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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. The decommissioning of the Barnwell nuclear fuel plant

    International Nuclear Information System (INIS)

    The decommissioning of the Barnwell Nuclear Fuel Plant is nearing completion. The owner's objective is to terminate the plant radioactive material license associated with natural uranium and transuranic contamination at the plant. The property is being released for commercial-industrial uses, with radiation exposure from residual radioactivity not to exceed 0.15 millisieverts per year. Historical site assessments have been performed and the plant characterized for residual radioactivity. The decommissioning of the uranium hexafluoride building was completed in April, 1999. Most challenging from a radiological control standpoint is the laboratory building that contained sixteen labs with a total of 37 glove boxes, many of which had seen transuranics. Other facilities being decommissioned include the separations building and the 300,000-gallon underground high-level waste tanks. This decommissioning in many ways is the most significant project of this type yet undertaken in South Carolina. Many innovations have been made to reduce the time and costs associated with the project. (author)

  6. Barnwell Nuclear Fuels Plant applicability study. Volume I. Summary of major findings and conclusions

    International Nuclear Information System (INIS)

    Description and status of the Barnwell Nuclear Fuels Plant (BNFP) and related fuel cycle facilities, alternative uses of the BNFP other than reprocessing, alternative uses of the BNFP in reprocessing modes, resource utilization and U.S. national security, and ownership/management options are discussed

  7. Studies and research concerning BNFP: spent fuel dry storage studies at the Barnwell Nuclear Fuel Plant

    International Nuclear Information System (INIS)

    Conceptual designs are presented utilizing the Barnwell Nuclear Fuel Plant for the dry interim storage of spent light water reactor fuel. Studies were conducted to determine feasible approaches to storing spent fuel by methods other than wet pool storage. Fuel that has had an opportunity to cool for several years, or more, after discharge from a reactor is especially adaptable to dry storage since its thermal load is greatly reduced compared to the thermal load immediately following discharge. A thermal analysis was performed to help in determining the feasibility of various spent fuel dry storage concepts. Methods to reject the heat from dry storage are briefly discussed, which include both active and passive cooling systems. The storage modes reviewed include above and below ground caisson-type storage facilities and numerous variations of vault, or hot cell-type, storage facilities

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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.)

  19. 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)

  20. 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.

  1. Plutonium processing at the Siemens Hanau fuel fabrication plant

    International Nuclear Information System (INIS)

    The vast amount of experience accumulated to date in the fabrication of plutonium fuel assemblies and the course taken by the protracted licensing procedure is outlined. A description of the processes applied and the plant equipment at the existing fabrication facility is provided. The two new production lines, including ancillary systems with a planned annual capacity of 120 tons of mixed oxide, are also described. The current status of implementation with all licenses granted is also presented

  2. The use of artificial intelligence for safeguard fuel reprocessing plants

    International Nuclear Information System (INIS)

    Recorded process data from minirun campaigns conducted at the Barnwell Nuclear Fuels Plant have been utilized to study the suitability of computer-based artificial intelligence (AI) methods for process monitoring for safeguards purposes. The techniques of knowledge engineering were used to formulate the decision-making software. The computer software accepted as input process data customarily used for process operations that had previously been recorded on magnetic tape during the 1980 miniruns. The OPS5 AI language was used to construct an expert system for simulated monitoring of the process. Such expert systems facilitate the employment of the heuristic reasoning used by human observers to form reasoned conclusions from incomplete, inaccurate, or otherwise fuzzy data

  3. 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.

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

    International Nuclear Information System (INIS)

    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

  5. Processing of organic effluents from spent fuel reprocessing plants

    International Nuclear Information System (INIS)

    In reprocessing chemical purification is based on liquid-liquid solvent extraction. The solvent is TBP diluted in hydrocarbon. Solvent management in UP3 reprocessing plant include an organic effluent processing plant based on distillation. The plant design takes into account thermal degradation of TBP and radioactivity. Study and development of this plant and original solutions are described, especially the use of very low pressure and thin film evaporation

  6. 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

  7. 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.

  8. 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.

  9. 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.

  10. Nuclear power plant and fuel process simulators for educational purposes and quantitative analyses

    International Nuclear Information System (INIS)

    The excellence of today's technique for plant and fuel process simulators (both in hardware and software) has reached a level that permits a multitude of additional applications beyond the traditional educational purpose. A duplex real-time simulation system, developed by Studsvik, representing the dynamics of a nuclear power plant and the performance of the fuel pins, may be utilized for a number of different important applications. The plant process simulator (Studsvik simulator) and the fuel pin process simulator (INTERPIN-FRPS) have been developed independently and may be operated on an individual basis. However, the combination of the two simulators, as established, implies two major advantages: The hardware (computer and graphics) can be saved, and the Studsvik simulator, particularly its core model, will serve the INTERPIN-FRPS with the necessary and accurate dynamic real-time input data for any local position of the fuel pins in the reactor core

  11. 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

  12. Reprocessing (1): Barnwell, USA

    International Nuclear Information System (INIS)

    The matter discussed is whether the US Administration will allow a large reprocessing plant, located in a South Carolina forest, to start operations. Constructed by private industry at a cost so far of some 250 million dollars, this facility could become either a key component in the US nuclear power programme, or a massively expensive white elephant. Designed as the first full-scale commercial plant to reprocess spent fuel from power reactors, the facility is falling victim to rising concerns about the proliferation of nuclear weapons, and its fate will probably hang on a complex series of regulatory, political and diplomatic decisions expected to be taken in the near future. Even if the Administration decides to allow the plant to start operations, however, its problems will not be entirely over. Before it can operate at full capacity additional facilities to solidify highly active wastes from the plant and to convert Pu nitrate to oxide will be required, estimated to cost 500 million dollars, a sum that private industry says it is unwilling to risk without government assistance. The plant is designed to reprocess fuel continuously from about 50 commercial power reactors, extracting Pu and U and recycling the materials as new reactor fuel. Activities of environmental and anti-nuclear groups with regard to large scale Pu production are discussed, together with the findings of the US Nuclear Regulatory Commission, including the holding of public hearings. Political developments are also discussed, including the establishment of international controls. The conclusion is reached that the future for reprocessing in the USA is uncertain. (U.K.)

  13. Model of iodine-129 process distributions in a nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    This paper documents the development, demonstration and verification of a model of iodine-129 pathways in a nuclear fuel reprocessing plant. Laboratory experimental results are presented on iodine-129 chemical forms and also on evaporator and solvent extraction behavior. In-plant sampling results for all accessable processes are also reported. A computer program using the developed model is documented. Although the ICPP is somewhat unique in its processes it is believed these results can be applied to other types of fuel reprocessing plants

  14. 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)

  15. Fulfilment of licensing requirements for the plant part mixed oxide processing of the Hanau fuel element fabrication plant

    International Nuclear Information System (INIS)

    Fulfilment of licensing requirements for the plant part mixed oxide processing of the Hanau fuel element fabrication plant. The licensing procedure according to para. 7 Atomic Energy Law is completed for the entire plant. The cost of the procedure as well as of reconstruction and reequipment measures in the course of interior work in the fabrication building, of automation, of the interim storage facility, of transport systems, and the cost of verification of safeguard aspects will amount to about DM 900 million. (DG)

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

    International Nuclear Information System (INIS)

    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

  17. 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.

  18. 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

  19. Disposal of defense spent fuel and HLW from the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    Acid high-level radioactive waste (HLW) resulting from fuel reprocessing at the Idaho Chemical Processing Plant (ICPP) for the US Department of Energy (DOE) has been solidified to a calcine since 1963 and stored in stainless steel bins enclosed by concrete vaults. Several different types of unprocessed irradiated DOE-owned fuels are also in storage ate the ICPP. In April, 1992, DOE announced that spent fuel would no longer be reprocessed to recover enriched uranium and called for a shutdown of the reprocessing facilities at the ICPP. A new Spent Fuel and HLW Technology Development program was subsequently initiated to develop technologies for immobilizing ICPP spent fuels and HLW for disposal, in accordance with the Nuclear Waste Policy Act. The Program elements include Systems Analysis, Graphite Fuel Disposal, Other Spent Fuel Disposal, Sodium-Bearing Liquid Waste Processing, Calcine Immobilization, and Metal Recycle/Waste Minimization. This paper presents an overview of the ICPP radioactive wastes and current spent fuels, with an emphasis on the description of HLW and spent fuels requiring repository disposal

  20. 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

  1. 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

  2. Thorium base fuels reprocessing at the L.P.R. (Radiochemical Processes Laboratory) experimental plant

    International Nuclear Information System (INIS)

    The availability of the LPR (Radiochemical Processes Laboratory) plant offers the possibility to demonstrate and create the necessary technological basis for thorium fuels reprocessing. To this purpose, the solvents extraction technique is used, employing TBP (at 30%) as solvent. The process is named THOREX, a one-cycle acid, which permits an adequate separation of Th232 and U233 components and fission products. For thorium oxide elements dissolution, the 'chopp-leach' process (installed at LPR) is used, employing a NO3 H 13N, 0.05M FH and 0.1M Al (NO3)3, as solvent. To adapt the pilot plant to the flow-sheet requirements proposed, minor modifications must be carried out in the interconnection of the existing decanting mixers. The input of the plant has been calculated by Origin Code modified for irradiations in reactors of the HWR type. (Author)

  3. Fuel gas conditioning process

    Science.gov (United States)

    Lokhandwala, Kaaeid A.

    2000-01-01

    A process for conditioning natural gas containing C.sub.3+ hydrocarbons and/or acid gas, so that it can be used as combustion fuel to run gas-powered equipment, including compressors, in the gas field or the gas processing plant. Compared with prior art processes, the invention creates lesser quantities of low-pressure gas per unit volume of fuel gas produced. Optionally, the process can also produce an NGL product.

  4. Process monitoring of the quality management system at the Pitesti Nuclear Fuel Plant

    International Nuclear Information System (INIS)

    The paper presents the results obtained by NFP (Nuclear Fuel Plant) during the development of the 'process monitoring' requested by the current reference documents applicable in Quality Management System (NMC-02, NMC-07, SR EN ISO 9001:2001). Based on reference requirements and taking into account the activity peculiarity, NFP issued the Process Record and established the specific targets and performance indicators for each process and department identified in the Management Manual. Then, the Process Manager was appointed and there were established the responsibilities for the follow-up and final reporting. The main expected achievements are the following: permanent control of the process, separately and in connection with the others, continuous improvement of the processes by identification of cases requiring corrective and/or preventive interventions. (author)

  5. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Mellinger, P.J.; Brackenbush, L.W.; Tanner, J.E.; Gilbert, E.S.

    1984-08-01

    The risks involved in the routine release of /sup 85/Kr from nuclear fuel reprocessing operations to the environment were compared to those resulting from the capture and storage of /sup 85/Kr. Instead of releasing the /sup 85/Kr to the environment when fuel is reprocessed, it can be captured, immobilized and stored. Two alternative methods of capturing /sup 85/Kr (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 /sup 85/Kr 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 /sup 85/Kr 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 /sup 85/Kr 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 /sup 3/H and /sup 14/C also encourage delaying implementation of the /sup 85/Kr recovery in the early plants.

  7. 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

  8. 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.)

  9. 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.)

  10. Process simulation for fuel delivery from storage and delivery system in fusion power plant

    International Nuclear Information System (INIS)

    The storage and delivery system (SDS) in fusion power plant should deliver the fuel gases, such as tritium and deuterium for the DT plasma operation. Under the environment with various fuelling scenarios and with the limitation of tritium compatible equipments it is needed to determine the process design for the fuel delivery in the SDS. The SDS has functions to satisfy the various fuelling scenarios, to minimize the tritium inventory in vapor state, and to operate safely. Based on the preliminary analysis, the configuration of pumps is selected as the three and two parallel-combined MB 601 pumps for the fuelling of T2 and D2(T) gases, respectively. The volumes of buffer vessels are determined as 0.4 m3 and 0.3 m3 as minimum values to satisfy the all fuelling scenarios with 120 kPa for the initial pressure for T2 and D2(T) gases, respectively. The numerical process simulations identify the new issue between the SDS and the fuelling system (FS). It needs the guideline for the lower bound of the inlet pressure in the FS to reduce the tritium inventory in long tubes between the SDS and the FS and to optimize the operability of the SDS.

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

    International Nuclear Information System (INIS)

    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 (m3) 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 ampersand 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

  12. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    Patterson, M.W.

    1994-10-01

    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&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.

  14. 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.

  15. 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

  16. 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.

  17. 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

  18. 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

  19. 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

  20. 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)

  1. 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.

  2. 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.

  3. 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

  4. 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

  5. Fuel rod reprocessing plant

    International Nuclear Information System (INIS)

    A plant for the reprocessing of fuel rods for a nuclear reactor comprises a plurality of rectangular compartments desirably arranged on a rectangular grid. Signal lines, power lines, pipes, conduits for instrumentation, and other communication lines leave a compartment just below its top edges. A vehicle access zone permits overhead and/or mobile cranes to remove covers from compartments. The number of compartments is at least 25% greater than the number of compartments used in the initial design and operation of the plant. Vacant compartments are available in which replacement apparatus can be constructed. At the time of the replacement of a unit, the piping and conduits are altered to utilize the substitute equipment in the formerly vacant compartment, and it is put on stream prior to dismantling old equipment from the previous compartment. Thus the downtime for the reprocessing plant for such a changeover is less than in a traditional reprocessing plant

  6. 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.)

  7. Biomass conversion to hydrocarbon fuels using the MixAlco™ process at a pilot-plant scale

    International Nuclear Information System (INIS)

    Texas A and M University has built a MixAlco™ pilot plant that converts biomass to hydrocarbons (i.e., jet fuel, gasoline) using the following steps: fermentation, descumming, dewatering, thermal ketonization, distillation, hydrogenation, and oligomerization. This study describes the pilot plant and reports results from an 11-month production campaign. The focus was to produce sufficient jet fuel to be tested by the U.S. military. Because the scale was relatively small, energy-saving features were not included in the pilot plant. Further, the equipment was operated in a manner to maximize productivity even if yields were low. During the production campaign, a total of 6.015 Mg of shredded paper and 120 kg of chicken manure (dry basis) were fermented to produce 126.5 m3 of fermentation broth with an average concentration of 12.5 kg m−3. A total of 1582 kg of carboxylate salts were converted to 587 L of raw ketones, which were distilled and hydrogenated to 470 L of mixed alcohols ranging from C3 to C12. These alcohols, plus 300 L of alcohols made by an industrial partner (Terrabon, Inc.) were shipped to an independent contractor (General Electric) and transformed to jet fuel (∼100 L) and gasoline (∼100 L) byproduct. - Highlights: • We produce hydrocarbons from paper and chicken manure in a pilot-scale production using the MixAlco™ process. • About 100 L of jet fuel were produced for military testing. • High production rates and good product quality were preferred rather than high yields or energy efficiency. • The MixAlco™ process converted successfully lignocellulosic biomass to hydrocarbons and viable for commercial-scale production

  8. Feasibility study for Hilo Coast Processing Company, Pepeekeo, Hawaii: 11. 4-million gallon-per-year motor-fuel-grade ethanol plant. Volume IV. Process design

    Energy Technology Data Exchange (ETDEWEB)

    Messick, J.R.; Kaupisch, K.F.; Yeats, C.; Hicks, H.W.; Wagner, R.C.; Moon, G.D.; Katzen, R.

    1981-05-01

    A study to determine the technial and economic feasibility for the construction and operation of an 11.4 million gallon per year fuel grade ethanol plant in Pepeekeo, Hawaii, has been conducted. This volume contains the following appendices concerning process design: vendor's list; analytical procedures; molasses analysis and fermentation test procedures from HSPA; fermentation test procedures; soils report summary; by-product recovery analysis; preliminary investment estimate; stillage composition; materials of construction memorandum. (DMC)

  9. 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...

  10. 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

  11. Design of alpha bearing industrial waste processing facility associated with a nuclear fuel fabrication plant: incineration and ashes containment

    International Nuclear Information System (INIS)

    As part of a COGEMA project for the construction of a mixed oxide nuclear fuels production plant (UPu)O2 to be used for the recycling of plutonium in light water reactors, COGEMA, USSI and the AEC (CEA) present the main options decided upon for the creation of a treatment and embedding unit for the wastes which will be produced by the plant from 1993 onwards. A 15 kg.h-1 capacity incinerator capable of processing 420 m3.year-1 of alpha solid technological wastes is described. This description is completed by information concerning the research and development program adopted by the CEA for incineration, recovery of Pu in the ashes and the embedding of incineration ashes. An initial estimate is made of the volume reduction factor achieved by incineration (ratio of the volume of waste before incineration to the volume of embedded products)

  12. 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...

  13. 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

  14. Concerning change in nuclear fuel material processing business at Tokai plant of Japan Nuclear Fuel Conversion Co., Ltd. Report to Prime Minister

    International Nuclear Information System (INIS)

    The Nuclear Safety Committee of Japan on April 7, 1988, directed the Nuclear Safety Expert Group to make a study concerning the proposed changes in the nuclear fuel material processing business at the Tokai plant of Japan Nuclear Fuel Conversion Co., Ltd., and after receiving and reviewing the report from the Group, concluded that the proposed changes should be approved. The conclusions together with results of the study were reported to the Prime Minister on June 9. 1988. The proposed plan included changes in the maximum processing capacity of the No.2 processing facilities; construction of a new powder warehouse and changes in the maximum capacity of the No.3 powder storage room and No.2 powder warehouse; reuse of No.1 powder warehouse as No.3 solid waste warehouse; and abolition of UF6 dispensing equipment installed at the No.1 processing facilities and changes in procedures for criticality control of the hydrolysis facilities. The safety of these facilities were studied in terms of resistance to earthquakes, prevention of fire and explosion, criticality control, operations of waste processing, and radiation management. Exposure doses expected during normal operations were also examined to confirm that the possible exposure doses to the public would be sufficiently small. (N.K.)

  15. 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...

  16. 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

  17. Process simulation of oxy-fuel combustion for a 300 MW pulverized coal-fired power plant using Aspen Plus

    International Nuclear Information System (INIS)

    Graphical abstract: This paper studied the combustion processes of pulverized coal in a 300 MW power plant using Aspen Plus software. The amount of each component in flue gas in coal-fired processes with air or O2/CO2 as oxidizer was obtained. The differences between the two processes were identified, and the parameter influences of temperature, excess oxygen ratio and molar fraction of O2/CO2 on the proportions of different components in flue gas were examined by sensitivity analysis. - Highlights: • Combustion processes were studied with Aspen Plus for a 300 MW pulverized coal power plant. • The amount of each flue gas component in coal-fired processes with air or O2/CO2 as oxidizer was obtained. • Differences between the two process models were identified. • The influences of operation parameters on the flue gas components were examined. - Abstract: This work focuses on the amounts and components of flue gas for oxy-fuel combustion in a coal-fired power plant (CFPP). The combustion process of pulverized coal in a 300 MW power plant is studied using Aspen Plus software. The amount of each component in flue gas in coal-fired processes with air or O2/CO2 as oxidizer is obtained. The differences between the two processes are identified, and the influences of temperature, excess oxygen ratio and molar fraction of O2/CO2 on the proportions of different components in flue gas are examined by sensitivity analysis. The process simulation results show that replacing atmospheric air by a 21%O2/79%CO2 mixture leads the decrease of the flame temperature from 1789 °C to 1395 °C. The equilibrium amount of NOx declines obviously but the SOx are still at the same level. The mass fraction of CO2 in flue gas increased from 21.3% to 81.5%. The amount of NOx is affected sensitively by the change of temperature and the excess oxygen ratio, but the change of O2/CO2 molar fraction has a little influence to the generation of NOx. With the increasing of O2 concentration, the

  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. 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%

  20. Fuel cells technologies for fuel processing

    CERN Document Server

    Shekhawat, Dushyant, II; Berry, David A, I

    2014-01-01

    Fuel Cells: Technologies for Fuel Processing provides an overview of the most important aspects of fuel reforming to the generally interested reader, researcher, technologist, teacher, student, or engineer. The topics covered include all aspects of fuel reforming: fundamental chemistry, different modes of reforming, catalysts, catalyst deactivation, fuel desulfurization, reaction engineering, novel reforming concepts, thermodynamics, heat and mass transfer issues, system design, and recent research and development. While no attempt is made to describe the fuel cell itself, there is sufficient

  1. 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.

  2. 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.

  3. Lessons learned from the Barnwell chosure to 31 states

    International Nuclear Information System (INIS)

    The low-level radioactive waste disposal facility at Barnwell, South Carolina, closed to companies and institutions outside its region in July, 1994. An estimated 3,000 companies and institutions that use radioactive materials and generate low-level radioactive waste requiring disposal during 1992, 1993 and 1994, located in 31 states, were left stranded without a place to dispose of their low-level radioactive waste. Within a year of the Barnwell restriction Organization United for Responsible Low-Level Radioactive Waste Solutions (open-quotes Organizations Unitedclose quotes) sponsored a survey to discover the current and prospective effects, if any, on companies, institutions and consumers. Soon after Barnwell restricted access, stories of how companies were dealing with on-site storage of waste began to surface. Companies were managing the waste safely, but some companies were forced to use space previously designed for other purposes, such as parking garages. Stories of negative impacts for consumers and medical patients also began to surface. On July 1, 1995, the Barnwell facility re-opened to all states except North Carolina - an unexpected reprieve. Thus the survey timing afforded a unique opportunity to see what would happen if disposal again became unavailable, because Barnwell's reopening is only a temporary solution that could change with the political winds, the survey offers a look at the likely consequences if new facilities are not developed to replace the Barnwell facility

  4. 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

  5. In-process inventory estimation in a reprocessing facility for near-real-time accounting

    International Nuclear Information System (INIS)

    An In-Process Inventory Technique (IPI) has been developed and tested at the Barnwell Nuclear Fuel Plant (BNFP) to provide frequent inventories without cost or instrusiveness to plant operability. A computerized measurement system makes available process measurements and process control analytical information. These data are processed to determine the process inventory. The calculation routines use routinely available process control measurements and sample results. The technique requires no shutdown, no special preparations, and no special measurements, or samples. With this technique, hourly inventory frequencies and material balance closures have been achieved during demonstration runs in the 1500 MTU/y at BNFP. Results show sensitivities of 2 to 5% of the normal process inventory are achievable during normal operations. Recent improvements in data handling routines indicate the technique can be sensitive during transient process conditions as well

  6. Waste management in MOX fuel fabrication plants

    International Nuclear Information System (INIS)

    After a short description of a MOX fuel fabrication plant's activities the waste arisings in such a plant are discussed according to nature, composition, Pu-content. Experience has shown that proper recording leads to a reduction of waste arisings by waste awareness. Aspects of the treatment of α-waste are given and a number of treatment processes are reviewed. Finally, the current waste management practice and the α-waste treatment facility under construction at ALKEM are outlined. (orig./RW)

  7. 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)

  8. 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)

  9. A Medium-Scale 50 MW fuel Biomass Gasification Based Bio-SNG Plant: A Developed Gas Cleaning Process

    OpenAIRE

    Ramiar Sadegh-Vaziri; Marko Amovic; Rolf Ljunggren; Klas Engvall

    2015-01-01

    Natural gas is becoming increasingly important as a primary energy source. A suitable replacement for fossil natural gas is bio-SNG, produced by biomass gasification, followed by methanation. A major challenge is efficient gas cleaning processes for removal of sulfur compounds and other impurities. The present study focuses on development of a gas cleaning step for a product gas produced in a 50 MW fuel gasification system. The developed gas cleaning washing process is basically a modificatio...

  10. THE TESTING OF COMMERCIALLY AVAILABLE ENGINEERING AND PLANT SCALE ANNULAR CENTRIFUGAL CONTACTORS FOR THE PROCESSING OF SPENT NUCLEAR FUEL

    Energy Technology Data Exchange (ETDEWEB)

    Jack D. Law; David Meikrantz; Troy Garn; Nick Mann; Scott Herbst

    2006-10-01

    Annular centrifugal contactors are being evaluated for process scale solvent extraction operations in support of United State Advanced Fuel Cycle Initiative goals. These contactors have the potential for high stage efficiency if properly employed and optimized for the application. Commercially available centrifugal contactors are being tested at the Idaho National Laboratory to support this program. Hydraulic performance and mass transfer efficiency have been measured for portions of an advanced nuclear fuel cycle using 5-cm diameter annular centrifugal contactors. Advanced features, including low mix sleeves and clean-in-place rotors, have also been evaluated in 5-cm and 12.5-cm contactors.

  11. 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

  12. Welding with the TIG automatic process of the end fittings for the execution of the Embalse nuclear power plant fuel channel rechange

    International Nuclear Information System (INIS)

    The present work describes the methodology for the cutting of the existing welding and subsequent welding applied by the TIG process of the coupling composed by the shroud ring and the end fitting ring from one of Embalse nuclear power plant's fuel channels. The replacement will be previously determined by the SLAR-ETTE mechanism where a displacement operated among the Gartner Spring rings, the pressure tubes are separated from the Calandria tubes. The welding to be carried out has the function of stamping the CO2 annular gas (thermal insulator) circulating between the pressure tube and the Calandria one during the functioning of the plant. (Author)

  13. 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)

  14. Safety demonstration tests of postulated solvent fire accidents in extraction process of a fuel reprocessing plant, (3)

    International Nuclear Information System (INIS)

    Demonstration tests of hypothetical solvent fire in an extraction process of the reprocessing plant were carried out from 1983 to 1984 in JAERI, focusing on the fire behavior in a cell by a large-scale fire facility (FFF) to evaluate the safety of air-ventilation system in the plant. Fire data from the demonstration test were obtained by focusing on fire behavior at cells and ducts in the ventilation system, smoke generation during the fire, transport and deposition of smoke, and integrity of HEPA filters by using the FFF simulating an air-ventilation system of the reference reprocessing plant in Japan. The present report is published in a series of the report Phase II of the demonstration test. Test results in the report will be used for the verification of a computer code FACE to evaluate the safety of postulated fire accidents in the reprocessing plant. (author)

  15. Tritium management in PWR fuel reprocessing plants

    International Nuclear Information System (INIS)

    Activity, quantity and nature of tritium compounds obtained during head end process (cutting and dissolution) are determined to estimate environmental release hazards in fuel reprocessing plants. Measurements on representative PWR reactor fuels (burnup 33,000 MWdt-1, specific power 30 MW dt-1) show that about 60% of the tritium produced in the reactor diffuses in the cladding where it is fixed. Remaining tritium stays in the irradiated oxide and is found as tritiated water in the solution obtained during fuel dissolution. In the UP3 plant at La Hague (France) tritiated water is disposed into the sea without environmental problems. In the case of a reprocessing plant far from the sea, the PUREX process is slightly modified for concentration of tritium in a limited amount of water (TRILEX process). It is verified experimentally in αβγ lab on actual fuel and by simulation at the pilot seale that the supplementary step ''tritium washing'' of the solvent can be obtained in pulsed columns. 4 tables, 7 figs

  16. 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)

  17. 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

  18. Performance of candu-6 fuel bundles manufactured in romania nuclear fuel plant

    International Nuclear Information System (INIS)

    The purpose of this article is to present the performance of nuclear fuel produced by Nuclear Fuel Plant (N.F.P.) - Pitesti during 1995 - 2012 and irradiated in units U1 and U2 from Nuclear Power Plant (N.P.P.) Cernavoda and also present the Nuclear Fuel Plant (N.F.P.) - Pitesti concern for providing technology to prevent the failure causes of fuel bundles in the reactor. This article presents Nuclear Fuel Plant (N.F.P.) - Pitesti experience on tracking performance of nuclear fuel in reactor and strategy investigation of fuel bundles notified as suspicious and / or defectives both as fuel element and fuel bundle, it analyzes the possible defects that can occur at fuel bundle or fuel element and can lead to their failure in the reactor. Implementation of modern technologies has enabled optimization of manufacturing processes and hence better quality stability of achieving components (end caps, chamfered sheath), better verification of end cap - sheath welding. These technologies were qualified by Nuclear Fuel Plant (N.F.P.) - Pitesti on automatic and Computer Numerical Control (C.N.C.) programming machines. A post-irradiation conclusive analysis which will take place later this year (2013) in Institute for Nuclear Research Pitesti (the action was initiated earlier this year by bringing a fuel bundle which has been reported defective by pool visual inspection) will provide additional information concerning potential damage causes of fuel bundles due to manufacturing processes. (authors)

  19. 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

  20. Safety demonstration tests of postulated solvent fire accidents in extraction process of a fuel reprocessing plant, (2)

    International Nuclear Information System (INIS)

    Demonstration tests of hypothetical solvent fire in an extraction process of the reprocessing plant were carried out from 1984 to 1985 in JAERI, focusing on the confinement of radioactive materials during the fire by a large-scale fire facility (FFF) to evaluate the safety of air-ventilation system in the plant. Fire data from the demonstration test were obtained by focusing on fire behavior at cells and ducts in the ventilation system, smoke generation during the fire, transport and deposition of smoke containing simulated radioactive species in the ventilation system, confinement of radioactive materials, and integrity of HEPA filters by using the FFF simulating an air-ventilation system of the reference reprocessing plant in Japan. The present report is published in a series of the report Phase I (JAERI-M 91-145) of the demonstration test. Test results in the report will be used for the verification of a computer code FACE to evaluate the safety of postulated fire accidents in the reprocessing plant. (author)

  1. Nuclear fuel control in fuel fabrication plants

    International Nuclear Information System (INIS)

    The basic control problems of measuring uranium and of the environment inside and outside nuclear fuel fabrication plants are reviewed, excluding criticality prevention in case of submergence. The occurrence of loss scraps in fabrication and scrap-recycling, the measuring error, the uranium going cut of the system, the confirmation of the presence of lost uranium and the requirement of the measurement control for safeguard make the measurement control very complicated. The establishment of MBA (material balance area) and ICA (item control area) can make clearer the control of inventories, the control of loss scraps and the control of measuring points. Besides the above basic points, the following points are to be taken into account: 1) the method of confirmation of inventories, 2) the introduction of reliable NDT instruments for the rapid check system for enrichment and amount of uranium, 3) the introduction of real time system, and 4) the clarification of MUF analysis and its application to the reliability check of measurement control system. The environment control includes the controls of the uranium concentration in factory atmosphere, the surface contamination, the space dose rate, the uranium concentration in air and water discharged from factories, and the uranium in liquid wastes. The future problems are the practical restudy of measurement control under NPT, the definite plan of burglary protection and the realization of the disposal of solid wastes. (Iwakiri, K.)

  2. 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.

  3. 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

  4. 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)

  5. 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.)

  6. 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...

  7. 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.)

  8. 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)

  9. Control room - ergonomic factors and their influence on the quality of exploitation process conduction in the coal fueled power plants

    International Nuclear Information System (INIS)

    In the Control Room in which control and regulation is performed upon the overall process of electric energy production, the operator plays essential role as an ultimate decision factor, particularly in the states of emergency. From the Control Room the operator performs a real-time supervision and management of the production process thus introducing exquisite quality into the operating fitness maintenance, creating optimal conditions for uninterrupted and safe production. The engagements of the operator in the Control Room require mutual accordance of the anthropology-technical and bio mechanical characteristics with the psychophysiological attributes of the operator. Any command and signaling equipment mishandling may cause numerous unwanted consequences, leading to a production control system breakdown for the power plant. In order to achieve a balanced optimization in the system operation, such as appropriate working conveniences, protection, certain economic effects, etc. an ergonomic organization and arrangement of the Control Room working environment is required. Re existing working environment solutions of the kind in our milieu show outstanding deviations towards the anthropology-physiological and psychophysiological capabilities of the operator on duties of the kind, as well as towards the collocation of signaling and command facilities and other equipment units at the Control Room site - the reason being a lack of appropriate investigation before setup of the systems. Solution to this kind of problems is aimed to provide maximum functional capability, efficiency and safety to the Control Room operator's domain of activities, which will essentially improve the reliability of the entire energy production control system of a thermoelectric power plant. (Author)

  10. 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.

  11. 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

  12. 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

  13. 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)

  14. 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.)

  15. 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

  16. Nonaqueous processing methods

    International Nuclear Information System (INIS)

    A high-temperature process utilizing molten salt extraction from molten metal alloys has been developed for purification of spent power reactor fuels. Experiments with laboratory-scale processing operations show that purification and throughput parameters comparable to the Barnwell Purex process can be achieved by pyrochemical processing in equipment one-tenth the size, with all wastes being discharged as stable metal alloys at greatly reduced volume and disposal cost. This basic technology can be developed for large-scale processing of spent reactor fuels. 13 references, 4 figures

  17. LEU fuel element produced by the Egyptian fuel manufacturing pilot plant

    International Nuclear Information System (INIS)

    The Egyptian Fuel Manufacturing Pilot Plant, FMPP, is a Material Testing Reactor type (MTR) fuel element facility, for producing the specified fuel elements required for the Egyptian Second Research Reactor, ETRR-2. The plant uses uranium hexafluoride (UF6, 19.75% U235 by wt) as a raw material which is processed through a series of the manufacturing, inspection and test plan to produce the final specified fuel elements. Radiological safety aspects during design, construction, operation, and all reasonably accepted steps should be taken to prevent or reduce the chance of accidents occurrence. (author)

  18. Egg Processing Plant Sanitation

    Science.gov (United States)

    Hazard analysis and critical control programs (HACCP) will eventually be required for commercial shell egg processing plants. Sanitation is an essential prerequisite program for HACCP and is based upon current Good Manufacturing Practices (cGMPs) as listed in the Code of Federal Regulations. Good ...

  19. 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

  20. Applications of sub-optimality in dynamic programming to location and construction of nuclear fuel processing plant

    International Nuclear Information System (INIS)

    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)

  1. 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.)

  2. Mixed U/Pu oxide fuel fabrication facility co-processed feed, pelletized fuel

    International Nuclear Information System (INIS)

    Two conceptual MOX fuel fabrication facilities are discussed in this study. The first facility in the main body of the report is for the fabrication of LWR uranium dioxide - plutonium dioxide (MOX) fuel using co-processed feed. The second facility in the addendum is for the fabrication of co-processed MOX fuel spiked with 60Co. Both facilities produce pellet fuel. The spiked facility uses the same basic fabrication process as the conventional MOX plant but the fuel feed incorporates a high energy gamma emitter as a safeguard measure against diversion; additional shielding is added to protect personnel from radiation exposure, all operations are automated and remote, and normal maintenance is performed remotely. The report describes the fuel fabrication process and plant layout including scrap and waste processing; and maintenance, ventilation and safety measures

  3. 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

  4. 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

  5. The trapping of iodine in spent fuel reprocessing plants

    International Nuclear Information System (INIS)

    Main processes for trapping radioactive iodine on solids or liquids in fuel reprocessing plants are reviewed. For each process chemical reaction mechanisms are described, influence of main parameters on trapping performance is examined (temperature, relative humidity, iodine content, etc), advantages and disadvantages are indicated. 63 refs

  6. 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

  7. 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

    International Nuclear Information System (INIS)

    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.)

  8. 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.)

  9. Safety aspects of fuel reprocessing plants

    International Nuclear Information System (INIS)

    The reprocessing of irradiated reactor fuels is an important activity in the total fuel cycle. The reprocessing step has special radiological, technological and operational problems associated with it since it renders the high integrity solid reactor fuel into highly dispersible forms resulting in problems of containment and confinement of toxic materials like plutonium and fission products. This operation also makes plutonium available in a concentrated and pure form. The design and operation of a reprocessing plant must result in very low environmental releases under these conditions. The irradiated fuel must be reprocessed periodically for one or more of the following reasons : i) For separation of accumulated fission product poisons which adversely affects the reactivity in the reactor; ii) For recovery of unspent fissile and fertile materials; iii) For recovery of the reactor produced plutonium and iv) Due to possible physical changes in the fuel rendering reactor operation difficult

  10. Microbial fuel cell treatment of fuel process wastewater

    Energy Technology Data Exchange (ETDEWEB)

    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. 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.

  12. 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.

  13. 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.

  14. Health risk assessment for fuel reprocessing plant

    International Nuclear Information System (INIS)

    A health risk assessment for 85Kr was conducted. The purpose of the study was to evaluate radiological impacts of the EPA 85Kr legislation as embodied in 40 CFR 190. This was done by conducting a health risk assessment of the comparative risks involved in a routine release scenario versus 85Kr capture alternatives at a fuel reprocessing plant (FRP). The krypton contained in dissolver offgas, has historically been released routinely into the environment from FRP operations. There is an alternative to the routine release and that is capture, concentrate, and store the gas for long periods of time. Cryogenic distillation or fluorocarbon absorption are alternative methods for the capture of krypton. Ion implantation/sputtering is a method of immobilizing krypton received from the two capture processes. These technologies were evaluated based on the assumption that, for the extremely low doses and dose rates involved, the risks to individuals in the work force can be compared directly to the risks to members of the general public. Early conceptual facility designs for the three processes were taken from the literature

  15. 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

  16. 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

  17. Method of processing spent fuel

    International Nuclear Information System (INIS)

    In a reprocessing process for spent fuels and wet recovery process for scrapped fuels, since an organic solvent used in the extraction step are generally degradated due to the effects of radioactive rays or acids, they are reused after removing degradation products by means of sodium hydroxide and sodium carbonate solution. However, the organic solvents degradated considerably can no more be regenerated and, since they contain much sodium, their de-voluming treatment is restricted to complicate the solidification treatment. In view of the above, the degradation products are removed from the degraded solvents by using a vacuum-freeze-drying method and a vacuum-distillation method for the spent solvents in a solvent cleaning step, and the recovered solutions are reused as well as the most of the radioactive materials are recovered as residues, to thereby reduce the volume of the liquid wastes and simplify the liquid wastes treatment. Further, solutions of plutonium and uranium are powderized by means of the vacuum-freeze-drying method, and resultant nitrates are applied with thermal decomposition, denitration and reduction under calcination into oxide powder. (N.H.)

  18. 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)

  19. Optimization of hydrocarbon fuels combustion variable composition in thermal power plants

    Science.gov (United States)

    Saifullin, E. R.; Larionov, V. M.; Busarov, A. V.; Busarov, V. V.

    2016-01-01

    It is known that associated petroleum gas and refinery waste can be used as fuel in thermal power plants. However, random changes in the composition of such fuels cause instability of the combustion process. This article explores the burning of hydrocarbon fuel in the case of long continuous change of its specific heat of combustion. The results of analysis were used to develop a technique of optimizing the combustion process, ensuring complete combustion of the fuel and its minimum flow.

  20. Spent fuel storage process equipment development

    International Nuclear Information System (INIS)

    Nuclear energy which is a major energy source of national energy supply entails spent fuels. Spent fuels which are high level radioactive meterials, are tricky to manage and need high technology. The objectives of this study are to establish and develop key elements of spent fuel management technologies: handling equipment and maintenance, process automation technology, colling system, and cleanup system. (author)

  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. Sulfur balance in biomass-fueled plants

    International Nuclear Information System (INIS)

    The aim of this project has been to establish a standard deduction for sulphur retained in the ash. This is accomplished by establishing sulphur balances for biomass plants in order to document the in- and outgoing flows. The ingoing flow is the sulphur in the input fuel while the outgoing flows are different ash fractions and sulphur dioxide measured in the stack. Four balances have been established for straw fired units, three balances for wood chip fired units, and two balances for wood pellet fired units. Two previous projects provide further data on both straw and wood fired units. The main conclusions and recommendations are: For wood pellets the sulphur tax should be removed as the sulphur content in the pellets is extremely low and the emitted fraction very small. For pellets manufactured with a binder containing sulphur, the taxation should continue but with a standard deduction of 60 to 70%. Also, the rate should be reduced as the sulphur content in pellets produced with a binder containing sulphur is lower than the estimated 0,2% of the fuel. Statistics indicate that 0,1% reflects the true sulphur content in these pellets; For wood chips the tax should be removed as the sulphur content based on the fuel is considerably lower than the limit in the law (0,034% versus 0,05%). Furthermore, the emission from these plants are only between 20 and 32%. It is recommended that the plants keep the ph-value in the scrubber water above 7 as it is believed that this improves the absorption of SO2 greatly; For straw the tax should remain, but a standard deduction of 35-40% should be made. Technologies for improving the sulphur retentions should be developed. This could be scrubbers as they are very efficient towards removing especially sulphur in the form of SO2, which is by far the largest source of sulphur emission from straw fired plants. (au) 11 refs

  3. Safeguards implementation in the nuclear fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Keepin, G.R.

    1978-01-01

    Today's trend toward tightening regulations and increasingly stringent safeguards underscores the necessity for safeguards criteria to be incorporated at an early stage in the design of future fuel cycle facilities. IAEA and national safeguards systems are discussed. The U.S. Safeguards R and D program is described in some detail: reference facility (Barnwell) safeguards system design, dynamic materials accounting systems (DYMAC), etc. The safeguards problem of the conversion process (Pu nitrate to PuO/sub 2/) is considered. Recent developments and trends in measurement technology are reviewed. 79 references, 6 figures. (DLC)

  4. 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

  5. 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.

  6. 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...

  7. The effect of wood fuels on power plant availability

    International Nuclear Information System (INIS)

    The objective of this research is to determine critical properties of wood fuels in respect of power plant availability, to determine the optimal conditions for reducing detriments, and to study the effect of storing and processing of wood fuels on the boiler operation. Both, the CFB and BFB technologies are studied. The project started in December 2000 and it will be ended in March 2003. Experts of the Energy Production research field at VTT Processes carry out the majority of the research activities. Experts in the research field of Mineral Processing, located in Outokumpu, participate in analytics, and the research field of Material and Manufacturing Technology of VTT Industrial Systems in Otaniemi participates in the research on material effects. System Technology Laboratory of Oulu University, under the supervision of Professor Urpo Kortela, is responsible for the power plant automation and for the research on boiler control technology. Co-operation related to the analytics of heat transfer surface deposition and corrosion with the EU's JRC has continued as established in the Combustion of Forest Chips -project but mainly in a so-called 'CORBI'-EU-project. Additionally, VTT co-operates with Swedish Vaermeforsk Ab in the form of information exchange on experiences of wood fuel utilization in Swedish power plants. The following companies participate in the project: Etelae-Savon Energia Oy, Foster Wheeler Energia Oy, Kvaerner Pulping Oy, Simpele pasteboard factory of M-Real Oyj and Vaermeforsk Ab (Sweden). (orig.)

  8. 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.

  9. Fuel quality processing study, volume 1

    Science.gov (United States)

    Ohara, J. B.; Bela, A.; Jentz, N. E.; Syverson, H. T.; Klumpe, H. W.; Kessler, R. E.; Kotzot, H. T.; Loran, B. L.

    1981-01-01

    A fuel quality processing study to provide a data base for an intelligent tradeoff between advanced turbine technology and liquid fuel quality, and also, to guide the development of specifications of future synthetic fuels anticipated for use in the time period 1985 to 2000 is given. Four technical performance tests are discussed: on-site pretreating, existing refineries to upgrade fuels, new refineries to upgrade fuels, and data evaluation. The base case refinery is a modern Midwest refinery processing 200,000 BPD of a 60/40 domestic/import petroleum crude mix. The synthetic crudes used for upgrading to marketable products and turbine fuel are shale oil and coal liquids. Of these syncrudes, 50,000 BPD are processed in the existing petroleum refinery, requiring additional process units and reducing petroleum feed, and in a new refinery designed for processing each syncrude to produce gasoline, distillate fuels, resid fuels, and turbine fuel, JPGs and coke. An extensive collection of synfuel properties and upgrading data was prepared for the application of a linear program model to investigate the most economical production slate meeting petroleum product specifications and turbine fuels of various quality grades. Technical and economic projections were developed for 36 scenarios, based on 4 different crude feeds to either modified existing or new refineries operated in 2 different modes to produce 7 differing grades of turbine fuels. A required product selling price of turbine fuel for each processing route was calculated. Procedures and projected economics were developed for on-site treatment of turbine fuel to meet limitations of impurities and emission of pollutants.

  10. 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.

  11. 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

  12. Dry Processing of Used Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

    K. M. Goff; M. F. Simpson

    2009-09-01

    Dry (non-aqueous) separations technologies have been used for treatment of used nuclear fuel since the 1960s, and they are still being developed and demonstrated in many countries. Dry technologies offer potential advantages compared to traditional aqueous separations including: compactness, resistance to radiation effects, criticality control benefits, compatibility with advanced fuel types, and ability to produce low purity products. Within the Department of Energy’s Advanced Fuel Cycle Initiative, an electrochemical process employing molten salts is being developed for recycle of fast reactor fuel and treatment of light water reactor oxide fuel to produce a feed for fast reactors. Much of the development of this technology is based on treatment of used Experimental Breeder Reactor II (EBR-II) fuel, which is metallic. Electrochemical treatment of the EBR-II fuel has been ongoing in the Fuel Conditioning Facility, located at the Materials and Fuel Complex of Idaho National Laboratory since 1996. More than 3.8 metric tons of heavy metal of metallic fast reactor fuel have been treated using this technology. This paper will summarize the status of electrochemical development and demonstration activities with used nuclear fuel, including high-level waste work. A historic perspective on the background of dry processing will also be provided.

  13. 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.

  14. 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...

  15. 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

  16. 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

  17. 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...

  18. 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

  19. IFR fuel cycle - pyro-process development

    International Nuclear Information System (INIS)

    The Integral Fast Reactor (IFR) fuel cycle is based on the use of a metallic fuel alloy, nominally U-20Pu-10Zr. In its present state of development, this fuel system offers excellent high-burnup capabilities. Test fuel has been carried to burnups in excess of 20 atom% in EBR-II irradiations and to peak burnups over 15 atom % in FFTF. The metallic fuel possesses physical characteristics that facilitate a high degree of passive inherent safety in the IFR design. Equally as important the use of metallic fuel permits the use of an innovative reprocessing method known as pyro processing featuring fused-salt electrorefining of the spent fuel. Development of the IFR pyro-process has been underway at the Argonne National Laboratory for over five years and great progress has been made toward a commercially-viable process. Pyro processing of IFR spent fuel begins with the dismantling of irradiated fuel assemblies and chopping of the fuel pins into short segments. The fuel pin segments are placed in a metal basket and inserted into the IFR electrorefining cell. The electrorefining cell is a low-alloy steel vessel, on the order of 1-m diameter and 1-m high that contains an electrolyte salt (eutectic LiCl-KCl mixture) floating on a layer of liquid cadmium The cell is operated at a temperature of 700-775 K. The basket containing the chopped fuel pin segments is made the anode and uranium is electro transported to a solid steel cathode, forming a dendritic deposit containing about 85-90 wt% uranium and the balance salt with minor amounts of fuel alloy zirconium and cadmium. Typical batch sizes are 10 kg heavy metal per electrode. The relative free energies of formation of the chlorides of uranium and the transuranic elements preclude deposition of plutonium and the minor actinides on a solid cathode, so a liquid cadmium cathode located in the salt phase is utilized. The deposition of Pu, Am, Np, and Cm takes place at the liquid cadmium cathode in the form of cadmium intermetallic

  20. 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.

  1. 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.

  2. 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

  3. 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.

  4. 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.

  5. 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

  6. Transition to integrated safeguards at nuclear fuel fabrication plants

    International Nuclear Information System (INIS)

    Full-text: This paper presents the improvements in efficiency and effectiveness of the safeguards approach applied at depleted, natural and low enriched uranium (DNLEU) conversion and fuel fabrication plants (FFPs) following a transition from traditional safeguards (TS) to integrated safeguards1 (IS). The paper will explain the relationship between the Agency drawing a broader conclusion for a State and the implementation of IS, highlight how the transition from TS to IS can be accomplished, and describe a process by which IS can be introduced through a combination of good IAEA-National Authority cooperation and field trials. For demonstration purposes, a comparison of the onsite safeguards activities before and after the introduction of IS at a fuel fabrication plant which manufactures both PWR (Pressurized Water Reactors) fuel assemblies and CANDU fuel bundles will be examined. It is expected that this will provide a good reference baseline on the safeguards improvements made possible by the introduction of IS at fuel fabrication facilities without mixed oxide fuels (MOX). The paper will also show the operational and logistical differences between the TS and IS regimes and highlight some of the advantages to a State for which a broader conclusion has been drawn by the Agency. The paper will offer technical insight to safeguards coverage of nuclear material borrowing scenarios and implementation of other safeguards measures such as the introduction of short notice random inspections (SNRI), use of a secure mailbox system at the FFP, and implementation of random interim inspections (RIIs) at LWRs (Light Water Reactors) and CANDU power reactors. (author)

  7. Fuel corrosion processes under waste disposal conditions

    International Nuclear Information System (INIS)

    Under the oxidizing conditions likely to be encountered in the Yucca Mountain Repository, fuel dissolution is a corrosion process involving the coupling of the anodic dissolution of the fuel with the cathodic reduction of oxidants available within the repository. The oxidants potentially available to drive fuel corrosion are environmental oxygen, supplied by the transport through the permeable rock of the mountain and molecular and radical species produced by the radiolysis of available aerated water. The mechanism of these coupled anodic and cathodic reactions is reviewed in detail. While gaps in understanding remain, many kinetic features of these reactions have been studied in considerable detail, and a reasonably justified mechanism for fuel corrosion is available. The corrosion rate is determined primarily by environmental factors rather than the properties of the fuel. Thus, with the exception of increase in rate due to an increase in surface area, pre-oxidation of the fuel has little effect on the corrosion rate

  8. Investigation of low decontamination pellet fuel fabrication plant configuration. Investigation report

    International Nuclear Information System (INIS)

    In the third year of feasibility studies on commercialized FBR cycle system phase II, design consideration of fuel fabrication equipments at lower processes than the fuel element fabrication and line composition examination, regarding low decontamination pellet fuel fabrication facilities, were conducted. Incidental facilities such as flushing and decontamination facilities of solid waste were also studied. A concept of fuel fabrication plant in 200t-HM/y scale was shown as well as system properties data acquisition concerning economics and environmental burden reduction of fuel fabrication plant. In addition to this, 50t-HM/y scale plant was schematically studied based on the facility design above and system properties data were obtained similarly. In the case of 200t-HM/y scale plant, its line composition becomes 2 fabrication lines for inner core fuel, 1 line for each of outer core, axial and radial blanket fuel at the pellet fabrication processes, 1 line for each of inner core, outer core and radial blanket fuel at the fuel element fabrication/inspection processes, and 1 line for each of core and blanket fuel at fuel assembling/inspection processes, and the building of 1 underground story and 2 story above the ground is compact with 30,000 m3 of cubic capacity. The construction cost estimation increased around 25% compared to the result obtained in phase I because of design progress of its material handling and remote maintenance facilities, and 20 tons of solid waste generation per year was estimated. On the contrary in the case of 50t-HM/y scale, because it becomes 1 line for each of core hand blanket fuel at the pellet fabrication processes and 1 line at lower processes than the fuel element fabrication, it is reduced to 70% at cubic capacity of the building, 50% in the construction cost and 40% of 200t-HM/y scale in the solid waste generation. (author)

  9. Effect of wood fuels on power plant operability

    International Nuclear Information System (INIS)

    The objective of the research is to determine the critical properties of wood fuels on the basis of power plant operability, to determine the optimal conditions for reduction of harmful detriments, and to study how the storage and processing of wood fuels effect on the operability. Both the CFB and BFB technologies are studied. The project started in December 2000 and it will be ended by the end of 2002. Experts of the Fuels and Combustion research field of VTT Energy carry out the main parts of the research. Experts of the research field of Mineral Processing of VTT Chemical Technology, located in Outokumpu, and Kemian tutkimuspalvelut Oy/Oulu University, located in Outokumpu, participate in the analytics, and the research field of Materials and Manufacturing Technology of VTT Manufacturing Technology in Otaniemi participates in the research on material effects. System Technology Laboratory of Oulu University carries out the power plant automation and boiler control technology research under supervision of Professor Urpo Kortela. Co-operation with the materials research unit of EU's JRC, located in Petten, which started in the research 'Combustion of Forest Chips', will be continues in this research. Co-operation will be made with Swedish Vaermeforsk in the field of information exchange on experiences in utilisation of wood fuels in Swedish power plants and possibilities to join in the projects of Vaermeforsk in this research field. Following companies participate in the project: Etelae-Savon Energia Oy, Foster Wheeler Energia Oy, Kvaerner Pulping Oy, Simpele pasteboard factory of M-Real Oyj and Vaermeforsk AB (Sweden). (orig.)

  10. Nuclear energy. Rulings of the Hessian Administrative Court from the 21.07.1993 (fuel element plant Hanau)

    International Nuclear Information System (INIS)

    Rulings of the Hessian Administrative Court from the 21.7.1993 (fuel element plant Hanau). Reasons for the judgment are now available in written form (Hessian Administrative Court, 21.7.1993). They refer to the first, third and fourth partial licence for the mixed oxide processing plant in the fuel element plant in Hanau. (orig./HP)

  11. 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

  12. Sensitivity analysis of oxy-fuel power plant system

    International Nuclear Information System (INIS)

    Highlights: • The half-dry mode of flue gas provides the highest efficiency for coal oxy-firing. • Air leakage exerts the largest impact on the net efficiency of oxy-coal process. • Utilizing the thermal energy of hot flue gas can improve process efficiency. - Abstract: A comprehensive sensitivity analyses has been conducted to assess the performance of a purpose-designed 600 MW supercritical steam oxy-fuel bituminous coal-fired power plant system, which includes three modes for the recirculation of flue gas (RFG), i.e. dry, half-dry and wet. The assessment was conducted by considering the changes to eight major operating parameters, the flue gas acid dew point, and the fuel consumption rate. Optimization of the system was also considered to minimize the energy loss of the oxy-fuel process. The results suggest that air leakage exerts the largest impact on the output of the system. The half-dry RFG oxy-fuel system is the most practical due to its high efficiency and easiness in operation, compared with the other two flue gas recirculation modes. The acid dew point of the half-dry RFG system is about 10 °C higher than that of the dry RFG system and approximately 5 °C lowers than the wet RFG system. For the optimization purpose, the improvement in the turbine system through utilizing the thermal energy of the hot flue gas is of prime importance. By heating the feed water at the outlet of the secondary feed water heater upstream of the deaerator and cooling down the hot flue gas to a temperature which is 10 °C above its acid dew point, the net efficiency of an oxy-fuel process can raise by around 1.0%, which narrows the energy penalty to less than 10% compared to the reference air-firing system. This is smaller than an energy penalty of around 12% for the oxy-fuel process without the recovery of heat in the hot flue gas. It is also found that the efficiency elevation through the thermal integration with turbine system is greater for the wet model than the

  13. Fort Calhoun Station disposal of spent fuel pool racks

    International Nuclear Information System (INIS)

    The original plan was to have the racks pulled out of the pool, washed down and wrapped and placed in Sea/Lands to be sent to a vendor for free release and disposal. In the winter of 93 the proposed quotations on the Spent Fuel Rerack Processing were all rejected. With the rerack job starting in March of 94 and the closing of Barnwell in July we were faced with what to do with the racks. Processing of the existing racks were required since if the racks were sent to Barnwell for burial intact the cost would be prohibitive, that is, if Barnwell would have stayed open. If the racks were sent to a smelter, such as Scientific Ecology Group (SEG), there are restrictions on the length of the components that can go through the smelter. If SEG were to do the rack processing (sectioning) at their facility, the cost would also be prohibitive and they would not be in a position to receive the racks until June, 1995. Therefore, bid specifications were requested for on-site volume reduction processing of the existing spent fuel storage racks, with further ultimate disposal to be performed by SEG. The processing of the racks included piping and supports. Volume reduction (VR) was an issue in the evaluation since after this process the racks were to be shipped to SEG. If a low VR ratio option was chosen, OPPD would need a significant number of shipping containers and required more radwaste shipments versus if a high VR ratio option were chosen

  14. Fuel management technologies for improved plant profitability

    International Nuclear Information System (INIS)

    Instead of an efficient system, today's technologies build in redundancies and inaccuracies that make gas under-utilized or require more pipeline or supply capacity than necessary to demonstrate that true reliability exists. For example, average pipeline throughputs are 71% of peak day capacities (as reported in a 1992 DOE study). Further, LDC and electric loads may be more compatible on an hourly basis than some industry players may believe. This un-needed redundancy causes pipeline rates to be higher than may be necessary and forces the inefficient use of the pipeline system. More accurate current information can allow the same level of reliability, but instead of having excess physical capacity, the more accurate knowledge allows for high reliability by the use of the entire pipeline and electric utility infrastructure. Currently, a number of technologies are used to mitigate fuel management risks and improve power plant profitability. The remainder of the paper discuss the vulnerabilities, current technologies, and a future project for the industry to improve plant profitability

  15. 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.

  16. Status of PBMR process heat plant project

    International Nuclear Information System (INIS)

    Conventional nuclear power plants only supply energy in a portion of the electricity sector, while the transportation and industrial energy sectors remain to rely exclusively on fossil fuels for its energy needs. However, the transportation and industrial sectors are vast consumers of energy and jointly contribute to approximately 66% of global CO2 emissions. Industry concerns for escalating cost of natural gas and petroleum, energy security and environmental acceptability are driving interest in using nuclear energy as primary energy source for transportation and industrial applications. An opportunity exists to introduce nuclear process heat into the world's energy market, but to succeed any technology must be available commercially in the needed timeframe, be demonstrably safe in order to be located close to the process plant, be economical, match the process energy needs and must produce the required temperatures. The Pebble Bed Modular Reactor (PBMR), under development in South Africa, fits each of these requirements. The PBMR is an advanced helium-cooled, graphite-moderated High Temperature Gas-cooled Reactor (HTGR). A 400 MWt (165 MWe) Demonstration Power Plant (DPP) for the production of electricity is being developed in South Africa for its national utility Eskom. The DPP project is envisioned to form the platform to launch future commercial PBMR products, notably including a variety of process heat applications for the transport and industrial sectors. PBMR Company has partnered with the Shaw Group, Westinghouse and others to develop and pilot its nuclear process heat technology. The team proposes that the first demonstration facility involve a consortium of industrial clients and is currently working to that end. One of these collaborative projects includes the Westinghouse-led consortium that was awarded the principal contract for the initial phase of pre-conceptual engineering services and planning for the Next Generation Nuclear Plant (NGNP) by the U

  17. Feasibility study of fuel grade ethanol plant for Alcohol Fuels of Mississippi, Inc. , Vicksburg, Mississippi

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-01-01

    The results are presented of a feasibility study performed to determine the technical and economic viability of constructing an alcohol plant utilizing the N.Y.U. continuous acid hydrolysis process to convert wood wastes to fuel grade alcohol. The following is a summary of the results: (1) The proposed site in the Vicksburg Industrial Foundation Corporation Industrial Park is adequate from all standpoints, for all plant capacities envisioned. (2) Local hardwood sawmills can provide adequate feedstock for the facility. The price per dry ton varies between $5 and $15. (3) Sale of fuel ethanol would be made primarily through local distributors and an adequate market exists for the plant output. (4) With minor modifications to the preparation facilities, other waste cellulose materials can also be utilized. (5) There are no anticipated major environmental, health, safety or socioeconomic risks related to the construction and operation of the proposed facility. (6) The discounted cash flow and rate of return analysis indicated that the smallest capacity unit which should be built is the 16 million gallon per year plant, utilizing cogeneration. This facility has a 3.24 year payback. (7) The 25 million gallon per year plant utilizing cogeneration is an extremely attractive venture, with a zero interest break-even point of 1.87 years, and with a discounted rate of return of 73.6%. (8) While the smaller plant capacities are unattractive from a budgetary viewpoint, a prudent policy would dictate that a one million gallon per year plant be built first, as a demonstration facility. This volume contains process flowsheets and maps of the proposed site.

  18. 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

  19. Westinghouse fuel consolidation process evolution

    International Nuclear Information System (INIS)

    Production rates for fuel consolidation services offered by Westinghouse in the early 1980s were quoted at four assemblies per day, based on the automated equipment system and full bundle pulling concept envisioned at that time. Results from the recent consolidation campaign conducted at Prairie Island indicate that such production rates are still currently achievable, with a simpler approach than in the earlier concepts. With an equipment system comprised of only one assembly unloading station, with its attendant transition canister, feeding into one storage can loading station, a peak production rate of 2.3 assemblies per day was achieved at Prairie Island. Improvement studies since then show that output with this equipment can be increased easily to the desired 4 assemblies per day with the addition of a second unloading station to feed the can loading station and incorporation of refinements identified from the first Prairie Island campaign

  20. 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.

  1. 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

  2. Quality control in the fuel elements production process

    International Nuclear Information System (INIS)

    Recently great attention has been paid at the international level to the analysis of production processes and quality control of fuel and fuel elements with the aim to speed up activity of proposing and accepting standards and measurement methods. IAEA also devoted great interest to these problems appealing to more active participation of all users and producers fuel elements in a general effort to secure successful work of nuclear plants. For adequate and timely participation in future in the establishment and analysis of general requirements and documentation for the control of purchased or self produced fuel elements in out country it is necessary to be well informed and to follow this activity at the international level. (author)

  3. 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...

  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. Dry spent fuel storage facility at Kozloduy Nuclear Power Plant

    International Nuclear Information System (INIS)

    The Dry Spent Fuel Storage Facility (DSF) is financed by the Kozloduy International Decommissioning Support Fund (KIDSF) which is managed by European Bank for Reconstruction and Development (EBRD). On behalf of the Employer, the Kozloduy Nuclear Power Plant, a Project Management Unit (KPMU) under lead of British Nuclear Group is managing the contract with a Joint Venture Consortium under lead of RWE NUKEM mbH. The scope of the contract includes design, manufacturing and construction, testing and commissioning of the new storage facility for 2800 VVER-440 spent fuel assemblies at the KNPP site (turn-key contract). The storage technology will be cask storage of CONSTOR type, a steel-concrete-steel container. The licensing process complies with the national Bulgarian regulations and international rules. (authors)

  6. Viewpoint of utilities regarding fuel management of nuclear power plants

    International Nuclear Information System (INIS)

    The engagement of utilities in nuclear power requires them to engage in an increasing amount of fuel management activities in order to carry out all the tasks involved. Essentially, these activities involve two main areas: The procurement of all steps of the fuel cycle from the head to the back end; and in-core fuel management. A general survey of the different steps of the nuclear fuel cycle is presented together with the related activities and responsibilities which have to be borne by the utilities. Today's increasing utility involvement in the nuclear fuel management is shown, as well as future fuel management trends. The fuel management activities of the utilities are analysed with respect to organizational, technical, safeguarding, and financial aspects. The active participation of the utilities in fuel management helps to achieve high availability and flexibility of the nuclear power plant during its whole life as well as safe waste isolation. This can be ensured by continuous optimization of all fuel management aspects of the power plant or, on a larger scale, of a power plant system, i.e. activities by utilities to minimize fuel-cycle effects on the environment, which include optimization of fuel behaviour, and radiation exposure to the public and personnel; and technical and economic evaluations by utilities of out- and in-core fuel management. (author)

  7. 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.)

  8. 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

  9. 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.

  10. Pyrochemical processes for LWR spent fuel

    International Nuclear Information System (INIS)

    Pyrochemical processes are under development at Argonne National Laboratory for recovery of transuranium (TRU) elements from light water reactor spent fuel. The recovered TRU elements will be used as fuel in the integral fast reactor (IFR). Burning these long-lived isotopes for electrical power generation has the additional benefit of reducing the burden on the geological repository for their long-term containment. The goals for the process include: greater than 99.90% recovery of TRU elements, a metal product that is compatible with the IFR fuel cycle, retention of some fission products in the TRU product to enhance proliferation resistance, and a simple process that is economically attractive. The TRU product will be inserted into the IFR fuel cycle for fission product decontamination and incorporation into the fuel. Based on research and development at ANL in the 1960 and 1970 and a comparison of known processes for separation of TRU elements from uranium fuel, three conceptual processes were identified that seem to offer high potential for achieving the desired goals. All three conceptual processes include a reduction step to convert the oxide fuel to metal, an electrochemical step to recover the reductant (calcium) from its oxide, a TRU extraction step to separate TRU elements from the bulk uranium, and a retort step to recover the TRU product from a solvent metal. The candidate processes differ primarily in the methods used to separate the TRU elements from uranium. The salt transport process effects this separation by molten salt extraction; the magnesium extraction process uses the differential solubility of TRU elements in magnesium relative to that of uranium; and the zinc-magnesium process uses phase separation to recover TRU elements, which are soluble in a Zn-Mg alloy. The chemical feasibility of each step of the three concepts has been demonstrated in small-scale experiments. Candidate containment materials have been selected and tested at the

  11. 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)

  12. 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.

  13. 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.

  14. 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

  15. Radiotracers in understanding plant processes

    International Nuclear Information System (INIS)

    Nuclear and allied techniques have immense applications in the area of agricultural research. Radioisotopes have been exceptionally useful to understand the various physiological functions of the metabolic changes induced under varying growth environments and among different crops. These have helped in improving our understanding of crop variation in carbon influx and assimilation, source sink relationship, ion influx into apoplasm, nutrient uptake, interaction of ions, foliar uptake, transport, utilisation/assimilation. Isotopes yield an analytical advantage that they can be easily traced and measured in minute quantities and analysis remains uncomplicated by the presence of large cellular pools of the ions in question. In fact radioisotopes can be used effectively in developing modern agro-techniques for better understanding of the mineral fertilizer-, water-use and biological nitrogen efficiency. It is important to collate and critical analyze the available research knowledge and leads on the advances made in the field of plant mineral nutrition through the use of radioisotopes and stable isotopes. 14C can be used to assess source sink relationship and to measure the carbon exudates that are released by plant roots for ensuing rhizosphereic modifications. Radiotracers offer a unique advantage in terms of high sensitivity, their simplicity and small expense (compared to competing technologies such as mass spectrometry). In a well-designed experiment, the presence of radiotracers does not affect the system under study and any analysis is non-destructive. Radiotracers can be used to study the dynamic biological processes like the ion transport across cell membranes, turnover, intermediary metabolism, or translocation in plants that were earlier being studied indirectly with a greater degree of analytical error. Radiotracer technology also aids in identification of the rate determining step in any biological process. Innovative radiological tools like Positron

  16. 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.)

  17. 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.

  18. Development of advanced spent fuel management process

    International Nuclear Information System (INIS)

    This study is to develop an advanced spent fuel management process for countries which have not yet decided a back-end nuclear fuel cycle policy. The aims of this process development based on the pyroreduction technology of PWR spent fuels with molten lithium, are to reduce the storage volume by a quarter and to reduce the storage cooling load in half by the preferential removal of highly radioactive decay-heat elements such as Cs-137 and Sr-90 only. From the experimental results which confirm the feasibility of metallization technology, it is concluded that there are no problems in aspects of reaction kinetics and equilibrium. However, the operating performance test of each equipment on an engineering scale still remain and will be conducted in 1999. (author). 21 refs., 45 tabs., 119 figs

  19. Decommissioning of the Siemens Hanau fuel fabrication plant and hot cells

    International Nuclear Information System (INIS)

    In the early and mid-1990s, a series of decisions had to be made - partially as a result of political requirements but also, in some cases, for economic reasons - to permanently shut down four facilities operated by the Nuclear Fuel Cycle Division of Siemens' Power Generation Group (KWU). 1989 saw the closure of the hot cells in Karlstein in which Germany's most extensive post-irradiation examinations of fuel assemblies had been carried out since 1967. In 1994/95, manufacture of gadolinium-bearing uranium fuel assemblies was abandoned at the Siemens Karlstein Fuel Fabrication Plant which had been in operation since 1963. At the Siemens Hanau Fuel Fabrication Plant, the facilities for manufacturing mixed-oxide (MOX) fuel assemblies and uranium fuel assemblies were permanently shut down in 1991 and 1995, respectively. The uranium processing facility had been in operation since 1969, and the MOX processing facility since 1970. Shutdown and decommissioning of these four facilities have mainly been proceeding in the following stages. First of all the facilities are cleaned out and all process equipment is removed. Then the auxiliary and support systems are dismantled. Finally the buildings are decontaminated and, in some cases, demolished. Possibly contaminated soil will be removed and the site restorated, after which it is released for unrestricted use and is no longer subject to the licensing requirements of the German Atomic Energy Act. Nuclear fuel materials as well as a few of the process components have been given to other nuclear fuel manufacturers. (orig.)

  20. ICP-AES technique in spent nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    This report describes the glove box adaptation of a High Resolution Atomic Emission Spectrometer (HR-AES) for the determination of trace metallic elements in products of Reprocessing plant and various raw materials used for nuclear spent fuel reprocessing

  1. Integrated coal preparation and CWF processing plant

    Energy Technology Data Exchange (ETDEWEB)

    McHale, E.T.; Paul, A.D.; Bartis, J.T. [Science Applications International Corp., McLean, VA (United States)

    1993-12-31

    At the request of the U.S. Department of Energy (DOE), Pittsburgh Energy Technology Center, a study was conducted to provide DOE with a reliable, documented estimate of the cost of producing coal-water fuel (CWF). The approach to the project was to specify a plant capacity and location, identify and analyze a suitable coal, and develop a conceptual design for an integrated coal preparation and CWF processing plant. Using this information a definitive costing study was then conducted, on the basis of which an economic and sensitivity analysis was performed utilizing a financial evaluation model to determine a price for CWF in 1992. The scale of the coal preparation and CWF plant design chosen for the study is 200 tons per hour coal output on a dry basis (285 tph CWF). The baseline case assumes round-the-clock operation with an annual operating capacity of 83 percent, corresponding to 166 tph dry coal average output or about 1.5 million tons per year. This is equivalent to the energy required to fuel approximately 500 MW of continuous electric generating capacity. (Other approximate equivalencies are 27,000 barrels per day of CWF or three unit trains per week of CWF delivery.) The design and costing are based on a battery-limit, integrated plant located at or near a coal mine site. As such, it is assumed that roads, rail lines, electric service, water access, auxiliaries, etc., will be available. Also, no provision is made for raw coal storage, since coal storage is assumed to be part of the mining operation. CWF delivery can be by rail, barge or pipeline. The normal operating mode is assumed to the out-loading of CWF directly into unit trains made up of rail tank cars. Storage is provided for two days production of CWF. Costs for off-site disposal of dewatered refuse are included in the final cost figure. The CWF type at which the study was directed is a boiler grade fuel intended to be burned in utility or large industrial units.

  2. Fuel Receiving and Storage Station. Nuclear Regulatory Commission's draft environmental statement

    International Nuclear Information System (INIS)

    A draft of the environmental impact statement for the Barnwell Fuel Receiving and Storage Station is presented. This facility is being constructed on a 1700 acre site about six miles west of the city of Barnwell in Barnwell County, South Carolina. The following topics are discussed: the site, the station, environmental effects of site preparation and station construction, environmental effects of station operation, effluent and environmental monitoring programs, environmental effects of accidents , need for the station, benefit-cost analysis of alternatives, and conclusions. (U.S.)

  3. 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

  4. 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.

  5. Thermodynamic analysis of SOFC (solid oxide fuel cell)–Stirling hybrid plants using alternative fuels

    International Nuclear Information System (INIS)

    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. Simulations of the proposed system were conducted using different fuels, which should facilitate the use of a variety of fuels depending on availability. Here, the results for natural gas (NG), ammonia, di-methyl ether (DME), methanol and ethanol are presented and analyzed. The system behavior is further investigated by comparing the effects of key factors, such as the utilization factor and the operating conditions under which these fuels are used. Moreover, the effect of using a methanator on the plant efficiency is also studied. The combined system improves the overall electrical efficiency relative to that of a stand-alone Stirling engine or SOFC plant. For the combined SOFC and Stirling configuration, the overall power production was increased by approximately 10% compared to that of a stand-alone SOFC plant. System efficiencies of approximately 60% are achieved, which is remarkable for such small plant sizes. Additionally, heat is also produced to heat the family home when necessary. - Highlights: • Integrating a solid oxide fuel with a Stirling engine • Design of multi-fuel hybrid plantsPlants running on alternative fuels; natural gas, methanol, ethanol, DME and ammonia • Thermodynamic analysis of hybrid SOFC–Stirling engine plants

  6. 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)

  7. 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.

  8. 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.

  9. Head-end demonstration test for nuclear fuel reprocessing plant 'outline of the test results'

    International Nuclear Information System (INIS)

    Japan Nuclear Fuel Ltd. (JNFL) is now constructing a nuclear fuel reprocessing plant at Rokkasho-mura (which is called Rokkasho Reprocessing plant). Concerning the head-end process, which includes shearing and dissolving processes for spent fuel and rinsing processes for end-pieces of spent fuel assemblies and chopped fuel rods, a full-scale mock-up test facility was constructed in Kobe Shipyard of Mitsubishi Heavy Industries, LTD (MHI). And then, functional and performance tests were performed using a dummy fuel assembly and chopped fuel rods, from 1988 to 1993. These tests using this full-scale mock-up test facility was called head-end demonstration test (HEDT), and this paper summarizes the results of HEDT. This HEDT facility includes five components: tilting crane, shearing machine, dissolver, hull rinser and end-piece rinser. The design of these components manufactured by MHI is based on CEA/COGEMA/SGN technology. The suitability of the design, the functional reliability, the operability, the controllability and the maintenability were evaluated through functional tests such as an operation test, for example a shearing test, under cold conditions (non radioactive). It was demonstrated that the test results were satisfactory. The component performance data and our manufacturing and operation experience will be greatly useful for the final design process and the choice of operational parameters for these head-end components of the Rokkasho Reprocessing Plant. (author)

  10. Head-end demonstration test for nuclear fuel reprocessing plant. Outline of the test results

    International Nuclear Information System (INIS)

    Japan Nuclear Fuel Ltd. (JNFL) is now constructing a nuclear fuel reprocessing plant (Rokkasho Reprocessing Plant) at Rokkasho-mura. Concerning the head-end process, which includes shearing and dissolving processes for spent fuel and rinsing processes for upper and lower end-pieces of spent fuel assemblies and chopped fuel rods, a full-scale mock-up test facility was constructed and functional and performance tests were performed using a dummy fuel assembly and chopped fuel rods. This paper summarizes results the tests conducted from 1988 to 1993 by Mitsubishi Heavy Industries, Ltd. (MHI). The head-end demonstration test (HEDT) facility includes five components: tilting crane, shearing machine, dissolver, hull rinser and end-piece rinser. The design of these components manufactured by MHI is based on SGN technology. The suitability of the design, the functional reliability, the operability, the controllability and the maintainability were evaluated through functional tests such as an operation test, a shearing test, a transfer test, a heating and cooling test and a remote maintenance test under cold (non radioactive) conditions. The test results were satisfactory. The component performance data and our manufacturing and operation experience will greatly facilitate the final design process and support the choice of operational parameters for these head-end components of the Rokkasho Reprocessing Plant. (author)

  11. Construction of the Plant RT-2 as a way for solving the problem of VVER-1000 spent fuel management in Russia

    International Nuclear Information System (INIS)

    Nuclear power in the Russian Federation in the future will be based on the VVER-1000 and it's modifications. To manage the spent fuels from this plant, the Plant RT-2 was designed to process the spent fuel. Plant construction was started in 1984 and stopped in 1989 due to economic difficulties. The necessity of the continuation of the plant is discussed

  12. Construction of the Plant RT-2 as a way for solving the problem of VVER-1000 spent fuel management in Russia

    Energy Technology Data Exchange (ETDEWEB)

    Lazarev, L.N.; Lyubtsev, R.I. [V.G. Khlopin Radium Institute, St. Petersburg (Russian Federation); Egorov, N.N. [Russian Ministry of Nuclear Power, Moscow (Russian Federation); Lebedev, V.A.; Revenko, Y.A.; Fedosov, Y.G. [Mining-Chemical Works, Krasnoyarsk (Russian Federation); Dubrovskii, V.M.

    1993-12-31

    Nuclear power in the Russian Federation in the future will be based on the VVER-1000 and it`s modifications. To manage the spent fuels from this plant, the Plant RT-2 was designed to process the spent fuel. Plant construction was started in 1984 and stopped in 1989 due to economic difficulties. The necessity of the continuation of the plant is discussed.

  13. 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

  14. 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)

  15. Licensing procedure for the Hanau fuel element fabrication plant

    International Nuclear Information System (INIS)

    Licensing procedure for the Hanau fuel element fabrication plant. The fuel element plant at Hanau fabricates at present fuel elements on the basis of licences according to para. 9 Atomic Energy Law. In 1975, however, it was decided to carry out a subsequent licensing procedure according to para. 7 Atomic Energy Law. This led to protracted proceedings before the Administrative Court and, in addition, to criminal proceedings against the managing director and officials. Most of the proceedings were settled in favor of the operator. The present state of partial licenses is described. (DG)

  16. 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

  17. Express diagnostics of WWER fuel rods at nuclear power plants

    International Nuclear Information System (INIS)

    Higher safety and economical efficiency of nuclear power plants (NPP) call for a continuous design modification and technological development of fuel assemblies and fuel rods as well as optimization of their operating conditions. In doing so the efficiency of new fuel introduction depends on the completeness of irradiated fuel data in many respects as well as on the rapidity and cost of such data obtaining. Standard examination techniques of fuel assemblies (FA) and fuel rods (FR) intended for their use in hot cell conditions do not satisfy these requirements in full extent because fuel assemblies require preliminary cooling at NPP to provide their shipment to the research center. Expenditures for FA transportation, capacity of hot cells and expenditures for the examined fuel handling do not make it possible to obtain important information about the condition of fuel assemblies and fuel rods after their operation. In order to increase the comprehensiveness of primary data on fuel assemblies and fuel rods immediately after their removal from the reactor, inspection test facilities are widely used for these purposes. The inspection test facilities make it possible to perform nondestructive inspection of fuel in the NPP cooling pools. Moreover these test facilities can be used to repair failed fuel assemblies. The ultrasonic testing of failed fuel rods inside the fuel assembly was developed for stands of inspection and repair of TVSA WWER-1000 for the Kalinin NPP and Temelin NPP. This method was tested for eight leaking fuel assemblies WWER-440 and WWER-1000 with a burnup of ∼14 up to 38 MW·day/kgU. The ultrasonic testing proved its high degree of reliability and efficiency. The defectoscopy by means of the pulsed eddy-current method was adapted for the stand of inspection and repair of TVSA WWER-1000 for the Kalinin NPP. This method has been used at RIAR as an express testing method of FR claddings during the post-irradiation examinations of fuel assemblies WWER

  18. Building dismantlement and site remediation at the Apollo Fuel Plant: When is technology the answer?

    International Nuclear Information System (INIS)

    The Apollo fuel plant was located in Pennsylvania on a site known to have been used continuously for stell production from before the Civil War until after World War II. Then the site became a nuclear fuel chemical processing plants. Finally it was used to convert uranium hexafluoride to various oxide fuel forms. After the fuel manufacturing operations were teminated, the processing equipment was partially decontaminated, removed, packaged and shipped to a licensed low-level radioactive waste burial site. The work was completed in 1984. In 1990 a detailed site characterization was initiated to establishe the extent of contamination and to plan the building dismantlement and soil remediation efforts. This article discusses the site characterization and remedial action at the site in the following subsections: characterization; criticality control; mobile containment; soil washing; in-process measurements; and the final outcome of the project

  19. 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.

  20. 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)

  1. Idaho Chemical Processing Plant and Plutonium-Uranium Extraction Plant phaseout/deactivation study

    International Nuclear Information System (INIS)

    The decision to cease all US Department of Energy (DOE) reprocessing of nuclear fuels was made on April 28, 1992. This study provides insight into and a comparison of the management, technical, compliance, and safety strategies for deactivating the Idaho Chemical Processing Plant (ICPP) at Westinghouse Idaho Nuclear Company (WINCO) and the Westinghouse Hanford Company (WHC) Plutonium-Uranium Extraction (PUREX) Plant. The purpose of this study is to ensure that lessons-learned and future plans are coordinated between the two facilities

  2. 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.

  3. Recycling of nuclear spent fuel with AIROX processing

    International Nuclear Information System (INIS)

    This report examines the concept of recycling light water reactor (LWR) fuel through use of a dry-processing technique known as the AIROX (Atomics International Reduction Oxidation) process. In this concept, the volatiles and the cladding from spent LWR fuel are separated from the fuel by the AIROX process. The fuel is then reenriched and made into new fuel pins with new cladding. The feasibility of the concept is studied from a technical and high level waste minimization perspective

  4. Tecnored process - high potential in using different kinds of solid fuels

    Directory of Open Access Journals (Sweden)

    José Henrique Noldin Júnior

    2005-12-01

    Full Text Available One important feature of the Brazilian Tecnored ironmaking process is its flexibility to use different types of solid fuels, other than metallurgical coke, as proved in the pilot plant tests by extensively using green petroleum coke, biomasses, high ash cokes, etc. Even if new solid fuels not thus far used are envisaged for a given project, thru the bench scale simulator of the process it is possible to predict the behavior of such solid fuels in the Tecnored furnace and establish the best techno-economical-environmental equation for its use. This paper discusses the key aspects involved in the use of alternative solid fuels in the Tecnored process.

  5. Fuel switching in power-plants: Modelling and impact on the analysis of energy projects

    International Nuclear Information System (INIS)

    Highlights: • The impact of fuel-switching in electricity generation is researched. • 15 Scenarios of fuel-technology combinations are compared using a computational model. • Fuel-switching results to higher yields compared to single-fuelled plants. • Plants with natural gas combined cycle and solid fuel supercritical boilers are optimal. • Fuel-switching, offers higher flexibility and security of fuel supply. - Abstract: In electricity markets, where conditions are uncertain, the choice of the best technology and the optimisation of production processes may not anymore be enough to ensure optimal investment yield of energy business plans. Providing some aspects of flexibility might enhance their financial performance; fuel switching may prove to be an alternative option, offering operational flexibility over time, as well as significant financial benefits. Traditional investment analysis methods are considered marginally useful to analyse this case. Instead, the recent tools of time-dependent investment analysis are more appropriate, since they are not inherently restricted to immediate, irreversible decisions. In the present work, a time-dependent computational model is presented and applied in the case study of the Greek Power Sector, in order to estimate the potential advantages of the fuel switching concept. Moreover, the optimal timing of switching is derived, to ensure increasing yields of an average-capacity power-plant. The results of the research indicate significant financial benefits anticipated in most scenarios from applying fuel switching, compared to single-fuelled electricity generation units. Security of fuel supply and enhanced flexibility may also be offered to the power plant since more than one technology and fuels may be engaged

  6. Quantifying Tc-99 contamination in a fuel fabrication plant - 59024

    International Nuclear Information System (INIS)

    The Springfields facility manufactures nuclear fuel products for the UK's nuclear power stations and for international customers. Fuel manufacture is scheduled to continue into the future. In addition to fuel manufacture, Springfields is also undertaking decommissioning activities. Today it is run and operated by Springfields Fuels Limited, under the management of Westinghouse Electric UK Limited. The site has been operating since 1946 manufacturing nuclear fuel. As part of the decommissioning activities, there was a need was to quantify contamination in a large redundant building. This building had been used to process uranium derived from uranium ore concentrate but had also processed a limited quantity of recycled uranium. The major non-uranic contaminant was Tc-99. The aim was to be able to identify any areas where the bulk activity exceeded 0.4 Bq/g Tc-99 as this would preclude the demolition rubble being sent to the local disposal facility. The problems associated with this project were the presence of significant uranium contamination, the realisation that both the Tc-99 and the uranium had diffused into the brickwork to a significant depth and the relatively low beta energy of Tc-99. The uranium was accompanied by Pa-234m, an energetic beta emitter. The concentration/depth profile was determined for several areas on the plant for Tc-99 and for uranium. The radiochemical analysis was performed locally but the performance of the local laboratory was checked during the initial investigation by splitting samples three ways and having confirmation analyses performed by 2 other laboratories. The results showed surprisingly consistent concentration gradients for Tc-99 and for uranium across the samples. Using that information, the instrument response was calculated for Tc-99 using the observed diffusion gradient and averaged through the full 225 mm of brick wall, as agreed by the regulator. The Tc-99 and uranium contributions to the detector signal were separated

  7. 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.

  8. 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

  9. Plant Design Nuclear Fuel Element Production Capacity Optimization to Support Nuclear Power Plant in Indonesia

    International Nuclear Information System (INIS)

    The optimization production capacity for designing nuclear fuel element fabrication plant in Indonesia to support the nuclear power plant has been done. From calculation and by assuming that nuclear power plant to be built in Indonesia as much as 12 NPP and having capacity each 1000 MW, the optimum capacity for nuclear fuel element fabrication plant is 710 ton UO2/year. The optimum capacity production selected, has considered some aspects such as fraction batch (cycle, n = 3), length of cycle (18 months), discharge burn-up value (Bd) 35,000 up 50,000 MWD/ton U, enriched uranium to be used in the NPP (3.22 % to 4.51 %), future market development for fuel element, and the trend of capacity production selected by advances country to built nuclear fuel element fabrication plant type of PWR. (author)

  10. Preliminary analysis of treatment strategies for transuranic wastes from reprocessing plants

    International Nuclear Information System (INIS)

    This document provides a comparison of six treatment options for transuranic wastes (TRUW) resulting from the reprocessing of commercial spent fuel. Projected transuranic waste streams from the Barnwell Nuclear Fuel Plant (BNFP), the reference fuel reprocessing plant in this report, were grouped into the five categories of hulls and hardware, failed equipment, filters, fluorinator solids, and general process trash (GPT) and sample and analytical cell (SAC) wastes. Six potential treatment options were selected for the five categories of waste. These options represent six basic treatment objectives: (1) no treatment, (2) minimum treatment (compaction), (3) minimum number of processes and products (cementing or grouting), (4) maximum volume reduction without decontamination (melting, incinerating, hot pressing), (5) maximum volume reduction with decontamination (decontamination, treatment of residues), and (6) noncombustible waste forms (melting, incinerating, cementing). Schemes for treatment of each waste type were selected and developed for each treatment option and each type of waste. From these schemes, transuranic waste volumes were found to vary from 1 m3/MTU for no treatment to as low as 0.02 m3/MTU. Based on conceptual design requirements, life-cycle costs were estimated for treatment plus on-site storage, transportation, and disposal of both high-level and transuranic wastes (and incremental low-level wastes) from 70,000 MTU. The study concludes that extensive treatment is warranted from both cost and waste form characteristics considerations, and that the characteristics of most of the processing systems used are acceptable. The study recommends that additional combinations of treatment methods or strategies be evaluated and that in the interim, melting, incineration, and cementing be further developed for commercial TRUW. 45 refs., 9 figs., 32 tabs

  11. Development of pyrochemical process in molten salts applied to the radioactive wastes from nuclear power plants and nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Toshiba started to develop a series of methods of radioactive waste treatment in 1980's. Our original methods developed to date are; an abrasive blast decontamination method, a water jet method, a chemical decontamination method, an electrolytic decontamination method in aqueous solution etc. However, these decontamination methods have one common problem such as difficulties in decontamination of waste materials of complicated shapes and another common problem to cause large volume of secondary wastes such as used reagents and resin. Pyrochemical treatment in molten salts is a promising process for decontamination of radioactive waste in complicated shapes without producing a large amount of secondary wastes because the electric current is distributed effectively entire surface of the waste in high conductive molten salts and the decontaminated species by anodic dissolution are recovered on the cathode. We have applied this process to the radioactive waste such as Magnox end crops, metallic waste contaminated with uranium, wasted chemical traps for UF6 and channel boxes zircaloy wasted from boiling water reactors (BWR). This paper reviews pyrochemical processes in molten salts applied to the radioactive waste treatment. (author)

  12. 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

  13. 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.

  14. 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)

  15. 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

  16. Prospects for advanced coal-fuelled fuel cell power plants

    International Nuclear Information System (INIS)

    As part of ECN's in-house R and D programmes on clean energy conversion systems with high efficiencies and low emissions, system assessment studies have been carried out on coal gasification power plants integrated with high-temperature fuel cells (IGFC). The studies also included the potential to reduce CO2 emissions, and to find possible ways for CO2 extraction and sequestration. The development of this new type of clean coal technology for large-scale power generation is still far off. A significant market share is not envisaged before the year 2015. To assess the future market potential of coal-fuelled fuel cell power plants, the promise of this fuel cell technology was assessed against the performance and the development of current state-of-the-art large-scale power generation systems, namely the pulverized coal-fired power plants and the integrated coal gasification combined cycle (IGCC) power plants. With the anticipated progress in gas turbine and gas clean-up technology, coal-fuelled fuel cell power plants will have to face severe competition from advanced IGCC power plants, despite their higher efficiency. (orig.)

  17. Fuel management for the Beznau nuclear power plant in Switzerland

    International Nuclear Information System (INIS)

    The Beznau nuclear power plant consists of two 350 MW(e) PWRs of Westinghouse design. A number of special features characterize the nuclear industry in Switzerland: there is no fuel cycle industry; nuclear materials must be moved through several countries before they arrive in our country, it is therefore important that agreements are in place between those countries and Switzerland; nearly all of the materials and services required have to be paid in foreign currencies; the interest rate in Switzerland is traditionally low. Aspects of fuel management at the Beznau plant discussed against this background are: the procurement of natural uranium, its conversion and enrichment; fuel fabrication, in-core management, reprocessing and plutonium recycling; and fuel cycle costs. (author)

  18. 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

  19. 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...

  20. 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

  1. Management of Spent Nuclear Fuel from Nuclear Power Plant Reactor

    International Nuclear Information System (INIS)

    Management of spent nuclear fuel from Nuclear Power Plant (NPP) reactor had been studied to anticipate program of NPP operation in Indonesia. In this paper the quantity of generated spent nuclear fuel (SNF) is predicted based on the national electrical demand, power grade and type of reactor. Data was estimated using Pressurized Water Reactor (PWR) NPP type 1.000 MWe and the SNF management overview base on the experiences of some countries that have NPP. There are four strategy nuclear fuel cycle which can be developed i.e: direct disposal, reprocessing, DUPlC (Direct Use of Spent PWR Fuel In Candu) and wait and see. There are four alternative for SNF management i.e : storage at the reactor building (AR), away from reactor (AFR) using wet centralized storage, dry centralized storage AFR and prepare for reprocessing facility. For the Indonesian case, centralized facility of the wet type is recommended for PWR or BWR spent fuel. (author)

  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. Mixing and sampling tests for Radiochemical Plant

    International Nuclear Information System (INIS)

    The paper describes results and test procedures used to evaluate uncertainly and basis effects introduced by the sampler systems of a radiochemical plant, and similar parameters associated with mixing. This report will concentrate on experiences at the Barnwell Nuclear Fuels Plant. Mixing and sampling tests can be conducted to establish the statistical parameters for those activities related to overall measurement uncertainties. Density measurements by state-of-the art, commercially availability equipment is the key to conducting those tests. Experience in the U.S. suggests the statistical contribution of mixing and sampling can be controlled to less than 0.01 % and with new equipment and new tests in operating facilities might be controlled to better accuracy

  4. 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

  5. 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.

  6. Discussion on the Safety Analysis Approach in Fuel Cycle Facility and Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Soon Joon; Chung, Young Wook [FNC Tech., SNU, Seoul (Korea, Republic of); Jeong, Seung Young [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2011-10-15

    Domestic in-service light water reactors of 16 units generate spent fuel of around 320 ton/year and the heavy water reactors of 4 units around 380 tons/year, and 10,761 ton of spent fuel are deposited in plant sites. Electricity portion of nuclear power plants is planned to increase up to 59% share by 2030. So more spent fuel is expected to be produced. However, spent fuel in itself is also a very useful energy source. Thus, the safe management of spent fuel is very important confronting job in domestic nuclear industry. Advanced fuel cycle (AFC) using pyro-process is an innovative technology, by which environmental load is drastically relieved because the extracted long-lived fission products are burn in fast breeder reactors. Domestic nuclear industry also has a perspective road map for the construction of AFC facilities. However, there is not a sufficiently detailed licensing regulatory system yet. Moreover, there is no systematic frame for the safety evaluation. For the advancement toward the development of safety this paper reviewed the feature of conventional safety approaches in nuclear power plants and non-reactor nuclear facilities, in particular fuel cycle facilities

  7. Financial risks of post-closure custodial care for the Barnwell radioactive waste disposal facility - 16155

    International Nuclear Information System (INIS)

    This paper reports evaluations of the adequacy of the Barnwell Extended Care Fund in light of identified risks, with the conclusion that the fund is sufficient to cover the costs and uncertainties associated with planned post-closure care of the Barnwell, South Carolina low-level radioactive waste disposal facility. It reviews background information pertinent to the facility's post-closure monitoring and maintenance and describes financial responsibility for post-closure activities. It identifies and briefly characterizes the activities planned to be conducted following facility closure and presents the midrange estimate of planned post-closure costs. The paper identifies and quantifies sources of uncertainty in activities and costs planned for post-closure care and presents 50-, 80-, and 95-percent confidence levels of planned costs. The fund is currently sufficient to cover some but not all of the costs that might be incurred as a result of unplanned events. The paper identifies, characterizes, and quantifies unplanned events, possible consequences, and probabilities of occurrence. The paper presents costs that might be incurred in responding to the unplanned initiating events and identifies levels of confidence that the fund is adequate to cover such costs. (authors)

  8. Decommissioning of the Spent Fuel Pool at the A1 Nuclear Power Plant, Slovakia

    International Nuclear Information System (INIS)

    The spent fuel pool of A1 nuclear power plant long term storage facility was used for temporary storage of spent fuel after its removal from the reactor and cooling in the short term storage facility. The dimensions of the pool were 12 m × 7 m × 9 m (width × length × depth) and the bottom was at the −3.75 m level. Stainless steel plates with a thickness in the range of 3–5 mm covered the concrete walls and bottom of the pool, and the volume of water in the pool was 560 m3. Fuel assemblies were stored in casks filled with heat transfer media — chrompik:2 or dowtherm3. During storage, some fuel fission and corrosion products were released to chrompik or dowtherm, and, during handling of fuel and storage casks, these were released into the pool water. As a result, coolant media (chrompik, dowtherm and pool water) and all surfaces inside the spent fuel pool were significantly contaminated. Even after the transfer of all spent fuel to the Russian Federation (completed in 1999), the spent fuel pool contained a significant inventory of radioactivity in different forms. To this day, it continues to be one of the major technical problems for the A1 nuclear power plant decommissioning process. The risk of leakage of radioactive substances into the surrounding space inside the reactor building constantly increases, owing to the expiration of the service life of the facility and lower protection by its physical barriers. The radiological situation in the spent fuel pool and the inaccessibility of some pieces of equipment do not allow completion of physical characterization. These aspects were taken into account by the regulators, who require the emptying of the spent fuel pool and its decontamination by the end of 2018. Retrieval of radioactive waste from the spent fuel pool calls for the development and deployment of unique and technically complex equipment and implementation of non-standard technological processes

  9. Electoral structure of building foundations in nuclear fuel element plant

    International Nuclear Information System (INIS)

    Plant structures of nuclear fuel elements have a substantial burden. This requires analysis of the selection of the proper foundation for building support for a variety of different soil conditions found in two locations, first at a location near the nuclear power plant in Jepara and the second location BATAN Serpong area. Expected to know the location of soil conditions, we can determined the type of foundation that will be used based on the criteria requirements of the building. (author)

  10. Safety first at Siemens' new Hanau MOX fuel plant

    International Nuclear Information System (INIS)

    Siemens expects to begin production in 1992 at its new Hanau mixed oxide fuel plant, whose capacity will eventually rise to 120tHM/y. The seismically-designed building is particularly orientated to minimizing exposure, so that a staff member can work in the plant for 40 years without exceeding the limit of 40 rem. Fire protection, radioactivity release prevention and security measures are also described. (author)

  11. 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

  12. Verification of criticality Safety for ETRR-2 Fuel Manufacturing pilot Plant (FMPP) at Inshas

    International Nuclear Information System (INIS)

    The criticality safety of the fuel manufacturing pilot plant (FMPP) at inshas is studied and analyzed during normal and abnormal operation conditions. the multiplication factor during all stages of the manufacturing processes is determined. several accident scenarios were simulated and the criticality of these accidents were investigated. two codes are used in the analysis : MCNP 4 B code, based on monte Carlo method, and CITATION code , based on diffusion theory. the results are compared with the designer calculations and satisfactory agreement were found. the results of the study indicated that the safety of the fuel manufacturing pilot plant is confirmed

  13. The PUREX process as designated for the Wackersdorf reprocessing plant

    International Nuclear Information System (INIS)

    The Wackersdorf plant was designed on the basis of national and international experience with reprocessing plants for a throughput of 2 Mg of nuclear fuel per day. The long-proven PUREX process was adapted to local requirements and simplified by the introduction of electrolytical process stages. The amount of secondary waste was minimized by virtually complete recycling of the chemicals. For the first time in a commercial reprocessing plant, concentration of the dissolved tritium in a relatively small stream of waste water, which can be treated separately, was intended. The equipment is arranged in modules and can be remotely maintained, repaired and replaced. In this way, the exposure of the personnel to radiation is reduced to a minimum, not only during operation and maintenance, but also during repairs and decommissioning of the plant. (orig.)

  14. 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

  15. Operation of Atucha I nuclear power plant with 25 cooling channels without fuel elements

    International Nuclear Information System (INIS)

    In view of the need of removing the irradiation probes from the reactor of Atucha I nuclear power plant, a study about the consequences of operating with 25 channels without their respective fuel elements was performed. This condition was simulated by means of the code PUMA symmetry I and the consequences were analyzed. From the study resulted a program of stepped power reduction of the nuclear plant that would take place during the process of channel emptying. (Author)

  16. A NEPA follow-up study of DOE loan guarantee fuel ethanol plants

    International Nuclear Information System (INIS)

    This study was implemented to examine and characterize the actual environmental impacts of three fuel ethanol plants constructed under the US Department of Energy, Office of Alcohol Fuels Loan Guarantee Program, and to compare actual impacts with those predicted about six years ago in environmental assessments (EAs) prepared for these facilities. The objective of the program, established under the Energy Security Act of 1980, was to conserve petroleum resources by promoting the use of fuel ethanol in motor vehicles. The plants were designed to produce fuel-grade ethanol for blending with gasoline and reflect differentfeedstocks, processes, fuel sources, and site locations. Although two of the facilities as constructed differed substantially from those assessed previously, actual environmental impacts generally occurred in the areas predicted by the EAs. Major impacts not anticipated include odor from air emissions, effects of wastewater discharge on operation of a municipal sewage treatment plant, possible classification of treated wastewater from a molasses-based process as a nuisance, and habitat losses from both vegetation removal and unforeseen construction of barge terminals. In all cases, impacts were judged to be not significantn the final outcome, either because plant management (or other involved parties) took corrective action or because the resources affected in these particular cases were not important. Mitigation measures reliedon in the EAs to limit adverse impacts to insignificant levels were implemented and were required by permit condition, law, or regulation. Future follow-up studies would benefit from the availability of ambientmonitoring data to more thoroughly characterize actual impacts

  17. Characterization of the head end cells at the West Valley Nuclear Fuel Reprocessing Plant

    Energy Technology Data Exchange (ETDEWEB)

    Vance, R.F.

    1986-11-01

    The head-end cells at the West Valley Nuclear Fuel Reprocessing Plant are characterized in this report. These cells consist of the Process Mechanical Cell (PMC) where irradiated nuclear fuel was trimmed of excess hardware and sheared into short segments; and the General Purpose Cell (GPC) where the segments were collected and stored prior to dissolution, and leached hulls were packaged for disposal. Between 1966 and 1972, while Nuclear Fuels Services operated the plant, these cells became highly contaminated with radioactive materials. The purpose of this characterization work was to develop technical information as a basis of decontamination and decommissioning planning and engineering. It was accomplished by performing remote in-cell visual examinations, radiation surveys, and sampling. Supplementary information was obtained from available written records, out-of-cell inspections, and interviews with plant personnel.

  18. Characterization of the head end cells at the West Valley Nuclear Fuel Reprocessing Plant

    International Nuclear Information System (INIS)

    The head-end cells at the West Valley Nuclear Fuel Reprocessing Plant are characterized in this report. These cells consist of the Process Mechanical Cell (PMC) where irradiated nuclear fuel was trimmed of excess hardware and sheared into short segments; and the General Purpose Cell (GPC) where the segments were collected and stored prior to dissolution, and leached hulls were packaged for disposal. Between 1966 and 1972, while Nuclear Fuels Services operated the plant, these cells became highly contaminated with radioactive materials. The purpose of this characterization work was to develop technical information as a basis of decontamination and decommissioning planning and engineering. It was accomplished by performing remote in-cell visual examinations, radiation surveys, and sampling. Supplementary information was obtained from available written records, out-of-cell inspections, and interviews with plant personnel

  19. Seismic analysis with FEM for fuel transfer system of PWR nuclear power plant

    International Nuclear Information System (INIS)

    In the PWR nuclear power plant, the function of the fuel transfer system (FTS) is to transfer the fuel assembly between the reactor building and the fuel building. The seismic analysis of the transfer system structure should be carried out to ensure the safety under OBE and SSE. Therefore, the ANASYS 12.0 software is adopted to construct the finite element analysis model for the fuel transfer system in a million kilowatt nuclear power plant. For the various configurations of FTS in the operating process, the stresses of the main structures, such as the transfer tube, fuel assembly container, fuel conveyor car, lifting frame in the reactor building, lifting frame in the fuel building, support and guide structure of conveyor car and the lifting frame in both buildings, are computed. The stresses are combined with the method of square root of square sum (SRSS) and assessed under various seismic conditions based on RCCM code, the results of the assessment satisfy the code. The results show that the stresses of the fuel transfer system structure meet the strength requirement, meanwhile, it can withstand the earthquake well. (authors)

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

    DEFF Research Database (Denmark)

    Rokni, Masoud

    2016-01-01

    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......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...... using SOFC. Plant performances and CO2 emissions are compared for the suggested repowered plants....

  1. 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

  2. A literature review of methods for handling solid residues arising from fuel dissolution in a nuclear fuel recycle plant

    International Nuclear Information System (INIS)

    This report reviews the literature on the management of solid residues, principally Zircaloy fuel hulls, arising from fuel dissolution in nuclear fuel recycle plants. Emphasis is placed on information likely to be relevant to possible future recycling of CANDU fuel. The report was prepared as part of the supporting documentation for the evaluation of fuel-waste treatment and disposal options in the Canadian Nuclear Fuel Waste Management Program

  3. Modeling of large-scale oxy-fuel combustion processes

    OpenAIRE

    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, among which radiative heat transfer under oxy-fuel conditions is one of the fundamental issues. This paper demonstrates the nongray-gas effects in modeling of large-scale oxy-fuel combustion processes...

  4. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    Olsen, A.R.

    1979-09-01

    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.

  6. Corrosion prevention and control at Sellafield nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    British Nuclear Fuels Ltd (BNFL) has established at Sellafield fuel management strategies and a pond water chemistry which ensures minimal corrosion of stored irradiated fuels. An extensive R and D programme evaluated materials for the Thermal oxide reprocessing plant (Thorp). Drawing on 35 years experience with Magnox reprocessing, the stainless steels selected for Thorp were nitric acid grade 18-10L and 304L with 310L used to construct fuel dissolvers. Thorp makes extension use of zirconium where minimal corrosion is required, e.g. heat transfer surfaces and demisting column packing. To augment the materials selection procedures, BNFL has instituted a policy of remote inspection and on line corrosion monitoring for its reprocessing plants. Facilities for remote repair are also being developed. Decommissioning of plant may involve corroded and degraded structures. Methods have been developed for the non-destructive examination of concrete and rebars to aid decommissioning scheduling. High level and intermediate level radioactive waste, arising from the reprocessing operations, will be stored at Sellafield until a final disposal policy is formulated. Corrosion resistant container materials have been selected for all major waste streams. A concurrent R and D programme is aimed at understanding the corrosion mechanisms pertinent to reprocessing plants and seeking improved methods and materials. (author)

  7. 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.)

  8. 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.

  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 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.)

  11. Data on facilities and processes of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    This report compiles important data on domestic and foreign facilities and processes of the nuclear fuel cycle. The data refer to the status of January 1986 and include the following parts of the nuclear fuel cycle: Uranium enrichment, fuel fabrication, transportation casks for irradiated fuel elements, interim storage, fuel reprocessing, radioactive waste management, final disposal of radioactive wastes and irradiated fuel elements. A short survey of German facilities is given in the introductory chapter. This report does not claim to be complete but provides by means of its compressed representation a prompt overview on existing or planned installations of the nuclear fuel cycle. (orig.)

  12. Status of radioiodine control for nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    This report summarizes the status of radioiodine control in a nuclear fuel reprocessing plant with respect to capture, fixation, and disposal. Where possible, we refer the reader to a number of survey documents which have been published in the last four years. We provide updates where necessary. Also discussed are factors which must be considered in developing criteria for iodine control. For capture from gas streams, silver mordenite and a silver nitrate impregnated silica (AC-6120) are considered state-of-the-art and are recommended. Three aqueous scrubbing processes have been demonstrated: Caustic scrubbing is simple but probably will not give an adequate iodine retention by itself. Mercurex (mercuric nitrate-nitric acid scrubbing) has a number of disadvantages including the use of toxic mercury. Iodox (hyperazeotropic nitric acid scrubbing) is effective but employs a very corrosive and hazardous material. Other technologies have been tested but require extensive development. The waste forms recommended for long-term storage or disposal are silver iodide, the iodates of barium, strontium, or calcium, and silver loaded sorbents, all fixed in cement. Copper iodide in bitumen (asphalt) is a possibility but requires testing. The selection of a specific form will be influenced by the capture process used

  13. Concept of a HTR modular plant for generation of process heat in a chemical plant

    International Nuclear Information System (INIS)

    This final report summarizes the results of a preliminary study on behalf of Buna AG and Leunawerke AG. With regard to the individual situations the study investigated the conditions for modular HTR-2 reactors to cover on-site process heat and electric power demands. HTR-2 reactor erection and operation were analyzed for their economic efficiency compared with fossil-fuel power plants. Considering the prospective product lines, the technical and economic conditions were developed in close cooperation with Buna AG and Leunawerke AG. The study focused on the technical integration of modular HTR reactors into plants with regard to safety concepts, on planning, acceptance and erection concepts which largely exclude uncalculable scheduling and financial risks, and on comparative economic analyses with regard to fossil-fuel power plants. (orig.)

  14. Investigation on optimization of reprocessing process in nuclear fuel cycling system

    International Nuclear Information System (INIS)

    In the present reprocessing plant, solid/liquid/vapor waste forms in large volume, and needs a lot of labors to process them. And, most of wastes are not defined their disposal conditions yet. Then, on considering non-process type wastes formed at operation of reprocessing plant, it is important how to do on quantitative evaluation of waste amounts forming at the reprocessing plant. In this study, it was attempted to extend the nuclear fuel reprocessing flow-sheet preparation and analysis system developed on a base of a process flow sheet preparation and analysis system to the waste processing system. Then, it was investigated to develop a method to effectively calculate a process flow-sheet calculation on a process flow-sheet geometrically expressed streams and units. And, in order to examine effectiveness of the developed system, a flow-sheet analysis was conducted on a representative process in the nuclear fuel reprocessing process. (G.K.)

  15. Development of inspection data collection and evaluation system for large scale MOX fuel fabrication plant (2)

    International Nuclear Information System (INIS)

    Inspection Data Collection and Evaluation System is the system not only to storage inspection data and operator declaration data collected from various measurement equipments, which are installed in fuel fabrication processes of the large-scale MOX fuel fabrication plant, but also to make safeguards evaluation based on Near Real Time Accountancy (NRTA). Nuclear Material Control Center developed a simulator for model fuel fabrication process and to generate measurement data by simulating in-process material. A verification evaluation system built in the simulator calculates various statistics and conducts statistical tests in NRTA in order to verify the adequacy of material accountancy for the fabrication process. We are currently investigating influences of process elements such as amount of unmeasured material on the verification results, evaluating availabilities of verification conditions from current safeguards approach and searching detection capability in accordance with various elements of the material accountancy. We explain the simulation result of detection capabilities with variables that would influence the results. (author)

  16. 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.

  17. Replacement of cowdung by fermentation of aquatic and terrestrial plants for use as fuel, fertilizer and biogas plant feed

    Energy Technology Data Exchange (ETDEWEB)

    Das, C.R. (Tata Energy Research Inst., Bombay, India); Ghatnekar, S.D.

    1981-01-01

    The problem of fuel for cooking in rural india (85% of the population), where 98% of the fuel requirement is for cooking purposes, is addressed. Currently, women and children spend 8 hours/day foraging for firewood and cowdung. As a solution to the problem (and to prevent further deforestation) a replacement material is suggested which is produced by simple technology and is within the reach of the poorest village dwellers. It is suggested that aquatic and terrestrial plants (water hyacinth, water lettuce, African payal, duck weed, paragrass, durva grass, etc.) be fermented in plastic bags for periods of 14 to 33 days. The fermented products would be made into cakes which can be burned as fuel or used as a fertilizer. Also, the cakes could be used as plant feed for a biogas process to produce methane. Experiments are described in which it is shown that the process is feasible, that the fermented mass is a suitable fuel, and that the fermented mass can be used as biogas plant feed. Plans for future experiments are outlined. (MJJ)

  18. A vitrocerus process for processing irradiated fuels in research reactors

    International Nuclear Information System (INIS)

    The search for viable solutions that guarantee a safe destination for the final disposal of MTR fuels irradiated from research reactors led the Nuclear Materials division of the Bariloche Atomic Center to develop a method for their immobilization in order to reduce the possibility of migration or dispersion of radionuclides during handling, storage and final disposal. Starting with simulated fuel elements from research reactors (MTR, Material Test Reactor) a ceramic matrix was created with irradiated uranium silicide (U3Si2) fuels - enriched to 10 % then removed from the reactor and U3O8 added for the 11:1 isotope dilution, with additions of VG98 borosilicate glass in a low enough proportion to facilitate sintering: vitrocerus process (ceramization of radioactive elements in sintered uranium with the addition of glass) submitted to heat treatments at 1200oC to obtain vitroceramic blocks. The method involves simple physical processes carried out in a hot cell that does not include reprocessing the fuel nor the extraction of the reusable materials. This process also permits working with considerably smaller volumes than those that would be used in conventional vitrification. The isotope dilution with natural uranium prevents the proliferation of fissile material and reduces their criticality. This would provide the resulting product with the capacity to be temporarily placed in dry storage or in some other proposed manner. The addition of a maximum of 10% by weight of vg98 visibly favored the solidity of the resulting material that was evaluated by submitting the samples to lixiviation tests in distilled water, with satisfactory results for the lixiviation properties in relation to the compounds without the added glass. The Brazilian mechanical resistance test was used to determine the tensile strengths together with Vickers microhardness tests which recorded poor resistance to traction tensions and compression and penetration for the samples without added glass

  19. 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

  20. 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.

  1. 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)

  2. 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...

  3. Property-process relationships in nuclear fuel fabrication

    International Nuclear Information System (INIS)

    Nuclear fuels are fabricated using many different techniques as they come in a large variety of shapes and compositions. The design and composition of nuclear fuels are predominantly dictated by the engineering requirements necessary for their function in reactors of various designs. Other engineering properties requirements originate from safety and security concerns, and the easy of handling, storing, transporting and disposing of the radioactive materials. In this chapter, the more common of these fuels will be briefly reviewed and the methods used to fabricate them will be presented. The fuels considered in this paper are oxide fuels used in LWRs and FRs, metal fuels in FRs and particulate fuels used in HTGRs. Fabrication of alternative fuel forms and use of standard fuels in alternative reactors will be discussed briefly. The primary motivation to advance fuel fabrication is to improve performance, reduce cost, reduce waste or enhance safety and security of the fuels. To achieve optimal performance, developing models to advance fuel fabrication has to be done in concert with developing fuel performance models. The specific properties and microstructures necessary for improved fuel performance must be identified using fuel performance models, while fuel fabrication models that can determine processing variables to give the desired microstructure and materials properties must be developed. (author)

  4. 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

  5. Study of CO2 capture processes in power plants

    International Nuclear Information System (INIS)

    The aim of the present study is 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 by methanol and oxy-fuel combustion with cryogenic recovery of CO2. These processes were evaluated using the process software Aspen PlusTM to give some clues for choosing the best option for each type of power plant. With regard to post-combustion, an aqueous solution based on a mixture of amines (N-methyldiethanolamine (MDEA) and triethylene tetramine (TETA)) was developed. Measurements of absorption were carried out between 298 and 333 K in a Lewis cell. CO2 partial pressure at equilibrium, characteristic of the CO2 solubility in the solvent, was determined up to 393 K. The solvent performances were compared with respect to more conventional solvents such as MDEA and monoethanolamine (MEA). For oxy-fuel combustion, a recovery process, based on a cryogenic separation of the components of the flue gas, was developed and applied to power plants. The study showed that O2 purity acts on the CO2 concentration in the flue gas and thus on the performances of the recovery process. The last option is natural gas reforming with CO2 pre-combustion capture. Several configurations were assessed: air reforming and oxygen reforming, reforming pressure and dilution of the synthesis gas. 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. (author)

  6. Criticality and safeguards at the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    Reprocessing of high enriched irradiated reactor fuel at the Idaho Chemical Processing Plant (ICPP) presents significant potential problems to the Criticality Safety (CS) and Safeguards and Security (S and S) Sections. Two major interactions between these sections occurs when irradiated fuel is stored and fuel is dissolved. S and S is assigned the responsibility of maintaining a centralized records and reporting system which provides detailed, timely knowledge of the location, quantity and measurement uncertainties associated with accountable nuclear material, including uranium and plutonium. The Criticality Safety Section uses this information in providing criticality safety evaluations with support analyses, inspection, field surveillance and audits to ensure criticality safety implementation. The interactions of these sections has minimized operational constraints and maximized criticality safeguards controls

  7. Fuel burnup extension effect on the fuel utilization and economical impact for a typical PWR plant

    International Nuclear Information System (INIS)

    Currently in Japan, fuel assembly average burn-up is limited to 48GWd/t and is going to be extended to 55GWd/t in these years. Moreover, R and D programs for further extension are under operation. Simultaneous extension of fuel burn-up limitation and cycle length reduces the number of fuel required to produce a given amount of energy reducing the radioactive waste generation, the occupational radiation exposure and the electricity generation cost. In this paper, the effect of fuel burn-up and operation cycle length extension is estimated from the view point of electricity generation cost and amount of discharged fuel assemblies, and the desirable burn-up extension in the future is studied. The present 5wt% uranium-235 enrichment restriction for commercial reactors divides the burn-up extension implementation in two steps. The fuel burn-up achievable with the present 5wt% enrichment limitation and without it is analyzed. A standard 3 loop PWR plant loading 17x17 fuel assemblies has been chosen for the feasibility study of operation cycle longer than 15 months and up to 24 months under extended fuel burn-up limitation. With the 5wt% enrichment limitation, the maximum assembly average burn-up is between 60GWd/t and 70GWd/t. Three batches reload fuel strategy and 18 months operation cycle allow the electricity generation cost reduction in about 4% and the number of fuel assemblies discharged per year is reduced in approximately 15% compared with the current 48GWd/t fuel. Relaxing the enrichment limitation, for the 24 months operation cycle with 3 batches reload fuel strategy, the maximum assembly average burn-up become 80GWd/t. The electricity generation cost reduction is about 8% and the number of fuel assemblies discharged per year is reduced in approximately 35% compared with the current condition. This study shows the contribution of simultaneous extension of fuel burn-up limitation and operation cycle length to reduce the electricity generation cost and the number

  8. 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.)

  9. A dry process fuel cycle analysis for a sodium-cooled fast reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Joon Jeong; Gyu, Hong Roh; Hangbok, Choi [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2005-07-01

    The Korean nuclear fuel cycle with the dry-processed oxide fuel sodium-cooled fast reactor (SFR) has been studied by the dynamic analysis method. In addition to the SFR, the current operating Pressurized Water Reactor (PWR) and Canadian Deuterium Uranium (Candu) reactors were considered. For the analysis, the equilibrium fuel cycle of the reference core was chosen from a modified BN-600 core. In the reactor scenario, the existing nuclear power plant construction plan was considered up to 2016, while the nuclear demand growth rate from the year 2016 was assumed to be 1%. In this study, the spent fuel inventory as well as the amount of plutonium, minor actinides (MA) and fission products (FP) of the recycling fuel cycle were estimated and compared to that of the once-through fuel cycle. The results of the once-through fuel cycle have shown that the demand increases up to 64 GWe and total amount of spent fuel is about 102 kt in 2100. When the dry-processed fuel SFR scenario is implemented, it is expected that the total spent fuel inventory can be reduced by about 80%. Also, the plutonium inventory can be reduced by about 25%. However it was found that the SFR scenario does not contribute to the reduction of the MA and FP, which are important when designing a repository. For a further destruction of the MA, an actinide burner can be considered in a future nuclear fuel cycle. (authors)

  10. 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...

  11. 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...

  12. 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.

  13. 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...... to that of a stand-alone Stirling engine or SOFC plant. For the combined SOFC and Stirling configuration, the overall power production was increased by approximately 10% compared to that of a stand-alone SOFC plant. System efficiencies of approximately 60% are achieved, which is remarkable for such small plant sizes...

  14. Internationalisation of the BNFL fuel and waste treatment plant designs the challenges and benefits

    International Nuclear Information System (INIS)

    Since the late 1970's BNFL has considerably expanded its range of fuel cycle plants, involving an investment of over US$7.5bn (55bn Won). This has included significant development of its Sellafield site with a wide variety of plants and processes to deal with spent fuel and development of its fuel fabrication facilities at the Spring fields Site. In contrast to reactors, fuel plants are constructed infrequently and it is therefore crucial to 'get it right first time'. The achievement of high levels of safety has been an important factor in the development of these facilities. BNFL has applied safety criteria which are as stringent as any other international safety criteria in terms of the extent to which radiation doses to plant workers and people off-site are minimised from both routine operations and possible fault conditions. Because the plant designs are established and supported by robust safety cases they are capable of being licensed overseas. The benefits of this are lower financial risk and shorter project timescales, due to avoiding the high design and safety case development costs (typically of the order of 20% of project cost) which are incurred in the production of a 'first of a kind' design. This paper briefly discusses the role of safety cases in the UK licensing process and the principle safety standards which are applied to BNFL plants and shows how they achieve high levels of safety by comparing them with equivalent IAEA and US based standards. It illustrates how the plants meet or exceed these safety standards by using specific data from existing safety cases supported by operational data where applicable. It discusses some of the important features of the UK approach to safety and licensing and emphasises the need to examine safety provisions on a case by case basis rather than adopting a prescriptive approach to implementing design provisions if cost effectiveness is to be achieved

  15. 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.

  16. 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

  17. Decommissioning of the HOBEG fuel element fabrication plant in Hanau

    International Nuclear Information System (INIS)

    The HOBEG fuel element fabrication plant was operated to manufacture graphite fuel elements for the thorium/high-temperature reactor in Hamm/Westf., Germany. The site comprises a 6000-m2 fenced area, an office/laboratory unit, and the production unit. In 1989, Nukem applied for a license to shut down the HOBEG fabrication plant in compliance with German atomic law (ATG article 7.3) and the radiation protection code with the goal of using the site and buildings for any other nonradioactive purpose. Approval for decommissioning was received in April 1995. Meanwhile, the existing equipment is being dismantled on the basis of single planning permissions and release for further use, for remelting, or for intermediate storage

  18. Evaluation of bioassay program at uranium fuel fabrication plants

    International Nuclear Information System (INIS)

    Results of a comprehensive study of urinalysis, lung burden and personal air sample measurements for workers at a uranium fuel fabrication plant are presented. Correlations between measurements were found and regression models used to explain the relationship between lung burden, daily intakes and urinary excretions of uranium. Assuming the ICRP lung model, the lung burden histories of ten workers were used to estimate the amounts in each of the long-term compartments of the lung. Estimates of the half lives of each compartment and of the maximum relative contributions to the urine from each compartment are given. These values were then used to predict urinary excretions from the long-term compartments for workers at another fuel fabrication plant. The standard error of estimate compared well with the daily variation in urinary excretion. (author)

  19. The investigation of HTGR fuel regeneration process

    International Nuclear Information System (INIS)

    The aim of this report is the investigation of HTGR fuel regeneration. The operation in the technologic scheme of uranium extraction from fuel depleted elements is separation of fuel from graphite. Available methods of graphite matrix destruction are: mechanical destruction, chemical destruction, and burning. Mechanical destruction is done in combination with leaching or chlorination. Methods of chemical destruction of graphite matrix are not sufficiently studied. Most of the investigations nowadays sre devoted to removal of graphite by burning

  20. Decommissioning and reconstruction of the fast reactor fuel reprocessing plant, Dounreay

    International Nuclear Information System (INIS)

    The conversion of the Fast Reactor Irradiated Fuel Reprocessing Plant at Dounreay from its original function of servicing the Dounreay Experimental Fast Reactor (15 MW(e)) fuel cycle to that of reprocessing fuel from the Dounreay Prototype Fast Reactor (250 MW(e)) led to an extensive modification exercise. This necessitated entry into, decontamination, and rebuilding of the greater part of the plant. In-cell plant conditions at the beginning of the exercise ranged down from radiation areas at above 1000 R/h gamma, and contamination levels 500 R/h beta-gamma and 1000 counts/s alpha. This exercise consequently proved to be the largest of its kind undertaken to date in the United Kingdom, and demonstrated the ability to decommission active plant facilities. It was necessary for personnel, to enter all sections of the active plant other than the DFR fuel disassembly cave and the DFR fuel dissolver cell. Several different types of cell were entered; namely - HA (beta-gamma) fuel breakdown caves, HA dissolver cells, and both HA and LA extraction cells. The conditions varied from total in-cave or cell contamination to cells containing mainly internally contaminated vessels. The radiological hazards embraced variously high gamma radiation levels and high plutonium contamination levels. The extent of the work varied from complete cell strip out - and in some cases demolition - to limited relocation and addition of process equipment. The above features, taken together, determined the objective adopted, either: (i) conversion to a contamination-free working area, or (ii) acceptance of limited contamination and radiation levels and working in air line suits

  1. 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

  2. Advance purex process for the new reprocessing plants in France and in Japan

    International Nuclear Information System (INIS)

    In the early Eighties, Japanese utilities formed the Japan Nuclear Fuel Service Co (JNFS), which is in charge of the construction and the operation of the first commercial reprocessing plant in Japan to be erected in Rokkasho Village, Aomori Prefecture. Following a thorough worldwide examination of available processes and technologies, JNFS selected the French technology developed for UP3 and UP2 800 for the plants' main facilities. For these three new plants, the 40-year old PUREX process which is used worldwide for spent fuel reprocessing, has been significantly improved. This paper describes some of the innovative features of the selected processes

  3. Safeguards planning in a plant design process

    International Nuclear Information System (INIS)

    The safeguards efforts for the partitioning fuel cycle are considered. Included in the discussion are the organization of the safeguards study, the development of safeguards criteria, the expression of these criteria as requirements for facility design, and some preliminary details of the implementation of these requirements in facility and process layout

  4. Safeguards planning in a plant design process

    Energy Technology Data Exchange (ETDEWEB)

    Heinrich, L.A.

    1977-01-01

    The safeguards efforts for the partitioning fuel cycle are considered. Included in the discussion are the organization of the safeguards study, the development of safeguards criteria, the expression of these criteria as requirements for facility design, and some preliminary details of the implementation of these requirements in facility and process layout. (LK)

  5. 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.

  6. Radiation shielding calculation for the MOX fuel fabrication plant Melox

    International Nuclear Information System (INIS)

    Radiation shielding calculation is an important engineering work in the design of the MOX fuel fabrication plant MELOX. Due to the recycle of plutonium and uranium from UO2 spent fuel reprocessing and the large capacity of production (120t HM/yr.), the shielding design requires more attention in this LWR fuel plant. In MELOX, besides several temporary storage facilities of massive fissile material, about one thousand radioactive sources with different geometries, forms, densities, quantities and Pu concentrations, are distributed through different workshops from the PuO2 powder reception unit to the fuel assembly packing room. These sources, with or without close shield, stay temporarily in different locations, containers and glove boxes. In order to optimize the dimensions, the material and the cost of shield as well as to limit the calculation work in a reasonable engineer-hours, a calculation scheme for shielding design of MELOX is developed. This calculation scheme has been proved to be useful in consideration of the feedback from the evolutionary design and construction. The validated shielding calculations give a predictive but reliable radiation doses information. (authors). 2 figs., 10 refs

  7. 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.)

  8. 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)

  9. 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.

  10. Thermodynamic analysis applied to a food-processing plant

    Energy Technology Data Exchange (ETDEWEB)

    Ho, J.C.; Chandratilleke, T.T.

    1987-01-01

    Two production lines of a multi-product, food-processing plant are selected for energy auditing and analysis. Thermodynamic analysis showed that the first-law and second-law efficiencies are 81.5% and 26.1% for the instant-noodles line and 23.6% and 7.9% for the malt-beverage line. These efficiency values are dictated primarily by the major energy-consuming sub-processes of each production line. Improvements in both first-law and second-law efficiencies are possible for the plants if the use of steam for heating is replaced by gaseous or liquid fuels, the steam ejectors for creating vacuum are replaced by a mechanical pump, and employing the cooler surroundings to assist in the cooling process.

  11. Automation system for transfer of spent fuel for nuclear reprocessing plants

    International Nuclear Information System (INIS)

    The Division of Remote Handling and Robotics (DRHR) has been working on design and development of various remote handling tools and automation system for handling active radioisotopes/spent fuel for various process systems. This article brings out first-of-its-kind advanced automation system designed for transfer of spent fuel bundles (pressurized heavy water reactors) for nuclear reprocessing plants. Introduction of this automation system for reprocessing plant is aimed at transferring the fuel bundles directly from fuel handling area (FHA) of storage pool to the dissolver cell in an automated way, without the necessity of using charging cask. This also contributes in eliminating dependency on skilled man-power and reduction of man-rem consumption. System design is such that it can easily be adopted to handle fuel from 220 MWe PHWR as well as 540 MWe/700 MWe PHWRs with minimum changes. Provision has also been kept for manual changing of spent fuel in case of nonavailability of automation system. (author)

  12. Description of ECRI (CNEA'S MTR fuel fabrication plant)

    International Nuclear Information System (INIS)

    The ECRI Plant is dedicated to the development and fabrication of high-density fuel elements and targets for 99Mo. In this sector had been done the start up Fuel Elements for the Reactors of Peru, Iran, Algeria and Egypt. All of them were made with U3O8. The targets for 99Mo using HEU were fabricated too in the last years. The new material of high-density for Fuel Elements as U3Si2 were done in this sector, three prototypes were fabricated, two are still under irradiation. (P06 and P07). As new developments we are working with U-Mo (7%) Fuel Plates with both material Korean and HMD. This work is under the RERTR Program and two fuel elements, manufactured by us, with both powders, will be irradiated in Petten. For 99Mo targets, we are fabricating miniplates of LEU with an AlUx powder by pulvi-metallurgy technique. And it is under development the foils targets under the RERTR Program. A general view of the fabrication facilities and control sector will be shown. The different operations that are done in each sector will be explained. All our activities will be certified under the ISO 9000 and we are working hard to get it in the middle of 2003. (author)

  13. 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

  14. 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

  15. 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

  16. 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....

  17. 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)

  18. 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.

  19. Handbook on process and chemistry on nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    '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 UO2 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)

  20. 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)

  1. THE EFFECTS OF UTILIZING GEOTHERMAL ENERGY IN THERMAL POWER PLANTS ON THE PLANT PERFORMANCE AND FUEL SAVING

    OpenAIRE

    Ahmet DAĞDAŞ

    2006-01-01

    The share of electricity production from thermal power plants for Turkey is about 61 %. Since the fossil fuels are rapidly consumed, the concept of fossil fuel saving is very important for humanity. In this paper, the effects of boiler feed water preheating by means of geothermal brine on overall performance and fossil fuel savings in thermal power plants are examined. According to the performed analysis, power plant thermal efficiency could be increased of 2-4 % via geothermal preheating. In...

  2. Castor and Pollux - shielded cells for studying fuel treatment processes

    International Nuclear Information System (INIS)

    CASTOR and POLLUX, two alpha, beta, gamma cells are described in the present paper. They are located in the CEN at Fontenay-aux-Roses (France). They are designed for improvement studies of the various aqueous separation processes used in irradiated fuels reprocessing plants. Located in the same air-tight steel encasement, they arc inter-connected by a pneumatic transfer. These two cells have a similar in-line conception and they include: a gamma shielding in lead of 10 cm of thickness; an inner air-tight box, made with stainless steel and plexiglas, is maintained in lowering in comparison to room pressure. Eleven Hobson model seven master-slave manipulators allow inner manipulations. Then the inner equipment is described briefly. (author)

  3. Modified ADS molten salt processes for back-end fuel cycle of PWR spent fuel

    International Nuclear Information System (INIS)

    The back-end fuel cycle concept for PWR spent fuel is explained. This concept is adequate for Korea, which has operated both PWR and CANDU reactors. Molten salt processes for accelerator driven system (ADS) were modified both for the transmutation of long-lived radioisotopes and for the utilisation of the remained fissile uranium in PWR spent fuels. Prior to applying molten salt processes to PWR fuel, hydrofluorination and fluorination processes are applied to obtain uranium hexafluoride from the spent fuel pellet. It is converted to uranium dioxide and fabricated into CANDU fuel. From the remained fluoride compounds, transuranium elements can be separated by the molten salt technology such as electrowinning and reductive extraction processes for transmutation purpose without weakening the proliferation resistance of molten salt technology. The proposed fuel cycle concept using fluorination processes is thought to be adequate for our nuclear program and can replace DUPIC (Direct Use of spent PWR fuel in CANDU reactor) fuel cycle. Each process for the proposed fuel cycle concept was evaluated in detail

  4. Need for higher fuel burnup at the Hatch Plant

    International Nuclear Information System (INIS)

    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

  5. 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.

  6. Process control in nuclear power plants

    International Nuclear Information System (INIS)

    Optimum technical design of a nuclear power plant needs to be parallelled by effective process control in the stage of output operation. The author briefly demonstrates the pertinent criteria like operational organization, functional areas, crews, training of staff, process monitoring, industrial safety, incident prevention, and emergency manual. (DG)

  7. Inventories of high burn up LWR UO2 spent fuel and ATR MOX spent fuel in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    This report describes calculated results of inventory of radioactivity in the Tokai Reprocessing Plant with calculation code, based on initial conditions and nuclear data library. The inventories were compared with three types of spent fuels, High burn up U oxide for light water reactor, U-Pu mixed oxide for advanced thermal reactor and the design based fuel for Tokai Reprocessing Plant. (author)

  8. 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

  9. 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

  10. Improved WWER fuel design and manufacturing process, operational experience

    International Nuclear Information System (INIS)

    The WWER fuel design and manufacturing processes applied by OAO MSZ are continuously improved. There are no remarks on the operation of the fuel assemblies with introduced innovations. All the improvements have been justified and are directed at a higher operational reliability and technological effectiveness of the fuel. The transition is in progress to the fuel cycles based on the profiled fuel of 3,82% average enrichment; the profiled fuel assemblies with U/Gd of 4,38% average enrichment are introduced and the second generation fuel of 4,25% average enrichment to be used for a 5-year fuel cycle, as well as the fuel assemblies of 3,82% average enrichment for the scram system with hafnium plates in the joint unit. Besides the above mentioned fuel the profiled U/Gd fuel of 3,84% average enrichment is launched for operation of the scram system. There is a continuous rate of growth of fuel operational time. 71% of the MSZ's fuel assemblies unloaded from the 14 WWER-440 reactors of the second generation (V-213 type) operated during 4 campaigns and more. In 2006 maximum burnup of the WWER-440 fuel was achieved at the Dukovany-4 NPP (49,23 MWd/kgU) for the 3,82% enriched fuel (average). Maximum burnup achieved by the WWER-1000 fuel is 62,24 MWd/kgU (for TVSA operated for 7 campaigns). The average leakage ratio of OAO MSZ's fuel manufactured for the WWER-440 reactors (V-213 type) located outside of Russia and Ukraine over the last 5 years makes 6.6x10-7 and is comparable with the best world achievements. (authors)

  11. 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.

  12. General description and production lines of the Egyptian fuel manufacturing pilot plant

    International Nuclear Information System (INIS)

    The Egyptian Fuel Manufacturing Pilot Plant, FMPP, is a new facility, producing an MTR-type fuel elements required for the Egyptian Second Research Reactor, ETRR-2, as well as other plates or elements for an external clients with the same type and enrichment percent or lower, (LEU). General description is presented. The production lines in FMPP, which begin from uranium hexaflouride (UF6, 19.7±0.2 % U235 by wt), aluminum powder, and nuclear grade 6061 aluminium alloy in sheets, bars, and rods with the different heat treatments and dimensions as a raw materials, are processed through a series of the manufacturing, inspection, and quality control plan to produce the final specified MTR-type fuel elements. All these processes and the product control in each step are presented. The specifications of the final product are presented. (author)

  13. 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.

  14. 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

  15. 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)

  16. Factors influencing the design of the Remote Analytical Laboratory at the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    The Remote Analytical Laboratory is a special purpose laboratory designed specifically to provide routine analytical chemistry support for the fuel reprocessing operations at the Idaho Chemical Processing Plant near Idaho Falls. It was built to replace the obsolete Remote Analytical Facility, a double line of 30 shielded cubicles equipped with Castle manipulators, which had served the plant since 1953

  17. 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.

  18. DUPIC nuclear fuel manufacturing and process technology development

    International Nuclear Information System (INIS)

    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. 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

  20. First and second law performance variations of a coal gasification fuel-cell-based combined cogeneration plant with varying load

    Energy Technology Data Exchange (ETDEWEB)

    Ghosh, S. [Deemed University, Howrah (India). Dept. of Mechanical Engineering; De, S. [Jadavpur University, Calcutta (India). Dept. of Mechanical Engineering

    2004-12-01

    An advanced combined cogeneration plant based on a solid oxide fuel cell (SOFC) stack, fuelled by synthetic gas by coal gasification, upstream of a gas turbine and heat recovery steam generator (HRSG) to generate power as well as process steam downstream of it, has been thermodynamically modelled. While the plant supplies a base load power and process heat, provision of a fuel cell bypass mechanism for the synthetic gas stream offers the flexibility of matching the varying electrical power or the process heat load on the plant. The simulated energetic and exergetic performance of such a plant is presented in this paper and the optimum point of operation is reported. The exergy analysis shows the second law performance variation of significant components of the plant with varying loads. (author)

  1. Intelligent plant operation support system for plant and process control

    Energy Technology Data Exchange (ETDEWEB)

    Kawaguchi, K.; Oishi, S.; Nishiya, T. (Hitachi, Ltd., Tokyo (Japan))

    1992-02-01

    Hitachi is introducing some AI (artificial intelligence) software packages, such as the advanced plant operation support system (APOS) and the intelligent alarm system (IMARK) which marks the process data with significant words, to reduce the workload of operators. APOS is a domain shell for the plant control expert system based on the real-time inference engine EUREKA-II (Electronic Understanding and Reasoning by Knowledge Activation-II). On the other hand, IMARK has been developed as one of the intelligent alarms to mark the time-series process data and report signs of an event to an operator. The present review article introduces the software packages for process computers, which includes APOS and IMARK, and also describes how AI techniques are used in them. 4 refs., 10 figs., 3 tabs.

  2. 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.

  3. Criticality safety evaluation in Tokai reprocessing plant. High burn up LWR UO2 spent fuel and ATR MOX spent fuel

    International Nuclear Information System (INIS)

    This report presents criticality safety evaluation of each equipment in Tokai reprocessing plant for two types of spent fuels, High burn up 4.2 % enrichment U oxide spent fuel for light water reactor and U-Pu mixed oxide spent fuel for advanced thermal reactor. As a result, it was confirmed that the equipments were safe enough for two types of the spent fuels from view point of criticality safety of single unit and multiple units. (author)

  4. MEU/Th fuel cycle optimization for the Lead Plant

    International Nuclear Information System (INIS)

    The reference equilibrium cycle fuel composition for the Lead Plant was specified previously by a C/Th ratio of 850 and a fuel rod diameter of 1.17 cm, which is optimal for non-recycle operation and close to optimal for recycle of bred U-233. Subsequent work has emphasized the importance of full recycle of all discharged uranium to maintain the competitive advantage of the MEU/Th cycle. Cycles with full recycle optimize at higher thorium loadings and larger rod diameters. This is an additional benefit for core design and reduces fabrication problems. New optimization studies based on full recycle lead to an equilibrium cycle composition characterized by a C/Th ratio of 600 and a rod diameter of 1.35 cm. The average packing fraction of fuel particles in the rod is 0.43. The C/Th ratio for the initial core is 350, which can also be accommodated with the 1.35 cm rod diameter. Mass flow data for 30 year operation and fuel cycle cost data have been obtained for this cycle and for several other thorium loadings

  5. Irradiated fuel sipping, inspection, and repair at Point Beach Nuclear Plant

    International Nuclear Information System (INIS)

    Point Beach Nuclear Plant has developed several tools to verify and help maintain adequate nuclear fuel performance. A cornerstone is a fuel assembly sipping system that has proved to be a fast and reliable method for determining fuel-clad integrity. If a fuel assembly is found with a damaged fuel rod, techniques have been developed to remove the affected rod. These efforts have resulted in significant benefits in radiation level control and fuel cost savings

  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. 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)

  8. 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

  9. Fossil fuel power plant combustion control: Research in Italy

    International Nuclear Information System (INIS)

    Electric power demand forecasts for Italy to the year 2000 indicate an increase of about 50% which, due to the current moratorium on nuclear energy, should be met entirely by fossil fuel power plants. Now, there is growing public concern about possible negative health impacts due to the air pollution produced through the combustion of fossil fuels. In response to these concerns, ENEL (Italian National Electricity Board) is investing heavily in air pollution abatement technology R ampersand D. The first phase involves the investigation of pollution mechanisms in order to develop suitable mathematical models and diagnostic techniques. The validity of the models is being tested through through measurements made by sophisticated instrumentation placed directly inside the combustion chambers of steam generator systems. These are allowing engineers to develop improved combustion control methods designed to reduce air pollution at source

  10. Fuel for the next Brazilian nuclear power plants

    International Nuclear Information System (INIS)

    The conclusion of the Angra III nuclear power plant ends a cycle of the nuclear energy in Brazil that started about forty years ago. Nowadays the country is planning the installation of 4 GWe to 8 GWe of nuclear power up to the year 2030. The nuclear reactors considered for this new cycle should take into account the current technologic development and environment of the nuclear market. They certainly will have significant differences in relation to the Angra I, II, and III reactors. Important impacts may result on the nuclear fuel production chain, e. g., case high temperature reactors were chosen, which can deliver electricity and heat. The differences between the fuels of the candidate reactors after Angra III are analyzed and development lines are suggested to minimize these impacts. (author)

  11. 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.

  12. Cost of transporting irradiated fuels and maintenance costs of a chemical treatment plant for irradiated fuels

    International Nuclear Information System (INIS)

    Numerous studies have been made of the cost of a fuel cycle, but many of them are based on a priori studies and are therefore to be treated with reserve. Thus, in the part dealing with the treatment of irradiated fuels, some important factors in the cost have only rarely been given on the basis of practical experience: the cost of transporting the fuels themselves and the plant maintenance costs. Investigations relating to transport costs are generally based on calculations made from somewhat arbitrary data. The studies carried out in France on the transport of irradiated uranium between the EDF reactors at Chinon and the retreatment plant at La Hague of the irradiated uranium from research reactors to foreign retreatment plants, are reported; they show that by a suitable choice of transport containers and details of expedition it has been possible to reduce the costs very considerably. This has been achieved either by combining rail and road transport or by increasing the writ capacities of the transport containers: an example is given of a container for swimming-pool pile elements which can transport a complete pile core at one time, thus substantially reducing the cost. Studies concerning the maintenance costs of retreatment plants are rarer still, although in direct maintenance plants these figures represent an appreciable fraction of the total treatment cost. An attempt has been made, on the basis of operational experience of a plant, to obtain some idea of these costs. Only maintenance proper has been considered, excluding subsidiary operations such as the final decontamination of apparatus, the burial of contaminated material and radioprotection operations Maintenance has been divided into three sections: mechanical maintenance, maintenance of electrical equipment and maintenance of control and adjustment apparatus. In each of these sections the distinction has been made between manpower and the material side. In order to allow comparisons to be made with

  13. Safety concerning partial modification of fuel reprocessing plant of Power Reactor and Nuclear Fuel Development Corporation

    International Nuclear Information System (INIS)

    The Nuclear Safety Commission following the investigation, recognized the safety of this modification on which the report was presented from the Committee on Examination of Nuclear Fuel Safety on August 8, 1979, and submitted a report to the Prime Minister on August 13, 1979, about the partial modification of the nuclear fuel reprocessing plant of the Power Reactor and Nuclear Fuel Development Corporation. The safety evaluation was conducted by the special sectional meeting on fuel reprocessing in the Committee on Examination of Nuclear Fuel Safety. This meeting was composed of eighteen experts, and was divided to A group in charge of equipments, accident analysis and aseismatic design, and B group in charge of radiation management and radiation exposure management. The content of the partial modification is to construct newly a facility for developing krypton recovery technique. Emphasis was placed on the aseismatic structure, the countermeasure to explosion the management of radioactive material release and the personal radiation exposure dose under the hypothetical accident condition, in this safety evaluation. The dynamic analysis of class A buildings and equipments was conducted for the aseismatic safety, and tritium release in the sea was investigated for radiation management. Concerning radiation exposure, beta ray and gamma ray dose were estimated under the accident condition due to the abnormal operation of a raw material gas compressor. (Nakai, Y.)

  14. A survey of methods to immobilize tritium and carbon-14 arising from a nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    This report reviews the literature on methods to separate and immobilize tritium (3H) and carbon-14 (14C) released from U02 fuel in a nuclear fuel reprocessing plant. It was prepared as part of a broader review of fuel reprocessing waste management methods that might find future application in Canada. The calculated inventories of both 3H and 14C in used fuel are low; special measures to limit releases of these radionuclides from reprocessing plants are not currently in place, and may not be necessary in future. If required, however, several possible approaches to the concentration and immobilization of both radionuclides are available for development. Technology to control these radionuclides in reactor process streams is in general more highly developed than for reprocessing plant effluent, and some control methods may be adaptable to reprocessing applications

  15. 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

  16. 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.

  17. 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

  18. 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)

  19. Optimized evaluation of aging fossil-fueled power plants

    International Nuclear Information System (INIS)

    The continued use of aging fossil-fueled power plants presents a number of unique challenges to utilities worldwide. To confront these challenges has required the simultaneous development of engineering methods and of strategic and planning approaches. New viewpoints and new tools have been required to assess the condition of existing equipment and to predict expected performance of older units. This paper reviews the recent evolution of methods for optimized use of older plants, both for the assessment of individual components and for cost-effective and integrated planning. The present state of understanding, current trends, implications, and lessons learned from a three-year demonstration project that included 10 US and Canadian utilities are discussed. (author)

  20. 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.

  1. SANITATION IN SHELL EGG PROCESSING PLANTS

    Science.gov (United States)

    Hazard analysis and critical control programs (HACCP) will eventually be required for commercial shell egg processing plants. Sanitation is an essential prerequisite program for HACCP and is based upon current Good Manufacturing Practices (cGMPs) as listed in the Code of Federal Regulations. Good ...

  2. 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

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

    International Nuclear Information System (INIS)

    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. Process for assembling a nuclear fuel element

    International Nuclear Information System (INIS)

    Before insertion into the spacers, the fuel rocks are coated with a self-hardening layer of water-soluble polyvinyl and/or polyether polymer to prevent scratches on the cladding tubes. After insertion, the protective conting is removed by means of water. (orig.)

  5. 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)

  6. Performance of a Wet Flue Gas Desulfurization Pilot Plant under Oxy-Fuel Conditions

    DEFF Research Database (Denmark)

    Hansen, Brian Brun; Fogh, Folmer; Knudsen, Niels Ole;

    2011-01-01

    Oxy-fuel firing is a promising technology that should enable the capture and storage of anthropogenic CO2 emissions from large stationary sources such as power plants and heavy industry. However, this new technology has a high energy demand for air separation and CO2 compression and storage....... Unresolved issues, such as determination of the optimal recycle location of flue gas, the flue gas cleaning steps required (SO2, NOx, and particles), and the impact of an oxy-fuel flue gas on the cleaning steps, also persist. The aim of this work was to study the performance of the wet flue gas...... desulfurization (FGD) process under operating conditions corresponding to oxy-fuel firing. The most important output parameters were the overall degree of desulfurization and the residual limestone concentration in the gypsum slurry. Pilot-scale experiments quantified that the introduction of a flue gas with 90...

  7. 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...

  8. Impact of plant life extension on new reactor and fuel cycle development

    International Nuclear Information System (INIS)

    Nuclear energy is back on the agenda worldwide. In order to prepare for the next decades and to set priorities in nuclear research and investment, it is essential to develop nuclear fuel cycle assessments. This allows to identify the triggers which influence the market penetration of prospective nuclear reactor technologies. To this purpose, fuel cycle scenarios for a future nuclear reactor park in Europe have been analysed applying an integrated dynamic process modelling technique. The assessment has been undertaken using the DANESS code (Dynamic Analysis of Nuclear Energy System Strategies, developed by Argonne National Laboratory (US)). This code allows the drawing of a complete picture of mass-flows between fuel cycle facilities and the economics of the various nuclear fuel cycle scenarios. The present assessment recognizes the integrated nuclear fuel cycle. It focuses on the effect of lifetime extension of the current reactor park on the market penetration of Gen IV reactor designs in the case of various nuclear energy demand scenarios. The analyses show that the implementation of lifetime extension of the current reactor park has a significant influence on the future reactor park development. Varying the time period in which the current reactor park is replaced might trigger different reactor designs to penetrate the market during different periods. Furthermore, the effect on the deployment of fuel cycle facilities, their impact on the radiation dose to the public, the electricity generation costs, and the workforce which is necessary to operate the existing fleet and construct the future plants, will be shown. (authors)

  9. A feasible approach to implement a commercial scale CANDU fuel manufacturing plant in Egypt

    International Nuclear Information System (INIS)

    Many planning scenarios have been examined to assess and evaluate the economic estimates for implementing a commercial scale CANDU fuel manufacturing plant in Egypt. The cost estimates indicated strong influence of the annual capital costs on total fuel manufacturing cost; this is particularly evident in a small initial plant where the proposed design output is only sufficient to supply reload fuel for a single CANDU-6 reactor. A modular approach is investigated as a possible way, to reduce the capital costs for a small initial fuel plant. In this approach the plant would do fuel assembly operations only and the remainder of a plant would be constructed and equipped in the stages when high production volumes can justify the capital expenses. Such approach seems economically feasible for implementing a small scale CANDU fuel manufacturing plant in developing countries such as Egypt and further improvement could be achieved over the years of operation. (author)

  10. 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

  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. Calculating primary fuel load of a nuclear reactor and planning the fuel component at a nuclear power plant

    International Nuclear Information System (INIS)

    The existing differences in the method for calculating costs for nuclear fuel, relating them to one or another type of industrial asset (fixed assets or long-term working capital), can lead to distortion in the engineering and economic indicators that characterize the efficiency of nuclear power plants, and to differences in the results of evaluating their efficiency in comparison with other methods for producing energy. Calculating costs for nuclear fuel is discussed and it is concluded that despite a series of specific features of nuclear fuel from a theoretical standpoint we must consider the fuel load of a reactor as long-term working capital of a nuclear power plant. Dividing up the complex costs into types of production of two-purpose nuclear power plants should be carried out with consideration of the consumer cost of secondary nuclear fuel, i.e., with consideration of both the efficiency of subsequent utilization for production of electrical energy and the cost levels associated with this. A reduction in long-term working capital of nuclear plants is advisable not by accelerated recording of the portion of the cost for nuclear fuel determined by the level of its residual cost, but on the basis of a corresponding organization of calculations within branches for utilization of nuclear fuel that consider the efficiency of its utilization both at the nuclear power plant and in the fuel cycle of the nuclear energy association as a whole

  14. Process for producing oxidic sintered fuel pellets

    International Nuclear Information System (INIS)

    Oxidic nuclear fuel sintered compacts are produced from compacts of uranium oxide powder, from a mixture of uranium oxide powder and plutonium oxide powder or from uranium-plutonium oxide mixed crystal powder by a thermal treatment at a sintering temperature in the range of 10000C to 14000C in an oxidizing and then reducing gas atmosphere. For facilitating the setting up of concentrations of evenly distributed coarse grain in the microstructure of the nuclear fuel sintered compact, the starting powder and/or compacts are preroasted below sintering temperature by developing U4O9 crystalline phase or (U,Pu)4O9 crystalline phase and then, by preserving this crystalline phase, cooled down to the starting temperature. Proceeding from this starting temperature the compacts are heated to sintering temperature by preserving the U4O9 crystalline phase or (U,Pu)4O9 crystalline phase. (orig.)

  15. Safety analysis of IFR fuel processing in the Argonne National Laboratory Fuel Cycle Facility

    International Nuclear Information System (INIS)

    The Integral Fast Reactor (IFR) concept developed by Argonne National Laboratory (ANL) includes on-site processing and recycling of discharged core and blanket fuel materials. The process is being demonstrated in the Fuel Cycle Facility (FCF) at ANL's Idaho site. This paper describes the safety analyses that were performed in support of the FCF program; the resulting safety analysis report was the vehicle used to secure authorization to operate the facility and carry out the program, which is now under way. This work also provided some insights into safety-related issues of a commercial IFR fuel processing facility. These are also discussed

  16. Purex co-processing of spent LWR fuels: comparative fuel cycle cost analyses

    International Nuclear Information System (INIS)

    Nuclear fuel cycle costs for purex reprocessing and co-processing cycles are to be evaluated, by calculating unit costs of recovered, accordingly treated and fabricated products and then comparing those to the unit cost of fresh uranium fuel ready to be loaded into a typical LWR on the once-through cycle

  17. Fuel thermal performance analysis using thermal models of dry-processed fuel

    International Nuclear Information System (INIS)

    Recently, the performance analyses of a dry-processed fuel were carried out through the irradiation test in HANARO and post irradiation examination. Addition to these tests, the computer code for fuel performance analysis was required to be developed. In order to do that, FEMAXI-IV code was modified with thermal conductivity model so that it can be applied to fuel performance analysis of the dry-processed fuel. And the safety reports for the irradiation test in HANARO were prepared with using its results. But, FEMAXI-V has been recently developed with the update of numerical scheme and high burnup application and published in open literature. Hence, FEMAXI-V code, which has been applied to PWR and BWR fuel rod, was selected for the establishment of computer code system for dry-processed fuel performance analysis modifying the program modules related to the thermal properties, especially thermal conductivity and thermal expansion. The thermal characteristics of UO2 fuel and dry-processed fuel were compared by the calculation results obtained from the modified FEMAXI-V code. Also, these results will be utilized to compare with the irradiation and post-irradiation test data which were obtained from the 3th and the 4th irradiations of the mini-elements in HANARO

  18. 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)

  19. 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...... 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.......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...

  20. Idaho Chemical Processing Plant product denitrator upgrade

    International Nuclear Information System (INIS)

    The uranium product denitrator at the Idaho Chemical Processing Plant has had serious operating problems since 1970, including inadequate contamintion control, fluidized bed caking, frequent bed heater failure, product overflow plugging, and poor feed control. These problems were minimized through selective redesign and upgrade of the process equipment as part of a process upgrade program completed in March 1981. Following startup and testing of the rebuilt product denitrator, 1044 kg of enriched uranium was processed in three weeks while demonstrating greater reliability, ease of operation, and improved contamination control. To maximize personnel safety in the future, the denitrator vessel should be made critically safe by geometry and process instrumentation isolated from the process for semi-remote operation

  1. Characteristics and performance of the plant for refabrication of vibrocompacted fuel elements for the BOR-60 reactor

    International Nuclear Information System (INIS)

    The paper deals with the characterization of an automated pilot plant for the refabrication of fuel elements for the Soviet experimental BOR-60 fast breeder reactor. In addition, it describes the results, experience, and problems encountered in respect of the technological process of fuel element manufacture and quality assurance. The electrodynamic vibration procedure for densification of the uranium-plutonium mixed oxide is given special attention. (orig.)

  2. 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

  3. 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)

  4. Fuel cost analysis of CANDU-PHWR Wolsung Nuclear Power Plant unit 1

    International Nuclear Information System (INIS)

    Being based on the Segal method, calculation was carried out for the natural uranium nuclear fuel cost with Zircaloy-4 cladding having design parameters of Wolsung Nuclear Power Plant, CANDU-PHWR (Unit 1), currently under construction in Korea aiming at its completion in 1982. An attempt was also made for the sensitivity analysis of each fuel component; i.e., depreciation of fuel manufacturing plant caused by its life time, its load factor, production scale expansion of plant facilities, variations of construction and operating costs of fuel manufacturing plant, fluctuation of interest rates, extent of uranium ore price increases and effect of learning factor. (author)

  5. Fuel-element inspection stand in the cooling pond of an atomic power plant

    International Nuclear Information System (INIS)

    A fuel-element inspection stand has been built in the cooling pool of the second power unit at the Ignalina Atomic Power Plant for the purpose of monitoring fuel elements unloaded from the reactor and for performing research involving the acquisition and analysis of statistically significant information concerning the reliability and efficiency of fuel elements and fuel bundles. The uses and specifications of the fuel-element inspection stand are given in this paper. 1 ref., 4 figs

  6. 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.

  7. Optimal process design for thermochemical production of fuels from biomass

    OpenAIRE

    Gassner, Martin; Maréchal, François

    2008-01-01

    Transport applications are a major global source of greenhouse gas emissions and the production of fuels that are renewable and neutral in CO2 is an important issue in chemical process research and development. Contrary to the biological routes that produce bioethanol and -diesel on industrial scale through fermentation or esterification, 2nd generation biofuels obtained through thermochemical processing of lignocellulosic and waste biomass by means of gasification and fuel reforming are expe...

  8. RENUW - A dry halide process for nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    The RENUW Dry Halide Process for reprocessing nuclear fuel will be described. Analysis has shown that the RENUW process will significantly reduce the waste produces from processing irradiated nuclear fuel compared to aqueous processes. Waste reduction is accomplished by recovering the zirconium and uranium for reuse. The RENUW process uses hot chlorine gas to chlorinate the feed; separation is accomplished by exploiting the large differences between the relative volatilities of the fission products and the uranium and zirconium. The flow sheet is quite simple and uses readily commercial technologies

  9. RENUW - A dry halide process for nuclear fuel reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Lahoda, E.J.; McLaughlin, D.F.; Peterson, S.H.; Burgman, H.A. [Westinghouse Electric Corporation, Pittsburgh, PA (United States); Behrens, R. Jr.; Johnston, S.C.; Vosen, S.R. [Sandia National Laboratories, Livermore, CA (United States); Christian, J.D. [Westinghouse Idaho Nuclear Company, Idaho Falls, ID (United States)

    1993-12-31

    The RENUW Dry Halide Process for reprocessing nuclear fuel will be described. Analysis has shown that the RENUW process will significantly reduce the waste produces from processing irradiated nuclear fuel compared to aqueous processes. Waste reduction is accomplished by recovering the zirconium and uranium for reuse. The RENUW process uses hot chlorine gas to chlorinate the feed; separation is accomplished by exploiting the large differences between the relative volatilities of the fission products and the uranium and zirconium. The flow sheet is quite simple and uses readily commercial technologies.

  10. Nuclear liability and research reactor fuel. A plant supplier's view

    International Nuclear Information System (INIS)

    Contracts on Research Reactors are normally entered into by the owner and - very often - later user and the supplier of such plants. They are not concluded by the fuel supplier, except fuel supplier and plant supplier are identical. Thus, the fuel supplier mostly has no direct influence into the contract negotiations and the clauses which are eventually agreed upon between the parties. So has any other subcontractor for any other system or component. Any such subsupplier can and will negotiate a subsidiary supply contract (subcontract) with the supplier of the plant. The supplier drafts the related clauses so as to pass on to the subsupplier as many risks out of his contracts as possible. The subsupplier, on the other hand, tries to protect himself, tries to limit the risks he takes over, e.g. to the worth of his subcontract maximum. A critical issue in such negotiations is those concerning the risks the supplier had to accept and the subsupplier, although he may be responsible later for the risk changing to reality; i.e. the occurrence of a loss, cannot be hold liable for in full because the subcontract limits his liability, e.g. to the subcontract value or a certain delay penalty. A typical example for this conflict are delays of the entire project caused by one subsupplier. A very specific case in this context is the so-called nuclear liability. Nuclear liability means being hold responsible for the consequences or damages originating from a nuclear event in the plant. Those consequences or damages may be suffered by third parties, which are neither the owner/operator nor the supplier and result in a liability to such party (third party liability). Several of the aspects below may be related to the nuclear liability issue: The supplier often has its registered office not in the country where the plant is; The supplier may have far bigger assets than the owner/operator. The legal system of the supplier's country may be more favourable for enforcing claims of

  11. 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

  12. 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)

  13. Evaluation of 450-MWe BGL GCC power plants fueled with Pittsburgh No. 8 coal

    International Nuclear Information System (INIS)

    In this study, a conceptual design and cost estimate were developed for a nominal 450 MW integrated gasification combined cycle plant using the British Gas/Lurgi slagging gasification process. The present study is a design update of a previous study (EPRI Report AP-6011). The major design improvements incorporated include use of the latest GE 7F gas turbine rating, integrating the air separation plant with gas turbine, use of fuel gas saturation for NOx control, use of treated gasifier waste water as makeup water for the fuel gas saturation, and several process changes in the acid gas removal and sulfur recovery areas. Alternate design options for feeding the excess coal fines to the gasifier, treating the gasifier waste water, and the use of conventional air separation without integration with gas turbine were evaluated. The design improvements incorporated were found to increase significantly the overall plant efficiency and reduce the cost reported in the previous study. The various design options evaluated were found to have significant impacts on the plant efficiency but negligible impacts on the cost of electricity

  14. Strategy for decommissioning of the glove-boxes in the Belgonucleaire Dessel MOX fuel fabrication plant

    International Nuclear Information System (INIS)

    Available in abstract form only. Full text of publication follows: BELGONUCLEAIRE has been operating the Dessel plant from the mid-80's at industrial scale. In this period, over 35 metric tons of plutonium (HM) was processed into almost 100 reloads of MOX fuel for commercial West-European Light Water Reactors. In late 2005, the decision was made to stop the production because of the shortage of MOX fuel market remaining accessible to BELGONUCLEAIRE after the successive capacity increases of the MELOX plant (France) and the commissioning of the SMP plant (UK). As a significant part of the decommissioning project of this Dessel plant, about 170 medium-sized glove-boxes are planned for dismantling. In this paper, after having reviewed the different specifications of ±-contaminated waste in Belgium, the authors introduce the different options considered for cleaning, size reduction and packaging of the glove-boxes, and the main decision criteria (process, α-containment, mechanization and radiation protection, safety aspects, generation of secondary waste, etc) are analyzed. The selected strategy consists in using cold cutting techniques and manual operation in shielded disposable glove-tents, and packaging α-waste in 200-liter drums for off-site conditioning and intermediate disposal. (authors)

  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. 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

  17. Production of nuclear ceramic fuel for nuclear power plants at 'Ulba metallurgical plant' OSC

    International Nuclear Information System (INIS)

    The paper describes the flow-sheet of production of uranium dioxide powders and nuclear ceramic fuel pellets of them existing at the facility. 'UMP' OSC applies ADU extraction process of UO2 powders production. An indisputable success of the process is the possibility of use of the wide range of raw materials. Uranium hexafluoride, uranium oxides, uranium metal, uranium tetrafluoride, uranyl salts, uranium ore concentrates, all possible types of uranium-containing materials the processing of which by routine methods is difficult (ashes, scraps, etc.) are used as the raw materials. In addition, a reprocessed nuclear fuel can be used for fuel production. The quality of uranium dioxide powder produced does not depend on the type of uranium raw material used. High selectivity of extraction refining makes possible to obtain material with rather low impurities content that meets practically all specifications for uranium dioxide known to us. Ceramic and process features of uranium dioxide powders, namely, specific surface, bulk density, grain size and sinterability make possible to produce nuclear ceramic fuel with specified features. Quality of uranium dioxide powders produced by 'UMP' OSC was highly rated by General Electric company that is one of the leading companies from fuel manufactures in the USA market . It has certified 'UMP' OSC as its supplier. Currently, our company makes great efforts on establishing production of uranium dioxide powders with natural isotopes content for production of fuel for CANDU reactors. Trial lots of such powders are under tests at some companies manufacturing fuel for this type reactors in Canada, USA and Corea

  18. 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

  19. Radiometry of radiochemical processing plant box

    International Nuclear Information System (INIS)

    Radiometry method is used to detect shielding losses in the newly designed processing plants, to control the personnel exposure handling the radioactivity. The acceptable radiation level in occupied area at the working place, as per AERB regulatory guidelines is 1 μSv/h (0.1mR/h). Hence a stringent control on the shielding is mandatory. The shielding integrity was evaluated using a sealed source of 900 mCi 60Co (1.17 MeV and 1.33 MeV g photons of 100% abundance), by radiometry at -the newly designed 100 mm lead shielded SS 6 cell -plant box used for processing 5 -10Ci of 32P, 51Cr,153Sm, 177Lu, 166Ho etc. The radiometry source introduced into plant box through the loading chamber in H2 can (Dia. 25 mm and length 40 mm) was loaded in the plant. MS stand was fabricated and used for housing the radiometry source at different elevations (300, 600 and 900 mm). The stand was kept in the center of the plant at different locations viz., 845 mm, 1445 mm and 2045 mm distance from one side. The transmitted radiation field was mapped using radiation survey meter at marked grid segments of 100 mm x 100 mm in all sides and top of the plant box. The transmitted radiation field in all sides and top of the plant box were mapped using radiation survey meter. At certain grids the radiation levels indicated shielding losses, all such cavities were filled up, the gap was plugged and the radiometry dose mapping was repeated. Due to this rectification, radiation level at most of the places was reduced and the results showed that the shielding had improved. There was higher transmitted radiation field on the plant during opening of sliding doors. Whenever doors are opened during some work, alarm of audio alarm system indicates door opening condition. Installation of the same had been made mandatory to control occupational exposure. The radiation level may not exceed the limit of 1 μ iSv/h for the permanent occupancy of lab personnel at the working place

  20. 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

  1. 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...

  2. 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

  3. 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)

  4. The nuclear power plant aging management process

    International Nuclear Information System (INIS)

    Aging management is not an end product rather it is a process that can be used by utilities to collect pertinent data; to assess the life of systems, structures, and components; to develop and assess alternative aging management strategies; and to implement strategies that provide the maximum economic and safety benefits at the least cost. Aging management is a process for: determining current component condition through data collection techniques such as D and M, inservice inspection, trending, and materials research; evaluating data obtained using various life assessment methods; calculating the end of functional life from estimates of functional degradation over time; identifying and implementing actions to maintain or improve plant safety and economics. The time-dependent rate of change in the condition of equipment is the governing parameter in the life assessment process; it has to be determined by aging management techniques as a part of the integrated aging management process. The aging management process provides benefits to a utility and its customers by maintaining or improving plant performance and safety. A systematic and well-planned program is required to: determine critical systems, structures, and components and their priority ranking; predict end of functional life for critical components; determine adequacy of operating and maintenance procedures and practices; recommend necessary improvements and implement them during scheduled refueling outages; provide documented justification for optimal set of performance improvement activities A number of tools and techniques that add value in the aging management process have been or are being developed. These tools offer economic and safety benefits to plant owners

  5. 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

  6. 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

  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. Production process and quality control for the HTTR fuel

    International Nuclear Information System (INIS)

    Development of the production and inspection technology for High Temperature Engineering Test Reactor (HTTR) fuel has been carried out by cooperative work between Japan Atomic Energy Research Institute (JAERI) and Nuclear Fuel Industries, Ltd (NFI). The performance and the quality level of the developed fuel are well established to meet the design requirements of the HTTR. For the commercial scale production of the fuel, statistical quality control and quality assurance must be carefully considered in order to assure the safety of the HTTR. It is also important to produce the fuel under well controlled process condition. To meet these requirements in the production of the HTTR fuel, a new production process and quality control system is to be introduced in the new facilities. The main feature of the system is a computer integrated control system. Process control data at each production stage of products and semi-products are all gathered by terminal computers and processed by a host computer. The processed information is effectively used for the production, quality and accountancy control. With the aid of this system, all the products will be easily traceable from starting materials to final stages and the statistical evaluation of the quality of products becomes more reliable. (author). 8 figs

  9. 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

  10. 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

  11. Fuel-oil cogeneration plant for textile Industry. Central de cogeneracion a fueloleo para industria textil

    Energy Technology Data Exchange (ETDEWEB)

    Navarro Larrauri, M.; Diez Hernandez, J.; Villasante Diaz, A. (IDOM, Ingenieria y Consultoria, S.A. (Spain))

    1993-10-01

    Aznar S.A. is a textile factory especially sensitive to electricity distribution failures. They produce the subsequent shut down at the manufacturing process and several hours of maintenance tasks. A cogeneration plant has been installed to provide electricity and thermal energy to the process. Since the location is far from Natural Gas pipelines the system includes fuel-oil as energy source. Annual electricity production will be 23.300 MWh and 6.400 MWh of them will be exported into the grid. Fuel-oil consumption at the heat exchanger is reduced by 47%, but the whole factory consumption increases a 247% due to the high consumption of the engine. This increase is compensated by revenues from selling electricity and electricity savings. These facts, together with maintenance cost saving leads to a pay back time of 3.3. years. (Author)

  12. 10 CFR Appendix B to Part 50 - Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants B Appendix B to Part 50 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Pt. 50, App. B Appendix B to Part 50—Quality Assurance Criteria for Nuclear Power Plants and...

  13. 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)

  14. 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

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

    International Nuclear Information System (INIS)

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

  16. Pressurized water reactor fuel performance problems connected with fuel cladding corrosion processes

    International Nuclear Information System (INIS)

    Generally, Pressurized Water Reactor (WWER, PWR) Fuel Element Performance is connected with fuel cladding corrosion and crud deposition processes. By transient to extended fuel cycles in nuclear power reactors, aiming to achieve higher burnup and better fuel utilization, the role of these processes increases significantly. This evolution modifies the chemical and electrochemical conditions in the reactor primary system, including change of fuel claddings' environment. The higher duty cores are always attended with increased boiling (sub-cooled nucleate boiling) mainly on the feed fuel assemblies. This boiling process on fuel cladding surfaces can cause different consequences on fuel element cladding's environment characteristics. In the case of boiling at the cladding surfaces without or with some cover of corrosion product deposition, the behavior of gases dissolved in water phase is strongly influenced by the vapor generation. The increase of vapor partial pressure will reduce the partial pressures of dissolved gases and will cause their stripping out. By these circumstances the concentrations of dissolved gases in cladding wall water layer can dramatically decrease, including also the case by which all dissolved gases to be stripped out. On the other hand it is known that the hydrogen is added to primary coolant in order to avoid the production of oxidants by radiolysis of water. It is clear that if boiling strips out dissolved hydrogen, the creation of oxidizing conditions at the cladding surfaces will be favored. In this case the local production of oxidants will be a result from local processes of water radiolysis, by which not only both oxygen (O2) and hydrogen (H2) but also hydrogen peroxide (H2O2) will be produced. While these hydrogen and oxygen will be stripped out preferentially by boiling, the bigger part of hydrogen peroxide will remain in wall water phase and will act as the most important factor for creation of oxidizing conditions in fuel cladding

  17. 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

  18. Nuclear reactor fuel cycle technology with pyroelectrochemical processes

    International Nuclear Information System (INIS)

    A group of dry technologies and processes of vibro-packing granulated fuel in combination with unique properties of vibro-packed FEs make it possible to implement a new comprehensive approach to the fuel cycle with plutonium fuel. Testing of a big number of FEs with vibro-packed U-Pu oxide fuel in the BOR-60 reactor, successful testing of experimental FSAs in the BN-600 rector, reliable operation of the experimental and research complex facilities allow to make the conclusion about a real possibility to develop a safe, economically beneficial U-Pu fuel cycle based on the technologies enumerated above and to use both reactor-grade and weapon-grade plutonium in nuclear reactors with a reliable control and accounting system

  19. 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)

  20. Safety demonstration tests of solvent fire accidents in a fuel reprocessing plant

    International Nuclear Information System (INIS)

    Demonstration tests to evaluate the safety of air-ventilation system for hypothetical solvent fire in a cell as DBA in an extraction process of nuclear fuel reprocessing plant were carried out by a large-scale fire and filter facility (FFF) in JAERI under the auspices of the Science and Technology Agency of Japan. Demonstration test data were obtained by focusing on fire behavior during solvent burning in the cell, generation of smoke containing simulant fission products from flame, transport and deposition of smoke in ducts, confinement of radioactive materials in the ventilation system and integrity of HEPA filters by using a fire and filter facility simulating a ventilation system of reference reprocessing plant in Japan. The results of the test in the present report were ready for verification of computer codes which evaluate the safety of a reprocessing plant in solvent fire accidents. (author)

  1. 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.

  2. Synthetic-fuel plants: potential tumor risks to public health.

    Science.gov (United States)

    Moskowitz, P D; Morris, S C; Fischer, H; Thode, H C; Hamilton, L D

    1985-09-01

    This article quantifies potential public health risks from tumor-producing pollutants emitted from two synthetic-fuel plants (direct liquefaction--Exxon Donor Solvent: and indirect liquefaction--Lurgi Fischer-Tropsch) located at a representative site in the eastern United States. In these analyses gaseous and aqueous waste streams were characterized; exposures via inhalation, terrestrial and aquatic food chains, and drinking water supplies were modeled. Analysis suggested that emissions of "polycyclic aromatic hydrocarbons," "aromatic amines," "neutral N, O, S heterocyclics," "nitriles," and "other trace elements" pose the largest quantifiable risks to public health. Data and analysis for these pollutant categories should be refined to more accurately match compound-specific estimated exposure levels with tumorigenic potency estimates. Before these results are used for regulatory purposes, more detailed analysis for selected pollutant classes are needed, and more sophisticated aquatic exposure models must be developed. Also, differences in geographic scales among the environmental transport models used need to be rectified. PMID:3843682

  3. Simulation of spent fuel reprocessing processes: Realizations and prospects

    International Nuclear Information System (INIS)

    The separation of uranium and plutonium in the Purex process is very complex and for the extension of reprocessing plants optimization of the process requires mathematical modelling. The development of this model is reviewed

  4. 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.

  5. 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.

  6. IAEA expert review mission completes assessment of fuel cleaning incident at Paks Nuclear Power Plant

    International Nuclear Information System (INIS)

    Full text: The IAEA today completed its expert review mission to investigate the 10 April fuel cleaning incident at the Paks nuclear power plant in Hungary. The mission was requested by the Hungarian Government to provide an independent assessment of the causes and actions taken by the plant and Hungarian authorities. The team was composed of nuclear and radiation experts from the IAEA, Austria, Canada, Finland, Slovakia, the United Kingdom and the United States. In a press conference, team leader Miroslav Lipar highlighted the team's findings in five areas: On management, the team concluded that the Hungarian Atomic Energy Authority and Paks are committed to improving the safety of the plant. They noted that as a result of steam generator decontamination in previous years, deposits became attached to the fuel assemblies. A decision was made to clean the fuel and contract an outside company to develop and operate a fuel cleaning process. The team found that the design and operation of the fuel cleaning tank and system was not accomplished in the manner prescribed by the IAEA Safety Standards. Neither the Hungarian Atomic Energy Authority nor Paks used conservative decision-making in their safety assessments for this unproven fuel cleaning system. The team determined that there was an over-reliance on the contractor that had been selected for the design, management and operation of the fuel cleaning system. Time pressure related to a prescribed fuel outage schedule, combined with confidence generated by previous successful fuel cleaning operations, contributed to a weak assessment of a new design and operation, which involved fuel directly removed from the reactor following a planned shutdown. On regulatory oversight, the IAEA team concluded that the Hungarian Atomic Energy Authority underestimated the safety significance of the proposed designs for the fuel cleaning system, which resulted in a less than rigorous review and assessment than should have been necessary

  7. Remote repair robots for dissolvers in nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    In nuclear facilities, for the purpose of the reduction of radiation exposure of workers, the shortening of working time and the improvement of capacity ratio of the facilities, the technical development of various devices for remote maintenance and inspection has been advanced so far. This time, an occasion came to inspect and repair the pinhole defects occurred in spent fuel dissolving tanks in the reprocessing plant of Tokai Establishment, Power Reactor and Nuclear Fuel Development Corp. However, since the radiation environmental condition and the restricting condition due to the object of repair were extremely severe, it was impossible to cope with them using conventional robot techniques. Consequently, a repair robot withstanding high level radiation has been developed anew, which can work by totally remote operation in the space of about 270 mm inside diameter and about 6 m length. The repair robot comprises a periscope reflecting mirror system, a combined underwater and atmospheric use television, a grinder, a welder, a liquid penetrant tester and an ultrasonic flaw detector. The key points of the development were the parts withstanding high level radiation and the selection of materials, to make the mechanism small size and the realization of totally remote operation. (Kako, I.)

  8. Spent fuel storage in the storage pools of nuclear power plants

    International Nuclear Information System (INIS)

    The pools for storing spent fuel elements in the reactor buildings of nuclear power plants allow the afterheat of fuel unloaded from the reactor for good to decay to a level at which the fuel then can be shipped in special casks. Consequently, these storage pools were designed in Germany in the past so as to accommodate the volume of fuel elements unloaded over approximately two to ten years of operation, depending on the power plant in question before the fuel had to be shipped off. As a consequence of the omnibus law amending the German Atomic Energy Act, which permits direct disposal of spent fuel elements as a legally equivalent alternative to reprocessing, the operators of nuclear power plants have had an opportunity to reassess the nuclear fuel cycle. If the direct disposal option is to be used, this necessitates long-term interim storage of the fuel. This can be achieved, on the one hand, in the storage pools of nuclear power plants and, on the other hand, in separate fuel stores in which the fuel elements can be kept in combined shipping and storage casks. If such relatively sophisticated storage casks are to be loaded economically in nuclear power plants, the afterheat generated by the fuel elements should have decayed as far as possible, as heat removal and radiation dose rate on the surface of the cask are limiting factors. There is yet another aspect, namely the trends towards higher discharge burnups and towards using nuclear recycle fuel. Both measures increase the decay heat produced by spent fuel. In countries where long-term interium storage has been practiced for a long time already (e.g. Spain, Korea), Siemens in the past few years equipped the storage pools of nuclear power plants with compact fuel stores which make optimum use of the storage pools. These innovative two-region stores are being used already in ten of these nuclear power plants. (orig.)

  9. 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.

  10. 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

  11. 76 FR 53970 - Carolina Power & Light; Brunswick Steam Electric Plant, Units 1 and 2; Independent Spent Fuel...

    Science.gov (United States)

    2011-08-30

    ... accordance with the NRC E-Filing rule (72 FR 49139, August 28, 2007). The E-Filing process requires... Licenses Nos. DPR-71 and DPR-62 for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2, including the BSEP Independent Spent Fuel Storage Installation, currently held by Carolina Power & Light Company,...

  12. Analysis of the ATR fuel element swaging process

    International Nuclear Information System (INIS)

    This report documents a detailed evaluation of the swaging process used to connect fuel plates to side plates in Advanced Test Reactor (ATR) fuel elements. The swaging is a mechanical process that begins with fitting a fuel plate into grooves in the side plates. Once a fuel plate is positioned, a lip on each of two side plate grooves is pressed into the fuel plate using swaging wheels to form the joints. Each connection must have a specified strength (measured in terms, of a pullout force capacity) to assure that these joints do not fail during reactor operation. The purpose of this study is to analyze the swaging process and associated procedural controls, and to provide recommendations to assure that the manufacturing process produces swaged connections that meet the minimum strength requirement. The current fuel element manufacturer, Babcock and Wilcox (B ampersand W) of Lynchburg, Virginia, follows established procedures that include quality inspections and process controls in swaging these connections. The procedures have been approved by Lockheed Martin Idaho Technologies and are designed to assure repeatability of the process and structural integrity of each joint. Prior to July 1994, ATR fuel elements were placed in the Hydraulic Test Facility (HTF) at the Idaho National Engineering Laboratory (AGNAIL), Test Reactor Area (TRA) for application of Boehmite (an aluminum oxide) film and for checking structural integrity before placement of the elements into the ATR. The results presented in this report demonstrate that the pullout strength of the swaged connections is assured by the current manufacturing process (with several recommended enhancements) without the need for- testing each element in the HTF

  13. 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)

  14. 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.)

  15. 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...

  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. The economics of nuclear fuel reprocessing: a case study of the Windscale Thorp plant

    International Nuclear Information System (INIS)

    The economics of the THORP fuel reprocessing plant under construction at Windscale in Cumbria are discussed, comparing the costs of reprocessing with disposal of oxide fuels. The possibility of a fast reactor programme in the UK is then introduced into the discussion and the economics of using reprocessed plutonium as the fuel considered. (U.K.)

  18. 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

  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. Automatic failure identification of the nuclear power plant pellet fuel

    International Nuclear Information System (INIS)

    This paper proposed the development of an automatic technique for evaluating defects to help in the stage of fabrication of fuel elements. Was produced an intelligent image analysis for automatic recognition of defects in uranium pellets. Therefore, an Artificial Neural Network (ANN) was trained using segments of histograms of pellets, containing examples of both normal (no fault) and of defectives pellets (with major defects normally found). The images of the pellets were segmented into 11 shares. Histograms were made of these segments and trained the ANN. Besides automating the process, the system was able to obtain this classification accuracy of 98.33%. Although this percentage represents a significant advance ever in the quality control process, the use of more advanced techniques of photography and lighting will reduce it to insignificant levels with low cost. Technologically, the method developed, should it ever be implemented, will add substantial value in terms of process quality control and production outages in relation to domestic manufacturing of nuclear fuel. (author)

  1. TAMARA - an uranium extraction pilot plant for demonstration of computerized process-control in reprocessing. Pt. 1

    International Nuclear Information System (INIS)

    An uranium extraction pilot plant with in-line instrumentation is described. The plant was constructed in the course of the development and demonstration of a computer-based control of nuclear fuel reprocessing processes and is connected with the process computer system CALAS. The results gained until now are presented and discussed, and the future work suggested is mentioned. (orig.)

  2. 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.

  3. Software system for fuel management at Embalse nuclear power plant

    International Nuclear Information System (INIS)

    For accurate tracking of flux and power distribution in a CANDU reactor, the information needed is evaluated from a neutronic code calculation adjusted with experimental values, making use of in-core vanadium detectors at 102 locations together with auxiliary programs.The basic data that feed these programs come from the geometric and neutronic features and the actual instantaneous operating parameters. The system that provides all this information should be designed to meet with software quality assurance requirements. A software system was implemented at Embalse Nuclear Power Plant and it is in operation since 1998 after two year testing. This PC version replaced the former system introducing new concepts in its architecture. The neutronic code runs by procedures implemented in a language of macro instructions, so only new data are loaded for two consecutive instantaneous cases avoiding unnecessary data repetition. After each step, all results of neutronic calculation are stored in master files. Afterwards other auxiliary programs retrieve basic data for further evaluation and files are sorted in different thematic folders using a specific codification, for reevaluating further calculations over any specific case. The whole system can be installed in any PC. The package is provided with its general and particular support documentation and procedures for each program.The main purpose of the system is to track fuel and power distribution calculated after a certain period where fuelling operation were done in between. The main code, PUMA, evaluates in a 3-D, two-group scheme using finite difference diffusion theory. After neutronic calculation is performed, other programs allow to retrieve assorted information valid for fuel strategy and to build the fuelling operation list to be sent to the operation shifts. This program also permits to evaluate the accuracy of PUMA by doing comparisons with experimental values. Along with these features, some other system

  4. 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.

  5. 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.

  6. 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

  7. 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)

  8. Results of fuel management at Embalse nuclear power plant. Analysis of performance at other plants

    International Nuclear Information System (INIS)

    The operating experience of fuel management at the Embalse nuclear power plant from new core to the present situation (approximately 937 days at full power) is described. The average core burnup is about 4000 MW d/t U and the monthly averaged discharge burnup about 7800 MW d/t U. The neutron flux distribution is calculated by means of program PUMA-C, which is periodically checked by comparison between calculated and measured values of 102 vanadium detectors. A comparison of the performance of other reactors type CANDU 600 (Point Lepreau, Gentilly 2, Wolsung) from the point of view of fuel strategy is also presented. The data to perform the comparison were obtained by means of the CANDU system of information exchange between users (COG). (Author)

  9. 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.

  10. 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

  11. 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)

  12. Ageing processes in solid fuels; Verwitterungsverluste von festen Brennstoffen

    Energy Technology Data Exchange (ETDEWEB)

    Postrzednik, S.

    1997-12-31

    Low-temperature processes on the coal surface are discussed on the basis of influencing parameters determined by calculation and experimentally, and a method is developed for practical analysis of these processes, with particular regard to low-temperature oxidation of Polish bulk coal. The method is based on the data of technical analyses (moisture, ash content, calorific value) of solid fuels. (orig.)

  13. 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

  14. 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)

  15. THE EFFECTS OF UTILIZING GEOTHERMAL ENERGY IN THERMAL POWER PLANTS ON THE PLANT PERFORMANCE AND FUEL SAVING

    Directory of Open Access Journals (Sweden)

    Ahmet DAĞDAŞ

    2006-02-01

    Full Text Available The share of electricity production from thermal power plants for Turkey is about 61 %. Since the fossil fuels are rapidly consumed, the concept of fossil fuel saving is very important for humanity. In this paper, the effects of boiler feed water preheating by means of geothermal brine on overall performance and fossil fuel savings in thermal power plants are examined. According to the performed analysis, power plant thermal efficiency could be increased of 2-4 % via geothermal preheating. In this analysis, a hypothetical thermal power plant is considered and its performance is evaluated. According to analysis, 1 million US$ in fossil fuel savings and 4.1 % increase in thermal efficiency could be achieved by the use of geothermal preheating.

  16. 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.

  17. 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.

  18. The implications of plant design on the life-time costs for nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Utilising the experience gained during many years of design and project management of nuclear plant, BNFL is now approaching the final stages of the construction and commissioning of the Sellafield MOX Plant (SMP) in the UK. The paper uses the SMP project to highlight the benefits of these experiences, in particular addressing the implications of the approach to plant design on life time costs. In addition to providing BNFL with a state of the art, commercial scale MOX fuel fabrication facility, the construction of this 120 tHM/yr facility, which is currently in the advanced stages of commissioning, represents a significant demonstration of the design and project management skills of BNFL Engineering Ltd. As well as meeting the main process requirements, the plant design incorporates the highest standards of safety, together with input from the future plant operators and potential customers. As befits a commercial scale plutonium handling facility, SMP also incorporates material accountancy and security provisions that will meet all international requirements. Design, construction and commissioning of this complex and highly automated plant, has benefited from a totally integrated approach to design and documentation that considers not only project implementation but also overall lifetime costs. In addition, project management techniques, developed over many years of major project construction at Sellafield, have been utilised in order to ensure successful project implementation against a background of significant technical challenge and 'fast track' timescales. (author)

  19. 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

  20. 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

  1. 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)

  2. 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

  3. 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...

  4. 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)

  5. Energy analysis of a trigeneration plant based on solid oxide fuel cell and organic Rankine cycle

    Energy Technology Data Exchange (ETDEWEB)

    Al-Sulaiman, F.A. [Mechanical and Aerospace Engineering Dept., Carleton Univ., Ottawa, Ontario (Canada)], E-mail: falsulai@connect.carleton.ca; Dincer, I. [Faculty of Engineering and Applied Science, Univ. of Ontario Inst. of Technology, Oshawa, Ontario (Canada)], E-mail: Ibrahim.Dincer@uoit.ca; Hamdullahpur, F. [Mechanical and Aerospace Engineering Dept., Carleton Univ., Ottawa, Ontario (Canada)], E-mail: feridun_hamdullahpur@carleton.ca

    2009-07-01

    In this paper, energy analysis of a trigeneration plant based on Solid Oxide Fuel cell (SOFC) and organic Rankine cycle (ORC) is carried out. The physical and thermodynamic elements of the plant include a SOFC, ORC, a heating process and a single-effect absorption chiller. The waste heat from the SOFC is used as an input heat to the ORC. In turn, the waste heat from the ORC is used to heat the inlet water, and to provide the heat needed for the single-effect absorption chiller. The results obtained from this study show that the highest cycle efficiency that can be attained under the proposed scheme is 48% and the highest SOFC efficiency is 43%. Furthermore, it is found that the highest net work rate is 435 kW and the highest SOFC-AC work rate is 337 kW. At a current density higher than 0.87 A/cm{sup 2}, the SOFC and cycle efficiencies drop abruptly because of the sharp increase in the voltage losses of the SOFC. At a current density of 0.75 A/cm{sup 2}, the highest SOFC efficiency of 41% is obtained at the inlet fuel cell temperature of 890 K. The change in the inlet pressure of the turbine has insignificant effect on the efficiencies of the ORC and overall cycle. The study shows the effect of both the current density and the inlet fuel cell temperature on the cell voltage and voltage loss. (author)

  6. Energy analysis of a trigeneration plant based on solid oxide fuel cell and organic Rankine cycle

    International Nuclear Information System (INIS)

    In this paper, energy analysis of a trigeneration plant based on Solid Oxide Fuel cell (SOFC) and organic Rankine cycle (ORC) is carried out. The physical and thermodynamic elements of the plant include a SOFC, ORC, a heating process and a single-effect absorption chiller. The waste heat from the SOFC is used as an input heat to the ORC. In turn, the waste heat from the ORC is used to heat the inlet water, and to provide the heat needed for the single-effect absorption chiller. The results obtained from this study show that the highest cycle efficiency that can be attained under the proposed scheme is 48% and the highest SOFC efficiency is 43%. Furthermore, it is found that the highest net work rate is 435 kW and the highest SOFC-AC work rate is 337 kW. At a current density higher than 0.87 A/cm2, the SOFC and cycle efficiencies drop abruptly because of the sharp increase in the voltage losses of the SOFC. At a current density of 0.75 A/cm2, the highest SOFC efficiency of 41% is obtained at the inlet fuel cell temperature of 890 K. The change in the inlet pressure of the turbine has insignificant effect on the efficiencies of the ORC and overall cycle. The study shows the effect of both the current density and the inlet fuel cell temperature on the cell voltage and voltage loss. (author)

  7. Low and medium level liquid waste processing at the new La Hague reprocessing plant

    International Nuclear Information System (INIS)

    Reprocessing of spent nuclear fuels produces low and medium activity liquid wastes. These radioactive wastes are decontamined before release in environment. The new effluent processing plant, which is being built at La Hague, is briefly described. Radionuclides are removed from liquid wastes by coprecipitation. The effluent is released after decantation and filtration. Insoluble sludges are conditioned in bitumen

  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. 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.

  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. 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...... hydrocarbons in an adiabatic steam reformer (ASR). The pre-treated fuel then entered to the anode side of the SOFC. The remaining fuels after the SOFC stacks entered a catalytic burner for further combusting. The burned gases from the burner were then used to produce steam for the Rankine cycle in a heat...... and the pre-reformer reactor had no effect on the plant efficiency, which was also true when decreasing the anode temperature. However, increasing the cathode temperature had a significant effect on the plant efficiency. In addition, decreasing the SOFC utilization factor from 0.8 to 0.7, increases...

  12. Radiation resistant polymers and coatings for nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    Polymer based materials are extensively used in the nuclear industry for the reprocessing of spent fuels in highly radioactive and corrosive environment. Hence, these polymer materials are susceptible to damage by ionizing radiation, resulting in the degradation in properties. Polymers containing aromatic molecules generally possess higher resistance to radiation degradation than the aliphatic polymers. For improving the radiation resistance of polymers various methods are reported in the literature. Among the aromatic polymers, polyetheretherketone (PEEK) has the radiation tolerance up to 10 Mega Grey (MGy). To explore the possibility of enhancing the radiation resistance of PEEK, a study was initiated to develop PEEK - ceramic composites and evaluate the effect of radiation on the properties of the composites. PEEK and PEEK - alumina (micron size) composites were irradiated in a gamma chamber using 60Co source and the degradation in mechanical, structural, electrical and thermal properties, gel fraction, coefficient of friction and morphology were investigated. The degradation in the mechanical properties owing to radiation could be reduced by adding alumina filler to PEEK. Nano alumina filler was observed to be more effective in suppressing the damage caused by radiation on the polymer, when compared to micron alumina filler. For the protection of aluminium components in the manipulators and the rotors and stators of the motors of the centrifugal extractors employed in the plant from the attack by nitric acid vapour, PEEK coating based on liquid dispersion was developed, which has resistance to radiation, chemicals and wear. The effect of radiation and chemical vapour on the properties of the PEEK coating was estimated. The performance of the coating in the plant was evaluated and the coating was found to give adequate protection to the motors of centrifugal extractors against corrosion. (author)

  13. 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.

  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. 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. 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)

  17. 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.)

  18. Energy analysis of a trigeneration plant based on solid oxide fuel cell and organic Rankine cycle

    Energy Technology Data Exchange (ETDEWEB)

    Al-Sulaiman, Fahad A. [Mechanical and Aerospace Engineering Department, Carleton University, 1125 Colonel By Drive, Ottawa, Ontario (Canada); Dincer, Ibrahim [Faculty of Engineering and Applied Science, University of Ontario Institute of Technology, 2000 Simcoe Street North, Oshawa, Ontario (Canada); Hamdullahpur, Feridun [Mechanical and Mechatronics Engineering Department, University of Waterloo, 200 University Avenue West, Waterloo, Ontario (Canada)

    2010-05-15

    In this study, energy analysis of a trigeneration plant based on solid oxide fuel cell (SOFC) and organic Rankine cycle (ORC) is conducted. The physical and thermodynamic elements of the plant include an SOFC, an ORC, a heat exchanger for the heating process and a single-effect absorption chiller for cooling. The results obtained from this study show that there is at least a 22% gain in efficiency using the trigeneration plant compared with the power cycle (SOFC and ORC). The study also shows that the maximum efficiency of the trigeneration plant is 74%, heating cogeneration is 71%, cooling cogeneration is 57% and net electricity is 46%. Furthermore, it is found that the highest net power output that can be provided by the trigeneration plant considered in this study is 540 kW and, the highest SOFC-AC power is 520 kW. The study reveals that the inlet pressure of the turbine has an insignificant effect on the efficiency. The study also examines the effect of both the SOFC current density and the SOFC inlet flow temperature on the cell voltage and voltage loss. (author)

  19. 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.

  20. 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)

  1. 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)

  2. Fuel sparing: Control of industrial furnaces using process gas as supplemental fuel

    International Nuclear Information System (INIS)

    Combustible gases from industrial processes can be used to spare purchased fuels such as natural gas and avoid wasteful flaring of the process gases. One of the challenges of incorporating these gases into other furnaces is their intermittent availability. In order to incorporate the gases into a continuously operating furnace, the furnace control system must be carefully designed so that the payload is not affected by the changing fuel. This paper presents a transient computational fluid dynamics (CFD) model of an industrial furnace that supplements natural gas with carbon monoxide during furnace operation. A realistic control system of the furnace is simulated as part of the CFD calculation. The time dependent changes in fuels and air injection on the furnace operation is observed. It is found that there is a trade-off between over-controlling the furnace, which results in too sensitive a response to normal flow oscillations, and under-controlling, which results in a lagged response to the fuel change. - Highlights: •Intermittently available process gases used in a continuously operating furnace. •Study shows a trade-off between over-controlling and under-controlling the furnace. •Over-controlling: response too sensitive to normal flow oscillations. •Under-controlling: lagged response to changing fuel composition. •Normal flow oscillations in furnace would not be apparent in steady-state model

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

    International Nuclear Information System (INIS)

    Eltron Research Inc., and team members CoorsTek, McDermott Technology, inc., 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 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. 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

  4. 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)

  5. 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)

  6. Re-qualification of MTR-type fuel plates fabrication process

    International Nuclear Information System (INIS)

    The fabricability issues with increased uranium loading due to use low enrichment of uranium (LEU), i.e. less than 20 % of U235, increase the problems which occur during compact manufacturing, roll bonding of the fuel plates, potential difficulty in forming during rolling process, mechanical integrity of the core during fabrication, potential difficulty in meat homogeneity, and the ability to fabricate plates with thicker core as a means of increasing total uranium loading. To produce MTR- type fuel plates with high uranium loading (HUL) and keep the required quality of these plates, many of qualification process must be done in the commissioning step of fuel fabrication plant. After that any changing of the fabrication parameters, for example changing of any of the raw materials, devises, operators, and etc., a re- qualification process should be done in order to keep the quality of produced plates. Objective of the present work is the general description of the activities to be accomplished for re-qualification of manufacturing MTR- type nuclear fuel plates. For each process to be re-qualified, a detailed of re-qualification process were established. (author)

  7. Idaho Chemical Processing Plant failure rate database

    International Nuclear Information System (INIS)

    This report represents the first major upgrade to the Idaho Chemical Processing Plant (ICPP) Failure Rate Database. This upgrade incorporates additional site-specific and generic data while improving on the previous data reduction techniques. In addition, due to a change in mission at the ICPP, the status of certain equipment items has changed from operating to standby or off-line. A discussion of how this mission change influenced the relevance of failure data also has been included. This report contains two data sources: the ICPP Failure Rate Database and a generic failure rate database. A discussion is presented on the approaches and assumptions used to develop the data in the ICPP Failure Rate Database. The generic database is included along with a short discussion of its application. A brief discussion of future projects recommended to strengthen and lend credibility to the ICPP Failure Rate Database also is included

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

    Energy Technology Data Exchange (ETDEWEB)

    Carl R. Evenson; Anthony F. Sammells; Richard T. Treglio; U. Balachandran; Richard N. Kleiner; James E. Stephan; Frank E. Anderson; Clive Brereton; Warren Wolfs; James Lockhart

    2004-10-21

    During this quarter, work was focused on characterizing the stability of layered composite membranes in a one hundred percent permeate environment. Permeation data was also collected on cermets as a function of thickness. A thin film deposition procedure was used to deposit dense thin BCY/Ni onto a tubular porous support. Thin film tubes were then tested for permeation at ambient pressure. Process flow diagrams were prepared for inclusion of hydrogen separation membranes into IGCC power plants under varying conditions. Finally, membrane promoted alkane dehydrogenation experiments were performed.

  9. Reprocessing of FBTR mixed carbide fuel- some process chemistry aspects

    International Nuclear Information System (INIS)

    The successful closing of nuclear fuel cycle holds the key to the success of the breeder program. The Fast Breeder Test Reactor (FBTR) and the associated facilities at the Indira Gandhi Center for Atomic Research (IGCAR) at Kalpakkam provides the test bed for evaluating the various processes, equipment and systems so as to understand the various process and equipment issues. The FBTR mixed carbide fuel of unique composition (U0.3Pu0.7)C, which is being used for the first time in the world as the driver fuel, provides ample challenges and solving them leads to clear understanding of fast reactor fuel reprocessing. To establish the fast reactor fuel reprocessing technology, after two decades of sustained R and D efforts at the Reprocessing Development Laboratory (RDL), a comprehensive radioactive research facility at Reprocessing Group of IGCAR, namely, Lead Mini Cell (LMC) was built and commissioned in 2003. This paper describes the challenges overcome during the operational phase of various reprocessing campaigns. (author)

  10. 76 FR 44049 - Guidance for Fuel Cycle Facility Change Processes

    Science.gov (United States)

    2011-07-22

    ... COMMISSION Guidance for Fuel Cycle Facility Change Processes AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; extension of comment period. SUMMARY: On July 14, 2011 (76 FR 41527), the U.S...: Richard.Jervey@nrc.gov . SUPPLEMENTARY INFORMATION: On July 14, 2011 (76 FR 41527), the NRC published...

  11. 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)

  12. Oxy-fuel Combustion and Integrated Pollutant Removal as Retrofit Technologies for Removing CO2 from Coal Fired Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Ochs, T.L.; Oryshchyn, D.B.; Summers, C.A.; Gerdemann, S.J.

    2001-01-01

    One third of the US installed capacity is coal-fired, producing 49.7% of net electric generation in 20051. Any approach to curbing CO2 production must consider the installed capacity and provide a mechanism for preserving this resource while meeting CO2 reduction goals. One promising approach to both new generation and retrofit is oxy-fuel combustion. Using oxygen instead of air as the oxidizer in a boiler provides a concentrated CO2 combustion product for processing into a sequestration-ready fluid.... Post-combustion carbon capture and oxy-fuel combustion paired with a compression capture technology such as IPR are both candidates for retrofitting pc combustion plants to meet carbon emission limits. This paper will focus on oxy-fuel combustion as applied to existing coal power plants.

  13. 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.

  14. Treatment, Processing and Future Disposal of Radioactive Wastes at the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    Acidic wastes from the recovery of enriched uranium from aluminium, zirconium, and stainless-steel fuels at the Idaho Chemical Processing Plant are stored in underground tanks of two configurations and nominal sizes of 30,000 and 300,000 gallons. The design and operation of the waste-tank farm as well as the methods of environmental disposal of low-level wastes is described. The ''concentrate and contain'' philosophy of waste disposal has as its ultimate aim the production of a solid mass containing the fission products. The disadvantage of increased treatment costs may or may not be offset by reduction in storage costs. The low thermal conductivity of solids makes storage temperature considerations more important than for liquids. The acid aluminium nitrate wastes from the processing of fuels of the Material Testing Reactor type may be converted to granular alumina by calcining in a fluidized bed from 350° to 550° C. The major process components are the NaK heated calciner, an off-gas cleaning system and the solids storage vessels. The process design and the research and development programme are reviewed. On the basis of the successful demonstration of fluidized-bed calcining and high-temperature solids storage in conjunction with other considerations, a number of future storage concepts and their environmental connotations are discussed. (author)

  15. 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.

  16. 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.

  17. Analysis of technology and quality control the fuel elements production process

    International Nuclear Information System (INIS)

    Recently great attention has been paid at the international level to the analysis of production processes and quality control of fuel elements with the aim to speed up activity of proposing and accepting standards and measurement methods. IAEA also devoted great interest to these problems appealing to more active participation of all users and procedures of fuel elements in a general effort to secure successful work with nuclear plants. For adequate and timely participation in future of the establishment and analysis of general requirements and documentation for the control of purchased or self produced fuel elements in our country, it is necessary to be well informed and to follow this activity at the international level

  18. 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)

  19. Application of process simulation for evaluation of ecologically benefical developments in thermal power plant technology

    International Nuclear Information System (INIS)

    Responsibility for the environment and a sustainable utilization of resources gain also in the production of electric power more and more importance. For this reason existing power generation processes have to be improved and alternatives to existing processes have to be developed. As a first step in this procedure process simulation is a powerful tool to evaluate the potentials of new developments. In this work it is shown, how new thermal power processes are modeled and simulated based on well-known thermodynamic and chemical correlations. Processes for thermal power plants using lignite with high water content and biomass as fuel are studied. In each case simulations are carried out for complete plants including all important unit operations. Based on a conventional thermal power plant for lignite different variants for efficiency improvement by fuel drying are examined. Additionally the potential of a process with gasification and gas turbine is discussed. Compared to a lignite power plant the preconditions for a biomass power plant are different. A promising option for the future seems to be small, decentralized combined heat and power plants. Therefore a process with simple and compact design including gasifier and gas turbine is regarded and sensitivity analyses are carried out. As well as for the lignite processes possible improvements by fuel drying are studied. The basis lignite power plant (drying in an impact rotor mill with hot flue gas) has an overall electric efficiency of 36 %. Alternative fuel drying processes (reducing water content from 54 w % to 10 w %) can increase efficiency to nearly 43 %. Using integrated air-blown gasification combined with gas turbine and steam turbine and additional fuel drying raises the efficiency up to 49 % in the case of cold gas cleanup and up to 50 percent in the case of hot gas cleanup. Efficiencies of the regarded biomass power plants are in the range of about 20 % (with a biomass water content of 25 w %). By

  20. 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.