of the trommel and air classifier. Through the use of a novel mass balancing procedure, SRF quality is understood, thus improving on the understanding of quality assurance in SRF. Quantification of flows, transfer coefficients, and fuel properties allows recommendations to be made for process optimization and the production of a reliable and therefore marketable SRF product. PMID:23398118

  18. Study on process basic requirements of experimental facility of advanced spent fuel management process

    International Nuclear Information System (INIS)

    The advanced spent fuel management process, which was proposed to reduce the overall volume of the PWR spent fuel and improve safety and economy of the long-term storage of spent fuel, is under research and development. Hot cell facilities of α-γ type and inert atmosphere are required essentially for safe hot test and verification of this process. In this study, design basic data are established, and these data include process flow, process condition and yields, mass and radioactivity balance of radionuclides, process safety considerations, etc. And also, these data will be utilized for basic and detail design of hot cell facility, secured conservative safety and effective operability

  19. Technological, economic and sustainability evaluation of power plants using the Analytic Hierarchy Process

    International Nuclear Information System (INIS)

    Complexity of power plant evaluation is steadily rising, as more criteria are involved in the overall assessment while evaluation data change rapidly. Apart from evaluating several aspects of power plants separately, a multicriteria analysis based on hierarchically structured criteria is necessary, so as to address the overall assessment of power plants according to the technological, economic and sustainability aspects. For this reason, in this paper, ten types of power plant are evaluated using nine end node criteria properly structured under the Analytical Hierarchy Process. Moreover, pairwise comparisons allow for accurate subjective criteria weighting. According to the scenario based on the subjective criteria weighting, emphasis is laid on sustainability driving renewable energy power plants at the top of the overall ranking, while nuclear and fossil fuel power plants rank in the last five positions. End node criteria contribution to each power plant and power plant performance per end node criterion is presented for all types of power plant and end node criteria

  20. Technological, economic and sustainability evaluation of power plants using the analytic hierarchy process

    International Nuclear Information System (INIS)

    Complexity of power plant evaluation is steadily rising, as more criteria are involved in the overall assessment while evaluation data change rapidly. Apart from evaluating several aspects of power plants separately, a multicriteria analysis based on hierarchically structured criteria is necessary, so as to address the overall assessment of power plants according to the technological, economic and sustainability aspects. For this reason, in this paper, ten types of power plant are evaluated using nine end node criteria properly structured under the Analytical Hierarchy Process. Moreover, pairwise comparisons allow for accurate subjective criteria weighting. According to the scenario based on the subjective criteria weighting, emphasis is laid on sustainability driving renewable energy power plants at the top of the overall ranking, while nuclear and fossil fuel power plants rank in the last five positions. End node criteria contribution to each power plant and power plant performance per end node criterion is presented for all types of power plant and end node criteria. (author)

  1. Plant-scale anodic dissolution of unirradiated IFR fuel pins

    International Nuclear Information System (INIS)

    This report discusses anodic dissolution which is a major operation in the pyrometallurgical process for recycling spent metal fuels from the Integral Fast Reactor (IFR), an advanced reactor design developed at Argonne National Laboratory. This process involves electrorefining the heavy metals (uranium and plutonium) from chopped, steel-clad fuel segments. The heavy metals are electrotransported from anodic dissolution baskets to solid and liquid cathodes in a molten salt electrolyte (LiCl-KCI) at 500 degrees C. Uranium is recovered on a solid cathode mandrel, while a uranium-plutonium mixture is recovered in a liquid cadmium cathode. The anode configuration consists of four baskets mounted on an anode shaft. These baskets provide parallel circuits in the electrolyte and salt flow through the chopped fuelbed as the baskets are rotated. The baskets for the engineering-scale tests were sized to contain up to 2.5 kg of heavy metal. Anodic dissolution of 10 kg batches of chopped, steel-clad simulated tuel (U-10% Zr and U-Zr-Fs alloy) was demonstrated

  2. Analyzing the possibility of constructing the air heating system for an integrated solid fuel gasification combined-cycle power plant

    Science.gov (United States)

    Mikula, V. A.; Ryzhkov, A. F.; Val'tsev, N. V.

    2015-11-01

    Combined-cycle power plants operating on solid fuel have presently been implemented only in demonstration projects. One of possible ways for improving such plants consists in making a shift to hybrid process circuits of integrated gasification combined-cycle plants with external firing of solid fuel. A high-temperature air heater serving to heat compressed air is a key element of the hybrid process circuit. The article describes application of a high-temperature recuperative metal air heater in the process circuit of an integrated gasification combined-cycle power plant (IGCC). The available experience with high-temperature air heating is considered, and possible air heater layout arrangements are analyzed along with domestically produced heat-resistant grades of steel suitable for manufacturing such air heater. An alternative (with respect to the traditional one) design is proposed, according to which solid fuel is fired in a noncooled furnace extension, followed by mixing the combustion products with recirculation gases, after which the mixture is fed to a convective air heater. The use of this design makes it possible to achieve considerably smaller capital outlays and operating costs. The data obtained from thermal and aerodynamic calculations of the high-temperature air heater with a thermal capacity of 258 MW for heating air to a temperature of up to 800°C for being used in the hybrid process circuit of a combined-cycle power plant are presented.

  3. Alarm-Processing in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Information overload due to the activation of a great number of alarms in a short time is a common problem for the operator in the control room of a industrial plant, mainly in complex process like the nuclear power plants.The problem is the conventional conception of the alarm system, that defines each alarm like a separated and independent entity of the global situation of the plant.A direct consequence is the generation of multiple alarms during a significative disturbance in the process, being most of them redundant and irrelevant to the actual process state wich involves an extra load to the operator, who wastes time in acting selecting the important alarms of the group that appears or lead to a an erroneous action.The present work first describes the techniques developed in the last years to attack the avalanche of alarms problem.Later we present our approach to alarm-processing: an expert system as alarm-filter.Our objective is collect in the system the state of the art in the development of advanced alarm systems, offering an improvement of the information flow to the operators through the suppression of nonsignificant alarms and a structured visualization of the process state.Such support is important during a disturbance for the identification of plant state, diagnosis, consequence prediction and corrective actions.The system is arranged in three stages: alarm-generation, alarm-filter and alarm-presentation.The alarm-generation uses conventional techniques or receives them from an external system.The alarm-filter uses suppression techniques based on: irrelevance analysis with the operation mode and the state of components, causal reasoning and static importance analysis.The alarm presentation is made through a structured way using a priority scheme with three level.The knowledge representation of each alarm is based on frames and a graph of alarms for global knowledge, where the connections between nodes represent causal and irrelevance relations

  4. Management of external dose and contamination risk at the Belgonucleaire MOX fuel plant in Dessel

    International Nuclear Information System (INIS)

    In its facilities located at Dessel, Belgonucleaire is producing MOX fuel for light water reactors, yielding an average amount of 35 tonnes per year. The specific problems of safety and security that are related to plutonium processing imply a particular attention to the management of external dose and contamination risk in the plant. Substantial efforts for reducing doses has been and are taken, with a particular focus on collective protection means: operation control at distance from the production line, systematic shielding for working places, personnel awareness, etc. Causes of contamination are outlined (especially glove's piercing)

  5. Industrial Fuel Gas Demonstration Plant Program. Volume III. Demonstration plant environmental analysis (Deliverable No. 27)

    Energy Technology Data Exchange (ETDEWEB)

    1979-08-01

    An Environmental Report on the Memphis Light, Gas and Water Division Industrial Fuel Demonstration Plant was prepared for submission to the US Department of Energy under Contract ET-77-C-01-2582. This document is Volume III of a three-volume Environmental Report. Volume I consists of the Summary, Introduction and the Description of the Proposed Action. Volume II consists of the Description of the Existing Environment. Volume III contains the Environmental Impacts of the Proposed Action, Mitigating Measures and Alternatives to the Proposed Action.

  6. Processing of Non-PFP Plutonium Oxide in Hanford Plants

    International Nuclear Information System (INIS)

    Processing of non-irradiated plutonium oxide, PuO2, at the Hanford Site has been done at the Plutonium Finishing Plant (PFP) and in recycle of PuO2-bearing fuels through Hanford reprocessing plants. Plutonium oxide is notoriously refractory and difficult to dissolve. As such, losses of PuO2 residues from the PFP or from Hanford reprocessing plants can report to Hanford Site underground tank waste storage. Those stored wastes are destined to become feed to the Waste Treatment Plant, WTP. Information on the processing of non-PFP plutonium oxide in Hanford plants is provided in this brief report. To help gain perspective, information on PFP processing and plutonium additions to the tank farm system from other Hanford processing is also presented. Processing of non-irradiated plutonium oxide, PuO2, scrap for recovery of plutonium values occurred routinely at Hanford's Plutonium Finishing Plant (PFP) in glovebox line operations. Plutonium oxide is difficult to dissolve, particularly if it has been high-fired; i.e., calcined to temperatures above about 400 C and much of it was. Dissolution of the PuO2 in the scrap typically was performed in PFP's Miscellaneous Treatment line using nitric acid (HNO3) containing some source of fluoride ion, F-, such as hydrofluoric acid (HF), sodium fluoride (NaF), or calcium fluoride (CaF2). The HNO3 concentration generally was 6 M or higher whereas the fluoride concentration was ∼0.5 M or lower. At higher fluoride concentrations, plutonium fluoride (PuF4) would precipitate, thus limiting the plutonium dissolution. Some plutonium-bearing scrap also contained PuF4 and thus required no added fluoride. Once the plutonium scrap was dissolved, the excess fluoride was complexed with aluminum ion, Al3+, added as aluminum nitrate, Al(NO3)3·9H2O, to limit collateral damage to the process equipment by the corrosive fluoride. Aluminum nitrate also was added in low quantities in processing PuF4. The PuO2 dissolution was not perfect, however, and

  7. Digital mock-up for the spent fuel disassembly processes

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J. Y.; Kim, S. H.; Song, T. G.; Kim, Y. H.; Hong, D. H.; Yoon, J. S

    2000-12-01

    In this study, the graphical design system is developed and the digital mock-up is implemented for designing the spent fuel handling and disassembly processes. The system consists of a 3D graphical modeling system, a devices assembling system, and a motion simulation system. This system is used throughout the design stages from the conceptual design to the motion analysis. By using this system, all the process involved in the spent fuel handling and disassembly processes are analyzed and optimized. Also, this system is used in developing the on-line graphic simulator which synchronously simulates the motion of the equipment in a real time basis by connecting the device controllers with the graphic server through the TCP/IP network. This simulator can be effectively used for detecting the malfunctions of the process equipment which is remotely operated. Thus, the simulator enhances the reliability and safety of the spent fuel handling process by providing the remote monitoring function of the process. The graphical design system and the digital mock-up system can be effectively used for designing the process equipment, as well as the optimized process and maintenance process. And the on-line graphic simulator can be an alternative of the conventional process monitoring system which is a hardware based system.

  8. Pyrolysis process for producing fuel gas

    Science.gov (United States)

    Serio, Michael A. (Inventor); Kroo, Erik (Inventor); Wojtowicz, Marek A. (Inventor); Suuberg, Eric M. (Inventor)

    2007-01-01

    Solid waste resource recovery in space is effected by pyrolysis processing, to produce light gases as the main products (CH.sub.4, H.sub.2, CO.sub.2, CO, H.sub.2O, NH.sub.3) and a reactive carbon-rich char as the main byproduct. Significant amounts of liquid products are formed under less severe pyrolysis conditions, and are cracked almost completely to gases as the temperature is raised. A primary pyrolysis model for the composite mixture is based on an existing model for whole biomass materials, and an artificial neural network models the changes in gas composition with the severity of pyrolysis conditions.

  9. Proceedings of the workshop on hydrocarbon processing mixing and scale-up problems. [Fuels processing for fuel cells

    Energy Technology Data Exchange (ETDEWEB)

    Gabor, J. D. [ed.

    1978-01-01

    A workshop was convened by the Division of Fossil Fuel Utilization of the US Department of Energy in cooperation with the Particulate and Multiphase Process Program of the National Science Foundation to identify needs for fundamental engineering support for the design of chemical reactors for processing heavy hydrocarbon liquids. The problems associated with dispersing liquid hydrocarbons in a reacting gas and mixing within the gas phase are of primary concern. The transactions of the workshop begin with an introduction to the immediate goals of the Department of Energy. Fuel cell systems and current research and development are reviewed. Modeling of combustion and the problems of soot formation and deposits in hydrocarbon fuels are next considered. The fluid mechanics of turbulent mixing and its effect on chemical reactions are then presented. Current experimental work and process development provide an update on the present state-of-the-art.

  10. Construction and start-up of a 250 kW natural gas fueled MCFC demonstration power plant

    Energy Technology Data Exchange (ETDEWEB)

    Figueroa, R.A.; Carter, J.; Rivera, R.; Otahal, J. [San Diego Gas & Electric, CA (United States)] [and others

    1996-12-31

    San Diego Gas & Electric (SDG&E) is participating with M-C Power in the development and commercialization program of their internally manifolded heat exchanger (IMHEX{reg_sign}) carbonate fuel cell technology. Development of the IMHEX technology base on the UNOCAL test facility resulted in the demonstration of a 250 kW thermally integrated power plant located at the Naval Air Station at Miramar, California. The members of the commercialization team lead by M-C Power (MCP) include Bechtel Corporation, Stewart & Stevenson Services, Inc., and Ishikawajima-Harima Heavy Industries (IHI). MCP produced the fuel cell stack, Bechtel was responsible for the process engineering including the control system, Stewart & Stevenson was responsible for packaging the process equipment in a skid (pumps, desulfurizer, gas heater, turbo, heat exchanger and stem generator), IHI produced a compact flat plate catalytic reformer operating on natural gas, and SDG&E assumed responsibility for plant construction, start-up and operation of the plant.

  11. DUPIC nuclear fuel manufacturing and process technology development at KAERI

    International Nuclear Information System (INIS)

    DUPIC fuel cycle development project in KAERI of Korea was initiated in 1991 and has advanced in relevant technologies for last 10 years. The project includes five different topics such as nuclear fuel manufacturing, compatibility evaluation, performance evaluation, manufacturing facility management, and safeguards. The contents and results of DUPIC R and D up to now are as follow: - the basic foundation was established for the critically required pelletizing technology and powder treatment technology for DUPIC. - development of DUPIC process line and deployment of 20 each process equipment and examination instruments in DFDF. - powder and pellet characterization study was done at PIEF based on the simfuel study results, and 30 DUPIC pellets were successfully produced. - the manufactured pellets were used for sample fuel rods irradiated in July,2000 in HANARO research reactor in KAERI and has been under post irradiation examination. (Hong, J. S.)

  12. St. Louis demonstration final report: refuse processing plant equipment, facilities, and environmental evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Fiscus, D.E.; Gorman, P.G.; Schrag, M.P.; Shannon, L.J.

    1977-09-01

    The results are presented of processing plant evaluations of the St. Louis-Union Electric Refuse Fuel Project, including equipment and facilities as well as assessment of environmental emissions at both the processing and the power plants. Data on plant material flows and operating parameters, plant operating costs, characteristics of plant material flows, and emissions from various processing operations were obtained during a testing program encompassing 53 calendar weeks. Refuse derived fuel (RDF) is the major product (80.6% by weight) of the refuse processing plant, the other being ferrous metal scrap, a marketable by-product. Average operating costs for the entire evaluation period were $8.26/Mg ($7.49/ton). The average overall processing rate for the period was 168 Mg/8-h day (185.5 tons/8-h day) at 31.0 Mg/h (34.2 tons/h). Future plants using an air classification system of the type used at the St. Louis demonstration plant will need an emissions control device for particulates from the large de-entrainment cyclone. Also in the air exhaust from the cyclone were total counts of bacteria and viruses several times higher than those of suburban ambient air. No water effluent or noise exposure problems were encountered, although landfill leachate mixed with ground water could result in contamination, given low dilution rates.

  13. Plant and microorganisms support media for electricity generation in biological fuel cells with living hydrophytes.

    Science.gov (United States)

    Salinas-Juárez, María Guadalupe; Roquero, Pedro; Durán-Domínguez-de-Bazúa, María Del Carmen

    2016-12-01

    Plant support media may impact power output in a biological fuel cell with living plants, due to the physical and biochemical processes that take place in it. A material for support medium should provide the suitable conditions for the robust microbial growth and its metabolic activity, degrading organic matter and other substances; and, transferring electrons to the anode. To consider the implementation of this type of bio-electrochemical systems in constructed wetlands, this study analyzes the electrochemical behavior of biological fuel cells with the vegetal species Phragmites australis, by using two different support media: graphite granules and a volcanic slag, commonly known as tezontle (stone as light as hair, from the Aztec or Nahuatl language). Derived from the results, both, graphite and tezontle have the potential to be used as support medium for plants and microorganisms supporting a maximum power of 26.78mW/m(2) in graphite reactors. These reactors worked under mixed control: with ohmic and kinetic resistances of the same order of magnitude. Tezontle reactors operated under kinetic control with a high activation resistance supplying 9.73mW/m(2). These performances could be improved with stronger bacterial populations in the reactor, to ensure the rapid depletion of substrate.

  14. Design concepts and process analysis for transmuter fuel manufacturing

    International Nuclear Information System (INIS)

    The large-scale deployment of remote fabrication and re-fabrication processes (approx. 100 tons of Minor Actinides (MA) annually) will be required for all transmutation scenarios. Process automation has the potential to decrease the cost of remote fuel fabrication and to make transmutation a more economically viable process. The paper describes the design of hot cell fuel manufacturing processes using robotic equipment in hot cells. The dynamics of the robots and the objects handled by them are analyzed in detail using state of the art software tools. In addition to the evaluation and testing of normal assembly operations, the 3D simulation provides for a comprehensive analysis of normal work flows and atypical events such as collisions. The results permit a detailed analysis of the robotic assembly process in terms of forces, torques, and accidents. Detailed simulation results for several operations are presented. (author)

  15. One year of operation of the Belgonucleaire (Dessel) plutonium fuel fabrication plant

    International Nuclear Information System (INIS)

    Based on experience with plutonium since 1958, Belgonucleaire has successively launched a pilot plant and then a fuel fabrication plant for mixed uranium and plutonium oxides in 1968 and 1973 respectively. After describing briefly the plants and the most important stages in the planning, construction and operation of the Dessel plant, the present document describes the principal problems which were met during the course of operation of the plant and their direct incidence on the capacity and quality of the production of fuel elements

  16. The logistics and the supply chain in the Juzbado Nuclear Fuel Manufacturing Plant

    International Nuclear Information System (INIS)

    The paper describe the logistics and the supply chain in the Juzbado Nuclear Fuel Manufacturing Plant, located in Juzbado in the province of Salamanca. In the the article are described the principal elements in the supply chain and the difficulties of its management derived from the short period for the manufacturing of the nuclear fuel. It's also given a view in relation to the transportation by land sea of the nuclear components, uranium oxide powder and the manufactured fuel. The characteristics of the supply chain are determined by the plant production forecast, by the origin and high technology of the raw materials and by nuclear fuel delivery site locations. (Author)

  17. Cost and quality of fuels for electric utility plants: Energy data report. 1980 annual

    Energy Technology Data Exchange (ETDEWEB)

    1981-06-25

    In 1980 US electric utilities reported purchasng 594 million tons of coal, 408.5 million barrels of oil and 3568.7 billion ft/sup 3/ of gas. As compared with 1979 purchases, coal rose 6.7%, oil decreased 20.9%, and gas increased for the fourth year in a row. This volume presents tabulated and graphic data on the cost and quality of fossil fuel receipts to US electric utilities plants with a combined capacity of 25 MW or greater. Information is included on fuel origin and destination, fuel types, and sulfur content, plant types, capacity, and flue gas desulfurization method used, and fuel costs. (LCL)

  18. Nuclear fuel procurement management at nuclear power plant

    International Nuclear Information System (INIS)

    The market situation of nuclear fuel cycles is highlighted. It also summarises the possible contract models and the elements of effective management for nuclear fuel procurement at nuclear power station based upon the nuclear fuel procurement practice of Guangdong Daya Bay Nuclear Power Station (GNPS)

  19. Emerging environmental issues for gas processing plants

    International Nuclear Information System (INIS)

    An overview of emerging environmental issues of interest to the construction and ongoing management of gas processing plants was provided. Recent responses by the Alberta Energy and Utilities Board (AEUB) to certain environmental concerns, initiatives of Alberta Environmental Protection (AEP), and evolving developments by the federal government with respect to air quality issues are emphasized. AEUB''s specific responsibilities for air quality, incinerator stack emissions, flaring, fugitive emissions, sulphur recovery, soil and groundwater contamination, noise and emergency response support for upstream petroleum industry incidents and associated hazards are reviewed. A case study of Shell Oil''s Caroline application for increased throughput at its Caroline sour gas plant was discussed to illustrate the AEUB''s application of its on environmental protection mandate

  20. Infrared imaging of fossil fuel power plant boiler interiors

    Science.gov (United States)

    Howard, James W.; Cranton, Brian W.; Armstrong, Karen L.; Hammaker, Robert G.

    1997-08-01

    Fossil fuel power plant boilers operate continuously for months at a time, typically shutting down only for routine maintenance or to address serious equipment failures. These shutdowns are very costly, and diagnostic tools and techniques which could be used to minimize shutdown duration and frequency are highly desirable. Due to the extremely hostile environment in these boilers, few tools exist to inspect and monitor operating boiler interiors. This paper presents the design of a passively cooled, infrared borescope used to inspect the interior of operating boilers. The borescope operates at 3.9 micrometer, where flame is partially transparent. The primary obstacles overcome in the instrument design were the harsh industrial environment surrounding the boilers and the high temperatures encountered inside the boilers. A portable yet durable lens system and enclosure was developed to work with a scanning radiometer to address these two problems by both shielding the radiometer from the environment and by extending the optical train into a snout designed to be inserted into access ports on the sides of the boiler. In this manner, interior images of the boiler can be made while keeping the radiometer safely outside the boiler. The lens views a 40 degree field of view through any 2.5' or larger opening in a foot thick boiler wall. Three of these borescopes have been built, and high resolution images of boiler interiors have been obtained.

  1. The European experience in safeguarding nuclear fuel recycle processes and Pu stores

    International Nuclear Information System (INIS)

    Civil nuclear programs in the European Union member states have from their onset included fuel recycling as an option. The EURATOM Treaty gives to the European Commission the obligation to apply safeguards controls to all civil Nuclear Material in the European Union, and to facilitate the implementation of IAEA safeguards. The European Commission (EURATOM) has thus gained years of experience in safeguarding reprocessing plants, Pu storages, and MOX fuel fabrication plants and is currently participating in the development of approaches and measures for safeguarding long term repositories. The aim of this paper is to present the regulator's views and experience on safeguarding nuclear fuel recycle processes and Pu stores, which is based on the following principles: -) Early involvement of the control organizations in the design of the safeguards measures to be developed for a plant (currently referred to as Safeguards by Design); -) Early definition of a safeguards strategy including key measurement points; -) The design and development of plant specific Safeguards equipment, including an on site laboratory for sample analysis; -) The development by the operator of an appropriate Nuclear Material accountancy system to facilitate their declaration obligations; -) The introduction of an inspection regime allowing comprehensive controls under the restrictions imposed by financial and Human Resources limitations; -) Optimization of the inspection effort by using unattended measuring stations, containment and surveillance systems and secure remote transmission of data to the regulator's headquarters. The paper is followed by the slides of the presentation. (authors)

  2. Combustion of liquid fuel in the counter-swirled jets of a gas turbine plant annular combustion chamber

    Science.gov (United States)

    Tumanovskii, A. G.; Semichastnyi, N. N.; Sokolov, K. Iu.

    1986-03-01

    Tests were carried out on an annular combustion chamber rig with a stabilizer of the type used in the GTN-25 gas turbine plant to determine the feasibility of burning a liquid fuel (diesel fuel, GOST 4749-73) in a combustion chamber of this type. Very high performance was obtained for a number of important characteristics of the microflame combustion process in counterswirled jets where all the air was supplied through the front unit of the chamber. However, the tests did not make it possible to solve some of the problems which arise when operating under full-scale conditions, such as the required high combustion efficiency under variable operating conditions of a gas turbine plant; elimination of soot formation at the walls of the stabilizer and the internal surfaces of the pipes supplying fuel to the atomizers; and a decrease in smoking under conditions of excess air factor.

  3. Modelling of the application of near real time accountancy and process monitoring to plants

    International Nuclear Information System (INIS)

    Many statistical tests have been proposed for the analysis of accountancy data from nuclear fuel reprocessing plants. The purpose of this programme was to assess the performance of these tests by applying them to data streams which simulate the information that would be available from a real plant. In addition the problems of pre-processing the raw data from a plant were considered. A suite of programs to analyse the data has been written, which include colour graphical output to allow effective interpretation of the results. The commercial software package VisiCalc has been evaluated and found to be effective for the rapid production of material balances from plant data. (author)

  4. The French commercial plant for reprocessing and vitrification of spent reactor fuel

    International Nuclear Information System (INIS)

    The basic principles of the system for the reprocess ing of spent reactor fuel on a commercial basis at the plant at Marcoule in France are described. After four months cooling the canning is stripped mechanically and the fuel dissolved in boiling nitric acid. Using T B P the uranium and plutonium are separated from the fission products. The plutonium is then separated by valency change and aqueous extraction. The uranium is transferred to a refinery and stored as hexahydrate. The plutonium is concentrated and precipitated as oxalate, dried and converted via oxide to fluoride, thence to metal. The fission products are concentrated and converted to glass form in a process dependent on the reactor type, the burnup and their chemical processing. The two processes developed, the'pot' process and the continuous process, are described in some detail. The final disposal of the radioactive wastes is not yet decided, and temporary storage facilities have therefore been built, with a capacity for 30 years of reprocessing. (JIW)

  5. New nuclear plant design and licensing process

    International Nuclear Information System (INIS)

    This paper describes latest developments in the nuclear power reactor technology with emphasis on three areas: (1) the US technology of advanced passive light water reactors (AP600 and S BWR), (2) regulatory processes that certify their safety, and (3) current engineering concerns. The goal is to provide and insight of how the government's regulatory agency guarantees public safety by looking into how new passive safety features were designed and tested by vendors and how they were re-evaluated and retested by the US NRC. The paper then discusses the US 1989 nuclear licensing reform (10 CFR Part 52) whose objectives are to promote the standardization of nuclear power plants and provide for the early and definitive resolution of site and design issues before plants are built. The new licensing process avoids the unpredictability nd escalated construction cost under the old licensing process. Finally, the paper summarizes engineering concerns found in current light water reactors that may not go away in the new design. The concerns are related the material and water chemistry technology in dealing with corrosion problems in water-cooled nuclear reactor systems (PWRs and BWRs). These engineering concerns include core shroud cracking (BWRs), jet pump hold-down beam cracking (BWRs), steam generator tube stress corrosion cracking (PWR)

  6. Automated remote control of fuel supply section for the coal fired power plant

    Energy Technology Data Exchange (ETDEWEB)

    Chudin, O.V.; Maidan, B.V.; Tsymbal, A.A. [JSC Khabarovskenergo, Khabarovsk (Russian Federation). Heat and Power Plant No. 3

    1996-05-01

    Approximately 6,000 miles east of Moscow, lays the city of Khabarovsk. This city`s coal-fired Power Plant 3 supplies electricity, heat and hot water to approximately 250,000 customers. Plant 3 has three units with a combined turbine capacity of 540 MW, (3 {times} 180) electrical and 780 (3 {times} 260) Gkal an hour thermal capacity with steam productivity of 2010 (3 {times} 670) tons per hour at 540 C. Coal fired thermal electric power plants rely on the equipment of the fuel supply section. The mechanism of the fuel supply section includes: conveyor belts, hammer crushers, guiding devices, dumping devices, systems for dust neutralizing, iron separators, metal detectors and other devices. As a rule, the fuel path in the power plant has three main directions: from the railroad car unloading terminal to the coal warehouse; from the coal warehouse to the acceptance bunkers of the power units, and the railroad car unloading terminal to the acceptance bunkers of power units. The fuel supply section always has a reserve and is capable of uninterruptible fuel supply during routine maintenance and/or repair work. This flexibility requires a large number of fuel traffic routes, some of which operate simultaneously with the feeding of coal from the warehouse to the acceptance bunkers of the power units, or in cases when rapid filling of the bunkers is needed, two fuel supply routes operate at the same time. The remote control of the fuel handling system at Power Plant 3 is described.

  7. System approach to the analysis of an integrated oxy-fuel combustion power plant

    Science.gov (United States)

    Ziębik, Andrzej; Gładysz, Paweł

    2014-09-01

    Oxy-fuel combustion (OFC) belongs to one of the three commonly known clean coal technologies for power generation sector and other industry sectors responsible for CO2 emissions (e.g., steel or cement production). The OFC capture technology is based on using high-purity oxygen in the combustion process instead of atmospheric air. Therefore flue gases have a high concentration of CO2. Due to the limited adiabatic temperature of combustion some part of CO2 must be recycled to the boiler in order to maintain a proper flame temperature. An integrated oxy-fuel combustion power plant constitutes a system consisting of the following technological modules: boiler, steam cycle, air separation unit, cooling water and water treatment system, flue gas quality control system and CO2 processing unit. Due to the interconnections between technological modules, energy, exergy and ecological analyses require a system approach. The paper present the system approach based on the `input-output' method to the analysis of the: direct energy and material consumption, cumulative energy and exergy consumption, system (local and cumulative) exergy losses, and thermoecological cost. Other measures like cumulative degree of perfection or index of sustainable development are also proposed. The paper presents a complex example of the system analysis (from direct energy consumption to thermoecological cost) of an advanced integrated OFC power plant.

  8. System approach to the analysis of an integrated oxy-fuel combustion power plant

    Directory of Open Access Journals (Sweden)

    Ziębik Andrzej

    2014-09-01

    Full Text Available Oxy-fuel combustion (OFC belongs to one of the three commonly known clean coal technologies for power generation sector and other industry sectors responsible for CO2 emissions (e.g., steel or cement production. The OFC capture technology is based on using high-purity oxygen in the combustion process instead of atmospheric air. Therefore flue gases have a high concentration of CO2. Due to the limited adiabatic temperature of combustion some part of CO2 must be recycled to the boiler in order to maintain a proper flame temperature. An integrated oxy-fuel combustion power plant constitutes a system consisting of the following technological modules: boiler, steam cycle, air separation unit, cooling water and water treatment system, flue gas quality control system and CO2 processing unit. Due to the interconnections between technological modules, energy, exergy and ecological analyses require a system approach. The paper present the system approach based on the ‘input-output’ method to the analysis of the: direct energy and material consumption, cumulative energy and exergy consumption, system (local and cumulative exergy losses, and thermoecological cost. Other measures like cumulative degree of perfection or index of sustainable development are also proposed. The paper presents a complex example of the system analysis (from direct energy consumption to thermoecological cost of an advanced integrated OFC power plant.

  9. AN EXAMPLE OF ALTERNATIVE FUEL USE IN PRODUCING CLINKER PRODUCTS: AKCANSA BUYUKCEKMECE CEMENT PLANT

    OpenAIRE

    Ömer ÖZKAN; Cemal YILMAZ; APAY, Ahmet Celal

    2011-01-01

    In 2001, Ministry of Environment and Forestry issued a notification about the general rules to be followed in using waste as fuel. After that date, within that period, cement plants started to buy waste incineration license. On the other hand, the use of waste as fuel in the EU began in the 1990s. The use of alternative fuels in the production of clinker, allows maximum level of energy supply and less use of fossil fuel. Another feature of these fuels is that their waste products mix in c...

  10. Core and fuel feasibility study for improved flexibility on the Belgian Nuclear Power Plants

    International Nuclear Information System (INIS)

    A feasibility study has been performed for extended power modulations on Belgian NPPs. The goal is to make the existing nuclear power units in Belgium more flexible without implementing hardware modifications and guaranteeing safety at all times. As the critical part of the feasibility study, the impacts on the core behaviour and fuel performance have been studied in detail. It is concluded that all existing fuels loaded in the Belgian plants allow up to 30 power modulations per fuel cycle without changing the currently applied fuel cycle management. This is also supported by the extensive experience feedback of the fuel products for flexible operations in European countries. (author)

  11. Fuzzy Logic Based Controller for a Grid-Connected Solid Oxide Fuel Cell Power Plant

    OpenAIRE

    Chatterjee, Kalyan; Shankar, Ravi; Kumar, Amit

    2014-01-01

    This paper describes a mathematical model of a solid oxide fuel cell (SOFC) power plant integrated in a multimachine power system. The utilization factor of a fuel stack maintains steady state by tuning the fuel valve in the fuel processor at a rate proportional to a current drawn from the fuel stack. A suitable fuzzy logic control is used for the overall system, its objective being controlling the current drawn by the power conditioning unit and meet a desirable output power demand. The prop...

  12. Solid recovered fuel: influence of waste stream composition and processing on chlorine content and fuel quality.

    Science.gov (United States)

    Velis, Costas; Wagland, Stuart; Longhurst, Phil; Robson, Bryce; Sinfield, Keith; Wise, Stephen; Pollard, Simon

    2012-02-01

    Solid recovered fuel (SRF) produced by mechanical-biological treatment (MBT) of municipal waste can replace fossil fuels, being a CO(2)-neutral, affordable, and alternative energy source. SRF application is limited by low confidence in quality. We present results for key SRF properties centered on the issue of chlorine content. A detailed investigation involved sampling, statistical analysis, reconstruction of composition, and modeling of SRF properties. The total chlorine median for a typical plant during summer operation was 0.69% w/w(d), with lower/upper 95% confidence intervals of 0.60% w/w(d) and 0.74% w/w(d) (class 3 of CEN Cl indicator). The average total chlorine can be simulated, using a reconciled SRF composition before shredding to plants; and a lower 95% confidence limit of net calorific value (NCV) at 14.5 MJ kg(ar)(-1). The data provide, for the first time, a high level of confidence on the effects of SRF composition on its chlorine content, illustrating interrelationships with other fuel properties. The findings presented here allow rational debate on achievable vs desirable MBT-derived SRF quality, informing the development of realistic SRF quality specifications, through modeling exercises, needed for effective thermal recovery. PMID:22191490

  13. Effect of fuel size and process temperature on fuel gas quality from CFB gasification of biomass

    Energy Technology Data Exchange (ETDEWEB)

    Van der Drift, A.; Van Doorn, J. [ECN Biomass, Petten (Netherlands)

    2000-07-01

    A bench-scale circulating fluidized bed (CFB) gasifier with a capacity of max. 500 kWh{sub th} has been used to study the effect of fuel size and process temperature. A higher process temperature (range tested: 750 to 910C) results in more air needed to maintain the desired temperature, a lower heating value of the product gas, a higher carbon conversion and a net increase of cold gas efficiency of the gasifier. A higher process temperature also results in less heavy tars. However, light tars (measured using the solid phase adsorbent (SPA) method) do show an odd behaviour. Some individual components within the group of light tars even increase in concentration when process temperature is raised. The main reason probably is that heavy tars decompose to these relatively stable light tar components. The particle size of the fuel does influence some product gas parameters considerably. The presence of small particles seems to increase the (heavy) tar concentration and decrease the conversion of fuel-nitrogen to ammonia. Small particles can also be responsible for large temperature gradients along the axis of the riser of a CFB-gasifier. This effect can be avoided by either mixing the fuel with larger particles or feed the small particles at the bottom of the reactor. 5 refs.

  14. Development and testing of a near-real-time accounting system for the Barnwell Reprocessing Facility

    International Nuclear Information System (INIS)

    Allied-General Nuclear Services has developed and demonstrated under cold testing conditions a computerized nuclear materials control and accounting system for a large reprocessing plant. The system provides computerized data acquisition, calculation, and retention for conventional accounting measurements as well as for near-real-time estimation of in-process inventories and material balances. Application of this system as a tool for meeting projected safeguards requirements appears likely

  15. Energy optimization of integrated process plants

    Energy Technology Data Exchange (ETDEWEB)

    Sandvig Nielsen, J.

    1996-10-01

    A general approach for viewing the process synthesis as an evolutionary process is proposed. Each step is taken according to the present level of information and knowledge. This is formulated in a Process Synthesis Cycle. Initially the synthesis is conducted at a high abstraction level maximizing use of heuristics (prior experience, rules of thumbs etc). When further knowledge and information are available, heuristics will gradually be replaced by exact problem formulations. The principles in the Process Synthesis Cycle, is used to develop a general procedure for energy synthesis, based on available tools. The procedure is based on efficient use of process simulators with integrated Pinch capabilities (energy targeting). The proposed general procedure is tailored to three specific problems (Humid Air Turbine power plant synthesis, Nitric Acid process synthesis and Sulphuric Acid synthesis). Using the procedure reduces the problem dimension considerable and thus allows for faster evaluation of more alternatives. At more detailed level a new framework for the Heat Exchanger Network synthesis problem is proposed. The new framework is object oriented based on a general functional description of all elements potentially present in the heat exchanger network (streams, exchangers, pumps, furnaces etc.). (LN) 116 refs.

  16. Utilization as solid fuel and its physicochemical characteristic of hydroponic cultured plants for wastewater treatment; Suiko saibai shokubutsutai no kotai nenryoka to butsurigakuteki tokusei

    Energy Technology Data Exchange (ETDEWEB)

    Inoue, M.; Hirano, K. [Kanagawa Environmental Research Center, Kanagawa (Japan); Inamori, Y. [National Inst. for Environmental Studies, Tsukuba (Japan)

    1996-10-10

    A treatment of the wasted flower plants used for the waste water treatment process by the indoor drying and pressing method was studied for their effective reuse as columnar solid fuel. Three kinds of wasted flower plants were processed for making samples by indoor drying method for about two months. The samples which were chop plants about 10cm long, half powdery ones and powdery ones were made into the columnar solid fuels under 1-5 t{center_dot}cm{sup -2} pressure. According to the drop`s strength test for the solid fuels, it was investigated that they lost their physical strength rapidly in proportion to the elapsed time. The solid fuel made of powdery processed plants particularly lost its strength most rapidly. In the case of solid fuels made of chops, when they were pressed by the method that the trunk and the branches filled into the press`s vessel in the same direction against the press`s one, their physical strength were maintained for a long time. Furthermore, the form of solid fuels processed by this method looked like keeping their original one for a relatively long term. It was found that their combustible efficiency was excellent because the combustible calorie of the wasted plants ranged from 3,600 cal{center_dot}g{sup -1} to 3,800 cal{center_dot}g{sup -1}. 18 refs., 11 figs., 2 tabs.

  17. Fuel production from coal by the Mobil Oil process using nuclear high-temperature process heat

    International Nuclear Information System (INIS)

    Two processes for the production of liquid hydrocarbons are presented: Direct conversion of coal into fuel (coal hydrogenation) and indirect conversion of coal into fuel (syngas production, methanol synthesis, Mobil Oil process). Both processes have several variants in which nuclear process heat may be used; in most cases, the nuclear heat is introduced in the gas production stage. The following gas production processes are compared: LURGI coal gasification process; steam reformer methanation, with and without coal hydrogasification and steam gasification of coal. (orig./EF)

  18. Integration of the AVLIS [atomic vapor laser isotopic separation] process into the nuclear fuel cycle

    International Nuclear Information System (INIS)

    AVLIS RD and D efforts are currently proceeding toward full-scale integrated enrichment demonstrations in the late 1980's and potential plant deployment in the mid 1990's. Since AVLIS requires a uranium metal feed and produces an enriched uranium metal product, some change in current uranium processing practices are necessitated. AVLIS could operate with a UF6-in UF6-out interface with little effect to the remainder of the fuel cycle. This path, however, does not allow electric utility customers to realize the full potential of low cost AVLIS enrichment. Several alternative processing methods have been identified and evaluated which appear to provide opportunities to make substantial cost savings in the overall fuel cycle. These alternatives involve varying levels of RD and D resources, calendar time, and technical risk to implement and provide these cost reduction opportunities. Both feed conversion contracts and fuel fabricator contracts are long-term entities. Because of these factors, it is not too early to start planning and making decisions on the most advantageous options so that AVLIS can be integrated cost effectively into the fuel cycle. This should offer economic opportunity to all parties involved including DOE, utilities, feed converters, and fuel fabricators. 10 refs., 11 figs., 2 tabs

  19. High temperature polymer fuel cells and their Interplay with fuel processing systems

    DEFF Research Database (Denmark)

    Jensen, Jens Oluf; Qingfeng, Li; He, R.;

    2003-01-01

    This paper reports recent results from our group on polymer electrolyte membrane fuel cells (PEMFC) based on the temperature resistant polymer polybenzimidazole (PBI), which allow working temperatures up to 200°C. The membrane has a water drag number near zero and need no water management at all....... The high working temperature allows for utilization of the excess heat for fuel processing. Moreover, it provides an excellent CO tolerance of several percent, and the system needs no purification of hydrogen from a reformer. Continuous service for over 6 months at 150°C has been demonstrated....

  20. Modelling and Simulation of a Hybrid Solid Oxide Fuel Cell Coupled with a Gas Turbine Power Plant

    Directory of Open Access Journals (Sweden)

    Luca Andreassi

    2009-09-01

    Full Text Available

    The paper presents a simulation of a hybrid solid oxide fuel cell-gas turbine (SOFC-GT power generation system fueled by natural gas. In the system considered, the unreacted fuel from a topping solid oxide fuel cell is burnt in an afterburner to feed a bottoming gas turbine and produce additional power. Combustion gas expands in the gas turbine after having preheated the inlet air and fuel and it is used to generate steam required by the reforming reactions. A novel thermodynamic model has been developed for the fuel cell and implemented into the library of a modular object-oriented Process Simulator, CAMELPro™. The relevant plant performance indicators have been analyzed to evaluate the incremental increase in efficiency brought about by the introduction of the gas turbine and heat regeneration system. Simulations were performed for different values of the main plant parameters.

    • This paper is an updated version of a paper published in the ECOS'08 proceedings. 

  1. Impact of inlet fogging and fuels on power and efficiency of gas turbine plants

    Directory of Open Access Journals (Sweden)

    Basha Mehaboob

    2013-01-01

    Full Text Available A computational study to assess the performance of different gas turbine power plant configurations is presented in this paper. The work includes the effect of humidity, ambient inlet air temperature and types of fuels on gas turbine plant configurations with and without fogger unit. Investigation also covers economic analysis and effect of fuels on emissions. GT frames of various sizes/ratings are being used in gas turbine power plants in Saudi Arabia. 20 MWe GE 5271RA, 40 MWe GE-6561B and 70 MWe GE-6101FA frames are selected for the present study. Fogger units with maximum mass flow rate of 2 kg/s are considered for the present analysis. Reverse Osmosis unit of capacity 4 kg/s supplies required water to the fogger units. GT PRO software has been used for carrying out the analysis including; net plant output and net efficiency, break even electricity price and break even fuel LHV price etc., for a given location of Saudi Arabia. The relative humidity and temperature have been varied from 30 to 45 % and from 80 to 100° F, respectively. Fuels considered in the study are natural gas, diesel and heavy bunker oil. Simulated gas turbine plant output from GT PRO has been validated against an existing gas turbine plant output. It has been observed that the simulated plant output is less than the existing gas turbine plant output by 5%. Results show that variation of humidity does not affect the gas turbine performance appreciably for all types of fuels. For a decrease of inlet air temperature by 10 °F, net plant output and efficiency have been found to increase by 5 and 2 %, respectively for all fuels, for GT only situation. However, for GT with Fogger scenario, for a decrease of inlet air temperature by 10 °F, net plant output and efficiency have been found to further increase by 3.2 and 1.2 %, respectively for all fuels. For all GT frames with fogger, the net plant output and efficiency are relatively higher as compared to GT only case for all

  2. Mass, energy and material balances of SRF production process. Part 3: solid recovered fuel produced from municipal solid waste.

    Science.gov (United States)

    Nasrullah, Muhammad; Vainikka, Pasi; Hannula, Janne; Hurme, Markku; Kärki, Janne

    2015-02-01

    This is the third and final part of the three-part article written to describe the mass, energy and material balances of the solid recovered fuel production process produced from various types of waste streams through mechanical treatment. This article focused the production of solid recovered fuel from municipal solid waste. The stream of municipal solid waste used here as an input waste material to produce solid recovered fuel is energy waste collected from households of municipality. This article presents the mass, energy and material balances of the solid recovered fuel production process. These balances are based on the proximate as well as the ultimate analysis and the composition determination of various streams of material produced in a solid recovered fuel production plant. All the process streams are sampled and treated according to CEN standard methods for solid recovered fuel. The results of the mass balance of the solid recovered fuel production process showed that 72% of the input waste material was recovered in the form of solid recovered fuel; 2.6% as ferrous metal, 0.4% as non-ferrous metal, 11% was sorted as rejects material, 12% as fine faction and 2% as heavy fraction. The energy balance of the solid recovered fuel production process showed that 86% of the total input energy content of input waste material was recovered in the form of solid recovered fuel. The remaining percentage (14%) of the input energy was split into the streams of reject material, fine fraction and heavy fraction. The material balances of this process showed that mass fraction of paper and cardboard, plastic (soft) and wood recovered in the solid recovered fuel stream was 88%, 85% and 90%, respectively, of their input mass. A high mass fraction of rubber material, plastic (PVC-plastic) and inert (stone/rock and glass particles) was found in the reject material stream.

  3. A suitable model plant for control of the set fuel cell-DC/DC converter

    Energy Technology Data Exchange (ETDEWEB)

    Andujar, J.M.; Segura, F.; Vasallo, M.J. [Departamento de Ingenieria Electronica, Sistemas Informaticos y Automatica, E.P.S. La Rabida, Universidad de Huelva, Ctra. Huelva - Palos de la Frontera, S/N, 21819 La Rabida - Palos de la Frontera Huelva (Spain)

    2008-04-15

    In this work a state and transfer function model of the set made up of a proton exchange membrane (PEM) fuel cell and a DC/DC converter is developed. The set is modelled as a plant controlled by the converter duty cycle. In addition to allow setting the plant operating point at any point of its characteristic curve (two interesting points are maximum efficiency and maximum power points), this approach also allows the connection of the fuel cell to other energy generation and storage devices, given that, as they all usually share a single DC bus, a thorough control of the interconnected devices is required. First, the state and transfer function models of the fuel cell and the converter are obtained. Then, both models are related in order to achieve the fuel cell+DC/DC converter set (plant) model. The results of the theoretical developments are validated by simulation on a real fuel cell model. (author)

  4. The impact of fuel cladding failure events on occupational radiation exposures at nuclear power plants

    International Nuclear Information System (INIS)

    This paper summarizes two case studies that evaluated the impact of fuel cladding failures on occupational radiation exposures at pressurized water reactors (PWRs). For the case studies, radiation measurements were made both during routine operations and during the subsequent maintenance and refueling outage ata PWR with more than 0.2% failed fuel. Gamma spectroscopy measurements, radiation exposure rate determinations, thermoluminescent dosimeter assessments, and air sample analyses were made in the plant's radwaste, pipe penetration, and containment buildings. Small highly radioactive fuel particles, which contaminated the plant's fuel handling building, were also analyzed. Based on the data collected, fuel cladding failures increased radiation exposure rates an estimated 540% in some areas of the plant during routine operations. Furthermore, the fraction of the total exposure rates due to fission products remained relatively constant over the duration of the outage

  5. Site selection considerations for a reprocessing plant of spent fuel in China

    International Nuclear Information System (INIS)

    With conversion from moderately to actively for nuclear development strategy in China, the future nuclear power scale and the amount of the waste from spent nuclear fuels will be enormous, the construction of spent nuclear waste disposal plant will be necessary for meet the sustainable development requirement. The reprocessing of spent nuclear fuel is very important for the closed cycle of nuclear fuel and sustainable development of nuclear power. Because of the huge investment, long construction period and high environmental sensitivity, the site selection of spent nuclear fuel reprocessing plant is more complicated and sensitive than nuclear power plant. It supposed to take environment characteristic, transport condition of' nuclear spent fuel and solidified body of high-level radioactive wastes, as well as the social environmental characteristics into account. This article summarizes the site selection considerations from the technical feasibility, safety reliability, environmental compatibility and economic rationality for further discussion. (authors)

  6. Fuel cycle management by the electric enterprises and spanish nuclear Power plants

    International Nuclear Information System (INIS)

    The Nuclear Fuel Group reports to the Technology Committee of the UNESA Nuclear Energy Committee, and is constituted by representatives of both the Spanish Utilities and the Nuclear Power Plants. The Group addresses the nuclear plant common issues in relation to the operation and management of the nuclear fuel in their different stages of the Fuel Cycle. The article reviews the activities developed by the Group in the Front-End, mainly in the monitoring of international programs that define criteria to improve the Fuel Reliability and in the establishment of common bases for the implementation of changes in the regulation applying the nuclear fuel. Concerning the Back-End the Group focuses on those activities of coordination with third parties related to the management of used fuel. (Author)

  7. SCENARIO OF WOOD-FUEL PROCUREMENT FOR A NEW BOILER PLANT

    Directory of Open Access Journals (Sweden)

    Gerasimov Y. Y.

    2013-11-01

    Full Text Available This article shows the results of computer simulation of wood harvesting in the North Ladoga region with wood-fuel production and delivery of its part to the new boiler plant in Suojarvi being under construction

  8. Implementation of integrated safeguards at nuclear fuel plant Pitesti Romania

    Energy Technology Data Exchange (ETDEWEB)

    Olaru, Vasilica; Tiberiu, Ivana; Epure, Gheorghe [Nuclear Safety Department, Nuclear Fuel Plant Pitesti, Cimpului, No 1, 115400 Mioveni (Romania)

    2010-07-01

    The nuclear activity in Romania was for many years under Traditional Safeguards (TS) and has developed in good conditions this type of nuclear safeguards. Now it has the opportunity to improve the performance and quality of the safeguards activity and increase the accountancy and control of nuclear material by passing to Integrated Safeguards (IS). The legal framework is Law 100/2000 for ratification of the Protocol between Romania and International Atomic Energy Agency (IAEA), additional to the Agreement between the Socialist Republic of Romania Government and IAEA related to safeguards as part of the Treaty on the non-proliferation of nuclear weapons published in the Official Gazette no. 3/31 January 1970, and the Additional Protocol content published in the Official Gazette no. 295/ 29.06.2000. The first discussion about Integrated Safeguards (IS) between Nuclear Fuel Plant (FCN) representatives and IAEA inspectors was in June 2005. In Feb. 2007 an IAEA mission visited FCN and established the main steps for implementing the IS. There were visited the storages, technological flow, and was reviewed the residence times for different nuclear materials, the applied chemical analysis, metrological methods, weighting method and elaborating the documents and lists. At that time the IAEA and FCN representatives established the main points for starting the IS at FCN: perform the Short Notice Random Inspections (SNRI), communicate the eligible days for SNRI for each year, communicate the estimated deliveries and shipments for first quarter and then for the rest of the year, daily mail box declaration (DD) with respect to the residence time for several nuclear material, advance notification (AN) for each nuclear material transfer (shipments and receipts), others. At 01 June 2007 Romania has passed officially to Integrated Safeguards and FCN (RO-D) has taken all measures to realize this objective. (authors)

  9. FDD-1 System On-line Monitoring Fuel Rod Failure of Nuclear Power Plant

    Institute of Scientific and Technical Information of China (English)

    CHENPeng; ZHANGYing-chao; JISong-tao; GAOYong-guang; YINZhen-guo; HANChuan-bin

    2003-01-01

    The FDD-1 system developed by CIAE for on-line monitoring fuel rod failure of nuclear power plant consists of γ-ray detector, γ-ray spectrum analyzer, computer, and an analysis code for evaluating the status of fuel rod failure. It would be determined that the fuel rod failure occurs when a large amount of γ activity increases in the primary system measured by γ-ray detector near the CVCS.

  10. Plant life management processes and practices for heavy water reactors

    International Nuclear Information System (INIS)

    In general, heavy water reactor (HWR) nuclear power plant (NPP) owners would like to keep their NPPs in service as long as they can be operated safely and economically. Their decisions are depending on essentially business model. They involve the consideration of a number of factors, such as the material condition of the plant, comparison with current safety standards, the socio-political climate and asset management/ business planning considerations. Continued plant operation, including operation beyond design life, called 'long term operation, depends, among other things, on the material condition of the plant. This is influenced significantly by the effectiveness of ageing management. Key attributes of an effective plant life management program include a focus on important systems, structure and components (SSCs) which are susceptible to ageing degradation, a balance of proactive and reactive ageing management programmes, and a team approach that ensures the co-ordination of and communication between all relevant nuclear power plant and external programmes. Most HWR NPP owners/operators use a mix of maintenance, surveillance and inspection (MSI) programs as the primary means of managing ageing. Often these programs are experienced-based and/or time-based and may not be optimised for detecting and/or managing ageing effects. From time-to-time, operational history has shown that this practice can be too reactive, as it leads to dealing with ageing effects (degradation of SSCs) after they have been detected. In many cases premature and/or undetected ageing cannot be traced back to one specific reason or an explicit error. The root cause is often a lack of communication, documentation and/or co-ordination between design, commissioning, operation or maintenance organizations. This lack of effective communication and interfacing frequently arises because, with the exception of major SSCs, such as the fuel channels or steam generators, there is a lack of explicit

  11. Integration of a municipal solid waste gasification plant with solid oxide fuel cell and gas turbine

    DEFF Research Database (Denmark)

    Bellomare, Filippo; Rokni, Masoud

    2013-01-01

    it reacts with air and produces electricity. The exhausted gases out of the SOFC enter a burner for further fuel combusting and finally the off-gases are sent to a gas turbine to produce additional electricity. Different plant configurations have been studied and the best one found to be a regenerative gas...... in landfills. A Municipal Solid Waste Gasification Plant Integrated with Solid Oxide Fuel Cell (SOFC) and Gas Turbine (GT) has been studied and the plant is called IGSG (Integrated Gasification SOFC and GT). Gasification plant is fed by MSW to produce syngas by which the anode side of an SOFC is fed wherein...

  12. Better and more efficient collaboration for increased use of field fuel in heating plants; Baettre och effektivare samverkan foer oekad anvaendning av aakerbraenslen i vaermeverken

    Energy Technology Data Exchange (ETDEWEB)

    Arkeloev, Olof (Agrovaest, Skara (Sweden)); Hellstroem, Chris; Hollsten, Ronnie (KanEnergi Sweden AB, Skara (Sweden)); Lindh, Carina (LRF Konsult, Skara (Sweden))

    2010-05-15

    Despite that the potential for field fuels in SW Sweden is great and that the combustion characteristics of fuels are known, the interest for field fuels has been low from farmers and heating plants. The purpose of the project is to identify why the introduction of field fuel into heating plants is going so slow and to suggest possible solutions. Field fuel is missing the general structure and tradition that is found in forest fuels in terms of harvesting, processing, logistics and business models. The overall long-term objective is a better and more effective cooperation between heating plants, farmers and logistic companies for the increased use of field fuels in heating plants. The potential for field fuel in the area is great but won't be sufficient to cover the need. The raw materials that exist today and are deemed will be relevant in the future are willow, straw and grain kernel. We have divided the heating plants into two groups; Small plants with a furnace less than 35 MW, and large plants with an effect over 35 MW. Common to both small and large heating plants is that there must be a willingness to receive and combust field fuels for the share of field fuels to increase. For the small heating plants to be able to receive and combust field fuels the knowledge of the combustion properties of these fuels must increase. Larger heating plants have better opportunities to use field fuels in their boilers when it comes to the technology and the know how. They have a more controlled handling and receiving of fuels. It is not uncommon that storing and blending of fuels will take place at their own facility. They also have more experience of handling a larger number of suppliers at the same time. The heating plants would like to see standardization in terms of fuel characteristics, and they prefer to obtain approximately the same burning performance regardless of delivery date. Today, the small heating plants do not have the routines to manage multiple small

  13. Holistic analysis of thermochemical processes by using solid biomass for fuel production in Germany

    International Nuclear Information System (INIS)

    According to the German act ''Biokraftstoff-Nachhaltigkeitsverordnung'', biofuels must show a CO2eq-reduction compared to the fossil reference fuel (83.8 g CO2eq/MJfuel /Richtlinie 98/70/EG/) of 35 % beginning with 2011. In new plants, which go into operation after the 31.12.2016 the CO2eq-savings must be higher than 50 % in 2017 and higher than 60 % in 2018 /Biokraft-NachV/. The biofuels (methyl ester of rapeseed, bioethanol and biomethane) considered in this study do not meet these requirements for new plants. To comply with these rules new processes must be deployed. Alternative thermochemical generated fuels could be an option. The aim of this work is to evaluate through a technical, ecological and economic analysis (Well-to-Wheel) whether and under what conditions the thermochemical production of Fischer-Tropsch-diesel or -gasoline, hydrogen (H2) and Substitute Natural Gas (SNG) complies with the targets. Four different processes are considered (fast pyrolysis and torrefaction with entrained flow gasifier, CHOREN Carbo-V registered -gasifier, Absorption Enhanced Reforming (AER-) gasifier). Beside residues such as winter wheat straw and residual forest wood, wood from short-rotation plantations is taken into account. The technical analysis showed that at present status (2010) two and in 2050 six plants can be operated energy-self-sufficient. The overall efficiency of the processes is in the range of 41.5 (Fischer-Tropsch-diesel or -gasoline) and 59.4 % (H2). Furthermore, it was found that for 2010, all thermochemical produced fuels except the H2-production from wood from short-rotation plantations in decentralised or central fast pyrolysis and in decentralised torrefactions with entrained flow gasifier keep the required CO2eq-saving of 60 %. In 2050, all thermochemical produced fuels will reach these limits. The CO2eq-saving is between 72 (H2) and 95 % (Fischer-Tropsch-diesel or -gasoline). When the production costs of the thermochemical

  14. Fuel Gas Demonstration Plant Program: Small-Scale Industrial Project. Demonstration plant design manual, Phase I

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

    The plant will utilize fixed bed, stirred, two stage gasifiers. The lower stage will be a standard gasifier configuration. The upper stage will be an undivided distillation section containing a slowly rotating stirrer which will move vertically through the bed. The bottom of the gasifier will contain a standard dry grate and will have lock hoppers to discharge the ash. This type of gasifier provides high coal utilization. It also distills the tars and oils from the coal in the upper zone at minimum temperatures, thereby providing minimum viscosity liquid fuels which can be used for the induration of iron ore pellets. The very hot bottom gases leaving the combustion zone, after passing through a cyclone to remove coal and ash dust can be used to generate steam. This steam is in addition to the steam generated in the water jacket of the lower zone which is used in the steam air blast to the bottom of the gasifier retort.

  15. Concerning permission of change in nuclear fuel processing business of Japan Nuclear Fuel Co., Ltd

    International Nuclear Information System (INIS)

    In response to an inquiry on the title issue received on Jun. 17, 1988, the Nuclear Safety Commission made a study and submitted the findings to the Prime Minister on Jul. 21, 1988. The study was intended to determine the conformity of the permission to the applicable criteria specified in laws relating to control of nuclear material, nuclear fuel and nuclear reactor. The proposed modification plan included changes in the facilities in the No.1 processing building and changes in processing methods which were required to perform processing of blanket fuel assemblies for fast breeder reactor. It also included changes in the facilities in the No.2 building which were required to improve the processes. The safety study covered the anti-earthquake performance, fire/explosion prevention, criticality control, containment performance, radioactive waste disposal, and other major safety issues. Other investigations included exposure dose evaluation and accident analysis. Study results were examined on the basis of the Basic Guidelines for Nuclear Fuel Facilities Safety Review and the Uranium Processing Safety Review Guidelines. It was concluded that the modifications would not have adverse effect on the safety of the facilities. (Nogami, K.)

  16. French approach to plant safety reassessment: The benefits of visits to European nuclear fuel fabrication plants

    International Nuclear Information System (INIS)

    With a ten year periodicity, the French nuclear safety authority (DGSNR) and its technical support (IRSN) reassess the safety of the plants under survey. A special part is devoted to internal experience feedback, and the events that occurred during the past working period are carefully analysed. In the case of the French FBFC uranium fuel fabrication plant, it was decided to make a more systematic use of international feedback in the usual reassessment work for non-reactor facilities. A programme has been set up on the basis of peer to peer level bilateral meetings organized with the European safety authorities having similar plants under their responsibility. A special safety-oriented standard questionnaire was previously sent to each and returned. Each bilateral contact consists of a two day visit, which began with discussions about particular topics in the regulation area and methods for an efficient survey. In order to illustrate this, the two authorities visited the nuclear site the second day. In this way, European safety authorities of five countries (Belgium, Germany, United Kingdom, Spain and Sweden) have met, and plants belonging to Framatome-ANP, Westinghouse and ENUSA groups were visited. All the contacted authorities participated and when this programme was completed, it was possible for DGSNR and IRSN to get a more accurate measure of particular reassessment work. The main results of these actions were to 'standardize' the consultancy's judgement and, taking advantage of encountered good safety practices and good safety designs, it was possible to reinforce specific requests during the reassessment work. Moreover, it was an opportunity for the operators to participate in deepening information exchanges about safety topics. (author)

  17. Process development and fabrication for sphere-pac fuel rods. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    Welty, R.K.; Campbell, M.H.

    1981-06-01

    Uranium fuel rods containing sphere-pac fuel have been fabricated for in-reactor tests and demonstrations. A process for the development, qualification, and fabrication of acceptable sphere-pac fuel rods is described. Special equipment to control fuel contamination with moisture or air and the equipment layout needed for rod fabrication is described and tests for assuring the uniformity of the fuel column are discussed. Fuel retainers required for sphere-pac fuel column stability and instrumentation to measure fuel column smear density are described. Results of sphere-pac fuel rod fabrication campaigns are reviewed and recommended improvements for high throughput production are noted.

  18. Safety analysis of solvent fire accidents in a fuel reprocessing plant

    International Nuclear Information System (INIS)

    For analyzing the safety evaluation of solvent fire as DBA in an extraction process of nuclear fuel reprocessing plant, computer code named FACE was developed in JAERI under the auspices of the Science and Technology Agency of Japan. The code FACE can provide not only for calculations of temperature, pressure, flow rate and pressure drop in cells and ducts of the network in air-ventilation system by one- and two-dimensional analyses and smoke containing radioactive materials by burning solvent in the network but also for solvent fire behavior in the cell, transport of radioactive materials and its deposition in the network, integrity of HEPA filters, and release of radioactive materials to the environment. Calculations by FACE were compared with data obtained by large-scale demonstration tests in JAERI simulating solvent fire in the extraction process to verify mathematical modeling of the fire accident in the code. (author)

  19. Design and evaluation of an on-line fuel rod assay device for an HTGR fuel refabrication plant

    International Nuclear Information System (INIS)

    Refabricated HTGR fuel rods will contain from approx. 0.15 to 0.5 g 233U and/or 235U. The fuel rods are approx. 16 mm in diameter and 62 mm long. A typical commercial fuel refabrication facility will have six fuel rod production lines, each producing approximately one fuel rod every 4 seconds at design capacity. One on-line assay device will be present for each two production lines. The relative standard deviation in an individual fuel rod fissile material measurement must be less than 3% to satisfy process and quality control requirements. Systematic errors must be kept less than approx. 0.3% for fissile material measured in fuel rods produced over two months to satisfy material accountability requirements. Several nondestructive assay (NDA) methods were investigated. Because the gamma-ray activity of the refabricated fuel is relatively high due to the presence of 232U in the fuel and because the gamma-ray activity is not directly related to total or fissile uranium content, NDA methods employing gamma-ray detection did not appear practicable. A method using thermal neutron irradiation and fast-fission neutron detection was selected. An experimental assay device was fabricated based on this NDA method. Experiments were performed to determine the precision and accuracy of the measurements and to investigate potential interferences and systematic errors. Operating procedures were evaluated, and analysis procedures were identified

  20. Solar photochemical process engineering for production of fuels and chemicals

    Science.gov (United States)

    Biddle, J. R.; Peterson, D. B.; Fujita, T.

    1985-01-01

    The engineering costs and performance of a nominal 25,000 scmd (883,000 scfd) photochemical plant to produce dihydrogen from water were studied. Two systems were considered, one based on flat-plate collector/reactors and the other on linear parabolic troughs. Engineering subsystems were specified including the collector/reactor, support hardware, field transport piping, gas compression equipment, and balance-of-plant (BOP) items. Overall plant efficiencies of 10.3 and 11.6 percent are estimated for the flat-plate and trough systems, respectively, based on assumed solar photochemical efficiencies of 12.9 and 14.6 percent. Because of the opposing effects of concentration ratio and operating temperature on efficiency, it was concluded that reactor cooling would be necessary with the trough system. Both active and passive cooling methods were considered. Capital costs and energy costs, for both concentrating and non-concentrating systems, were determined and their sensitivity to efficiency and economic parameters were analyzed. The overall plant efficiency is the single most important factor in determining the cost of the fuel.

  1. A review of the separation and immobilisation of krypton arising from nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    The techniques for the separation and immobilisation of 85Kr are reviewed. Particular attention is paid to processes currently available or undergoing development on the technical to industrial scale. Of the separation processes, cryogenic distillation has reached the most advanced stage of development, with a pilot facility already undergoing radioactive demonstration. The PNC Kr-recovery pilot plant, which has a off-gas flow capacity of 110 m3 hr-1 (approximately 1/4 the scale of THORP), is currently undergoing tests at Tokai Mura. Low-temperature absorption and adsorption processes have also reached the pilot plant stage but have yet to undergo radiological tests. The separated krypton has been conventionally stored as the compressed gas in cylinders, but progress made in encapsulation techniques suggest that more secure immobilisation can be achieved by encapsulation within a metal or zeolite matrix. Processes based on the implantation of krypton in a metal or metal alloy have been demonstrated on the technical scale with the radioactive gas. It is concluded that the technology for the separation, isolation and immobilisation of radioactive krypton is available only on a reduced scale compared with THORP. The investment cost of a 85Kr management facility for THORP, based on cryogenic distillation followed by immobilisation by implantation in metal and assuming a 20 year plant life, is estimated at 51-57M pounds. The cost of prepurification of the off-gas stream is included in this figure. Accompanying operating costs, including those incurred by disposal of the encapsulate in geological formations, are estimated at 2.2-3.3 M pounds per annum. Further development work under radioactive conditions is still required prior to the application of existing technology to full-scale fuel reprocessing plant. (author)

  2. ADVANCED HYDROGEN TRANSPORT MEMBRANES FOR VISION 21 FOSSIL FUELS PLANTS

    Energy Technology Data Exchange (ETDEWEB)

    Shane E. Roark; Anthony F. Sammells; Richard Mackay; Stewart Schesnack; Scott Morrison; Thomas A. Zirbel; Thomas F. Barton; Sara L. Rolfe; U. Balachandran; Richard N. Kleiner; James E. Stephan; Frank E. Anderson; Aaron L. Wagner; Jon P. Wagner

    2003-07-31

    Eltron Research Inc. and team members CoorsTek, Sued Chemie, and Argonne National Laboratory are developing an environmentally benign, inexpensive, and efficient method for separating hydrogen from gas mixtures produced during industrial processes, such as coal gasification. This project was motivated by the National Energy Technology Laboratory (NETL) Vision 21 initiative, which seeks to economically eliminate environmental concerns associated with the use of fossil fuels. Currently, this project is focusing on four basic categories of dense membranes: (1) mixed conducting ceramic/ceramic composites, (2) mixed conducting ceramic/metal (cermet) composites, (3) cermets with hydrogen permeable metals, and (4) layered composites containing hydrogen permeable alloys. Ultimately, these materials must enable hydrogen separation at practical rates under ambient and high-pressure conditions, without deactivation in the presence of feedstream components such as carbon dioxide, water, and sulfur. This report presents hydrogen permeation data during long term tests and tests at high pressure in addition to progress with cermet, ceramic/ceramic, and thin film membranes.

  3. Radiation Monitoring System in Advanced Spent Fuel Conditioning Process Facility

    International Nuclear Information System (INIS)

    The Advanced spent fuel Conditioning Process is under development for effective management of spent fuel by converting UO2 into U-metal. For demonstration of this process, α-γ type new hot cell was built in the IMEF basement . To secure against radiation hazard, this facility needs radiation monitoring system which will observe the entire operating area before the hot cell and service area at back of it. This system consists of 7 parts; Area Monitor for γ-ray, Room Air Monitor for particulate and iodine in both area, Hot cell Monitor for hot cell inside high radiation and rear door interlock, Duct Monitor for particulate of outlet ventilation, Iodine Monitor for iodine of outlet duct, CCTV for watching workers and material movement, Server for management of whole monitoring system. After installation and test of this, radiation monitoring system will be expected to assist the successful ACP demonstration

  4. Fuel properties of pyrolytic oil of the straw and stalk of rape plant

    Energy Technology Data Exchange (ETDEWEB)

    Karaosmanoglu, F.; Tetik, E. [Istanbul Technical Univ., Chemical Engineering Dept., Istanbul (Turkey)

    1999-01-01

    Biomass is a potential renewable source of energy. Thermochemical conversion of biomass is one of the most common and convenient routes for conversion into energy. Pyrolysis is the most important process in thermal conversion processes of biomass. In this study, pyrolysis of the straw-stalk of rape plant within a tubular reactor under static atmosphere at 650degC pyrolysis temperature and at 30degC min{sup -1} heating rate, the various characteristics of pyrolytic oil acquired under these conditions were identified. Pyrolytic oil is a carbon rich, hydrocarbon mixture bearing oxygen at a considerable ratio and containing ash, sulphur and nitrogen in very small quantities. The empirical formula of pyrolytic oil that has a heating value of 27.15. MJ/kg was established as CH{sub 1.39} O{sub 0.46}. The results from the pyrolysis of straw-stalk of rape plants showed the potential of rape plant as an important source of liquid hydrocarbon fuels. (Author)

  5. Low Emissions Burner Technology for Metal Processing Industry using Byproducts and Biomass Derived Liquid Fuels

    Energy Technology Data Exchange (ETDEWEB)

    Agrawal, Ajay; Taylor, Robert

    2013-09-30

    This research and development efforts produced low-emission burner technology capable of operating on natural gas as well as crude glycerin and/or fatty acids generated in biodiesel plants. The research was conducted in three stages (1) Concept definition leading to the design and development of a small laboratory scale burner, (2) Scale-up to prototype burner design and development, and (3) Technology demonstration with field vefiication. The burner design relies upon the Flow Blurring (FB) fuel injection based on aerodynamically creating two-phase flow near the injector exit. The fuel tube and discharge orifice both of inside diameter D are separated by gap H. For H < 0.25D, the atomizing air bubbles into liquid fuel to create a two-phase flow near the tip of the fuel tube. Pressurized two-phase fuel-air mixture exits through the discharge orifice, which results in expansion and breakup of air bubbles yielding a spray with fine droplets. First, low-emission combustion of diesel, biodiesel and straight VO (soybean oil) was achieved by utilizing FB injector to yield fine sprays for these fuels with significantly different physical properties. Visual images for these baseline experiments conducted with heat release rate (HRR) of about 8 kW illustrate clean blue flames indicating premixed combustion for all three fuels. Radial profiles of the product gas temperature at the combustor exit overlap each other signifying that the combustion efficiency is independent of the fuel. At the combustor exit, the NOx emissions are within the measurement uncertainties, while CO emissions are slightly higher for straight VO as compared to diesel and biodiesel. Considering the large variations in physical and chemical properties of fuels considered, the small differences observed in CO and NOx emissions show promise for fuel-flexible, clean combustion systems. FB injector has proven to be very effective in atomizing fuels with very different physical properties, and it offers a

  6. Understanding the transport processes in polymer electrolyte membrane fuel cells

    Science.gov (United States)

    Cheah, May Jean

    Polymer electrolyte membrane (PEM) fuel cells are energy conversion devices suitable for automotive, stationary and portable applications. An engineering challenge that is hindering the widespread use of PEM fuel cells is the water management issue, where either a lack of water (resulting in membrane dehydration) or an excess accumulation of liquid water (resulting in fuel cell flooding) critically reduces the PEM fuel cell performance. The water management issue is addressed by this dissertation through the study of three transport processes occurring in PEM fuel cells. Water transport within the membrane is a combination of water diffusion down the water activity gradient and the dragging of water molecules by protons when there is a proton current, in a phenomenon termed electro-osmotic drag, EOD. The impact of water diffusion and EOD on the water flux across the membrane is reduced due to water transport resistance at the vapor/membrane interface. The redistribution of water inside the membrane by EOD causes an overall increase in the membrane resistance that regulates the current and thus EOD, thereby preventing membrane dehydration. Liquid water transport in the PEM fuel cell flow channel was examined at different gas flow regimes. At low gas Reynolds numbers, drops transitioned into slugs that are subsequently pushed out of the flow channel by the gas flow. The slug volume is dependent on the geometric shape, the surface wettability and the orientation (with respect to gravity) of the flow channel. The differential pressure required for slug motion primarily depends on the interfacial forces acting along the contact lines at the front and the back of the slug. At high gas Reynolds number, water is removed as a film or as drops depending on the flow channel surface wettability. The shape of growing drops at low and high Reynolds number can be described by a simple interfacial energy minimization model. Under flooding conditions, the fuel cell local current

  7. Performance Comparison on Repowering of a Steam Power Plant with Gas Turbines and Solid Oxide Fuel Cells

    Directory of Open Access Journals (Sweden)

    Masoud Rokni

    2016-05-01

    Full Text Available Repowering is a process for transforming an old power plant for greater capacity and/or higher efficiency. As a consequence, the repowered plant is characterized by higher power output and less specific CO2 emissions. Usually, repowering is performed by adding one or more gas turbines into an existing steam cycle which was built decades ago. Thus, traditional repowering results in combined cycles (CC. High temperature fuel cells (such as solid oxide fuel cell (SOFC could also be used as a topping cycle, achieving even higher global plant efficiency and even lower specific CO2 emissions. Decreasing the operating temperature in a SOFC allows the use of less complex materials and construction methods, consequently reducing plant and the electricity costs. A lower working temperature makes it also suitable for topping an existing steam cycle, instead of gas turbines. This is also the target of this study, repowering of an existing power plant with SOFC as well as gas turbines. Different repowering strategies are studied here, repowering with one gas turbine with and without supplementary firing, repowering with two gas turbines with and without supplementary firing and finally repowering using SOFC. Plant performances and CO2 emissions are compared for the suggested repowered plants.

  8. CO2 capture processes in power plants - Le captage du CO2 dans les centrales thermiques

    CERN Document Server

    Bouallou, Chakib

    2010-01-01

    This review is devoted to assess and compare various processes aiming at recover CO2 from power plants fed with natural gas (NGCC) and pulverized coal (PC). These processes are post combustion CO2 capture using chemical solvents, natural gas reforming for pre-combustion capture and oxy-fuel combustion with cryogenic recovery of CO2. These processes were evaluated to give some clues for choosing the best option for each type of power plant. The comparison of these various concepts suggests that, in the short and medium term, chemical absorption is the most interesting process for NGCC power plants. For CP power plants, oxy-combustion can be a very interesting option, as well as post-combustion capture by chemical solvents.

  9. HTGR fuel reprocessing pilot plant: results of the sequential equipment operation

    International Nuclear Information System (INIS)

    The second sequential operation of the HTGR fuel reprocessing cold-dry head-end pilot plant equipment has been successfully completed. Twenty standard LHGTR fuel elements were crushed to a size suitable for combustion in a fluid bed burner. The graphite was combusted leaving a product of fissile and fertile fuel particles. These particles were separated in a pneumatic classifier. The fissile particles were fractured and reburned in a fluid bed to remove the inner carbon coatings. The remaining products are ready for dissolution and solvent extraction fuel recovery

  10. Physical Simulation of Burning Process of Alternative Engine Fuels

    Directory of Open Access Journals (Sweden)

    M. S. Assad

    2008-01-01

    Full Text Available Visualization of burning process in the closed vessel has been fulfilled with the help of method high-speed photography through a transparent glass. This method as an efficient means for investigation of fast processes permits to obtain a visual, convenient visual perception insight about the development of the burning process and understand peculiarities of the development of flame in the closed vessels.The paper contains a description of an experimental stand and methodology for execution of an experiment on visualization of the flame development and measurement of main parameters of the burning process in a closed vessel that is in the simulating combustion chamber.According to the obtained photos an analysis of form, structure and dynamics of flame front development has been carried out; some peculiarities and differences of flames of various fuel-air mixtures have been established and the paper proves an occurrence of the secondary glow during burning in the closed vessel.Body of data obtained with the help of the visualization of burning process makes it possible to determine main parameters of the burning process. In particular, relation of the pressure developed in the chamber with the mass of burnt-out mixture has been investigated and dependence has been obtained that shows the law of fuel burning-out in the graphic form.

  11. Enhancing Elementary Pre-service Teachers' Plant Processes Conceptions

    Science.gov (United States)

    Thompson, Stephen L.; Lotter, Christine; Fann, Xumei; Taylor, Laurie

    2016-06-01

    Researchers examined how an inquiry-based instructional treatment emphasizing interrelated plant processes influenced 210 elementary pre-service teachers' (PTs) conceptions of three plant processes, photosynthesis, cellular respiration, and transpiration, and the interrelated nature of these processes. The instructional treatment required PTs to predict the fate of a healthy plant in a sealed terrarium (Plant-in-a-Jar), justify their predictions, observe the plant over a 5-week period, and complete guided inquiry activities centered on one of the targeted plant processes each week. Data sources included PTs' pre- and post-predictions with accompanying justifications, course artifacts such as weekly terrarium observations and science journal entries, and group models of the interrelated plant processes occurring within the sealed terraria. A subset of 33 volunteer PTs also completed interviews the week the Plant-in-a-Jar scenario was introduced and approximately 4 months after the instructional intervention ended. Pre- and post-predictions from all PTs as well as interview responses from the subgroup of PTs, were coded into categories based on key plant processes emphasized in the Next Generation Science Standards. Study findings revealed that PTs developed more accurate conceptions of plant processes and their interrelated nature as a result of the instructional intervention. Primary patterns of change in PTs' plant process conceptions included development of more accurate conceptions of how water is used by plants, more accurate conceptions of photosynthesis features, and more accurate conceptions of photosynthesis and cellular respiration as transformative processes.

  12. Fuel and power coproduction: The Liquid Phase Methanol (LPMEOH{trademark}) process demonstration at Kingsport

    Energy Technology Data Exchange (ETDEWEB)

    Drown, D.P.; Brown, W.R.; Heydorn, E.C.; Moore, R.B.; Schaub, E.S.; Brown, D.M.; Jones, W.C.; Kornosky, R.M.

    1997-12-31

    The Liquid Phase Methanol (LPMEOH{trademark}) process uses a slurry bubble column reactor to convert syngas (primarily a mixture of carbon monoxide and hydrogen) to methanol. Because of its superior heat management, the process is able to be designed to directly handle the carbon monoxide (CO)-rich syngas characteristic of the gasification of coal, petroleum coke, residual oil, wastes, or of other hydrocarbon feedstocks. When added to an integrated gasification combined cycle (IGCC) power plant, the LPMEOH{trademark} process converts a portion of the CO-rich syngas produced by the gasifier to methanol, and the remainder of the unconverted gas is used to fuel the gas turbine combined-cycle power plant. The LPMEOH{trademark} process has the flexibility to operate in a daily electricity demand load-following manner. Coproduction of power and methanol via IGCC and the LPMEOH{trademark} process provides opportunities for energy storage for electrical demand peak shaving, clean fuel for export, and/or chemical methanol sales.

  13. Advanced Hydrogen Transport Membranes for Vision 21 Fossil Fuel Plants

    Energy Technology Data Exchange (ETDEWEB)

    Carl R. Evenson; Shane E. Roark

    2006-03-31

    The objective of this project was to develop an environmentally benign, inexpensive, and efficient method for separating hydrogen from gas mixtures produced during industrial processes, such as coal gasification. A family of hydrogen separation membranes was developed including single phase mixed conducting ceramics, ceramic/ceramic composites, cermet membranes, cermet membranes containing a hydrogen permeable metal, and intermediate temperature composite layered membranes. Each membrane type had different operating parameters, advantages, and disadvantages that were documented over the course of the project. Research on these membranes progressed from ceramics to cermets to intermediate temperature composite layered membranes. During this progression performance was increased from 0.01 mL x min{sup -1} x cm{sup -2} up to 423 mL x min{sup -1} x cm{sup -2}. Eltron and team membranes not only developed each membrane type, but also membrane surface catalysis and impurity tolerance, creation of thin film membranes, alternative applications such as membrane promoted alkane dehydrogenation, demonstration of scale-up testing, and complete engineering documentation including process and mechanical considerations necessary for inclusion of Eltron membranes in a full scale integrated gasification combined cycle power plant. The results of this project directly led to a new $15 million program funded by the Department of Energy. This new project will focus exclusively on scale-up of this technology as part of the FutureGen initiative.

  14. Quality assurance systems for fossil-fuel power plants. Qualitaetssicherungssysteme fuer konventionelle Kraftwerke

    Energy Technology Data Exchange (ETDEWEB)

    Adams, H.W.; Haker, W. (Dr. Adams und Partner Unternehmensberatung GmbH, Duisburg (Germany, F.R.))

    1990-11-19

    Quality assurance systems are obviously successful in the service industry (e.g. software) and in the producing industry. In fossil-fuel power plants, they are still sceptically compared with the systems used in nuclear power plants. However, quality assurance systems, if rightly understood, can contribute to a better transparency of organization. (orig.).

  15. Thermodynamic analysis of an integrated gasification solid oxide fuel cell plant combined with an organic Rankine cycle

    DEFF Research Database (Denmark)

    Pierobon, Leonardo; Rokni, Masoud; Larsen, Ulrik;

    2013-01-01

    A 100 kWe hybrid plant consisting of gasification system, solid oxide fuel cells and organic Rankine cycle is presented. The nominal power is selected based on cultivation area requirement. For the considered output a land of around 0.5 km2 needs to be utilized. Woodchips are introduced into a fi......A 100 kWe hybrid plant consisting of gasification system, solid oxide fuel cells and organic Rankine cycle is presented. The nominal power is selected based on cultivation area requirement. For the considered output a land of around 0.5 km2 needs to be utilized. Woodchips are introduced...... into a fixed bed gasification plant to produce syngas which fuels the combined solid oxide fuel cells e organic Rankine cycle system to produce electricity. More than a hundred fluids are considered as possible alternative for the organic cycle using non-ideal equations of state (or state-of-the-art equations...... of state). A genetic algorithm is employed to select the optimal working fluid and the maximum pressure for the bottoming cycle. Thermodynamic and physical properties, environmental impacts and hazard specifications are also considered in the screening process. The results suggest that efficiencies...

  16. Enhancement of Electricity Production by Graphene Oxide in Soil Microbial Fuel Cells and Plant Microbial Fuel Cells

    OpenAIRE

    Goto, Yuko; Yoshida, Naoko; Umeyama, Yuto; Yamada, Takeshi; Tero, Ryugo; Hiraishi, Akira

    2015-01-01

    The effects of graphene oxide (GO) on electricity generation in soil microbial fuel cells (SMFCs) and plant microbial fuel cell (PMFCs) were investigated. GO at concentrations ranging from 0 to 1.9 g⋅kg−1 was added to soil and reduced for 10 days under anaerobic incubation. All SMFCs (GO-SMFCs) utilizing the soils incubated with GO produced electricity at a greater rate and in higher quantities than the SMFCs which did not contain GO. In fed-batch operations, the overall average electricity g...

  17. Guidebook on design, construction and operation of pilot plants for uranium ore processing

    International Nuclear Information System (INIS)

    The design, construction and operation of a pilot plant are often important stages in the development of a project for the production of uranium concentrates. Since building and operating a pilot plant is very costly and may not always be required, it is important that such a plant be built only after several prerequisites have been met. The main purpose of this guidebook is to discuss the objectives of a pilot plant and its proper role in the overall project. Given the wide range of conditions under which a pilot plant may be designed and operated, it is not possible to provide specific details. Instead, this book discusses the rationale for a pilot plant and provides guidelines with suggested solutions for a variety of problems that may be encountered. This guidebook is part of a series of Technical Reports on uranium ore processing being prepared by the IAEA's Division of Nuclear Fuel Cycle and Waste Management. 42 refs, 7 figs, 3 tabs

  18. Experiences on fuel and core design in Cofrentes nuclear power plants

    International Nuclear Information System (INIS)

    The electricity market deregulation in Spain is increasing the need for innovations and cost reductions in nuclear power production. In the fuel area this can be achieved by improving fuel and core designs and by introducing vendors competition. IBERDROLA has made significant efforts towards the introduction of mixed cores with fuel from different vendors at Cofrentes Nuclear Power Plant using the in-house nuclear design methodology (GIRALDA methodology) for design and licensing. The codes used in this methodology are independent from fuel vendors codes, thus permitting independent comparison of different types of fuel bundles. Commercial operation started in C. N. Cofrentes in 1984 with 12-month cycles at rated power. Both cycle length and thermal power have been increased, an the plant is currently operating cycle 13 at 104.2% power. There are plants to further update to 110% in cycle 14. The evolution in bundle geometrical design together with the vendors diversification program has resulted in mixed cores with bundles from the same supplier up to cycle 11, and from different suppliers thereafter. The experience acquired in nuclear design is reviewed in this paper. In particular, the following items are addressed, the following items are addressed: better core understanding, cooperation with fuel vendors; update of code versions; design margins; response to a fuel failure in cycle 12; comparison of core follow and design, auxiliary tools based on the design codes. The application of the GIRALDA methodology to the design and licensing of Cofrentes fuel loadings is giving satisfactory results. On the one hand, this methodology is showing its capability to adequately reproduce the core performance in cycles 12 and 13. On the other hand, the competition between fuel suppliers has led to fuel deregulated market. GIRALDA represents a continuous challenge for IBERDROLA and the main axis of its nuclear fuel management. (Author)

  19. System design methodology of non-fossil fuel fired power plants

    International Nuclear Information System (INIS)

    In most thermal system designs, economic and thermodynamic aspects of the design are not studied simultaneously early on in the design process. As a result, the economic ramification of thermodynamic changes to the system configuration, and vice versa, are not immediately apparent to the designer or the performance, involving both thermal and economic aspects of the plant. In this study, a rational approach is presented to formalize the design process of small power plants, typically, burning non-conventional fuel sources such as wood residues, tires, biofuels, etc. The method presented in this paper allows for handling of process information, both qualitative and quantitative, to enable the designer to change his design in an optimal manner. A two-level design structure (macro-level and micro-level), is introduced to enable the designer to adapt his design in an efficient manner to the available (or required) technology-level, type of application, economic factors, O and M requirements, etc. At the macro-level of design, economic feasibility (business) decisions are made, while at the micro-level of design, technical feasibility (engineering) decisions are made

  20. Integration of A Solid Oxide Fuel Cell into A 10 MW Gas Turbine Power Plant

    Directory of Open Access Journals (Sweden)

    Denver F. Cheddie

    2010-04-01

    Full Text Available Power generation using gas turbine power plants operating on the Brayton cycle suffers from low efficiencies. In this work, a solid oxide fuel cell (SOFC is proposed for integration into a 10 MW gas turbine power plant, operating at 30% efficiency. The SOFC system utilizes four heat exchangers for heat recovery from both the turbine outlet and the fuel cell outlet to ensure a sufficiently high SOFC temperature. The power output of the hybrid plant is 37 MW at 66.2% efficiency. A thermo-economic model predicts a payback period of less than four years, based on future projected SOFC cost estimates.

  1. 1986 fuel cell seminar: Program and abstracts

    Energy Technology Data Exchange (ETDEWEB)

    None

    1986-10-01

    Ninety nine brief papers are arranged under the following session headings: gas industry's 40 kw program, solid oxide fuel cell technology, phosphoric acid fuel cell technology, molten carbonate fuel cell technology, phosphoric acid fuel cell systems, power plants technology, fuel cell power plant designs, unconventional fuels, fuel cell application and economic assessments, and plans for commerical development. The papers are processed separately for the data base. (DLC)

  2. Development of Advanced Voloxidation Process for Treatment of Spent Fuel

    International Nuclear Information System (INIS)

    Data for evaluation of the effects of advanced voloxidation on pyroprocessing of spent oxide fuel with a determination for a path forward such was produced as follows: effect of particle size and particle structure on oxide reduction, assessment of decladding options for pyroprocessing, effect of removal timing of fission products, analysis of radioactivity and decay heat of advanced voloxidation process, proliferation resistance of advanced voloxidation process, Effect of advanced voloxidation process on shielding. Also, performance objectives for advanced voloxidation with respective to the down stream effects was established. The technology on design and manufacture of voloxidation and off gas treatment equipment was established. The possibility of fabrication of porous granule as a feed material for electro-reduction process was confirmed using rotary voloxidizer and SIMFUEL. The operational conditions for advanced voloxidation process consisting of 4 steps heat treatment was drawn to vaporize fission products and fabricate UO2 granule. The trapping test of Cs and Re(surrogate material of Tc) using newly developed filter were selectively separated at trapping efficiency of 99%, respectively. Data for oxidative decladding, vaporization rate of fission products, and particle size from experiment on voloxidation using spent fuel in ILN hot cell was acquisited including data of off gas trapping characteristics and verification of excellent performance of filter

  3. Quality control of CANDU6 fuel element in fabrication process

    International Nuclear Information System (INIS)

    To enhance the fine control over all aspects of the production process, improve product quality, fuel element fabrication process for CANDU6 quality process control activities carried out by professional technical and management technology combined mode, the quality of the fuel elements formed around CANDU6 weak links - - end plug , and brazing processes and procedures associated with this aspect of strict control, in improving staff quality consciousness, strengthening equipment maintenance, improved tooling, fixtures, optimization process test, strengthen supervision, fine inspection operations, timely delivery carry out aspects of the quality of information and concerns the production environment, etc., to find the problem from the improvement of product quality and factors affecting the source, and resolved to form the active control, comprehensive and systematic analysis of the problem of the quality management concepts, effectively reducing the end plug weld microstructure after the failure times and number of defects zirconium alloys brazed, improved product quality, and created economic benefits expressly provided, while staff quality consciousness and attention to detail, collaboration department, communication has been greatly improved and achieved very good management effectiveness. (authors)

  4. Inductive Double-Contingency Analysis of UO2 Powder Bulk Blending Operations at a Commercial Fuel Plant (U)

    International Nuclear Information System (INIS)

    An inductive double-contingency analysis (DCA) method developed by the criticality safety function at the Savannah River Site, was applied in Criticality Safety Evaluations (CSEs) of five major plant process systems at the Westinghouse Electric Corporation's Commercial Nuclear Fuel Manufacturing Plant in Columbia, South Carolina (WEC-Cola.). The method emphasizes a thorough evaluation of the controls intended to provide barriers against criticality for postulated initiating events, and has been demonstrated effective at identifying common mode failure potential and interdependence among multiple controls. A description of the method and an example of its application is provided

  5. A survey of methods for separating and immobilizing krypton-85 arising from a nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    This report reviews the literature on methods to separate and immobilize krypton-85 arising from dissolution or prior treatment of nuclear fuel in a reprocessing plant. It was prepared as part of a broader review of fuel reprocessing waste management methods that might find future applications in Canada. Cryogenic distillation is the most fully demonstrated method of separation of krypton from off-gases, but it is complex. In particular, it requires pretreatment of the gas stream to eliminate several other components before the final distillation. The most highly developed alternative process is fluorocarbon adsorption, while several other processes have been investigated on a bench scale. The simplest method of storing radioactive krypton is in compressed-gas cylinders, but the risks of accidental release are increased by the corrosive nature of the decay product, rubidium. Encapsulation in either a metal matrix or a hydrothermally vitrified zeolite appears to offer the most secure immobilization of krypton. Processes for both types of material have been demonstrated inactively on a scale approaching that required for treatment of off-gases from a commercial-scale fuel reprocessing plant. Low-operating temperatures and pressures of the metal encapsulation process, compared with encapsulation in zeolites, represent a definite advantage, but electrical power requirements for the former process are relatively high. It appears that suitable technology is available for separation and immobilization of radioactive krypton, should the need arise in Canada in the future

  6. Environmental assessment: Fuel processing restoration at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    The purpose of this Environmental Assessment (EA) is to provide sufficient evidence to assist DOE decision makers in determining whether to prepare an environmental impact statement or a finding of no significant impact for the proposed construction, operation, and decommissioning of the Fuel Processing Restoration (FPR) project at the Idaho National Engineering Laboratory (INEL). The FPR project includes (a) a replacement facility, to be called the Fuels Processing Facility (FPF), which would safely, efficiently, and effectively process recoverable irradiated naval and research reactor fuels to recover uranium for recycle and reuse in defense programs; and (b) a new liquid low-level waste (LLW) treatment and disposal system to improve waste management practices at the Idaho Chemical Processing Plant (ICPP). The EA examines and compares the environmental impacts of the proposed FPR project and reasonable alternatives at the ICPP. This Environmental Assessment (EA) has been prepared in accordance with the requirements of the National Environmental Policy Act of 1969, as amended (NEPA), and the requirements of the CEQ Regulations. 214 refs., 32 figs., 57 tabs

  7. High level waste vitrification at the SRP [Savannah River Plant] (DWPF [Defense Waste Processing Facility] summary)

    International Nuclear Information System (INIS)

    The Savannah River Plant has been operating a nuclear fuel cycle since the early 1950's. Fuel and target elements are fabricated and irradiated to produce nuclear materials. After removal from the reactors, the fuel elements are processed to extract the products, and waste is stored. During the thirty years of operation including evaporation, about 30 million gallons of high level radioactive waste has accumulated. The Defense Waste Processing Facility (DWPF) under construction at Savannah River will process this waste into a borosilicate glass for long-term geologic disposal. The construction of the DWPF is about 70% complete; this paper will describe the status of the project, including design demonstrations, with an emphasis on the melter system. 9 figs

  8. Review: Circulation of Inorganic Elements in Combustion of Alternative Fuels in Cement Plants

    DEFF Research Database (Denmark)

    Cortada Mut, Maria del Mar; Nørskov, Linda Kaare; Jappe Frandsen, Flemming;

    2015-01-01

    Cement production is an energy-intensive process, which traditionally has been dependent on fossil fuels. However, the use of alternative fuels, i.e., selected waste, biomass, and byproducts with recoverable calorific value, is constantly increasing. Combustion of these fuels is more challenging......, compared to fossil fuels, because of a lack of experience and different chemical and physical properties. When complete oxidation Of fuels in the calciner and main burner is not achieved, they burn in direct contact with the bed material of the rotary kiln, causing local reducing conditions and increasing...

  9. Hydrocarbon fuel processing of micro solid oxide fuel cell systems[Dissertation 17455

    Energy Technology Data Exchange (ETDEWEB)

    Stutz, M. J.

    2007-07-01

    The scope of this thesis is the numerical and experimental investigation of the fuel processing of a micro solid oxide fuel cell (SOFC) running on hydrocarbon fuel. The goal is to enhance the overall system efficiency by optimization of the reforming process in the steady state and the improvement of the start-up process. Micro SOFC are a potential alternative to the currently used batteries in portable devices. Liquid butane in a cartridge could be the energy source. This dissertation is focused on the fuel processing of the system, namely the reforming and post-combusting processes. The reformer converts the hydrocarbon fuel to a hydrogen rich gas that can be utilized by the SOFC. The post-combustor depletes the toxic and/or explosive gases before leaving the exhaust. Chapter One presents a short introduction to the field of hydrocarbon fuel processing in micro solid oxide fuel cell systems, the next three chapters deal with computational modeling of the transport phenomena inside a micro-reformer, which leads to a better understanding of the chemistry and the physics therein, hence progress in the design and operation parameters. The experimental part (i.e. Chapter Five) of this thesis focuses on the feasibility of a novel hybrid start-up method of a fuel cell system that employs existing components as an additional heat source. In Chapter Two the effect of wall heat conduction on the syngas (hydrogen and carbon monoxide) production of a micro-reformer, representing micro-fabricated channels or monoliths, is investigated. Methane is used as a model hydrocarbon fuel since its heterogeneous reaction path on rhodium is known and validated. The simulations demonstrate that the axial wall conduction strongly influences the performance of the micro-reformer and should not be neglected without a careful a priori investigation of its impact. Methane conversion and hydrogen yield are strongly dependent of the wall inner surface temperature, which is influenced by the

  10. CO₂ Capture Membrane Process for Power Plant Flue Gas

    Energy Technology Data Exchange (ETDEWEB)

    Toy, Lora [Research Triangle Inst. International, Research Triangle Park, NC (United States); Kataria, Atish [Research Triangle Inst. International, Research Triangle Park, NC (United States); Gupta, Raghubir [Research Triangle Inst. International, Research Triangle Park, NC (United States)

    2012-04-01

    Because the fleet of coal-fired power plants is of such importance to the nation's energy production while also being the single largest emitter of CO₂, the development of retrofit, post-combustion CO₂ capture technologies for existing and new, upcoming coal power plants will allow coal to remain a major component of the U.S. energy mix while mitigating global warming. Post-combustion carbon capture technologies are an attractive option for coal-fired power plants as they do not require modification of major power-plant infrastructures, such as fuel processing, boiler, and steam-turbine subsystems. In this project, the overall objective was to develop an advanced, hollow-fiber, polymeric membrane process that could be cost-effectively retrofitted into current pulverized coal-fired power plants to capture at least 90% of the CO₂ from plant flue gas with 95% captured CO₂ purity. The approach for this project tackled the technology development on three different fronts in parallel: membrane materials R&D, hollow-fiber membrane module development, and process development and engineering. The project team consisted of RTI (prime) and two industrial partners, Arkema, Inc. and Generon IGS, Inc. Two CO₂-selective membrane polymer platforms were targeted for development in this project. For the near term, a next-generation, high-flux polycarbonate membrane platform was spun into hollow-fiber membranes that were fabricated into both lab-scale and larger prototype (~2,200 ft²) membrane modules. For the long term, a new fluoropolymer membrane platform based on poly(vinylidene fluoride) [PVDF] chemistry was developed using a copolymer approach as improved capture membrane materials with superior chemical resistance to flue-gas contaminants (moisture, SO₂, NOx, etc.). Specific objectives were: - Development of new, highly chemically resistant, fluorinated polymers as membrane materials with minimum selectivity of 30 for CO₂ over N₂ and CO

  11. Development of a lignite-fired power plant concept with integrated pressurised fluidised-bed drying and fuel cells

    Energy Technology Data Exchange (ETDEWEB)

    Leidich, F.U.; Breitenfelder, R. [ALSTOM Power Generation AG, Mannheim (Germany); Mandel, H. [Vattenfall Europe Generation AG and Co., Cottbus (Germany); Krautz, J. [Technical Univ., Cottbus (Germany); Gniazdowski, M. [Babcock Borsik Service GmbH, Oberhausen (Germany)

    2005-07-01

    In the coming decades, lignite will become one of the most important fuels for power production in Germany. In the last five years, Vattenfall Europe and RWE have put power plants of the 800-1000 MW class with efficiency of up to more than 43% into service. Four to five per cent efficiency can further be gained by using pre-dried lignite as fuel (BOA plus concept of RWE). Additional steps are possible if the lignite-drying process and combustion are operated under pressure. This paper describes the first steps based on the A.M. technology whereby the waste heat of fuel cells is used for operation of the lignite dryer to achieve highest efficiency levels. (author)

  12. Fossil fuel biomarkers in plant waxes as pollution parameters

    OpenAIRE

    Bryselbout, Carine; Henner, Pascale; Lichtfouse, Eric

    1998-01-01

    International audience; Hopane and sterane derivatives typical of highly mature sedimentary organic matter, e.g. petroleum, have been identified in several plant species growing near Nancy, France. Analyses of plant waxes by gas chromatography-mass spectrometry over a restricted mass interval (m/z 185-195) allows definition of pollution parameters based on the relative concentration of fossil hopanes versus modern plant n alkanes. Indeed, such parameters are higher for Pinus nigra growing alo...

  13. Thermodynamic analyses of municipal solid waste gasification plant integrated with solid oxide fuel cell and Stirling hybrid system

    DEFF Research Database (Denmark)

    Rokni, Masoud

    2015-01-01

    is subject to chemical treatments through air or/and steam utilization; the result is a synthesis gas, called "Syngas" which is principally composed of hydrogen and carbon monoxide. Traces of hydrogen sulfide could also be present which can easily be separated in a desulfurization reactor. The gasification...... process is usually based on an atmospheric-pressure circulating fluidized bed gasifier coupled to a tar-cracking vessel. Syngas can be used as fuel in different kind of power plant such as gas turbine cycle, steam cycle, combined cycle, internal and external combustion engine and Solid Oxide Fuel Cell...... with incineration technologies. Moreover waste incinerators require the installation of sophisticated exhaust gas cleaning equipment that can be large and expensive and are not necessary in the studied plant....

  14. Plate-Based Fuel Processing System Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Carlos Faz; Helen Liu; Jacques Nicole; David Yee

    2005-12-22

    On-board reforming of liquid fuels into hydrogen is an enabling technology that could accelerate consumer usage of fuel cell powered vehicles. The technology would leverage the convenience of the existing gasoline fueling infrastructure while taking advantage of the fuel cell efficiency and low emissions. Commercial acceptance of on-board reforming faces several obstacles that include: (1) startup time, (2) transient response, and (3) system complexity (size, weight and cost). These obstacles are being addressed in a variety of projects through development, integration and optimization of existing fuel processing system designs. In this project, CESI investigated steam reforming (SR), water-gas-shift (WGS) and preferential oxidation (PrOx) catalysts while developing plate reactor designs and hardware where the catalytic function is integrated into a primary surface heat exchanger. The plate reactor approach has several advantages. The separation of the reforming and combustion streams permits the reforming reaction to be conducted at a higher pressure than the combustion reaction, thereby avoiding costly gas compression for combustion. The separation of the two streams also prevents the dilution of the reformate stream by the combustion air. The advantages of the plate reactor are not limited to steam reforming applications. In a WGS or PrOx reaction, the non-catalytic side of the plate would act as a heat exchanger to remove the heat generated by the exothermic WGS or PrOx reactions. This would maintain the catalyst under nearly isothermal conditions whereby the catalyst would operate at its optimal temperature. Furthermore, the plate design approach results in a low pressure drop, rapid transient capable and attrition-resistant reactor. These qualities are valued in any application, be it on-board or stationary fuel processing, since they reduce parasitic losses, increase over-all system efficiency and help perpetuate catalyst durability. In this program, CESI

  15. Technical considerations in repowering a nuclear plant for fossil fueled operation

    International Nuclear Information System (INIS)

    Repowering involves replacement of the reactor by a fossil fuel source of steam. This source can be a conventional fossil fueled boiler or the heat recovery steam generator (HRSG) on a gas turbine exhaust. The existing steam turbine plant is used to the extent possible. Alternative fuels for repowering a nuclear plant are coal, natural gas and oil. In today's world oil is not usually an alternative. Selection of coal or natural gas is largely a matter of availability of the fuel near the location of the plant. Both the fossil boiler and the HRSG produce steam at higher pressures and temperatures than the throttle conditions for a saturated steam nuclear turbine. It is necessary to match the steam conditions from the new source to the existing turbine as closely as possible. Technical approaches to achieve a match range from using a topping turbine at the front end of the cycle to attemperation of the throttle steam with feedwater. The electrical output from the repowered plant is usually greater than that of the original nuclear fueled design. This requires consideration of the ability to use the excess electricity. Interfacing of the new facility with the existing turbine plant requires consideration of facility layout and design. Site factors must also be considered, especially for a coal fired boiler, since rail and coal handling facilities must be added to a site for which these were not considered. Additional site factors that require consideration are ash handling and disposal

  16. Special considerations on operating a fuel cell power plant using natural gas with marginal heating value

    Energy Technology Data Exchange (ETDEWEB)

    Moses, L. Ng; Chien-Liang Lin [Industrial Technology Research Institute, Taiwan (China); Ya-Tang Cheng [Power Research Institute, Taiwan (China)

    1996-12-31

    In realizing new power generation technologies in Taiwan, a phosphoric acid fuel cell power plant (model PC2513, ONSI Corporation) has been installed in the premises of the Power Research Institute of the Taiwan Power Company in Taipei County of Taiwan. The pipeline gas supplying to the site of this power plant has a high percentage of carbon dioxide and thus a slightly lower heating value than that specified by the manufacturer. Because of the lowering of heating value of input gas, the highest Output power from the power plant is understandably less than the rated power of 200 kW designed. Further, the transient response of the power plant as interrupted from the Grid is also affected. Since this gas is also the pipeline gas supplying to the heavily populated Taipei Municipal area, it is conceivable that the success of the operations of fuel cells using this fuel is of vital importance to the promotion of the use of this power generation technology in Taiwan. Hence, experiments were set up to assess the feasibility of this fuel cell power plant using the existing pipeline gas in this part of Taiwan where fuel cells would most likely find useful.

  17. Mechanical separation process for decladding of LWR fuel elements

    International Nuclear Information System (INIS)

    A comparison of the advantages and disadvantages of known methods of decladding led to cavitation erosion being used as a decladding mechanism. This process attacks not the jacket of the fuel rod but the fuel itself. Cavitation erosion is the consequence of imploding vapour bubbles entailing dynamic stress of a high frequency and high amplitude. The separation effect is due to the different material properties. Ductile materials as a rule are much more resistant to dynamic stress than brittle materials. Systematic experiments at varying pressures, volume flow, nozzle geometries and distances between nozzle and sample led to optimized parameters. There was a conspicuous rise in the relations pressure to depth of erosion and volume flow to depth of erosion. This considered, p=700 bar and d=1.6 mm were found to be useful parameters. The relation of the distance from nozzle to sample and the erosion obtained also has an optimum at s=50 mm. This distance can be shortened in the course of the operation. A great entrance angle combined with a nozzle outlet channel of the length l=1/2 D improves the erosion result considerably. The attack of the cavitating water jet on the jacket of the fuel rod causes a weight loss of <=2per mille. (orig./HP)

  18. A CFD Simulation Process for Fast Reactor Fuel Assemblies

    Energy Technology Data Exchange (ETDEWEB)

    Kurt D. Hamman; Ray A. Berry

    2010-09-01

    A CFD modeling and simulation process for large-scale problems using an arbitrary fast reactor fuel assembly design was evaluated. Three-dimensional flow distributions of sodium for several fast reactor fuel assembly pin spacing configurations were simulated on high performance computers using commercial CFD software. This research focused on 19-pin fuel assembly “benchmark” geometry, similar in design to the Advanced Burner Test Reactor, where each pin is separated by helical wire-wrap spacers. Several two-equation turbulence models including the k–e and SST (Menter) k–? were evaluated. Considerable effort was taken to resolve the momentum boundary layer, so as to eliminate the need for wall functions and reduce computational uncertainty. High performance computers were required to generate the hybrid meshes needed to predict secondary flows created by the wire-wrap spacers; computational meshes ranging from 65 to 85 million elements were common. A general validation methodology was followed, including mesh refinement and comparison of numerical results with empirical correlations. Predictions for velocity, temperature, and pressure distribution are shown. The uncertainty of numerical models, importance of high fidelity experimental data, and the challenges associated with simulating and validating large production-type problems are presented.

  19. A CFD simulation process for fast reactor fuel assemblies

    Energy Technology Data Exchange (ETDEWEB)

    Hamman, Kurt D., E-mail: Kurt.Hamman@inl.go [Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-3840 (United States); Berry, Ray A. [Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-3840 (United States)

    2010-09-15

    A CFD modeling and simulation process for large-scale problems using an arbitrary fast reactor fuel assembly design was evaluated. Three-dimensional flow distributions of sodium for several fast reactor fuel assembly pin spacing configurations were simulated on high performance computers using commercial CFD software. This research focused on 19-pin fuel assembly 'benchmark' geometry, similar in design to the Advanced Burner Test Reactor, where each pin is separated by helical wire-wrap spacers. Several two-equation turbulence models including the k-{epsilon} and SST (Menter) k-{omega} were evaluated. Considerable effort was taken to resolve the momentum boundary layer, so as to eliminate the need for wall functions and reduce computational uncertainty. High performance computers were required to generate the hybrid meshes needed to predict secondary flows created by the wire-wrap spacers; computational meshes ranging from 65 to 85 million elements were common. A general validation methodology was followed, including mesh refinement and comparison of numerical results with empirical correlations. Predictions for velocity, temperature, and pressure distribution are shown. The uncertainty of numerical models, importance of high fidelity experimental data, and the challenges associated with simulating and validating large production-type problems are presented.

  20. Experience of MOX-fuel operation in the Gundremmingen BWR plant: Nuclear characteristics and in-core fuel management

    International Nuclear Information System (INIS)

    After 4 years of good experience with MOX-fuel operation in the BWR plants Gundremmingen units B and C the number of inserted MOX-FAs will be increased in the future continuously. Until now all MOX-FAs are in good condition. Furthermore calculations and measurements concerning zero power tests and tip measurements are in good agreement as expected: all results lead to the conclusion that MOX-FAs can be calculated with the same precision as uranium-FAs. (author)

  1. ADVANCED HYDROGEN TRANSPORT MEMBRANES FOR VISION 21 FOSSIL FUEL PLANTS

    Energy Technology Data Exchange (ETDEWEB)

    Shane E. Roark; Anthony F. Sammells; Richard Mackay; Stewart R. Schesnack; Scott R. Morrison; Thomas F. Barton; Sara L. Rolfe; U. Balachandran; Richard N. Kleiner; James E. Stephan; Frank E. Anderson; Aaron L. Wagner; Jon P. Wagner

    2003-10-30

    Eltron Research Inc. and team members CoorsTek, Sued Chemie, Argonne National Laboratory, and NORAM are developing an environmentally benign, inexpensive, and efficient method for separating hydrogen from gas mixtures produced during industrial processes, such as coal gasification. This project was motivated by the National Energy Technology Laboratory (NETL) Vision 21 initiative, which seeks to economically eliminate environmental concerns associated with the use of fossil fuels. Over the past 12 months, this project has focused on four basic categories of dense membranes: (1) mixed conducting ceramic/ceramic composites, (2) mixed conducting ceramic/metal (cermet) composites, (3) cermets with hydrogen permeable metals, and (4) layered composites containing hydrogen permeable alloys. Ultimately, these materials must enable hydrogen separation at practical rates under ambient and high-pressure conditions, without deactivation in the presence of feedstream components such as carbon dioxide, water, and sulfur. The ceramic/ceramic composites demonstrate the lowest hydrogen permeation rates, with a maximum of approximately 0.1 mL/min/cm{sup 2} for 0.5-mm thick membranes at 800 to 950 C. Under equivalent conditions, cermets achieve a hydrogen permeation rate near 1 mL/min/cm{sup 2}, and the metal phase also improves structural stability and surface catalysis for hydrogen dissociation. Furthermore, if metals with high hydrogen permeability are used in cermets, permeation rates near 4 mL/min/cm{sup 2} are achievable with relatively thick membranes. Layered composite membranes have by far the highest permeation rates with a maximum flux in excess of 200 mL {center_dot} min{sup -1} {center_dot} cm{sup -2}. Moreover, these permeation rates were achieved at a total pressure differential across the membrane of 450 psi. Based on these results, effort during the next year will focus on this category of membranes. This report contains long-term hydrogen permeation data over eight

  2. Improving cost-effectiveness for the furnace in a full-scale refinery plant with reuse of waste tail gas fuel

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chien-Li [Department of Leisure and Recreation Management, Diwan University, Tainan (China); Hou, Shuhn-Shyurng [Department of Mechanical Engineering, Kun Shan University (China); Lee, Wen-Jhy [Department of Environmental Engineering, National Cheng Kung University (China); Jou, Chih-Ju G. [Department of Safety, Health and Environmental Engineering, National Kaohsiung First University of Science and Technology, 2, Juoyue Rd., Nantz District, Kaohsiung 811 (China)

    2010-02-15

    The waste tail gas fuel emitted from refinery plant in Taiwan e.g. catalytic reforming unit, catalytic cracking unit and residue desulfurization unit, was recovered and reused as a replacement fuel. In this study, it was slowly added to the fuel stream of a heater furnace to replace natural gas for powering a full-scale distillation process. The waste tail gas fuel contained on average 60 mol% of hydrogen. On-site experimental results show that both the flame length and orange-yellowish brightness decrease with increasing proportion of waste gas fuel in the original natural gas fuel. Moreover, the adiabatic flame temperature increases as the content of waste gas fuel is increased in the fuel mixture since waste gas fuel has a higher adiabatic flame temperature than that of natural gas. The complete replacement of natural gas by waste gas fuel for a heater furnace operating at 70% loading (i.e. 3.6 x 10{sup 7} kcal/h of combustion capacity) will save 5.8 x 10{sup 6} m{sup 3} of natural gas consumption, and 3.5 x 10{sup 4} tons (or 53.4%) of CO{sub 2} emission annually. Recovering and reusing the waste tail gas fuel as natural gas replacement will achieve tremendous savings of natural gas usage and effectively lower the emission of carbon dioxide. (author)

  3. Radioactive waste management plan for PBMR (pty) ltd fuel plant - HTR2008-58247

    International Nuclear Information System (INIS)

    The Pebble Bed Modular Reactor (Pty) Ltd Fuel Plant (PFP) radioactive waste management plan caters for waste from generation, processing through storage and possible disposal. Generally, the amount of waste that will be generated from the PFP is Low and Intermediate Level Waste. The waste management plan outlines all waste streams and the management options for each stream. It also discusses how the Plant has been designed to ensure radioactive waste minimisation through recycling, recovery, reuse, treatment before considering disposal. Compliance to the proposed plan will ensure compliance with national legislative requirements and international good practice. The national and the overall waste management objective is to ensure that all PFP wastes are managed appropriately by capitalising on processes that minimise, reduce, recover and recycle without exposing employees, the public and the environment to unmitigated impacts. Both International Atomic Energy Agency (IAEA) and Dept. of Minerals and Energy (DME) principles act as a guide in the development of the strategy in order to ensure international best practice, legal compliance and ensuring that the impact of waste on employees, environment and the public is as low as reasonably achievable. The radioactive waste classification system stipulated in the Radioactive Waste Management Policy and Strategy 2005 will play an important role in classifying radioactive waste and ensuring that effective management is implemented for all waste streams be it gaseous, liquid or solid waste. (authors)

  4. Radioactive waste management plan for the PBMR (Pty) Ltd fuel plant

    International Nuclear Information System (INIS)

    The Pebble Bed Modular Reactor (Pty) Ltd Fuel Plant (PFP) radioactive waste management plan caters for waste from generation, processing through storage and possible disposal. Generally, the amount of waste that will be generated from the PFP is Low and Intermediate Level Waste. The waste management plan outlines all waste streams and the management options for each stream. It also discusses how the Plant has been designed to ensure radioactive waste minimisation through recycling, recovery, reuse, treatment before considering disposal. Compliance to the proposed plan will ensure compliance with national legislative requirements and international good practice. The national and the overall waste management objective is to ensure that all PFP wastes are managed appropriately by utilising processes that minimize, reduce, recover and recycle without exposing employees, the public and the environment to unacceptable impacts. Both International Atomic Energy Agency (IAEA) and Department of Minerals and Energy (DME) principles act as a guide in the development of the strategy in order to ensure international best practice, legal compliance and ensuring that the impact of waste on employees, environment and the public is as low as reasonably achievable. The radioactive waste classification system stipulated in the Radioactive Waste Management Policy and Strategy 2005 will play an important role in classifying radioactive waste and ensuring that effective management is implemented for all waste streams, for example gaseous, liquid or solid wastes.

  5. Computational fluid dynamics (CFD) analysis of the combustion process of a leather residuals gasification fuel gas: influence of fuel moisture content

    Energy Technology Data Exchange (ETDEWEB)

    Antonietti, Anderson Jose; Beskow, Arthur Bortolin; Silva, Cristiano Vitorino da [Universidade Regional Integrada do Alto Uruguai e das Missoes (URI), Erechim, RS (Brazil)], E-mails: arthur@uricer.edu.br, mlsperb@unisinos.br; Indrusiak, Maria Luiza Sperb [Universidade do Vale do Rio dos Sinos (UNISINOS), Sao Leopoldo, RS (Brazil)], E-mail: cristiano@uricer.edu.br

    2010-07-01

    This work presents a numerical study of the combustion process of leather residuals gasification gas, aiming the improvement of the process efficiency, considering different concentrations of water on the gas. The heating produced in this combustion process can be used to generation of thermal and/or electrical energy, for use at the leather industrial plant. However, the direct burning of this leather-residual-gas into the chambers is not straightforward. The alternative in development consists in processing this leather residuals by gasification or pyrolysis, separating the volatiles and products of incomplete combustion, for after use as fuel in a boiler. At these processes, different quantities of water can be used, resulting at different levels of moisture content in this fuel gas. This humidity can affect significantly the burning of this fuel, producing unburnt gases, as the carbon monoxide, or toxic gases as NOx, which must have their production minimized on the process, with the purpose of reducing the emission of pollutants to the atmosphere. Other environment-harmful-gases, remaining of the chemical treatment employed at leather manufacture, as cyanide, and hydrocarbons as toluene, must burn too, and the moisture content has influence on it. At this way, to increase understanding of the influence of moisture in the combustion process, it was made a numerical investigation study of reacting flow in the furnace, evaluating the temperature field, the chemical species concentration fields, flow mechanics and heat transfer at the process. The commercial CFD code CFX Ansys Inc. was used. Considering different moisture contents in the fuel used on the combustion process, with this study was possible to achieve the most efficient burning operation parameters, with improvement of combustion efficiency, and reduction of environmental harmful gases emissions. It was verified that the different moisture contents in the fuel gas demand different operation conditions

  6. Processes for converting methane to liquid fuels: economic screening through energy management

    International Nuclear Information System (INIS)

    Numerous process schemes have been proposed for converting methane to liquid hydrocarbon fuels. Economic evaluation studies generally conclude that none except the best of these schemes are attractive at present oil prices of < 20 $/bbl. Simple arguments are presented here to show why methane conversion processes are now not economically attractive and what needs to be done to improve on their economics. Particularly, an analysis of numerous fuel manufacturing processes based on coal, oil and gas feedstock will show the need to increase the plant scale, and reduce the energy losses as well as the overall heat and momentum transfer duty. Furthermore, simple calculations of the overall transfer duty of various methane conversion routes for liquid fuel manufacture allow us to rank them according to their expected capital cost and identify the improvements required for making each route competitive with the cheapest scheme identified here. The conversion routes considered here include methane pyrolysis, oxidative coupling, partial oxidation to methanol, methylchloride and methylbisulfate as well as commercial routes based on synthesis gas. (author)

  7. Leaked fuel detection device for nuclear power plant

    International Nuclear Information System (INIS)

    The present invention provides an inexpensive fuel leak detection device at a good detection sensitivity and of a simple structure. Specifically, the device of the present invention comprises (1) a sampling means for sampling water from a nuclear fuel mast tube, (2) a gas separation means for introducing sampled water to a separation chamber, jetting and stirring it in the separation chamber to separate gases, (3) a gas recycling means for delivering the gases in the separation chamber and returning them again, and (4) a measuring means for measuring radiation dose of the gases circulated by the gas circulation means. Since the device thus constituted has a simple gas separation means, the structure of the nuclear fuel mast tube is not complicated. Since the gas is recycled, the volume for the gas portion is reduced, so that the amount of the fission products per a predetermined volume is increased and the sensitivity for the leaked fuel detection is increased. Since the structure is simple, the cost can be reduced. (I.S.)

  8. Information interfaces for process plant diagnosis

    International Nuclear Information System (INIS)

    The paper describes a systematic approach to the design of information interfaces for operator support in diagnosing complex systems faults. The need of interpreting primary measured plant variables within the framework of different system representations organized into an abstraction hierarchy is identified from an analysis of the problem of diagnosing complex systems. A formalized approach to the modelling of production systems, called Multilevel Flow Modelling, is described. A MFM model specifies plant control requirements and the associated need for plant information and provide a consistent context for the interpretation of real time plant signals in diagnosis of malfunctions. The use of MFM models as a basis for functional design of the plant instrumentation system is outlined, and the use of knowledge Based (Expert) Systems for the design of man-machine interfaces is mentioned. Such systems would allow an active user participation in diagnosis and thus provide the basis for cooperative problem solving. 14 refs. (author)

  9. Interim storage of spent fuel assemblies from VVER-reactors, taking as an example the cask dry storage for the Czech Dukovany Nuclear Power Plant

    International Nuclear Information System (INIS)

    The nuclear fuel cycle services from the former Soviet Union were fundamentally changed in 1989. The necessity of intermediate spent fuel storage increased in Czechoslovakia in short term. After performing an international comparison and request for proposals, Czechoslovakia represented by the electrical utility CEZ in Prague, decided in favor of a dry cask storage concept for the nuclear power plant Dukovany. The selection process among the offered solutions and the dry cask storage concept is discussed

  10. Compact spent fuel storage at the Atucha I nuclear power plant

    International Nuclear Information System (INIS)

    The object of this report is to verify the possibility to increase the available storage of irradiated fuel assemblies, placed in the spent fuel pools of the Atucha I nuclear power plant. There is intends the realization of structural modifications in the storage bracket-suspension beam (single and double) for the upper and lower level of the four spent fuel pools. With these modifications that increase the storage capacity 25%, would arrive until the year 2014, it dates dear for the limit of the commercial operation of nuclear power plant. The increase of the capacity in function of the permissible stress for the supports of the bracket-suspension beam. They should be carried out 5000 re-accommodations of irradiated fuel assemblies. The task would demand approximately 3 years. (author)

  11. Power conversion and quality of the Santa Clara 2 MW direct carbonate fuel cell demonstration plant

    Energy Technology Data Exchange (ETDEWEB)

    Skok, A.J. [Fuel Cell Engineering Corp., Danbury, CT (United States); Abueg, R.Z. [Basic Measuring Instruments, Santa Clara, CA (United States); Schwartz, P. [Fluor Daniel, Inc., Irvine, CA (United States)] [and others

    1996-12-31

    The Santa Clara Demonstration Project (SCDP) is the first application of a commercial-scale carbonate fuel cell power plant on a US electric utility system. It is also the largest fuel cell power plant ever operated in the United States. The 2MW plant, located in Santa Clara, California, utilizes carbonate fuel cell technology developed by Energy Research Corporation (ERC) of Danbury, Connecticut. The ultimate goal of a fuel cell power plant is to deliver usable power into an electrical distribution system. The power conversion sub-system does this for the Santa Clara Demonstration Plant. A description of this sub-system and its capabilities follows. The sub-system has demonstrated the capability to deliver real power, reactive power and to absorb reactive power on a utility grid. The sub-system can be operated in the same manner as a conventional rotating generator except with enhanced capabilities for reactive power. Measurements demonstrated the power quality from the plant in various operating modes was high quality utility grade power.

  12. Binary co-generation power plant with night-temperature (SOFC) fuel cells of natural gas, v. 15(57)

    International Nuclear Information System (INIS)

    Binary co-generation power plant with height-temperature SOFC fuel cells of natural gas are presented in this paper. Based on before optimization calculations for this type of power plants is made: basic measures, number of modules, electric power and fuel cell efficiency; gas turbine electric power and efficiency; co-generation steam turbine electric and heat power efficiency. Compare analysis of binary co-generation power plant with SOFC fuel cells and co-generative power plant without fuel cells in relation of efficiency, ecological benefits and profitability (economy analysis) is given. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

    1994-05-01

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

  14. Processing and properties of a solid energy fuel from municipal solid waste (MSW) and recycled plastics.

    Science.gov (United States)

    Gug, JeongIn; Cacciola, David; Sobkowicz, Margaret J

    2015-01-01

    Diversion of waste streams such as plastics, woods, papers and other solid trash from municipal landfills and extraction of useful materials from landfills is an area of increasing interest especially in densely populated areas. One promising technology for recycling municipal solid waste (MSW) is to burn the high-energy-content components in standard coal power plant. This research aims to reform wastes into briquettes that are compatible with typical coal combustion processes. In order to comply with the standards of coal-fired power plants, the feedstock must be mechanically robust, free of hazardous contaminants, and moisture resistant, while retaining high fuel value. This study aims to investigate the effects of processing conditions and added recyclable plastics on the properties of MSW solid fuels. A well-sorted waste stream high in paper and fiber content was combined with controlled levels of recyclable plastics PE, PP, PET and PS and formed into briquettes using a compression molding technique. The effect of added plastics and moisture content on binding attraction and energy efficiency were investigated. The stability of the briquettes to moisture exposure, the fuel composition by proximate analysis, briquette mechanical strength, and burning efficiency were evaluated. It was found that high processing temperature ensures better properties of the product addition of milled mixed plastic waste leads to better encapsulation as well as to greater calorific value. Also some moisture removal (but not complete) improves the compacting process and results in higher heating value. Analysis of the post-processing water uptake and compressive strength showed a correlation between density and stability to both mechanical stress and humid environment. Proximate analysis indicated heating values comparable to coal. The results showed that mechanical and moisture uptake stability were improved when the moisture and air contents were optimized. Moreover, the briquette

  15. Processing and properties of a solid energy fuel from municipal solid waste (MSW) and recycled plastics.

    Science.gov (United States)

    Gug, JeongIn; Cacciola, David; Sobkowicz, Margaret J

    2015-01-01

    Diversion of waste streams such as plastics, woods, papers and other solid trash from municipal landfills and extraction of useful materials from landfills is an area of increasing interest especially in densely populated areas. One promising technology for recycling municipal solid waste (MSW) is to burn the high-energy-content components in standard coal power plant. This research aims to reform wastes into briquettes that are compatible with typical coal combustion processes. In order to comply with the standards of coal-fired power plants, the feedstock must be mechanically robust, free of hazardous contaminants, and moisture resistant, while retaining high fuel value. This study aims to investigate the effects of processing conditions and added recyclable plastics on the properties of MSW solid fuels. A well-sorted waste stream high in paper and fiber content was combined with controlled levels of recyclable plastics PE, PP, PET and PS and formed into briquettes using a compression molding technique. The effect of added plastics and moisture content on binding attraction and energy efficiency were investigated. The stability of the briquettes to moisture exposure, the fuel composition by proximate analysis, briquette mechanical strength, and burning efficiency were evaluated. It was found that high processing temperature ensures better properties of the product addition of milled mixed plastic waste leads to better encapsulation as well as to greater calorific value. Also some moisture removal (but not complete) improves the compacting process and results in higher heating value. Analysis of the post-processing water uptake and compressive strength showed a correlation between density and stability to both mechanical stress and humid environment. Proximate analysis indicated heating values comparable to coal. The results showed that mechanical and moisture uptake stability were improved when the moisture and air contents were optimized. Moreover, the briquette

  16. Nitrification Processes in Tehran Wastewater Treatment Plant

    OpenAIRE

    S. A. Sadrnejad

    2011-01-01

    A wastewater treatment plant is designed to daily treat 450000 m3 of wastewater collected from the city of Tehran. The wastewater treatment plant is located at the south of Shahr-Ray in southern Tehran with the area of 110 hectares. The treatment plant effluent will be transferred to Varamin agricultural lands to be used for the irrigation of crops. A conventional activated sludge for carbon removal and a high-rate trickling filter for nitrification of ammonia to nitrate are designed and cons...

  17. Plant Characteristics af a Multi-Fuel Sofc-Stirling Hybrid Configuration

    DEFF Research Database (Denmark)

    Rokni, Masoud

    2012-01-01

    A novel hybrid system ( kWe) for an average family house including heating is proposed. The system investigated, contains of a Solid Oxide Fuel Cell (SOFC) on top of a Stirling engine. The off-gases produced in the SOFC cycle is fed to the bottoming Stirling engine wherein additional power...... is generated. Simulations for the proposed system were conducted using different fuels which facilitate use of variety of fuels depending on availability. Here, results for Natural Gas (NG), ammonia, Di-Methyl Ether (DME), methanol and ethanol are presented and analysed. System behaviour is further...... investigated by comparing the effects of key factors such as: utilisation factor, operating conditions, Oxygen-to-Carbon (O/C) ratios and fuel preheating effects on these fuels. Moreover, effect of Methanator on plant efficiency is also studied. The combined system improves the overall electrical conversion...

  18. Identification of fuel effluents in waste water. Its influence in depuration process by active sludges. Identificacion de vertidos combustibles en agua residual. Su influencia en el proceso de depuracion por fongos activos

    Energy Technology Data Exchange (ETDEWEB)

    Parody, F.; Rebollo, M.C.; Azcarate, J.; Sammillan, I.; Beltran, V.M. (Ayuntamiento de Madrid (Spain))

    1994-01-01

    Frequently, fuel effluents are found in treatment water plants. This effluents are nocives for the biologic process. In this work the authors present an easy method for characterizing the fuel wastes in waste water and its chromatografic characterization in the water treatment plant in Madrid (Spain).

  19. Application of digital image processing for pot plant grading.

    NARCIS (Netherlands)

    Dijkstra, J.

    1994-01-01

    The application of digital image processing for grading of pot plants has been studied. Different techniques e.q. plant part identification based on knowledge based segmentation, have been developed to measure features of plants in different growth stage. Growth experiments were performed to identif

  20. A high-temperature gas-and-steam turbine plant operating on combined fuel

    Science.gov (United States)

    Klimenko, A. V.; Milman, O. O.; Shifrin, B. A.

    2015-11-01

    A high-temperature gas-steam turbine plant (GSTP) for ultrasupercritical steam conditions is proposed based on an analysis of prospects for the development of power engineering around the world and in Russia up to 2040. The performance indicators of a GSTP using steam from a coal-fired boiler with a temperature of 560-620°C with its superheating to 1000-1500°C by firing natural gas with oxygen in a mixingtype steam superheater are analyzed. The thermal process circuit and design of a GSTP for a capacity of 25 MW with the high- and intermediate-pressure high-temperature parts with the total efficiency equal to 51.7% and the natural gas utilization efficiency equal to 64-68% are developed. The principles of designing and the design arrangement of a 300 MW GSTP are developed. The effect of economic parameters (the level and ratio of prices for solid fuel and gas, and capital investments) on the net cost of electric energy is determined. The net cost of electric energy produced by the GSTP is lower than that produced by modern combined-cycle power plants in a wide variation range of these parameters. The components of a high-temperature GSTP the development of which determines the main features of such installations are pointed out: a chamber for combusting natural gas and oxygen in a mixture with steam, a vacuum device for condensing steam with a high content of nondensables, and a control system. The possibility of using domestically available gas turbine technologies for developing the GSTP's intermediate-pressure high-temperature part is pointed out. In regard of its environmental characteristics, the GSTP is more advantageous as compared with modern condensing power plants: it allows a flow of concentrated carbon dioxide to be obtained at its outlet, which can be reclaimed; in addition, this plant requires half as much consumption of fresh water.

  1. Indirect thermal liquefaction process for producing liquid fuels from biomass

    Energy Technology Data Exchange (ETDEWEB)

    Kuester, J.L.

    1980-01-01

    A progress report on an indirect liquefaction process to convert biomass type materials to quality liquid hydrocarbon fuels by gasification followed by catalytic liquid fuels synthesis has been presented. A wide variety of feedstocks can be processed through the gasification system to a gas with a heating value of 500 + Btu/SCF. Some feedstocks are more attractive than others with regard to producing a high olefin content. This appears to be related to hydrocarbon content of the material. The H/sub 2//CO ratio can be manipulated over a wide range in the gasification system with steam addition. Some feedstocks require the aid of a water-gas shift catalyst while others appear to exhibit an auto-catalytic effect to achieve the conversion. H/sub 2/S content (beyond the gasification system wet scrubber) is negligible for the feedstocks surveyed. The water gas shift reaction appears to be enhanced with an increase in pyrolysis reactor temperature over the range of 1300 to 1700/sup 0/F. Reactor temperature in the Fischer-Tropsch step is a significant factor with regard to manipulating product composition analysis. The optimum temperature however will probably correspond to maximum conversion to liquid hydrocarbons in the C/sub 5/ - C/sub 17/ range. Continuing research includes integrated system performance assessment, alternative feedstock characterization (through gasification) and factor studies for gasification (e.g., catalyst usage, alternate heat transfer media, steam usage, recycle effects, residence time study) and liquefaction (e.g., improved catalysts, catalyst activity characterization).

  2. Binary co-generative plants with height temperature SOFC fuel cells

    International Nuclear Information System (INIS)

    In this paper, a field of binary co-generative plants with height temperature SOFC fuel cells is presented. Special attention of application of height temperature SOFC fuel cells and binary co-generative units has been given. These units made triple electricity and heat. Principle of combination of fuel cells with binary cycles has been presented. A model and computer programme for calculation of BKPFC, has been created. By using the program, all the important characteristic-results are calculated: power, efficiency, emission, dimension and economic analysis. On base of results, conclusions and recommendations has been given. (Author)

  3. CARA CVN: inherently safe fuel element for PHWR power plants

    International Nuclear Information System (INIS)

    This paper presents design alternatives of the CARA fuel element with negative void reactivity coefficient (CVN) enhancing the PHWR safety for L-LOCA sequences. This design enhances the safety and the operation performance in Atucha and Embalse without changes in the operation conditions. This new design balances wide performance margins of CARA SEU 0.9% previous design, with new intrinsic safety requirements without economic penalties. (author)

  4. The Carnol process for CO{sub 2} mitigation from power plants and the transportation sector

    Energy Technology Data Exchange (ETDEWEB)

    Steinberg, M.

    1995-08-01

    A CO{sub 2} mitigation process is developed which converts waste CO{sub 2}, primarily recovered from coal-fired power plant stack gases with natural gas, to produce methanol as a liquid fuel and coproduct carbon as a materials commodity. The Carnol process chemistry consists of methane decomposition to produce hydrogen which is catalytically reacted with the recovered waste CO{sub 2} to produce methanol. The carbon is either stored or sold as a materials commodity. A process design is modelled and mass and energy balances are presented as a function of reactor pressure and temperature conditions. The Carnol process is a viable alternative to sequestering CO{sub 2} in the ocean for purposes of reducing CO{sub 2} emissions from coal burning power plants. Over 90% of the CO{sub 2} from the coal burning plant is used in the process which results in a net CO{sub 2} emission reduction of over 90% compared to that obtained for conventional methanol production by steam reforming of methane. Methanol as an alternative liquid fuel for automotive engines and for fuel cells achieves additional CO{sub 2} emission reduction benefits. The economics of the process is greatly enhanced when carbon can be sold as a materials commodity. Improvement in process design and economics should be achieved by developing a molten metal (tin) methane decomposition reactor and a liquid phase, slurry catalyst, methanol synthesis reactor directly using the solvent saturated with CO{sub 2} scrubbed from the power plant stack gases. The benefits of the process warrant its further development.

  5. The Carnol process for CO{sub 2} mitigation from power plants and the transportation sector

    Energy Technology Data Exchange (ETDEWEB)

    Steinberg, M. [Brookhaven National Lab., Upton, NY (United States). Dept. of Advanced Technology

    1995-05-01

    A CO{sub 2} mitigation process is developed which converts waste CO{sub 2} primarily recovered from coal-fired power plant stack gases with natural gas, to produce methanol as a liquid fuel and coproduct carbon as a materials commodity. The Carnol process chemistry consists of methane decomposition to produce hydrogen which is catalytically reacted with the recovered waste CO{sub 2} to produce methanol. The carbon is either stored or sold as a materials commodity. A process design is modeled and mass and energy balances are presented as a function of reactor pressure and temperature conditions. The Carnol process is a viable alternative to sequestering CO{sub 2} in the ocean for purposes of reducing CO{sub 2} emissions from coal burning power plants. Over 90% of the CO{sub 2} from the coal burning plant is used in the process which results in a net CO{sub 2} emission reduction of over 90% compared to that obtained for conventional methanol production by steam reforming of methane. Methanol as an alternative liquid fuel for automotive engines and for fuel cells achieves additional CO{sub 2} emission reduction benefits. The economics of the process is greatly enhanced when carbon can be sold as a materials commodity. Improvement in process design and economics should be achieved by developing a molten metal (tin) methane decomposition reactor and a liquid phase, slurry catalyst, methanol synthesis reactor directly using the solvent saturated with CO{sub 2} scrubbed from the power plant stack gases. The benefits of the process warrants its further development.

  6. Final disposal of spent nuclear fuel - regulatory system and roles of different actors during the decision process

    Energy Technology Data Exchange (ETDEWEB)

    2009-03-15

    In November 2006 Swedish Nuclear Fuels Co. applied for a license to build a plant for encapsulation of spent nuclear fuels at Oskarshamn, Sweden. The company also have plans to apply, in 2009, for a license to construct a underground repository for spent nuclear fuels. KASAM arranged a seminar in November 2006 in order to describe and discuss the licensing rules and regulations and the roles of different parties in the decision making. Another objective of the seminar was to point out possible ambiguities in this process. Another interesting question under discussion was in what ways the basic data for the decision should be produced. The seminar covered the part of the process beginning with the application for a license and ending with the government approval/rejection of the application. Most time was spent on the legal aspects of the process

  7. Development of advanced spent fuel management process. The fabrication and oxidation behavior of simulated metallized spent fuel

    International Nuclear Information System (INIS)

    The simulated metallized spent fuel ingots were fabricated and evaluated the oxidation rates and the activation energies under several temperature conditions to develop an advanced spent fuel management process. It was also checked the alloying characteristics of the some elements with metal uranium. (Author). 3 refs., 1 tab., 36 figs

  8. Liquid fuels from biomass via a hydrothermal process

    Energy Technology Data Exchange (ETDEWEB)

    Goudriaan, F.; Peferoen, D.G.R. (Koninklijke Shell, Amsterdam (Netherlands). Lab.)

    1990-01-01

    Preliminary process studies on the conversion of various biomass types into liquid fuels have indicated that HydroThermal Upgrading (HTU) is more attractive than pyrolysis or gasification. In HTU the biomass is treated at temperatures of 300-350{sup 0}C in the presence of liquid water for 5-15 min. A large proportion of the oxygen is removed as carbon dioxide. In a case study a process for the production of 3600 t/d hydrocarbons starting from wood is evaluated. Six HTU units convert wood into ''biocrude'' containing 10 %w oxygen. The biocrude is upgraded by catalytic hydrodeoxygenation in a central facility. The final products are kerosine and gas oil which may be expected to have excellent properties. The manufacturing cost is 400-450 $/t. (author).

  9. Process engineering of ceramic composite coatings for fuel cell systems

    Energy Technology Data Exchange (ETDEWEB)

    Li, G.; Kim, H.; Chen, M.; Yang, Q.; Troczynski, T. [British Columbia Univ., Vancouver, BC (Canada). Dept. of Metals and Materials Engineering

    2003-07-01

    Researchers at UBCeram at the Department of Metals and Materials Engineering at the University of British Columbia have developed a technology to chemically bond composite sol-gel (CB-CSG) coating onto metallic surfaces of complex or concave shapes. The process has been optimized for electrically resistive coatings and corrosion-resistant coatings. The CSG is sprayed onto metallic surfaces and is heat-treated at 300 degrees C to partially dehydrate the hydroxides. The CSG film is then chemically bonded through reaction of active alumina with metal phosphates, such as aluminium phosphate. A new chromate-free process is being developed to address the issue of coatings porosity. The electrodeposition technique involves polymer particles mixed with suspended fine alumina particles which are co-deposited by electrophoretic means or by electrocoagulation. The composite e-coatings have excellent mechanical properties and are being considered as a protective coating for various components of fuel cell systems. 9 refs., 7 figs.

  10. Role of thermal analysis in uranium oxide fuel fabrication process

    International Nuclear Information System (INIS)

    The present paper discusses the application of thermal analysis, particularly, differential thermal analysis (Dta) at various stages of fuel fabrication process. The useful role of Dta in knowing the decomposition pattern and calcination temperature of Adu along with de-nitration temperature is explained. The decomposition pattern depends upon the type of drying process adopted for wet ADU cake (ADU C). Also, the paper highlights the utility of DTA in determining the APS and SSA of UO2+x and U3O8 powders as an alternate technique. Further, the temperature difference (ΔTmax) between the two exothermic peaks obtained in UO2+x powder oxidation is related to sintered density of UO2 pellets. (author)

  11. Pilot plant experience of ultrafiltration membrane technology for removal of activity from fuel pond water in reprocessing plant

    International Nuclear Information System (INIS)

    Ultrafiltration membrane technology has been applied for removal of alpha and beta activity from fuel pond water. Pilot plant scale results showed that 12000 liters of fuel pond water was successfully treated and DF of 4 and 5 was obtained with respect to alpha and beta respectively. The final product obtained from UF has turbidity in the range of 0.05 to 0.1 (feed turbidity :0.3 NTU). Based on the same results, application can be proposed for the treatment of FHA water which could eliminate the use of ion-exchange columns for this purpose and provide a clean technology for treating FHA water. (author)

  12. Spectroscopic methods of process monitoring for safeguards of used nuclear fuel separations

    Science.gov (United States)

    Warburton, Jamie Lee

    To support the demonstration of a more proliferation-resistant nuclear fuel processing plant, techniques and instrumentation to allow the real-time, online determination of special nuclear material concentrations in-process must be developed. An ideal materials accountability technique for proliferation resistance should provide nondestructive, realtime, on-line information of metal and ligand concentrations in separations streams without perturbing the process. UV-Visible spectroscopy can be adapted for this precise purpose in solvent extraction-based separations. The primary goal of this project is to understand fundamental URanium EXtraction (UREX) and Plutonium-URanium EXtraction (PUREX) reprocessing chemistry and corresponding UV-Visible spectroscopy for application in process monitoring for safeguards. By evaluating the impact of process conditions, such as acid concentration, metal concentration and flow rate, on the sensitivity of the UV-Visible detection system, the process-monitoring concept is developed from an advanced application of fundamental spectroscopy. Systematic benchtop-scale studies investigated the system relevant to UREX or PUREX type reprocessing systems, encompassing 0.01-1.26 M U and 0.01-8 M HNO3. A laboratory-scale TRansUranic Extraction (TRUEX) demonstration was performed and used both to analyze for potential online monitoring opportunities in the TRUEX process, and to provide the foundation for building and demonstrating a laboratory-scale UREX demonstration. The secondary goal of the project is to simulate a diversion scenario in UREX and successfully detect changes in metal concentration and solution chemistry in a counter current contactor system with a UV-Visible spectroscopic process monitor. UREX uses the same basic solvent extraction flowsheet as PUREX, but has a lower acid concentration throughout and adds acetohydroxamic acid (AHA) as a complexant/reductant to the feed solution to prevent the extraction of Pu. By examining

  13. Decommissioning of a mixed oxide fuel fabrication plant at Winfrith Technolgy Centre

    International Nuclear Information System (INIS)

    The Alpha Materials Laboratory (Building A52) at Winfrith contained a mixed oxide fuel fabrication plant which had a capability of producing 10 te/yr of pelleted/compacted fuel and was in operation from 1962 until 1980, when the requirement for this type of fuel in the UK diminished, and the plant became surplus to requirements. A program to develop decommissioning techniques for plutonium plants was started in 1983, addressing the following aspects of alpha plant decommissioning: (1) Re-usable containment systems, (2) Strippable coating technology, (3) Mobile air filtration plant, (4) Size reduction primarily using cold cutting, (5) techniques, (6) Waste packing, and (7) Alpha plant decommissioning methodology. The technology developed has been used to safely and efficiently decommission radioactive plant and equipment including Pu contaminated glove boxes. (63 glove boxes to date) The technology has been widely adopted in the United Kingdom and elsewhere. This paper outlines the general strategies adopted and techniques used for glove box decommissioning in building A52

  14. Applications of sub-optimality in dynamic programming to location and construction of nuclear fuel processing plant; Application de la sous-optimalite en programmation dynamique a la localisation et la cadence optimales de construction des equipements

    Energy Technology Data Exchange (ETDEWEB)

    Thiriet, L.; Deledicq, A. [Commissariat a l' Energie Atomique, 92 - Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires, section des etudes economiques generales

    1968-09-01

    First, the point of applying Dynamic Programming to optimization and Operational Research problems in chemical industries are recalled, as well as the conditions in which a dynamic program is illustrated by a sequential graph. A new algorithm for the determination of sub-optimal politics in a sequential graph is then developed. Finally, the applications of sub-optimality concept is shown when taking into account the indirect effects related to possible strategies, or in the case of stochastic choices and of problems of the siting of plants... application examples are given. (authors) [French] On rappelle d'abord l'interet de la Programmation Dynamique dans les problemes d'optimisation et de Recherche Operationnelle dans les industries chimiques, et les conditions de representation d'un programme dynamique par un graphe sequentiel. On expose ensuite un nouvel algorithme de determination de politiques sous-optimales dans un graphe sequentiel. On montre enfin les applications du concept de sous-optimalite a la prise en compte d'effets indirects lies aux politiques possibles, aux choix dans l'aleatoire, a des problemes de localisation optimale d'usines... et on donne des exemples d'utilisation. (auteurs)

  15. RBMK fuel channel integrity. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    The fuel channel integrity in the RBMK NPPs is an issue of high safety concern. To date, three single fuel channel ruptures have occurred. Fuel channel rupture results in release of radioactivity to the reactor cavity and may lead to a release of radioactivity to the environment if the confinement safety system does not function properly. A multiple fuel channel rupture exceeding the venting capacity of the reactor cavity overpressure protection system poses a major impact on the plant safety. Further, due to incorrect prediction at the design stage the gas gap between the fuel channel pressure tube and the graphite blocks closes after approximately 17 years of plant operation. There is no safety justification available for the continued plant operation in this condition and the reactors are being retubed to avoid operation in this out of design condition, which may have negative impact on the fuel channel integrity. The loss of the mechanical integrity of fuel channel pressure tubes is a major safety concern for RBMK reactors since it may lead to overpressurization of the reactor cavity and consequently develop into a severe accident. In this report, information on the main design features of the RBMK reactor related to the fuel channel integrity is given. Further, detailed information on the fuel channel pressure tube and the graphite blocks with respect to their design, manufacture, in-service inspection, operating experience, ageing behaviour including degradation mechanisms is discussed in detail. The behaviour of the system fuel channel-graphite core including the corrective actions developed and implemented is discussed. Both normal operating conditions and accident conditions are addressed, considering also the gas gap closure process and its impact. The report also covers the fuel channel ducts. It is concluded in the report that for RBMK-1000 reactors and the adopted retubing strategy, limited local gas gap closure occurs at the time of pressure tube

  16. Underwater Nuclear Fuel Disassembly and Rod Storage Process and Equipment Description. Volume II

    International Nuclear Information System (INIS)

    The process, equipment, and the demonstration of the Underwater Nuclear Fuel Disassembly and Rod Storage System are presented. The process was shown to be a viable means of increasing spent fuel pool storage density by taking apart fuel assemblies and storing the fuel rods in a denser fashion than in the original storage racks. The assembly's nonfuel-bearing waste is compacted and containerized. The report documents design criteria and analysis, fabrication, demonstration program results, and proposed enhancements to the system

  17. ICONE-4: Proceedings. Volume 4: Nuclear plant operations and maintenance, nuclear fuel cycle, institutional and energy policy, non-proliferation and safeguards

    International Nuclear Information System (INIS)

    The proceedings of this conference are divided into five volumes. This volume covers the following topics: operational experience; maintenance methods and programs; organization, management, QA, and human factors; performance monitoring; instrument and control systems; analytical methods; risk methodology; plant and system improvements; fuel cycle technologies; fuel cycle related technologies--component applications; enrichment and processing; economics; technical issues in capacity and expansion in Russia; nuclear energy policy advances; energy mix--the role of nuclear energy; latest international developments in non-proliferation and safeguards; plutonium disposition and mixed oxide fuels; aspects of plutonium disposition; and plutonium burning and disposition reactors and accelerators. Separate abstracts were prepared for most papers in this volume

  18. Application of neutron well coincidence counting for plutonium determination in mixed oxide fuel fabrication plant

    International Nuclear Information System (INIS)

    Mixed oxide (MOX) fuel is an alternative to conventional enriched uranium oxide fuel in thermal reactors. Indian interest in plutonium recycle in thermal reactors is primarily due to the need to develop alternative indigenous fuel for two boiling water reactors (BWR) at Tarapur, which are designed to use imported light enriched uranium fuel. A few MOX assemblies have been fabricated and loaded into the reactors. Neutron well coincidence counting (NWCC) system has been successfully employed to check the enrichments of PuO2 in MOX blends. NWCC has also been successfully applied in developing dry recycling process of clean rejected oxide (CRO) and dirty rejected oxide (DRO). (author)

  19. Energy Efficiency and Carbon Management in Mineral Processing Plants

    OpenAIRE

    Miti, Wilson

    2014-01-01

    Copper processing plants involved in smelting, electro-refining and electro-winning are heat-intensive undertakings that provide extensive challenges for attainment of high energy efficiency. Literature has shown that most of these plants, especially smelters, operate at low overall energy efficiency due to the seemingly complex energy scenario where heat and electricity as forms of energy are treated distinctively from each other. Many copper processing plants have not yet explored both avai...

  20. Proposal to recirculate glove box and fabrication area air in a plutonium fuel fabrication plant

    International Nuclear Information System (INIS)

    Recirculating glove box and fabrication area ventilation systems are proposed for a 40 Te/yr mixed plutonium--uranium oxide fuel fabrication plant. The ventilation design criteria are outlined, features of the fabricating plant relating to the ventilation system are shown and the recirculating systems are described. A method of operating and recirculating systems during unusual situations, energy conservation and system advantages are discussed. (U.S.)

  1. Systems simulation of cotton gin waste as a supplemental fuel in a coal powered generating plant

    Energy Technology Data Exchange (ETDEWEB)

    Parnell, C.B. (Texas A and M Univ., College Station); Grubaugh, E.K.; Johnston, M.T.; Ladd, K.L.

    1981-01-01

    A systems simulation model of gin trash use at a Lamb County, Texas, power plant was developed. The model is being used to study gin trash supply, both quantity and transportation, fixed and variable cost, and economic benefit/costs of gin trash utilization. Preliminary results indicate the positive feasibility of using gin trash as a supplemental fuel in a coal fired power plant. (MHR)

  2. Thermodynamic analysis of SOFC (solid oxide fuel cell) - Stirling hybrid plants using alternative fuels

    DEFF Research Database (Denmark)

    Rokni, Masoud

    2013-01-01

    A novel hybrid power system (∼10 kW) for an average family home is proposed. The system investigated contains a solid oxide fuel cell (SOFC) on top of a Stirling engine. The off-gases produced in the SOFC cycle are fed to a bottoming Stirling engine, at which additional power is generated. Simula...

  3. Technical specifications on the welding in fuel reprocessing plants

    Energy Technology Data Exchange (ETDEWEB)

    Karino, Motonobu; Uryu, Mitsuru; Matsui, N.; Nakazawa, Fumio; Imanishi, Makoto; Koizumi; Kazuhiko; Sugawara, Junichi; Tanaka, Hideo

    1999-04-01

    The past specifications SGN of the welding in JNC was reexamined for the reprocessing plants in order to further promote the quality control. The specification first concerns the quality of raw materials, items of the quality tests, material management, and qualification standards of the welders. It extends over details of the welding techniques, welding design, welding testings, inspection and the judgment standards. (H. Baba)

  4. Solid Oxide Fuel Cell – Gas Turbine Hybrid Power Plant

    OpenAIRE

    Henke, Moritz; Willich, Caroline; Steilen, Mike; Kallo, Josef; Friedrich, K. Andreas

    2013-01-01

    A model of a hybrid power plant consisting of SOFC and a gas turbine is presented. Simulations are carried out for a different number of SOFC stacks while keeping the output power of the SOFC constant. Results show that the effect of stack number on system performance is only marginal within the investigated range. Operating conditions of the SOFC, however, are strongly influenced.

  5. Thermoeconomic analysis of large solid oxide fuel cell plants: Atmospheric vs. pressurized performance

    International Nuclear Information System (INIS)

    A detailed thermoeconomic analysis of two large solid oxide fuel cell-based power plants operating at atmospheric pressure and 20 bar, respectively, is assessed in this work. The analyzed systems employ SOFC-GT (gas turbine) modules as main power generators; a bottom HRSC (heat recovery steam cycle) to generate additional electricity from the SOFC-GT exhaust hot gases is also included. The thermodynamic and economic performance of the two plant configurations are studied in detail: the exergy analysis shows an enhanced exergetic performance for the pressurized cycle that features components with higher efficiency and consequently a lower rate of exergy destruction (∼20% less than the atmospheric plant). The economic analysis considers the capital cost of each component within the system and is developed aiming at estimating the levelized cost of electricity. In order to match both exergetic and economic parts, a rigorous thermoeconomic analysis following the theory of Valero and Bejan [1,2] is implemented. A well-defined set of rules for the exergoeconomic balance around each plant component is specified and specific cost balance equations are thus derived. Results show how pressurized plant outperforms the atmospheric one, with a (on exergo-economic base) cost of electricity of 47.7 $/MWh instead of 64.2 $/MWh. Therefore, both exergetic and economic advantages result from the adoption of a pressurized SOFC-GT cycle in the framework of future advance power plants based on high-temperature fuel cells. - Highlights: • Exergy analysis of atmospheric and pressurized SOFC plants. • Exergy destruction in a fuel cell hybrid power plant. • Rigorous thermoeconomic methodology to assess the performance of different power generation plants. • Economic performance of SOFC plants

  6. Characterization of nuclear decontamination solutions at the Idaho Chemical Processing Plant from 1982-1990

    Energy Technology Data Exchange (ETDEWEB)

    Zohner, S.K.

    1996-03-01

    This report represents possibly the single largest collection of operational decontamination data from a nuclear reprocessing facility at the Idaho National Engineering Laboratory and perhaps anywhere in the world. The uniqueness of this data is due to the Idaho Chemical Processing Plant`s (ICPP`s) ability to process different types of highly enriched nuclear fuel. The report covers an 8-year period, during which six campaigns were conducted to dissolve nuclear fuel clad in stainless steel, aluminum, graphite, and zirconium. Each fuel type had a separate head-end process with unique dissolution chemistry, but shared the same extraction process equipment. This report presents data about decontamination activities of the ICPP`s First Cycle extraction vessels, columns, piping, and aluminum dissolution vessels. Operating data from 1982 through 1990 has been collected, analyzed, and characterized. Chemicals used in the decontamination processes are documented along with quantities used. The chemical solutions are analyzed to compare effectiveness. Radioisotopic analysis is recorded, showing and quantifying what nuclides were removed by the various solutions. The original data is also provided to make it possible for researchers to address questions and test other hypotheses not discussed in this report.

  7. Investigation of the performance of a copper based oxygen carrier for chemical looping combustion in a 120 kW pilot plant for gaseous fuels

    International Nuclear Information System (INIS)

    Highlights: • A Cu based oxygen carrier for chemical looping combustion has been tested. • A 120 kW pilot plant designed as dual circulating fluidized bed has been used. • Solids inventory and circulation have been identified as critical for performance. • The results are compared with other pilot plants using the same oxygen carrier. • Recommendations for improved reactor designs have been made based on the results. - Abstract: A copper based oxygen carrier prepared by impregnation on a highly porous alumina support (14.2 wt% active CuO) has been tested in a 120 kW chemical looping pilot plant. This oxygen carrier has already been under investigation in other pilot plants up to 10 kW fuel power and showed very good performance, i.e. full fuel conversion was achieved. During the experiments, natural gas has been used as fuel and variations of several process parameters like temperature, fuel power, solids inventory and solids circulation rate have been performed. The copper particles showed good performance regarding conversion of CO and H2 (almost full conversion) but only moderate conversion of CH4 (up to 80%) was achieved. The three process parameters fuel reactor temperature, solids circulation between air and fuel reactor and solids inventory have been identified as significant parameters for fuel conversion, i.e. increasing one of these parameters improves fuel conversion. Continuous analysis of the oxygen carrier particles revealed an initial decay of active CuO content caused by attrition on the external surface of the particles. The CuO content stabilized after 30 h of operation at around 9 wt% and no further decrease was observed

  8. Six years working experience of the Marcoule plant for treatment of irradiated fuel

    International Nuclear Information System (INIS)

    The irradiated fuel treatment plant at Marcoule began treating rods from the pile G 1 in July 1958. These six years experience of the plant in operation have led to the confirmation or revision of the original ideas concerning the process as well as the technology or methods of exploitation. The process as a whole has suffered little modification, the performances having proved better than originally foreseen; the only alterations made were justified by greater simplicity of operation, better nuclear security (criticality) or for technological reasons. The processes of plutonium reduction from valency IV to valency III by uranium IV, and of concentration of fission product solutions in the presence of formaldehyde, have always given complete satisfaction. The initial concept of direct maintenance of the installations has been justified by experience. Certain maintenance jobs, originally considered impossible after the start of operations, have proved feasible and have been carried out under acceptable conditions; a number of examples are given. From experience it has been possible to define optimal conditions for the design of these installations such as to provide a maximum in robustness and ease of maintenance. The advantages of continuously-operating equipment have been shown. Certain installations have been altered in accordance with these new ideas. Analytical checking in the laboratory has been profoundly modified, and the plans adopted are such that complete safety in work on radioactive solutions is compatible with a very good working speed. Experience has also shown the advantages of having a group on the spot to carry out short-term applied studies. Finally, a strict working discipline and excellent collaboration with the radiation protection service have enabled us to reach the end of these six years, during some of which the exploitation was intensive, without irradiation accident. (authors)

  9. Process for reprocessing a nuclear reactor fuel rod

    International Nuclear Information System (INIS)

    In order to separate the nuclear fuel from the can material, the can is heated evenly in the gastight closed state together with the nuclear fuel contained in it, so that the diameter of the can expands, increasing the gap between the nuclear fuel and the can without cracks occurring in the can. The expanded can is then opened at one end and finally the nuclear fuel from the opened can and is treated separately from the can. (orig./HP)

  10. Exergo-Economic Fuel-Impact Analysis for Steam Turbines Sections in Power Plants

    Directory of Open Access Journals (Sweden)

    Javier Royo

    2003-09-01

    Full Text Available In this paper exergoeconomic fuel-impact models for steam turbines in power plants are proposed. They are applied to calculate the impact on the steam cycle when malfunctions are occurring during the operation of steam turbine sections. Concepts such as the exergetic consumption and the dissipation temperature are used to understand the proposed fuel-impact analysis. In order to validate these fuel-impact methods, well-known procedures, to simulate on- and off-design conditions of a steam power cycle, are used as references. Three different methods a ASME PTC-6, b existing fuel-impact formula, and c proposed exergoeconomic Fuel–Impact formulation, are compared with respect to the simulator results. The proposed models allow evaluating fuel-impact cost with more accurate results than conventional procedures. An example of a 158 MW conventional power plant is presented herein. The malfunction costs occurring in the steam turbines are inferred from the results. One perspective of this analysis is to establish an on-line monitoring system into power plants that permits to opportunely detect steam turbine malfunctions, without simulators.

  11. Process for dehydration of oregano using propane gas as fuel

    Directory of Open Access Journals (Sweden)

    Carlos O. Velásquez-Santos

    2014-08-01

    Full Text Available The article describes two important issues, the first is the process to design, implement and validate a mechanical dryer of oregano, using propane gas as fuel, and the second is the cost of the process of dehydrated, taking into account the cost of electric energy consumption by the fan and the cost of propane gas consumption by the heat exchanger. To achieve this, it was necessary review the state of the art and the study of the raw material (oregano, were established as premises of design the necessary technical specifications and the variables involved in the process, using conceptual methods and simulation to ensure that it complies with the ISO standard 7925:1999, which defines the requirements for the marketing of dried oregano and processed. Emphasis was made on the percentage of moisture that is 10%, the moisture of the product was found by the azeotropic distillation method, subsequently was validated the functionality and efficiency, comparing the results from an experimental design, then it was obtained the drying curve of oregano with the prototype of drying and it was checked if it meets ISO 7925:1999 standard and the NTC 4423 standard in order to obtain a final product dehydrated with the percentage of humidity appropriate.

  12. Integrated microchemical systems for fuel processing in micro fuel cell applications

    Science.gov (United States)

    Pattekar, Ashish V.

    Rapid advances in microelectronics technology over the last decade have led to the search for novel applications of miniaturization to all aspects of engineering. Microreaction engineering, which involves the development of miniature reactors on microchips for novel applications, has been a key area of interest in this quest for miniaturization. The idea of a fully integrated microplant with embedded control electronics, sensors and actuators on a single silicon chip has been gaining increasing acceptance as significant progress is being made in this area. The aim of this project has been to demonstrate a working microreaction system for hydrogen delivery to miniature proton exchange membrane (PEM) fuel cells through the catalytic steam reforming of methanol. The complete reformer - fuel cell unit is proposed as an alternative to conventional portable sources of electricity such as batteries due to its ability to provide an uninterrupted supply of electricity as long as a supply of methanol and water can be provided. This technology also offers significantly higher energy storage densities, which translates into less frequent 'recharging' through the refilling of methanol fuel. Various aspects of the design of a miniature methanol reformer on a silicon substrate are discussed with a focus on the theoretical understanding of microreactor operation and optimum utilization of the semiconductor-processing techniques used for fabricating the devices. Three prototype microreactor designs have been successfully fabricated and tested. Issues related to microchannel capping, on-chip heating and temperature sensing, introduction and trapping of catalyst particles in microchannels, microfluidic interfacing, pressure drop reduction, and thermal insulation have been addressed. Details regarding modeling and simulation of the designs to provide an insight into the working of the microreactor are presented along with a description of the microfabrication steps followed to

  13. Optimization of Water Chemistry to Ensure Reliable Water Reactor Fuel Performance at High Burnup and in Ageing Plant (FUWAC)

    International Nuclear Information System (INIS)

    This report presents the results of the Coordinated Research Project (CRP) on Optimization of Water Chemistry to Ensure Reliable Water Reactor Fuel Performance at High Burnup and in Ageing Plants (FUWAC, 2006-2009). It provides an overview of the results of the investigations into the current state of water chemistry practice and concerns in the primary circuit of water cooled power reactors including: corrosion of primary circuit materials; deposit composition and thickness on the fuel; crud induced power shift; fuel oxide growth and thickness; radioactivity buildup in the reactor coolant system (RCS). The FUWAC CRP is a follow-up to the DAWAC CRP (Data Processing Technologies and Diagnostics for Water Chemistry and Corrosion Control in Nuclear Power Plants 2001-2005). The DAWAC project improved the data processing technologies and diagnostics for water chemistry and corrosion control in nuclear power plants (NPPs). With the improved methods for controlling and monitoring water chemistry now available, it was felt that a review of the principles of water chemistry management should be undertaken in the light of new materials, more onerous operating conditions, emergent issues such as CIPS, also known as axial offset anomaly (AOA) and the ageing of operating power plant. In the framework of this CRP, water chemistry specialists from 16 nuclear utilities and research organizations, representing 15 countries, exchanged experimental and operational data, models and insights into water chemistry management. The CD-ROM attached to this IAEA-TECDOC includes the report itself, detailed progress reports of three Research Coordination Meetings (RCMs) (Annexes I-III) and the reports and presentations made during the project by the participants.

  14. Environmental assessment for radioisotope heat source fuel processing and fabrication

    International Nuclear Information System (INIS)

    DOE has prepared an Environmental Assessment (EA) for radioisotope heat source fuel processing and fabrication involving existing facilities at the Savannah River Site (SRS) near Aiken, South Carolina and the Los Alamos National Laboratory (LANL) near Los Alamos, New Mexico. The proposed action is needed to provide Radioisotope Thermoelectric Generators (RTG) to support the National Aeronautics and Space Administration's (NASA) CRAF and Cassini Missions. Based on the analysis in the EA, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, an Environmental Impact Statement is not required. 30 refs., 5 figs

  15. Evaluation of methods for decladding LWR fuel for a pyroprocessing-based reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Bond, W.D.; Mailen, J.C.; Michaels, G.E.

    1992-10-01

    The first step in reprocessing disassembled light-water reactor (LWR) spent fuel is to separate the zirconium-based cladding from the UO{sub 2} fuel. A survey of decladding technologies has been performed to identify candidate decladding processes suitable for LWR fuel and compatible with downstream pyropr for separation of actinides and fission products. Technologies for the primary separation of Zircaloy cladding from oxide fuel and for secondary separations (in most cases, a further decontamination of the cladding) were reviewed. Because cutting of the fuel cladding is a necessary step in all flowsheet options, metal cutting technologies were also briefly evaluated. The assessment of decladding processes resulted in the identification of the three or four potentially attractive options that may warrant additional near-term evaluation. These options are summarized, and major strengths and issues of each option are discussed.

  16. Evaluation of methods for decladding LWR fuel for a pyroprocessing-based reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Bond, W.D.; Mailen, J.C.; Michaels, G.E.

    1992-10-01

    The first step in reprocessing disassembled light-water reactor (LWR) spent fuel is to separate the zirconium-based cladding from the UO[sub 2] fuel. A survey of decladding technologies has been performed to identify candidate decladding processes suitable for LWR fuel and compatible with downstream pyropr for separation of actinides and fission products. Technologies for the primary separation of Zircaloy cladding from oxide fuel and for secondary separations (in most cases, a further decontamination of the cladding) were reviewed. Because cutting of the fuel cladding is a necessary step in all flowsheet options, metal cutting technologies were also briefly evaluated. The assessment of decladding processes resulted in the identification of the three or four potentially attractive options that may warrant additional near-term evaluation. These options are summarized, and major strengths and issues of each option are discussed.

  17. The effect of retrofitting Portuguese fossil fuel power plants with CCS

    International Nuclear Information System (INIS)

    Highlights: ► A map of mainland Portugal with potential CO2 source-sink matching was created. ► Four existing Portuguese power plants were simulated with and without CCS. ► Effect of CCS retrofit on performance and costs at each power plant was studied. ► The incremental COE was estimated at around 46 $/MW h for NGCC plants. ► The incremental COE was estimated at around 61 $/MW h for PC plants. -- Abstract: This work assesses the retrofit potential of existing Portuguese fossil fuel power plants with post-combustion CO2 capture and storage (CCS) technology. The Integrated Environmental Control Model (IECM) was used to provide a systematic techno-economic analysis of the cost of emission control equipment, the reduction in greenhouse gas emissions, and other key parameters which may change when CCS is implemented at a fossil fuel power plant. The results indicate that CCS requires a large capital investment and significantly increases the levelized cost of electricity. However, the economic viability of CCS increases with higher CO2 prices. The breakeven CO2 price for plants with and without CCS was estimated at $85–$140/t of CO2 depending on the technical parameters of the individual plants.

  18. CO2 capture processes in power plants - Le captage du CO2 dans les centrales thermiques

    OpenAIRE

    Bouallou, Chakib

    2010-01-01

    PDF file available for free at http://pubs.ub.ro/?pg=revues&rev=cscc6&num=201011&vol=1&aid=2975 International audience This review is devoted to assess and compare various processes aiming at recover CO2 from power plants fed with natural gas (NGCC) and pulverized coal (PC). These processes are post combustion CO2 capture using chemical solvents, natural gas reforming for pre-combustion capture and oxy-fuel combustion with cryogenic recovery of CO2. These processes were evaluated to giv...

  19. Model-based Fuel Flow Control for Fossil-fired Power Plants

    DEFF Research Database (Denmark)

    Niemczyk, Piotr

    2010-01-01

    -fired power plants represent the largest reserve of such controllable power sources in several countries. However, their production take-up rates are limited, mainly due to poor fuel flow control. The thesis presents analysis of difficulties and potential improvements in the control of the coal grinding...

  20. The environmental performance of three alcohol fuel plants producers of small, medium and big scale

    International Nuclear Information System (INIS)

    The article discusses the following issues of alcohol fuel plants producers: sizing; performance; natural resources; environmental aspects; and electric power generation. The environmental performance concept is introduced and a performance evaluation methodology are presented and applied. The results are also presented and criticized

  1. Butachlor residues in tomato plants and fate during tomato processing

    International Nuclear Information System (INIS)

    14C-butachlor incorporated with soil was taken up by tomato plants and translocated from roots to other plants. At harvest, the fruit contained 48% of the total residue in the plant. Commercial processing to tomato juice and canned fruit was simulated to evaluate the effect of processing procedures in removing the residues. As anticipated, water washing had hardly any effect on removing the residues. Residues in peel or seed wasted off in processing were much lower than those in juice or pulp. Processing into juice and canned fruit did not reduce the residue level. (author). 2 refs, 2 tabs

  2. Optimization of a local district heating plant under fuel flexibility and performance

    DEFF Research Database (Denmark)

    Rudra, Souman; Rosendahl, Lasse; From, Niels

    2011-01-01

    energyPRO which has been used to analyses the integration of large scale energy system into the domestic district heating system. A model of the current work on the basis of information from the plant (using fossil fuel) is established and named as a reference model. Then different solutions......Brovst is a small district in Denmark. Based on the case of Brovst, this paper analyses the role of district heating in future Renewable Energy Systems. The present use of fossil fuels in the Brovst DHP (district heating plant) represents an increasing environmental and climate-related load. So......, an investigation has been made to reduce the use of fossil fuels for district heating system and make use of the local renewable resources (Biogas, Solar and Geothermal) for district heating purpose. In this article, the techno-economic assessment is achieved through the development of a suite of models...

  3. Atmospheric benzenoid emissions from plants rival those from fossil fuels.

    Science.gov (United States)

    Misztal, P K; Hewitt, C N; Wildt, J; Blande, J D; Eller, A S D; Fares, S; Gentner, D R; Gilman, J B; Graus, M; Greenberg, J; Guenther, A B; Hansel, A; Harley, P; Huang, M; Jardine, K; Karl, T; Kaser, L; Keutsch, F N; Kiendler-Scharr, A; Kleist, E; Lerner, B M; Li, T; Mak, J; Nölscher, A C; Schnitzhofer, R; Sinha, V; Thornton, B; Warneke, C; Wegener, F; Werner, C; Williams, J; Worton, D R; Yassaa, N; Goldstein, A H

    2015-07-13

    Despite the known biochemical production of a range of aromatic compounds by plants and the presence of benzenoids in floral scents, the emissions of only a few benzenoid compounds have been reported from the biosphere to the atmosphere. Here, using evidence from measurements at aircraft, ecosystem, tree, branch and leaf scales, with complementary isotopic labeling experiments, we show that vegetation (leaves, flowers, and phytoplankton) emits a wide variety of benzenoid compounds to the atmosphere at substantial rates. Controlled environment experiments show that plants are able to alter their metabolism to produce and release many benzenoids under stress conditions. The functions of these compounds remain unclear but may be related to chemical communication and protection against stress. We estimate the total global secondary organic aerosol potential from biogenic benzenoids to be similar to that from anthropogenic benzenoids (~10 Tg y(-1)), pointing to the importance of these natural emissions in atmospheric physics and chemistry.

  4. Effect of diesel fuel on growth of selected plant species

    OpenAIRE

    Adam, G.; Duncan, H.J.

    1999-01-01

    Diesel oil is a complex mixture of hydrocarbons with an average carbon number of C8– C26. The majority of components consist of alkanes, both straight chained and branched and aromatic compounds including mono-, di- and polyaromatic hydrocarbons. Regardless of this complexity, diesel oil can be readily degraded by a number of soil microorganisms making it a likely candidate for bioremediation. The concept of using plants to enhance bioremediation, termed phytoremediation, is a ...

  5. Startup, testing, and operation of the Santa Clara 2MW direct carbonate fuel cell demonstration plant

    Energy Technology Data Exchange (ETDEWEB)

    Skok, A.J.; Leo, A.J. [Fuel Cell Engineering Corp., Danbury, CT (United States); O`Shea, T.P. [Santa Clara Demonstration Project, CA (United States)

    1996-12-31

    The Santa Clara Demonstration Project (SCDP) is a collaboration between several utility organizations, Fuel Cell Engineering Corporation (FCE), and the U.S. Dept. Of Energy aimed at the demonstration of Energy Research Corporation`s (ERC) direct carbonate fuel cell (DFC) technology. ERC has been pursuing the development of the DFC for commercialization near the end of this decade, and this project is an integral part of the ERC commercialization effort. The objective of the Santa Clara Demonstration Project is to provide the first full, commercial scale demonstration of this technology. The approach ERC has taken in the commercialization of the DFC is described in detail elsewhere. An aggressive core technology development program is in place which is focused by ongoing interaction with customers and vendors to optimize the design of the commercial power plant. ERC has selected a 2.85 MW power plant unit for initial market entry. Two ERC subsidiaries are supporting the commercialization effort: the Fuel Cell Manufacturing Corporation (FCMC) and the Fuel Cell Engineering Corporation (FCE). FCMC manufactures carbonate stacks and multi-stack modules, currently from its production facility in Torrington, CT. FCE is responsible for power plant design, integration of all subsystems, sales/marketing, and client services. FCE is serving as the prime contractor for the design, construction, and testing of the SCDP Plant. FCMC has manufactured the multi-stack submodules used in the DC power section of the plant. Fluor Daniel Inc. (FDI) served as the architect-engineer subcontractor for the design and construction of the plant and provided support to the design of the multi-stack submodules. FDI is also assisting the ERC companies in commercial power plant design.

  6. Laboratory studies of shear/leach processing of zircaloy clad metallic uranium reactor fuel

    Energy Technology Data Exchange (ETDEWEB)

    Swanson, J.L.; Bray, L.A.; Kjarmo, H.E.; Ryan, J.L.; Matsuzaki, C.L.; Pitman, S.G.; Haberman, J.H.

    1985-12-01

    The safety aspects addressed centered on understanding and explaining the undesirable reactions, ''fires,'' observed in a few instances during earlier processing of such fuel at the Nuclear Fuels Services (NFS) plant at West Valley, New York. Consideration of the dissolver fires that occurred at NFS leads to the conclusion that they resulted from rapid reactions with uranium metal, rather than with zirconium metal or with sensitized weld beads. The fires observed at NFS during hulls handling operations may have involved sensitized weld beads as suggested by earlier investigators, but current results suggest that these fires also could have been caused by reactions involving uranium metal. Very little pyrophoric activity was observed in leeached cladding hulls, indicating a very low probability for safety problems resulting from the U-Zr intermetallic zone in N-Reactor fuel. Consideration of the potential role of hydrides in the fires observed at NFS indicates that they were also not important factors. Consideration was also given to protective atmospheres to be used during shearing to prevent excessive reaction during that operation. A water deluge during shearing will likely provide adequate safety while meshing well with other process considerations. Studies on the dissolution of metallic uranium in nitric acid show an initial slower reaction followed by a faster reaction that proceeds at a sustained rate for a prolonged period of time. At solution concentrations typical of those encountered in practical uranium dissolver conditions, this sustained rate is governed by an equation such as: Dissolution rate = K (surface area) ((HNO3)+2(U))/sup 2.6/. Little difference was found in dissolution rates of as-fabricated and of irradiated fuel. The transuranic element content of leached cladding hulls was found to be approx. 400 nCi/g. This is too high to allow disposal as low-level waste.

  7. Laboratory studies of shear/leach processing of zircaloy clad metallic uranium reactor fuel

    International Nuclear Information System (INIS)

    The safety aspects addressed centered on understanding and explaining the undesirable reactions, ''fires,'' observed in a few instances during earlier processing of such fuel at the Nuclear Fuels Services (NFS) plant at West Valley, New York. Consideration of the dissolver fires that occurred at NFS leads to the conclusion that they resulted from rapid reactions with uranium metal, rather than with zirconium metal or with sensitized weld beads. The fires observed at NFS during hulls handling operations may have involved sensitized weld beads as suggested by earlier investigators, but current results suggest that these fires also could have been caused by reactions involving uranium metal. Very little pyrophoric activity was observed in leeached cladding hulls, indicating a very low probability for safety problems resulting from the U-Zr intermetallic zone in N-Reactor fuel. Consideration of the potential role of hydrides in the fires observed at NFS indicates that they were also not important factors. Consideration was also given to protective atmospheres to be used during shearing to prevent excessive reaction during that operation. A water deluge during shearing will likely provide adequate safety while meshing well with other process considerations. Studies on the dissolution of metallic uranium in nitric acid show an initial slower reaction followed by a faster reaction that proceeds at a sustained rate for a prolonged period of time. At solution concentrations typical of those encountered in practical uranium dissolver conditions, this sustained rate is governed by an equation such as: Dissolution rate = K (surface area) ([HNO3]+2[U])/sup 2.6/. Little difference was found in dissolution rates of as-fabricated and of irradiated fuel. The transuranic element content of leached cladding hulls was found to be approx. 400 nCi/g. This is too high to allow disposal as low-level waste

  8. AP1000R nuclear power plant safety overview for spent fuel cooling

    International Nuclear Information System (INIS)

    The AP1000R plant is an 1100-MWe class pressurized water reactor with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance, safety and costs. The AP1000 design uses passive features to mitigate design basis accidents. The passive safety systems are designed to function without safety-grade support systems such as AC power, component cooling water, service water or HVAC. Furthermore, these passive features 'fail safe' during a non-LOCA event such that DC power and instrumentation are not required. The AP1000 also has simple, active, defense-in-depth systems to support normal plant operations. These active systems provide the first level of defense against more probable events and they provide investment protection, reduce the demands on the passive features and support the probabilistic risk assessment. The AP1000 passive safety approach allows the plant to achieve and maintain safe shutdown in case of an accident for 72 hours without operator action, meeting the expectations provided in the U.S. Utility Requirement Document and the European Utility Requirements for passive plants. Limited operator actions are required to maintain safe conditions in the spent fuel pool via passive means. In line with the AP1000 approach to safety described above, the AP1000 plant design features multiple, diverse lines of defense to ensure spent fuel cooling can be maintained for design-basis events and beyond design-basis accidents. During normal and abnormal conditions, defense-in-depth and other systems provide highly reliable spent fuel pool cooling. They rely on off-site AC power or the on-site standby diesel generators. For unlikely design basis events with an extended loss of AC power (i.e., station blackout) or loss of heat sink or both, spent fuel cooling can still be provided indefinitely: - Passive systems, requiring minimal or no operator actions, are sufficient for at least 72 hours under all possible pool heat

  9. AP1000{sup R} nuclear power plant safety overview for spent fuel cooling

    Energy Technology Data Exchange (ETDEWEB)

    Gorgemans, J.; Mulhollem, L.; Glavin, J.; Pfister, A.; Conway, L.; Schulz, T.; Oriani, L.; Cummins, E.; Winters, J. [Westinghouse Electric Company LLC, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

    2012-07-01

    The AP1000{sup R} plant is an 1100-MWe class pressurized water reactor with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance, safety and costs. The AP1000 design uses passive features to mitigate design basis accidents. The passive safety systems are designed to function without safety-grade support systems such as AC power, component cooling water, service water or HVAC. Furthermore, these passive features 'fail safe' during a non-LOCA event such that DC power and instrumentation are not required. The AP1000 also has simple, active, defense-in-depth systems to support normal plant operations. These active systems provide the first level of defense against more probable events and they provide investment protection, reduce the demands on the passive features and support the probabilistic risk assessment. The AP1000 passive safety approach allows the plant to achieve and maintain safe shutdown in case of an accident for 72 hours without operator action, meeting the expectations provided in the U.S. Utility Requirement Document and the European Utility Requirements for passive plants. Limited operator actions are required to maintain safe conditions in the spent fuel pool via passive means. In line with the AP1000 approach to safety described above, the AP1000 plant design features multiple, diverse lines of defense to ensure spent fuel cooling can be maintained for design-basis events and beyond design-basis accidents. During normal and abnormal conditions, defense-in-depth and other systems provide highly reliable spent fuel pool cooling. They rely on off-site AC power or the on-site standby diesel generators. For unlikely design basis events with an extended loss of AC power (i.e., station blackout) or loss of heat sink or both, spent fuel cooling can still be provided indefinitely: - Passive systems, requiring minimal or no operator actions, are sufficient for at least 72 hours under all

  10. Fuel cell power plants for decentralised CHP applications; Brennstoffzellen-Kraftwerke fuer dezentrale KWK-Anwendungen

    Energy Technology Data Exchange (ETDEWEB)

    Ohmer, Martin; Mattner, Katja [FuelCell Energy Solutions GmbH, Dresden (Germany)

    2015-06-01

    Fuel cells are the most efficient technology to convert chemical energy into electricity and heat and thus they could have a major impact on reducing fuel consumption, CO{sub 2} and other emissions (NO{sub x}, SO{sub x} and particulate matter). Fired with natural or biogas and operated with an efficiency of up to 49 % a significant reduction of fuel costs can be achieved in decentralised applications. Combined heat and power (CHP) configurations add value for a wide range of industrial applications. The exhaust heat of approximately 400 C can be utilised for heating purposes and the production of steam. Besides, it can be also fed directly to adsorption cooling systems. With more than 110 fuel cell power plants operating worldwide, this technology is a serious alternative to conventional gas turbines or gas engines.

  11. Plutonium fuel program

    International Nuclear Information System (INIS)

    A review is presented of the development of the (UPu)C sphere-pac fuel project during 1978. In particular, the problems encountered in obtaining good fuel quality in the fabrication process and their solution is discussed. The development of a fabrication pilot plant is considered, and the post-irradiation examination of fuel pins is presented. (Auth.)

  12. FATE Unified Modeling Method for Spent Nuclear Fuel and Sludge Processing, Shipping and Storage - 13405

    International Nuclear Information System (INIS)

    A unified modeling method applicable to the processing, shipping, and storage of spent nuclear fuel and sludge has been incrementally developed, validated, and applied over a period of about 15 years at the US DOE Hanford site. The software, FATETM, provides a consistent framework for a wide dynamic range of common DOE and commercial fuel and waste applications. It has been used during the design phase, for safety and licensing calculations, and offers a graded approach to complex modeling problems encountered at DOE facilities and abroad (e.g., Sellafield). FATE has also been used for commercial power plant evaluations including reactor building fire modeling for fire PRA, evaluation of hydrogen release, transport, and flammability for post-Fukushima vulnerability assessment, and drying of commercial oxide fuel. FATE comprises an integrated set of models for fluid flow, aerosol and contamination release, transport, and deposition, thermal response including chemical reactions, and evaluation of fire and explosion hazards. It is one of few software tools that combine both source term and thermal-hydraulic capability. Practical examples are described below, with consideration of appropriate model complexity and validation. (authors)

  13. Preliminary safety analysis for offgas treatment system of DUPIC fuel manufacturing process at DFDF

    Energy Technology Data Exchange (ETDEWEB)

    Shin, J. M.; Lee, H. H.; Park, J. J.; Yang, M. S

    2000-09-01

    DUPIC fuel fabrication process is a dry processing technology to manufacture CANDU compatible fuel through a direct refabrication process from spent PWR fuel. DUPIC fuel fabrication process consists of the slitting of the spent PWR fuel rods, OREOX processing, homogeneous mixing, pelletizing and sintering. All these processes should be conducted by remote means in a M6 hot cell at IMEF. Since there is a lot of highly radioactive spent fuel(200 kg) to be used in DUPIC fuel fabrication process, safety analysis on DFDF facility is very important to improve the safety of hot cell and to reduce the dose exposure to operator. This report describes the design of IMEF facility, manufacturing equipment and process, offgas treatment system necessary for DUPIC fuel manufacturing process. Also, it provides the flow chart of arising and activity for each nuclide in offgas treatment system and final arising and activity for gaseous waste discharged from offgas treatment equipment into inside of M6 cell during OREOX and sintering processes in DUPIC fuel manufacturing process.

  14. Plant oil as fuel for household cooking stoves; Pflanzenoel als Brennstoff fuer Haushaltskochgeraete

    Energy Technology Data Exchange (ETDEWEB)

    Kratzeisen, M.; Mueller, J. [Hohenheim Univ., Stuttgart (Germany). Inst. fuer Agrartechnik, FB Agrartechnik in den Tropen und Subtropen; Stumpf, E. [Bosch und Siemens Hausgeraete GmbH, Bretten (Germany); Trojer, S. [Bosch und Siemens Hausgeraete GmbH, Muenchen (Germany)

    2007-07-01

    In developing countries and countries in transition more than 500 kg firewood per person is used for meal preparation on open cooking stoves annually. Firewood utilization results in uncontrolled deforestation and the problems resulting from it. Increasing prices for mineral oil products like kerosene and gas worsen the situation further. A possible solution is plant oil as an energy source for daily meal preparation. Different qualities of plant oils were tested for their suitability as fuel in a newly developed plant oil stove. (orig.)

  15. The installation of the defective identification device for irradiated fuel in nuclear power plant

    International Nuclear Information System (INIS)

    The sipping test devices are used to identify the defective fuel. The defective fuel can be identified by detecting the occurrence of the fission products entrained by the medium rising around the fuel rods. There are two kinds of sipping test device to inspect the tightness of the irradiated fuel assembly from nuclear power plant (NPP). The in-mast sipping taking the mast as the isolator, the air as the medium, and the Xe 133 as the indication nuclide is used for qualitative tightness test of each fuel assembly during refueling operation above the reactor. The poolside sipping taking the sipping cell as the isolator, the air and water as the medium is used for quantitative confirming the diagnosis of the in-mast sipping and identifying the tightness of the fuel at the side of the fuel storage pool after refueling. The design manufacture and calibration of three devices were successfully completed domestically step by step with serious quality assurance and quality control. (author)

  16. River Self-Restoration: Interactions between Plants and Fluvial Processes

    Science.gov (United States)

    Gurnell, Angela

    2014-05-01

    This paper presents evidence from European rivers of the nature and consequences of plant-fluvial process interactions. While the examples are representative of different climates, riparian and aquatic plant species, and river geomorphological types, they are linked by a general conceptual model of plant-fluvial process interactions that can be adapted to local conditions. Riparian and aquatic plants both affect and respond to fluvial processes. Their above ground biomass modifies the flow field and retains sediment, whereas their below-ground biomass affects the hydraulic and mechanical properties of the substrate and consequently the moisture regime and erodibility of the land surface. At the same time plants are disturbed, removed and buried by fluvial processes. Thus the margins of river systems provide a critical zone where plants and fluvial processes interact to produce a diverse mosaic of dynamic landforms that are characteristic of naturally-functioning river ecosystems. It is important to understand these interactions between aquatic and riparian plants and fluvial processes, and to recognize how they contribute to trajectories of natural river channel recovery from human interventions. The interactions have a significant influence on river systems across space scales from individual plants to entire river corridors. Plant-scale phenomena structure patch-scale geomorphological forms and processes. Interactions between patches contribute to larger-scale and longer-term river geomorphological phenomena. Furthermore, the influence of plants varies through time as above and below ground biomass alter within the annual growth cycle, over longer-term growth trajectories, and in response to drivers of change such as climatic and hydrological fluctuations and extremes. If river management and restoration works with these natural interactions and recovery processes, outcomes have the best chance of being cost-effective and sustainable.

  17. On the interaction between fuel crud and water chemistry in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Jiaxin Chen [Studsvik Material AB, Nykoeping (Sweden)

    2000-01-01

    This report has surveyed the current understanding about the characteristics of fuel crud, its deposition and dissolution behaviour, the influences of water chemistry, and the radioactivity transport in nuclear power plants. The references were mainly sought for from the International Nuclear Information System (INIS) database and some internal reports of Studsvik Material AB. The characteristics of fuel crud from discharged fuel rods have been extensively investigated over the last three decades. Fuel crud mainly consists of iron, nickel and chromium oxides. For BWR fuel crud the main phases are hematite and nonstoichiometric nickel ferrite spinels. For PWR fuel crud the main phases are nonstoichiometric nickel ferrite and nickel metal or nickel oxide. Fuel crud is usually thin and relatively porous in the outer layer but dense in the inner layer. Important information is lacking about the adhesion property of crud particles or agglomerates on fuel rods. Little, if any, information is reported about the characteristics of fuel crud before discharging in pool. It is uncertain if the fuel crud can, after pool discharge, largely preserve its characteristics appearing during reactor operation. Deposition behaviour of corrosion products on fuel rods, in both solid particles and ionic forms in reactor water, has been well studied in the simulated reactor water environments without irradiation. The influences on deposition rate of pH, heat flux, particle size, crud concentration, and flow rate have also been studied in detail. Most of the experimental observations may be qualitatively explained by the theories developed. However, the importance of each influencing parameter remains largely unknown in the complicated reactor water environments, because irradiation, among various influencing factors, may play an important role. The behaviour of crud dissolution has been extensively studied in various reactor water environments. Generally speaking, the more easily crud

  18. Factors Affecting Location Decisions of Food Processing Plants

    Science.gov (United States)

    Turhan, Sule; Canan Ozbag, Basak; Cetin, Bahattin

    The main aim of this study is to examine the determinants of location choices for food processing plants using the results of 59 personal surveys. The 61.3% of the food processing plants that were interviewed are small scale plants, 9.1% are large scale plants and 29.6% are medium scale plants. Sixteen of the firms process vegetables, 12 process poultry, 12 process dairy and 9 process seafood products. Business climate factors are divided into six categories (market, infrastructure, raw material, labor, personal and environmental) and 17 specific location factors are considered. The survey responses are analyzed by types of raw materials processed and by plant size. 43.7, 55.3 and 42.2% of the respondents cited categories of Market, Raw Material and Infrastructure respectively as important, while 44.3, 50.7 and 74.4% of the respondents cited, labor, personal and environmental regulation categories of as not important. Thus survey findings indicate that plant location choices are mainly driven by market, raw material and infra structural factors. Environmental factors such as environmental regulations and permissions are relatively insignificant.

  19. Processing and properties of a solid energy fuel from municipal solid waste (MSW) and recycled plastics

    Energy Technology Data Exchange (ETDEWEB)

    Gug, JeongIn, E-mail: Jeongin_gug@student.uml.edu; Cacciola, David, E-mail: david_cacciola@student.uml.edu; Sobkowicz, Margaret J., E-mail: Margaret_sobkowiczkline@uml.edu

    2015-01-15

    Highlights: • Briquetting was used to produce solid fuels from municipal solid waste and recycled plastics. • Optimal drying, processing temperature and pressure were found to produce stable briquettes. • Addition of waste plastics yielded heating values comparable with typical coal feedstocks. • This processing method improves utilization of paper and plastic diverted from landfills. - Abstract: Diversion of waste streams such as plastics, woods, papers and other solid trash from municipal landfills and extraction of useful materials from landfills is an area of increasing interest especially in densely populated areas. One promising technology for recycling municipal solid waste (MSW) is to burn the high-energy-content components in standard coal power plant. This research aims to reform wastes into briquettes that are compatible with typical coal combustion processes. In order to comply with the standards of coal-fired power plants, the feedstock must be mechanically robust, free of hazardous contaminants, and moisture resistant, while retaining high fuel value. This study aims to investigate the effects of processing conditions and added recyclable plastics on the properties of MSW solid fuels. A well-sorted waste stream high in paper and fiber content was combined with controlled levels of recyclable plastics PE, PP, PET and PS and formed into briquettes using a compression molding technique. The effect of added plastics and moisture content on binding attraction and energy efficiency were investigated. The stability of the briquettes to moisture exposure, the fuel composition by proximate analysis, briquette mechanical strength, and burning efficiency were evaluated. It was found that high processing temperature ensures better properties of the product addition of milled mixed plastic waste leads to better encapsulation as well as to greater calorific value. Also some moisture removal (but not complete) improves the compacting process and results in

  20. Processing and properties of a solid energy fuel from municipal solid waste (MSW) and recycled plastics

    International Nuclear Information System (INIS)

    Highlights: • Briquetting was used to produce solid fuels from municipal solid waste and recycled plastics. • Optimal drying, processing temperature and pressure were found to produce stable briquettes. • Addition of waste plastics yielded heating values comparable with typical coal feedstocks. • This processing method improves utilization of paper and plastic diverted from landfills. - Abstract: Diversion of waste streams such as plastics, woods, papers and other solid trash from municipal landfills and extraction of useful materials from landfills is an area of increasing interest especially in densely populated areas. One promising technology for recycling municipal solid waste (MSW) is to burn the high-energy-content components in standard coal power plant. This research aims to reform wastes into briquettes that are compatible with typical coal combustion processes. In order to comply with the standards of coal-fired power plants, the feedstock must be mechanically robust, free of hazardous contaminants, and moisture resistant, while retaining high fuel value. This study aims to investigate the effects of processing conditions and added recyclable plastics on the properties of MSW solid fuels. A well-sorted waste stream high in paper and fiber content was combined with controlled levels of recyclable plastics PE, PP, PET and PS and formed into briquettes using a compression molding technique. The effect of added plastics and moisture content on binding attraction and energy efficiency were investigated. The stability of the briquettes to moisture exposure, the fuel composition by proximate analysis, briquette mechanical strength, and burning efficiency were evaluated. It was found that high processing temperature ensures better properties of the product addition of milled mixed plastic waste leads to better encapsulation as well as to greater calorific value. Also some moisture removal (but not complete) improves the compacting process and results in

  1. Process monitoring for reprocessing plant safeguards: a summary review

    International Nuclear Information System (INIS)

    Process monitoring is a term typically associated with a detailed look at plant operating data to determine plant status. Process monitoring has been generally associated with operational control of plant processes. Recently, process monitoring has been given new attention for a possible role in international safeguards. International Safeguards Project Office (ISPO) Task C.59 has the goal to identify specific roles for process monitoring in international safeguards. As the preliminary effort associated with this task, a review of previous efforts in process monitoring for safeguards was conducted. Previous efforts mentioned concepts and a few specific applications. None were comprehensive in addressing all aspects of a process monitoring application for safeguards. This report summarizes the basic elements that must be developed in a comprehensive process monitoring application for safeguards. It then summarizes the significant efforts that have been documented in the literature with respect to the basic elements that were addressed

  2. Organizational processes and nuclear power plant safety

    International Nuclear Information System (INIS)

    The paper describes the effects organizational factors have on the risk associated with the operation of nuclear power plants. The described research project addresses three methods for identifying the organizational factors that impact safety. The first method consists of an elaborate theory-based protocol dealing with decision making procedures, interdepartmental coordination of activities, and communications. The second, known as goals/means/measures protocol, deals with identifying safey related goals. The third method is known as behaviorally anchored rating scale development. The paper discusses the importance of the convergence of these three methods to identify organizational factors essential to reactor safety

  3. Combustion behaviour of RDF-BO fuel by using gasification process

    International Nuclear Information System (INIS)

    Malaysia, like most of the developing countries, is facing an increase of waste generation and accompanying problems with the disposal of this waste. On average, municipal solid waste (MSW) generation in Malaysia is about 0.5 - 0.8 kg/person/day and has increased 1.7 kg/person/day in major cities. This has forced the local authorities to look at numerous options available for the treatment and processing of MSW. A local private company, Recycle Energy Sdn Bhd (RESB), took the initiative to develop Refuse-Derived Fuel (RDF) from Malaysia MSW. A pilot plant was set up to serve as the research ground for converting MSW into RDF. However, the calorific value of RDF developed, which is in the range of about 3,500 to 4,000 kcal/kg, is still far off to be a premium fuel even though it is twice over the calorific value of the original MSW. The targeted RDF calorific value to be developed is in the range of 4,000 kcal/kg to 5,000 kcal/kg. As to develop the high quality fuel, numerous studies have been performed to establish the relationship of RDF and various waste materials. Considering the prospective, a research on the project entitles Development of Refuse Derived Fuel (RDF) Fuel Pellets for Industrial and Commercial Usage from Municipal Solid Waste (MSW) In Malaysia has been carried out. The research has been conducted through collaboration with the company. From the study, it was accomplished that the blend of bunker oil and RDF in the ratio of 1:9 is able to produce new RDF or so called as RDF-BO fuel with calorific value higher than 4000 kcal/kg. Considerable the environmental pollution problems, the characteristics of the RDF combustion gasses demanded to be established. This paper will look at the findings and recommendations for work carried out on establishing the combustion behavior of RDF, either in its blended condition or when added with a few additives to reduce or arrest the pollution emission, by using gasification process. (Author)

  4. Dose Assurance in Radiation Processing Plants

    DEFF Research Database (Denmark)

    Miller, Arne; Chadwick, K.H.; Nam, J.W.

    1983-01-01

    Radiation processing relies to a large extent on dosimetry as control of proper operation. This applies in particular to radiation sterilization of medical products and food treatment, but also during development of any other process. The assurance that proper dosimetry is performed at the radiat...

  5. Solar production of intermediate temperature process heat. Phase I design. Final report. [For sugarcane processing plant in Hawaii

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-08-01

    This report is the final effort in the Phase I design of a solar industrial process heat system for the Hilo Coast Processing Company (HCPC) in Pepeekeo, Hawaii. The facility is used to wash, grind and extract sugar from the locally grown sugarcane and it operates 24 hours a day, 305 days per year. The major steam requirements in the industrial process are for the prime movers (mill turbines) in the milling process and heat for evaporating water from the extracted juices. Bagasse (the fibrous residue of milled sugarcane) supplied 84% of the fuel requirement for steam generation in 1979, while 65,000 barrels of No. 6 industrial fuel oil made up the remaining 16%. These fuels are burned in the power plant complex which produces 825/sup 0/F, 1,250 psi superheated steam to power a turbogenerator set which, in addition to serving the factory, generates from 7 to 16 megawatts of electricity that is exported to the local utility company. Extracted steam from the turbo-generator set supplies the plant's process steam needs. The system consists of 42,420 ft./sup 2/ of parabolic trough, single axis tracking, concentrating solar collectors. The collectors will be oriented in a North-South configuration and will track East-West. A heat transfer fluid (Gulf Synfluid 4cs) will be circulated in a closed loop fashion through the solar collectors and a series of heat exchangers. The inlet and outlet fluid temperatures for the collectors are 370/sup 0/F and 450/sup 0/F respectively. It is estimated that the net useable energy delivered to the industrial process will be 7.2 x 10/sup 9/ Btu's per year. With an HCPC boiler efficiency of 78% and 6.2 x 10/sup 6/ Btu's per barrel of oil, the solar energy system will displace 1489 barrels of oil per year. (WHK)

  6. CONCEPT-5, Cost and Economics Analysis for Nuclear Fuel or Fossil Fuel Power Plant

    International Nuclear Information System (INIS)

    1 - Description of problem or function: The CONCEPT computer code system was developed to provide conceptual capital cost estimates for nuclear and coal-fired power plants. Cost estimates can be made as a function of plant type, size, location, and date of initial operation. The output includes a detailed breakdown of the estimate into direct and indirect costs similar to the accounting system described in document NUS-531. Cost models are provided in CONCEPT5, the fifth generation in the development of the CONCEPT package, for single-unit coal-fired plants, pressurized-water reactors, boiling- water reactors, liquid-metal-cooled reactors, and multi-unit coal- fired plants based on today's average or best operating experience. Costs may be obtained for any of twenty U.S. cities, a hypothetical Middletown site, and two Canadian cities. CONCEPT5 models are updated models of those available in CONCEPT3 and, in addition, this edition contains historical factory equipment cost data for the generation of cost indices and escalation rates; indirect costs are calculated as a function of unit size rather than a function of direct costs; and an indirect cost account for owner's costs and an improved time-dependent escalation feature are included. The CONCEPT3 models and cost data are outdated; the package is being retained in the library since it is the only UNIVAC1108 machine version of CONCEPT available and could prove helpful in converting the latest IBM release. 2 - Method of solution: CONCEPT is based on the premise that any central station power plant involves approximately the same major cost components regardless of location or date of initial operation. The program has detailed cost models for each plant type at a reference condition. Through use of size, time, and location- dependent cost adjustments, a reference cost model is modified to produce a specific capital cost estimate. CONCEPT is supported by two auxiliary programs--CONTAC, which generates and maintains

  7. Development of molten carbonate fuel cell power plant technology. Quarterly technical progress report No. 2, January 1-March 31, 1980

    Energy Technology Data Exchange (ETDEWEB)

    Healy, H. C.; Sanderson, R. A.; Wertheim, F. J.; Farris, P. F.; Mientek, A. P.; Maricle, D. L.; Briggs, T. A.; Preston, Jr., J. L.; Louis, G. A.; Abrams, M. L.; Bushnell, C. L.; Nickols, R. C.; Gelting, R. L.; Katz, M.; Stewart, R. C.; Kunz, H. R.; Gruver, G. A.; Bregoli, L. J.; Steuernagel, W. H.; Smith, R.; Smith, S. W.; Szymanski, S. T.

    1980-08-01

    The overall objective of this 29-month program is to develop and verify the design of a prototype molten carbonate fuel cell stack which meets the requirements of 1990's competitive coal-fired electrical utility central station or industrial cogeneration power plants. During this quarter, effort was continued in all four major task areas: Task 1 - system studies to define the reference power plant design; Task 2 - cell and stack design, development and verification; Task 3 - preparation for fabrication and testing of the full-scale prototype stack; and Task 4 - developing the capability for operation of stacks on coal-derived gas. In the system study activity of Task 1, preliminary module and cell stack design requirements were completed. Fuel processor characterization has been completed by Bechtel National, Inc. Work under Task 2 defined design approaches for full-scale stack busbars and electrical isolation of reactant manifolds and reactant piping. Preliminary design requirements were completed for the anode. Conductive nickel oxide for cathode fabrication has been made by oxidation and lithiation of porous nickel sheet stock. A method of mechanizing the tape casting process for increased production rates was successfully demonstrated under Task 3. In Task 4, theoretical calculations indicated that hydrogen cyanide and ammonia, when present as impurities in the stack fuel gas, will have no harmful effects. Laboratory experiments using higher than anticipated levels of ethylene showed no harmful effects. Components for the mobile test facility are being ordered.

  8. Design and production process of bushing-type fuel elements for channel research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Afanasiev, V.L.; Aleksandrov, A.B.; Enin, A.A. [NZHK, Novosibirsk (Russian Federation)

    1998-07-01

    The design of bushing-type fuel elements (FEs) based on the dioxide fuel composition UO{sub 2}+Al for channel research reactors is described. Commercial technological process for bushing-type FEs with up to 0.8 g/cm{sup 3} uranium concentration in the fuel core is presented. This technology is based on fuel core production using powder metallurgy with subsequent chemical treatment of its surface and enclosing into the finished cladding. Commercial technological process for bushing-type FEs with 0.8-3.8 g/cm{sup 3} uranium concentration in the fuel composition is considered. This process is based on fuel core production by means of extrusion technology followed by fuel core enclosing into the cladding. (author)

  9. Spent Nuclear Fuel (SNF) Project Design Verification and Validation Process

    International Nuclear Information System (INIS)

    This document provides a description of design verification and validation activities implemented by the Spent Nuclear Fuel (SNF) Project. During the execution of early design verification, a management assessment (Bergman, 1999) and external assessments on configuration management (Augustenburg, 1999) and testing (Loscoe, 2000) were conducted and identified potential uncertainties in the verification process. This led the SNF Chief Engineer to implement corrective actions to improve process and design products. This included Design Verification Reports (DVRs) for each subproject, validation assessments for testing, and verification of the safety function of systems and components identified in the Safety Equipment List to ensure that the design outputs were compliant with the SNF Technical Requirements. Although some activities are still in progress, the results of the DVR and associated validation assessments indicate that Project requirements for design verification are being effectively implemented. These results have been documented in subproject-specific technical documents (Table 2). Identified punch-list items are being dispositioned by the Project. As these remaining items are closed, the technical reports (Table 2) will be revised and reissued to document the results of this work

  10. Spent Nuclear Fuel (SNF) Project Design Verification and Validation Process

    Energy Technology Data Exchange (ETDEWEB)

    OLGUIN, L.J.

    2000-09-25

    This document provides a description of design verification and validation activities implemented by the Spent Nuclear Fuel (SNF) Project. During the execution of early design verification, a management assessment (Bergman, 1999) and external assessments on configuration management (Augustenburg, 1999) and testing (Loscoe, 2000) were conducted and identified potential uncertainties in the verification process. This led the SNF Chief Engineer to implement corrective actions to improve process and design products. This included Design Verification Reports (DVRs) for each subproject, validation assessments for testing, and verification of the safety function of systems and components identified in the Safety Equipment List to ensure that the design outputs were compliant with the SNF Technical Requirements. Although some activities are still in progress, the results of the DVR and associated validation assessments indicate that Project requirements for design verification are being effectively implemented. These results have been documented in subproject-specific technical documents (Table 2). Identified punch-list items are being dispositioned by the Project. As these remaining items are closed, the technical reports (Table 2) will be revised and reissued to document the results of this work.

  11. Energy analysis and environmental impacts of a MSW oxy-fuel incineration power plant in China

    International Nuclear Information System (INIS)

    The entire life cycle of a municipal solid waste (MSW) oxy-fuel incineration power plant was evaluated using the method of life cycle assessment (LCA) to identify and quantify the fossil energy requirements and environmental impacts. The functional unit was 1000 kg (1 t) MSW. During the life cycle, the saving standard coal by electricity generation was more than diesel consumption, and the effect of soot and ashes was the greatest among all calculated categorization impacts. The total weighted resource consumption and total weighted environment potential of MSW oxy-fuel incineration were −0.37 mPR90 (milli person equivalent) and −0.27 PET2010 (person equivalent), better than MSW incineration with CO2 capture via monoethanolamine (MEA) absorption. The sensitivity analysis showed that the electric power consumption of air separation unit (ASU) was the primary influencing parameter, and the influence of electric power consumption of CO2 compressor was secondary, while transport distance had small influence. Overall, MSW oxy-fuel incineration technology has certain development potential with the increment of MSW power supply efficiency and development of ASU in the future. - Highlights: • Life cycle assessment of a MSW oxy-fuel incineration power plant is novel. • The MSW oxy-fuel incineration was better than the MSW incineration with MEA. • Among calculated impacts, the effect of soot and ashes was the greatest. • The electric power consumption of ASU was the primary influencing parameter

  12. Safety aspects of core management and fuel handling for nuclear power plants

    International Nuclear Information System (INIS)

    This Safety Guide was prepared as part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to nuclear power plants. It supplements the Code of Practice on Safety in Nuclear Power Plant Operation, including Commissioning and Decommissioning (IAEA Safety Series No. 50-C-O). This Guide describes the safety objectives of core management, the tasks which have to be accomplished to meet these objectives, and the activities undertaken to perform those tasks. It also covers the storage and handling of fuel and core components; the loading and unloading of fuel and core components; and the insertion and removal of other core materials such as moderator, coolant and absorbers, relevant to core management. The loading of the transport container with irradiated fuel and the preparation for transport off-site are further topics that are included. Transportation requirements and safety precautions for transport beyond the site, off-site storage and ultimate disposal of irradiated fuel and core components are not covered by this Guide, although the Operating Organization may be responsible for securing the services involved. Aspects of fuel accounting not directly related to safety are not considered

  13. Reintegration of areas of the IPEN's dismantled nuclear fuel cycle pilot plants as new laboratories of the CQMA

    International Nuclear Information System (INIS)

    IPEN has faced the problem of the dismantling of their Nuclear Fuel Cycle old facilities. Those facilities already played their roles of technological development and personnel's training, with transfer of the technology for institutions entrusted of the 'scale up' of the units. Most of the pilot plants interrupted the activities more than ten years ago, due to the lack of resources for the continuity of the research. The appropriate facilities maintenance has been also harmed by the lack of resources, with evident signs of deterioration in structures and equipment. The existence of these facilities also implicates in the need of constant surveillance, representing additional obligations, costs and problems. The reasons to promote as soon as possible the dismantling of the IPEN's Nuclear Fuel Cycle Pilot Plants elapse mainly from the need of physical space for new activities, since the R and D in the nuclear fuel cycle area were interrupted and from the loss of personnel that set up and operated the referred units, one of the most concerning aspects in case of the postponement of the dismantling process. One of these new activities is the IPEN's Environmental Program. In the building where there was the Uranium Dissolution and Purification Pilot Plant, already dismantled, it was decided to settle the Laboratory of Chemical and Environmental Analyses, being necessary its total liberation from the point of view of radioactive contamination. This paper describes the procedures, problems faced and results related to the reintegration of the former pilot plant areas as new laboratories of the Chemical and Environmental Technology Center - CQMA - of the IPEN. (author)

  14. Process flow model of solid oxide fuel cell system supplied with sewage biogas

    Science.gov (United States)

    Van herle, J.; Maréchal, F.; Leuenberger, S.; Membrez, Y.; Bucheli, O.; Favrat, D.

    A model for a 100 kW class solid oxide fuel cell (SOFC) system running on biogas from a sewage sludge digestion plant was implemented in a process flow scheme using external steam reforming. The model stack consisted of planar anode supported cells operated at 800 °C displaying state-of-the-art electrochemical performance (0.15 W/cm 2 at 80% fuel utilisation). Real annual data from an existing sewage plant were used as input to the model. From the input of 43 m 3/h biogas (63% CH 4), equivalent to 269 kW (higher heating value, HHV), the SOFC stack was calculated to deliver 131 kW el electricity (48.7%) using a steam-to-carbon ratio of 0.5. This would allow the sewage site to more than cover its own electrical needs, hence to depollute the waste stream at negative energy cost. In its current exploitation using a low efficient gas engine (130 kW), the site is only ≈50% self-sufficient. Special attention was given to the thermal balance of the stack. The stack developed heat (143 kW) could be balanced by endothermal reforming (78 kW) and by cathode excess air λ (=3), allowing a temperature difference between stack inlet and outlet of 200 K. The case was compared to other fuel scenarios. Steam-added biogas behaves basically identically to steam-reformed methane. For partial oxidation of biogas or pure hydrogen feeding, electrical efficiency drops to under 43% while λ needs to be raised to 4.5 to maintain the 200 K thermal gradient over the stack.

  15. Spanish experience of fuel performance under zinc injection conditions in high duty plants

    International Nuclear Information System (INIS)

    Zinc is being added to the reactor coolant system in three Spanish PWRs (Vandellos II, Asco I and Asco II), owned by Association Nuclear Asco Vandellos AIE (ANAV), to delay Primary Water Stress Corrosion Cracking (PWSCC) initiation. Although additional advantages from zinc addition are expected, in the short term some concern exists concerning fuel performance during the first cycles of zinc addition due to a possible elevation of corrosion products from system materials when zinc is initially added. Elevated corrosion product levels in a high duty plant may cause an enhancement on crud deposited on fuel, increasing Axial Offset Anomaly (AOA) risk and accelerated cladding corrosion. To demonstrate the acceptable performance of ZIRLOTM clad fuel under zinc chemistry at a high duty plant, EPRI's Fuel Reliability Program (FRP) has chosen Vandellos II as a zinc demonstration plant to perform oxide thickness measurements and crud scraping and analysis. This paper presents the results from Vandellos II and Asco II oxide measurements as well as the conclusions from the crud samples analyses performed at Vandellos II. Furthermore, the effect of zinc addition on corrosion product behavior and dose rates are be discussed

  16. Process modeling of fuel cell vehicle power system

    Institute of Scientific and Technical Information of China (English)

    CHEN LiMing; LIN ZhaoJia; MA ZiFeng

    2009-01-01

    Constructed here is a mathematic model of PEM Fuel Cell Vehicle Power System which is composed of fuel supply model, fuel cell stack model and water-heat management model. The model was developed by Matiab/Simulink to evaluate how the major operating variables affect the output performances. Itshows that the constructed model can represent characteristics of the power system closely by comparing modeling results with experimental data, and it can be used in the study and design of fuel cell vehicle power system.

  17. Conceptual design of light integrated gasification fuel cell based on thermodynamic process simulation

    International Nuclear Information System (INIS)

    Highlights: • Light integrated gasification fuel cell (L-IGFC) power plant is proposed. • Dry gas desulfurization (DGD) is a key to increase the efficiency of the L-IGFC. • Atmospheric L-IGFC gives electrical efficiency over 46%LHV. • Pressurized operation of solid oxide fuel cell offers electrical efficiency of L-IGFC over 50%LHV. - Abstract: Integration of solid oxide fuel cell (SOFC) in coal gasification power plant technology would be one of the most promising technology in the coal utilization for power generation. The clean syngas from gas cleanup unit serves as fuel for SOFC in integrated gasification fuel cell power plant. The heat generated by SOFC can be utilized by heat recovery steam generator to drive steam turbine for electricity production. In this study, proposed plants consisting of coal gasifier and SOFC on the top of a steam turbine (ST), called light integrated gasification fuel cell (L-IGFC), are investigated thermodynamically by using Aspen Plus software to evaluate their performance. The analyses are based on the SOFC module considering ohmic, activation and concentration losses at a certain current density of the cell operating at the intermediate temperature. The influences of gas cleanup unit models were also investigated. The results indicated that the proposed atmospheric L-IGFC plant could achieve electrical efficiency in the range of 39–46.35% in lower heating value

  18. Operational assessment of the transnuclear TN-9 truck spent fuel shipping cask: studies and research concerning BNFP

    International Nuclear Information System (INIS)

    This report presents the results of an operational assessment of the Transnuclear Inc., TN-9 spent fuel cask. This packaging system transports seven current generation boiling-water-reactor nuclear fuel assemblies in a truck shipping mode. The studies were performed at the Barnwell Nuclear Fuel Plant by employees of Allied-General Nuclear Services. The work was funded by the Department of Energy during fiscal year 1981. The cooperation of Transnuclear in this effort is gratefully acknowledged. The study is based on repeated simulated unloading runs of TN-9. Specific tasks and areas of study included: (1) sequential dry-run handling operations under simulated unloading conditions, (2) detailed time and manpower studies, (3) estimates of operator radiation exposure, (4) a general evaluation of the cask system capabilities as they relate to unloading and loading facility operations, and (5) preparation of operating procedures for both unloading (confirmed by practice runs) and loading (yet to be confirmed). Also included is general information on the cask, auxiliary equipment, and the Certificate of Compliance

  19. Reactor Physics Parametric and Depletion Studies in Support of TRISO Particle Fuel Specification for the Next Generation Nuclear Plant

    International Nuclear Information System (INIS)

    Reactor physics calculations were initiated to answer several major questions related to the proposed TRISO-coated particle fuel that is to be used in the prismatic Very High Temperature Reactor (VHTR) or the Next Generation Nuclear Plant (NGNP). These preliminary design evaluation calculations help ensure that the upcoming fuel irradiation tests will test appropriate size and type of fuel particles for a future NGNP reactor design. Conclusions from these calculations are expected to confirm and suggest possible modifications to the current particle fuel parameters specified in the evolving Fuel Specification. Calculated results dispel the need for a binary fuel particle system, which is proposed in the General Atomics GT-MHR concept. The GT-MHR binary system is composed of both a fissile and fertile particle with 350- and 500-micron kernel diameters, respectively. For the NGNP reactor, a single fissile particle system (single UCO kernel size) can meet the reactivity and power cycle length requirements demanded of the NGNP. At the same time, it will provide substantial programmatic cost savings by eliminating the need for dual particle fabrication process lines and dual fuel particle irradiation tests required of a binary system. Use of a larger 425-micron kernel diameter single fissile particle (proposed here), as opposed to the 350-micron GT-MHR fissile particle size, helps alleviate current compact particle packing fractions fabrication limitations (<35%), improves fuel block loading for higher n-batch reload options, and tracks the historical correlation between particle size and enrichment (10 and 14 wt% U-235 particle enrichments are proposed for the NGNP). Overall, the use of the slightly larger kernel significantly broadens the NGNP reactor core design envelope and provides increased design margin to accommodate the (as yet) unknown final NGNP reactor design. Maximum power-peaking factors are calculated for both the initial and equilibrium NGNP cores

  20. Spectrophotometric determination of uranium in liquid waste generated in Fuel Fabrication Plant

    International Nuclear Information System (INIS)

    During fabrication of uranium bearing nuclear fuels, liquid waste is being generated. The liquid waste contains impurities such as Ca, Na, Fe, Ni, Cr etc. The total dissolved solids (TDS) are high, upto 400 gram per litre (gpl). Study has been carried out for spectrophotometric determination of uranium in solution employing Arsenazo-III as metal indicator. The absorbance was measured at 655 nm. For U: Ca ratio 1:10 no interference was observed. For U:Ca ratio of 1:125, uranium concentration was reduced by ∼5%. The method can be applied for determination of uranium in liquid waste generated in fuel fabrication plant. (author)

  1. Grain growth and temperature distribution in the irradiated fuel elements designed for Qinshan Power Plant

    International Nuclear Information System (INIS)

    The micro-analysis results of UO2 fuel core of irradiated test elements designed for Qinshan Power Plant are presented. The temperature of element centers is quantitatively calculated by using the grain size measurement results according to the principle of grain growth dynamics, and the results are in accordance with that of the FRAP-CON calculation. Based on the post-irradiation examination data, the dynamic parameters, K and Q which are particularly suitable to description of irradiation behaviours of UO2 fuel made in China are deduced

  2. Implementation of the utilization program for the fuel elements of the Atucha I nuclear power plant

    International Nuclear Information System (INIS)

    The programming operation for the use of the fuel elements in the Atucha-1 nuclear power plant was initially under the responsibility of the KWU Company, as part of the services rendered due for the manufacturing of said elements. This job was done with the help of the TRISIC program, developed in the early seventies by CNEA and SIEMENS staff. From april 21, 1979 on, CNEA took over the responsibility and strategy of the interchange of fuel elements. The several stages carried out for the implementation of this service are detailed. (M.E.L.)

  3. Introduction of second fuel in regularly exploitation of the existing thermal power plants (in Macedonia)

    International Nuclear Information System (INIS)

    The limited sources of lignite in Macedonia establish the problem of rational use of remaining resources in existing thermal power plants. With aim to analyze the further development directions on time, this proposal will slow down the dynamics for use of existing exploitation beds. Also, the decisions for optimal perspective solutions will be made on more relaxed way. The use of secondary fuel in existing TPP's will allow us to deal continuously. The advantage of substituting one type of fuel with other is continual adaptation of equipment as well as staff. (Original)

  4. Seismic analysis of the nuclear fuel service reprocessing plant at West Valley, N. Y

    Energy Technology Data Exchange (ETDEWEB)

    Murray, R.C.; Nelson, T.A.; Davito, A.M.

    1977-05-24

    This report was prepared at the request of the Nuclear Regulatory Commission as a part of a license review of the nuclear fuel reprocessing plant operated by Nuclear Fuel Services, Inc., at West Valley, N.Y. The report discusses the approach used by the Lawrence Livermore Laboratory in performing an independent seismic analysis of the facility. It includes a description of the facility, our modeling and analysis techniques, failure criteria, results, and conclusions. Two modes of failure are identified and their consequences discussed.

  5. Materials management in an internationally safeguarded fuels reprocessing plant

    International Nuclear Information System (INIS)

    The following appendices are included: aqueous reprocessing and conversion technology, reference facilities, process design and operating features relevant to materials accounting, operator's safeguards system structure, design principles of dynamic materials accounting systems, modeling and simulation approach, optimization of measurement control, aspects of international verification problem, security and reliability of materials measurement and accounting system, estimation of in-process inventory in solvent-extraction contactors, conventional measurement techniques, near-real-time measurement techniques, isotopic correlation techniques, instrumentation available to IAEA inspectors, and integration of materials accounting and containment and surveillance

  6. Materials management in an internationally safeguarded fuels reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Hakkila, E.A.; Baker, A.L.; Cobb, D.D.

    1980-04-01

    The following appendices are included: aqueous reprocessing and conversion technology, reference facilities, process design and operating features relevant to materials accounting, operator's safeguards system structure, design principles of dynamic materials accounting systems, modeling and simulation approach, optimization of measurement control, aspects of international verification problem, security and reliability of materials measurement and accounting system, estimation of in-process inventory in solvent-extraction contactors, conventional measurement techniques, near-real-time measurement techniques, isotopic correlation techniques, instrumentation available to IAEA inspectors, and integration of materials accounting and containment and surveillance. (DLC)

  7. Biorefinery plant design, engineering and process optimisation

    DEFF Research Database (Denmark)

    Holm-Nielsen, Jens Bo; Ehimen, Ehiazesebhor Augustine

    2014-01-01

    applicable for the planning and upgrading of intended biorefinery systems, and includes discussions on the operation of an existing lignocellulosic-based biorefinery platform. Furthermore, technical considerations and tools (i.e., process analytical tools) which could be applied to optimise the operations...

  8. DOE Coal Gasification Multi-Test Facility: fossil fuel processing technical/professional services

    Energy Technology Data Exchange (ETDEWEB)

    Hefferan, J.K.; Lee, G.Y.; Boesch, L.P.; James, R.B.; Rode, R.R.; Walters, A.B.

    1979-07-13

    A conceptual design, including process descriptions, heat and material balances, process flow diagrams, utility requirements, schedule, capital and operating cost estimate, and alternative design considerations, is presented for the DOE Coal Gasification Multi-Test Facility (GMTF). The GMTF, an engineering scale facility, is to provide a complete plant into which different types of gasifiers and conversion/synthesis equipment can be readily integrated for testing in an operational environment at relatively low cost. The design allows for operation of several gasifiers simultaneously at a total coal throughput of 2500 tons/day; individual gasifiers operate at up to 1200 tons/day and 600 psig using air or oxygen. Ten different test gasifiers can be in place at the facility, but only three can be operated at one time. The GMTF can produce a spectrum of saleable products, including low Btu, synthesis and pipeline gases, hydrogen (for fuel cells or hydrogasification), methanol, gasoline, diesel and fuel oils, organic chemicals, and electrical power (potentially). In 1979 dollars, the base facility requires a $288 million capital investment for common-use units, $193 million for four gasification units and four synthesis units, and $305 million for six years of operation. Critical reviews of detailed vendor designs are appended for a methanol synthesis unit, three entrained flow gasifiers, a fluidized bed gasifier, and a hydrogasifier/slag-bath gasifier.

  9. Modeling of large-scale oxy-fuel combustion processes

    DEFF Research Database (Denmark)

    Yin, Chungen

    2012-01-01

    Quite some studies have been conducted in order to implement oxy-fuel combustion with flue gas recycle in conventional utility boilers as an effective effort of carbon capture and storage. However, combustion under oxy-fuel conditions is significantly different from conventional air-fuel firing....... The simulation results show that the gray and non-gray calculations of the same oxy-fuel WSGGM make distinctly different predictions in the wall radiative heat transfer, incident radiative flux, radiative source, gas temperature and species profiles. In relative to the non-gray implementation, the gray...... calculation of the oxy-fuel WSGGM remarkably over-predicts the radiative heat transfer to the furnace walls and under-predicts the gas temperature at the furnace exit plane, which also result in a higher incomplete combustion in the gray calculation. Moreover, the gray and non-gray calculations of the same...

  10. The development of corona discharge for iodine removal from nuclear fuel reprocessing plant off-gases

    International Nuclear Information System (INIS)

    Studies on single, wire-in-tube corona discharge experimental rigs have been carried out to examine the behaviour of molecular iodine, organic iodide and oxides of nitrogen (NOx) in both glow and streamer corona discharges. The parameters investigated include electrode potential, electrode geometry, gas composition and throughput, and for the streamer corona, pulse length and repetition frequency. Operations with continuous irrigation of the ground (tube) electrode for both glow and streamer discharges are also discussed. Organic iodine DFs in excess of 104 (>99.99% removal) have been readily achieved, and the use of streamer coronas has significantly reduced the interfering effects of NOx and moisture which have been established in earlier work. Two outline process options are presented, one based on a single stage irrigated streamer corona and the second on a two stage scheme utilising an irrigated glow discharge unit as the first stage for NOx removal, followed by a second stage dry streamer unit for iodine removal. The estimated power consumption and unit size of corona units for treating dissolver off-gases from a reprocessing plant with a nominal 5te/day fuel throughput are presented

  11. An intelligent emissions controller for fuel lean gas reburn in coal-fired power plants.

    Science.gov (United States)

    Reifman, J; Feldman, E E; Wei, T Y; Glickert, R W

    2000-02-01

    The application of artificial intelligence techniques for performance optimization of the fuel lean gas reburn (FLGR) system is investigated. A multilayer, feedforward artificial neural network is applied to model static nonlinear relationships between the distribution of injected natural gas into the upper region of the furnace of a coal-fired boiler and the corresponding oxides of nitrogen (NOx) emissions exiting the furnace. Based on this model, optimal distributions of injected gas are determined such that the largest NOx reduction is achieved for each value of total injected gas. This optimization is accomplished through the development of a new optimization method based on neural networks. This new optimal control algorithm, which can be used as an alternative generic tool for solving multidimensional nonlinear constrained optimization problems, is described and its results are successfully validated against an off-the-shelf tool for solving mathematical programming problems. Encouraging results obtained using plant data from one of Commonwealth Edison's coal-fired electric power plants demonstrate the feasibility of the overall approach. Preliminary results show that the use of this intelligent controller will also enable the determination of the most cost-effective operating conditions of the FLGR system by considering, along with the optimal distribution of the injected gas, the cost differential between natural gas and coal and the open-market price of NOx emission credits. Further study, however, is necessary, including the construction of a more comprehensive database, needed to develop high-fidelity process models and to add carbon monoxide (CO) emissions to the model of the gas reburn system.

  12. An intelligent emissions controller for fuel lean gas reburn in coal-fired power plants.

    Science.gov (United States)

    Reifman, J; Feldman, E E; Wei, T Y; Glickert, R W

    2000-02-01

    The application of artificial intelligence techniques for performance optimization of the fuel lean gas reburn (FLGR) system is investigated. A multilayer, feedforward artificial neural network is applied to model static nonlinear relationships between the distribution of injected natural gas into the upper region of the furnace of a coal-fired boiler and the corresponding oxides of nitrogen (NOx) emissions exiting the furnace. Based on this model, optimal distributions of injected gas are determined such that the largest NOx reduction is achieved for each value of total injected gas. This optimization is accomplished through the development of a new optimization method based on neural networks. This new optimal control algorithm, which can be used as an alternative generic tool for solving multidimensional nonlinear constrained optimization problems, is described and its results are successfully validated against an off-the-shelf tool for solving mathematical programming problems. Encouraging results obtained using plant data from one of Commonwealth Edison's coal-fired electric power plants demonstrate the feasibility of the overall approach. Preliminary results show that the use of this intelligent controller will also enable the determination of the most cost-effective operating conditions of the FLGR system by considering, along with the optimal distribution of the injected gas, the cost differential between natural gas and coal and the open-market price of NOx emission credits. Further study, however, is necessary, including the construction of a more comprehensive database, needed to develop high-fidelity process models and to add carbon monoxide (CO) emissions to the model of the gas reburn system. PMID:10680354

  13. Radiation processing plants in India - present status and trends

    International Nuclear Information System (INIS)

    We are the first engineering group who came out with the concept of setting up of multipurpose radiation processing facilities with split type of source frame with continuous process. The first such plant was designed and commissioned at Jhunsons Chemicals Pvt. Ltd., Bhiwadi - in the year 2009 and this plant started commercial operation in early 2010. During last four years the success of this plant for gamma irradiation of different product in different dose range is highly encouraging. The design concept of multipurpose irradiator of JCPL is as follows: Product overlapping type design, Mode of operation is continuous, Unique feature is no breakage of process cycle for box shuffling - it is integrated with continuous process of shuffle dwell system within the radiation cell. Split type source frame is designed to cater the low dose application for better flexibility of plant. The tote box is palletized to handle with forks. The maximum capacity of tote box is 250 kg of materials depending upon the product density and package size. The maximum speed of conveyor achieved is 52 boxes / hour, which is equivalent to 12 to 13 ton/hour, when 250 kg material loaded in the box. In last four years this plant has established new trends in contract radiation processing service. This plant has processed following materials in the last four years successfully within the stipulated dose rate

  14. Criticality accident in uranium fuel processing plant. Progress and reflection of the criticality accident in the uranium fuel processing plant

    International Nuclear Information System (INIS)

    As one year is already passing since forming of the JCO criticality accident, impact given by this accident was so large as to vibrate all of nuclear energy field. This accident was the first instantly forming criticality accident since beginning of peaceful use in nuclear energy in Japan, which formed some severe victims containing two dead and an experienced affair required for evacuation and shelter of the peripheral inhabitants. Direct cause of the instantly forming criticality accident in this accident is simple and clear, and is caused by failure in the most essential technology specific to nuclear energy called by criticality management. And that, it was caused not by instrument accident or human individual error but by recent exceptional blunder in and out of Japan at a point of direct reason on evil violation act due to management organization. And, for the response specific to the nuclear energy field, a drastic reinvestigation on safety filed, a drastic reinvestigation on safety regulation system is also required. On the other hand, in nuclear safety education requiring establishment of safety culture for its foundation, a reflection that it has remained only to moral action to bring a result to suppress power carrying out its practice inversely, was also recognized. And, it is necessary to carry out more efforts and devices for difficulty on management forecast in future in nuclear energy industry not so as to make a system of safety conservation weaker. (G.K.)

  15. Industrial applications for remote operation in a processing plant

    International Nuclear Information System (INIS)

    In the first part of this article, J. Hermier covers the use of remote handling equipment in the UP2-400 plant at La Hague near Cherbourg, in which for the most part master/slave mechanism remote handling units are used with a number of these employed in daily processing operations. As regards this subject, it is useful to remember that, at the time of the designing of this plant (UP2-400), this was the only equipment available on the market with remote-controlled remote handling equipment. In the second part, before speaking about the development of remote operation equipment in the plants now under construction and attempting to project what might be the remote operation role in future plants, R. Le Guennec reviews the problems faced by engineering in designing industrial-sized processing plants and, consequently, the motivations of engineering when faced with a choice between several possible solutions

  16. Improved material accounting for plutonium processing facilities and a /sup 235/U-HTGR fuel fabrication facility

    Energy Technology Data Exchange (ETDEWEB)

    McSweeney, T.I.; Johnston, J.W.; Schneider, R.A.; Granquist, D.P.

    1975-10-01

    This study described the general safeguards characteristics of a material measurement system and then describes typical accounting systems for a fuel reprocessing plant, a plutonium nitrate to oxide conversion facility, a LWR mixed oxide fuel fabrication facility, and a high-enriched uranium HTGR fuels plant. These facilities are commercial size, envisioned to be operating in the mid-1980s. Present facilities tend to have large static inventories of material whereas future facilities will have a high material throughput. Systematic errors will pose the greatest limit on measurement systems in future facilities. Recommendations are given for the licensing review process for material accounting performance, the capability of measurement systems and regulations governing cumulative LEMUF and series of MUFs. Present regulations and the recommendations should result in improved material accounting in future facilities. Improvements specific to a particular facility were also identified. The recommendations should greatly improve the material accounting characteristics of future plutonium and high-enriched uranium processing facilities. Benefits of an improved material accounting system are compared with the costs of the improvements. The requirement for a formal quarterly inventory over the separations area of a reprocessing plant results in an annual lost production cost of $25M. This high penalty prevents reducing the formal inventory requirement from the present semiannual regulatory requirement. In all other cases, the cost-benefit relationship of the improvements is favorable. 8 fig., 53 tables. (DLC)

  17. Method for the processing of irradiated nuclear fuel

    International Nuclear Information System (INIS)

    The improved Purex method to process U, Pu, neptunium, as well as fission products Zr 95, Nb 95, Ru 103 and Ru 106 results in a higher decontamination factor than sofar achieved. The fuel contained in an aqueous nitric acid solution is treated by extraction with an organic solvent containing tributyl phosphate and a water-non-mixable hydrocarbon diluting agent (kerosin or n-dedocane). The organic solution is thus introduced into a multistage return flow column and the U concentration is kept at over 90% saturation. To maintain a degree of acidity of 1 mol, one adds nitric acid to the aqueous return flow via the extraction region. The tributyl phosphate is introduced at the lower end of the column in counter-current to the return flow. The concentrated uranium-containing organic solution obtained at the upper end is passed into an aqueous solution in countercurrent to a ca. 0.01 molar nitric acid solution for the U conversion. (DG)

  18. Heterogeneous catalytic process for alcohol fuels from syngas

    Energy Technology Data Exchange (ETDEWEB)

    Minahan, D.M.; Nagaki, D.A.

    1995-12-31

    This project is focused on the discovery and evaluation of novel heterogeneous catalyst for the production of oxygenated fuel enhancers from synthesis gas. Catalysts have been studied and optimized for the production of methanol and isobutanol mixtures which may be used for the downstream synthesis of MTBE or related oxygenates. Higher alcohols synthesis (HAS) from syngas was studied; the alcohols that are produced in this process may be used for the downstream synthesis of MTBE or related oxygenates. This work has resulted in the discovery of a catalyst system that is highly selective for isobutanol compared with the prior art. The catalysts operate at high temperature (400{degrees}C), and consist of a spinel oxide support (general formula AB{sub 2}O{sub 4}, where A=M{sup 2+} and B = M{sup 3+}), promoted with various other elements. These catalysts operate by what is believed to be an aldol condensation mechanism, giving a product mix of mainly methanol and isobutanol. In this study, the effect of product feed/recycle (methanol, ethanol. n-propanol, isopropanol, carbon dioxide and water) on the performance of 10-DAN-55 (spinel oxide based catalyst) at 400{degrees}C, 1000 psi, GHSV = 12,000 and syngas (H{sub 2}/CO) ratio = 1:2 (alcohol addition) and 1:1 (carbon dioxide and water addition) was studied. The effect of operation at high temperatures and pressures on the performance of an improved catalyst formulation was also examined.

  19. B Plant process piping replacement feasibility study

    Energy Technology Data Exchange (ETDEWEB)

    Howden, G.F.

    1996-02-07

    Reports on the feasibility of replacing existing embedded process piping with new more corrosion resistant piping between cells and between cells and a hot pipe trench of a Hanford Site style canyon facility. Provides concepts for replacement piping installation, and use of robotics to replace the use of the canyon crane as the primary means of performing/supporting facility modifications (eg, cell lining, pipe replacement, equipment reinstallation) and operational maintenenace.

  20. B Plant process piping replacement feasibility study

    International Nuclear Information System (INIS)

    Reports on the feasibility of replacing existing embedded process piping with new more corrosion resistant piping between cells and between cells and a hot pipe trench of a Hanford Site style canyon facility. Provides concepts for replacement piping installation, and use of robotics to replace the use of the canyon crane as the primary means of performing/supporting facility modifications (eg, cell lining, pipe replacement, equipment reinstallation) and operational maintenenace