MOX fuel transport: the French experience

International Nuclear Information System (INIS)

Sanchis, H.; Verdier, A.; Sanchis, H.

1999-01-01

In the back-end of the fuel cycle, several leading countries have chosen the Reprocessing, Conditioning, Recycling (RCR) option. Plutonium recycling in the form of MOX fuel is a mature industry, with successful operational experience and large-scale fabrication plants an several European countries. The COGEMA Group has developed the industrialized products to master the RCR operation including transport COGEMA subsidiary, TRANSNUCLEAIRE has been operating MOX fuel transports on an industrial scale for more than 10 years. In 1998, around 200 transports of Plutonium materials have been organised by TRANSNUCLEAIRE. These transports have been carried out by road between various facilities in Europe: reprocessing plants, manufacturing plants and power plants. The materials transported are either: PuO 2 and MOX powder; BWR and PWR MOX fuel rods; BWR and PWR MOX fuel assemblies. Because MOX fuel transport is subject to specific safety, security and fuel integrity requirements, the MOX fuel transport system implemented by TRANSNUCLEAIRE is fully dedicated. Packaging have been developed, licensed and manufactured for each kind of MOX material in compliance with relevant regulations. A fleet of vehicles qualified according to existing physical protection regulations is operated by TRANSNUCLEAIRE. TRANSNUCLEAIRE has gained a broad experience in MOX transport in 10 years. Technical and operational know-how has been developed and improved for each step: vehicles and packaging design and qualification; vehicle and packaging maintenance; transport operations. Further developments are underway to increase the payload of the packaging and to improve the transport conditions, safety and security remaining of course top priority. (authors)

Transport of irradiated nuclear fuel

International Nuclear Information System (INIS)

1980-01-01

In response to public interest in the transport by rail through London of containers of irradiated fuel elements on their way from nuclear power stations to Windscale, the Central Electricity Generating Board and British Rail held three information meetings in London in January 1980. One meeting was for representatives of London Borough Councils and Members of Parliament with a known interest in the subject, and the others were for press, radio and television journalists. This booklet contains the main points made by the principal speakers from the CEGB and BR. (The points covered include: brief description of the fuel cycle; effect of the fission process in producing plutonium and fission products in the fuel element; fuel transport; the fuel flasks; protection against accidents; experience of transporting fuel). (U.K.)

Spent fuels transportation coming from Australia

International Nuclear Information System (INIS)

2002-01-01

Maritime transportation of spent fuels from Australia to France fits into the contract between COGEMA and ANSTO, signed in 1999. This document proposes nine information cards in this domain: HIFAR a key tool of the nuclear, scientific and technological australian program; a presentation of the ANSTO Australian Nuclear Science and Technology Organization; the HIFAR spent fuel management problem; the COGEMA expertise in favor of the research reactor spent fuel; the spent fuel reprocessing at La Hague; the transports management; the transport safety (2 cards); the regulatory framework of the transports. (A.L.B.)

Solid fuel applications to transportation engines

Energy Technology Data Exchange (ETDEWEB)

Rentz, Richard L.; Renner, Roy A.

1980-06-01

The utilization of solid fuels as alternatives to liquid fuels for future transportation engines is reviewed. Alternative liquid fuels will not be addressed nor will petroleum/solid fuel blends except for the case of diesel engines. With respect to diesel engines, coal/oil mixtures will be addressed because of the high interest in this specific application as a result of the large number of diesel engines currently in transportation use. Final assessments refer to solid fuels only for diesel engines. The technical assessments of solid fuels utilization for transportation engines is summarized: solid fuel combustion in transportation engines is in a non-developed state; highway transportation is not amenable to solid fuels utilization due to severe environmental, packaging, control, and disposal problems; diesel and open-cycle gas turbines do not appear worthy of further development, although coal/oil mixtures for slow speed diesels may offer some promise as a transition technology; closed-cycle gas turbines show some promise for solid fuels utilization for limited applications as does the Stirling engine for use of cleaner solid fuels; Rankine cycle engines show good potential for limited applications, such as for locomotives and ships; and any development program will require large resources and sophisticated equipment in order to advance the state-of-the-art.

Alternatives to traditional transportation fuels: An overview

Energy Technology Data Exchange (ETDEWEB)

1994-06-01

This report presents the first compilation by the Energy Information Administration (EIA) of information on alternatives to gasoline and diesel fuel. The purpose of the report is: (1) to provide background information on alternative transportation fuels and replacement fuels compared with gasoline and diesel fuel, and (2) to furnish preliminary estimates of alternative transportation fuels and alternative fueled vehicles as required by the Energy Policy Act of 1992 (EPACT), Title V, Section 503, ``Replacement Fuel Demand Estimates and Supply Information.`` Specifically, Section 503 requires the EIA to report annually on: (1) the number and type of alternative fueled vehicles in existence the previous year and expected to be in use the following year, (2) the geographic distribution of these vehicles, (3) the amounts and types of replacement fuels consumed, and (4) the greenhouse gas emissions likely to result from replacement fuel use. Alternative fueled vehicles are defined in this report as motorized vehicles licensed for on-road use, which may consume alternative transportation fuels. (Alternative fueled vehicles may use either an alternative transportation fuel or a replacement fuel.) The intended audience for the first section of this report includes the Secretary of Energy, the Congress, Federal and State agencies, the automobile manufacturing industry, the transportation fuel manufacturing and distribution industries, and the general public. The second section is designed primarily for persons desiring a more technical explanation of and background for the issues surrounding alternative transportation fuels.

Fuel element transport container

International Nuclear Information System (INIS)

Benna, P.; Neuenfeldt, W.

1979-01-01

The reprocessing system includes a large number of waterfilled ponds next to each other for the intermediate storage of fuel elements from LWR's. The fuel element transport device is allocated to a middle pond. The individual ponds are separated from each other by walls, and are only accessible from the middle pond via narrow passages. The transport device includes a telescopic running rail for a trolley with a grab device for the fuel element. The running rail is supported in turn by a second trolley, which can be moved by wheels on rails. Part of the drive of the first trolley is arranged on the second one. Using this transport device, adjacent ponds can be served through the passage openings. (DG) [de

Transportation of irradiated fuel elements

International Nuclear Information System (INIS)

1980-01-01

A critique is presented of current methods of transporting spent nuclear fuel and the inadequacies of the associated contingency plans, with particular reference to the transportation of irradiated fuel through London. Anti-nuclear and pro-nuclear arguments are presented on a number of factors, including tests on flasks, levels of radiation exposure, routine transport arrangements and contingency arrangements. (U.K.)

Nuclear fuel quality assurance

International Nuclear Information System (INIS)

1976-01-01

Full text: Quality assurance is used extensively in the design, construction and operation of nuclear power plants. This methodology is applied to all activities affecting the quality of a nuclear power plant in order to obtain confidence that an item or a facility will perform satisfactorily in service. Although the achievement of quality is the responsibility of all parties participating in a nuclear power project, establishment and implementation of the quality assurance programme for the whole plant is a main responsibility of the plant owner. For the plant owner, the main concern is to achieve control over the quality of purchased products or services through contractual arrangements with the vendors. In the case of purchase of nuclear fuel, the application of quality assurance might be faced with several difficulties because of the lack of standardization in nuclear fuel and the proprietary information of the fuel manufacturers on fuel design specifications and fuel manufacturing procedures. The problems of quality assurance for purchase of nuclear fuel were discussed in detail during the seminar. Due to the lack of generally acceptable standards, the successful application of the quality assurance concept to the procurement of fuel depends on how much information can be provided by the fuel manufacturer to the utility which is purchasing fuel, and in what form and how early this information can be provided. The extent of information transfer is basically set out in the individual vendor-utility contracts, with some indirect influence from the requirements of regulatory bodies. Any conflict that exists appears to come from utilities which desire more extensive control over the product they are buying. There is a reluctance on the part of vendors to permit close insight of the purchasers into their design and manufacturing procedures, but there nevertheless seems to be an increasing trend towards release of more information to the purchasers. It appears that

Alternatives to traditional transportation fuels 1993

Energy Technology Data Exchange (ETDEWEB)

1995-01-01

In recent years, gasoline and diesel fuel have accounted for about 80 percent of total transportation fuel and nearly all of the fuel used in on-road vehicles. Growing concerns about the environmental effects of fossil fuel use and the Nation`s high level of dependence on foreign oil are providing impetus for the development of replacements or alternatives for these traditional transportation fuels. (The Energy Policy Act of 1992 definitions of {open_quotes}replacement{close_quotes} and {open_quotes}alternative{close_quotes} fuels are presented in the following box.) The Alternative Motor Fuels Act of 1988, the Clean Air Act Amendments of 1990 (CAAA90) and the Energy Policy Act of 1992 (EPACT) are significant legislative forces behind the growth of replacement fuel use. Alternatives to Traditional Transportation Fuels 1993 provides the number of on-road alternative fueled vehicles in use in the United States, alternative and replacement fuel consumption, and information on greenhouse gas emissions resulting from the production, delivery, and use of replacement fuels for 1992, 1993, and 1995.

Spent fuel transportation problems

International Nuclear Information System (INIS)

Kondrat'ev, A.N.; Kosarev, Yu.A.; Yulikov, E.A.

1977-01-01

In this paper, problems of transportation of nuclear spent fuel to reprocessing plants are discussed. The solutions proposed are directed toward the achievement of the transportation as economic and safe as possible. The increase of the nuclear power plants number in the USSR and the great distances between these plants and the reprocessing plants involve an intensification of the spent fuel transportation. Higher burnup and holdup time reduction cause the necessity of more bulky casks. In this connection, the economic problems become still more important. One of the ways of the problem solution is the development of rational and cheap cask designs. Also, the enforcement in the world of the environmental and personnel health protection requires to increase the transportation reliability and safety. The paper summarizes safe transportation rules with clarifying the following questions: the increase of the transport unit quantity of the spent fuel; rational shipment organization that minimizes vehicle turnover cycle duration; development of the reliable calculation methods to determine strength, thermal conditions and nuclear safety of transport packaging as applied to the vehicles of high capacity; maximum unification of vehicles, calculation methods and documents; and cask testing on models and in pilot scale on specific test rigs to assure that they meet the international safe fuel shipment rules. Besides, some considerations on the choice and use of structural materials for casks are given, and problems of manufacturing such casks from uranium and lead are considered, as well as problems of the development of fireproof shells, control instrumentation, vehicles decontamination, etc. All the problems are considered from the point of view of normal and accidental shipment conditions. Conclusions are presented [ru

CNG: a potential transport fuel

International Nuclear Information System (INIS)

Anon.

1992-01-01

Compressed Natural Gas (CNG) is an alternative transport fuel. Advantages of its use are briefly described. Infra structural requirements, if it is to be used in India are outlined. Applications of CNG as transport fuel for buses and trucks in India are discussed. (P.R.K.). 5 refs

Intermodal transportation of spent fuel

International Nuclear Information System (INIS)

Elder, H.K.

1983-09-01

Concepts for transportation of spent fuel in rail casks from nuclear power plant sites with no rail service are under consideration by the US Department of Energy in the Commercial Spent Fuel Management program at the Pacific Northwest Laboratory. This report identifies and evaluates three alternative systems for intermodal transfer of spent fuel: heavy-haul truck to rail, barge to rail, and barge to heavy-haul truck. This report concludes that, with some modifications and provisions for new equipment, existing rail and marine systems can provide a transportation base for the intermodal transfer of spent fuel to federal interim storage facilities. Some needed land transportation support and loading and unloading equipment does not currently exist. There are insufficient shipping casks available at this time, but the industrial capability to meet projected needs appears adequate

Standard casks for the transport of LWR spent fuel. Storage/transport casks for long cooled spent fuel

International Nuclear Information System (INIS)

Blum, P.; Sert, G.; Gagnon, R.

1983-01-01

During the past decade, TRANSNUCLEAIRE has developed, licensed and marketed a family of standard casks for the transport of spent fuel from LWR reactors to reprocessing plants and the ancillary equipments necessary for their operation and transport. A large number of these casks are presently used for European and intercontinental transports and manufactured under TRANSNUCLEAIRE supervision in different countries. The main advantages of these casks are: - large payload for considered modes of transport, - moderate cost, - reliability due to the large experience gained by TRANSNUCLEAIRE as concerns fabrication and operation problems, - standardization faciliting fabrication, operation and spare part supply. Recently, TRANSNUCLEAIRE also developed a new generation of casks for the dry storage and occasional transport of LWR spent fuel which has been cooled for 5 years or 7 years in case of consolidated fuel rods. These casks have an optimum payload which takes into account the shielding requirements and the weight limitations at most sites. This paper deals more particularly with the TN 24 model which exists in 4 versions among which one for 24 PWR 900 fuel assemblies and another one for the consolidated fuel rods from 48 of same fuel assemblies

Cost reductions of fuel cells for transport applications: fuel processing options

Energy Technology Data Exchange (ETDEWEB)

Teagan, W P; Bentley, J; Barnett, B [Arthur D. Little, Inc., Cambridge, MA (United States)

1998-03-15

The highly favorable efficiency/environmental characteristics of fuel cell technologies have now been verified by virtue of recent and ongoing field experience. The key issue regarding the timing and extent of fuel cell commercialization is the ability to reduce costs to acceptable levels in both stationary and transport applications. It is increasingly recognized that the fuel processing subsystem can have a major impact on overall system costs, particularly as ongoing R and D efforts result in reduction of the basic cost structure of stacks which currently dominate system costs. The fuel processing subsystem for polymer electrolyte membrane fuel cell (PEMFC) technology, which is the focus of transport applications, includes the reformer, shift reactors, and means for CO reduction. In addition to low cost, transport applications require a fuel processor that is compact and can start rapidly. This paper describes the impact of factors such as fuel choice operating temperature, material selection, catalyst requirements, and controls on the cost of fuel processing systems. There are fuel processor technology paths which manufacturing cost analyses indicate are consistent with fuel processor subsystem costs of under $150/kW in stationary applications and $30/kW in transport applications. As such, the costs of mature fuel processing subsystem technologies should be consistent with their use in commercially viable fuel cell systems in both application categories. (orig.)

Transport and reprocessing of irradiated nuclear fuel

International Nuclear Information System (INIS)

Lenail, B.

1981-01-01

This contribution deals with transport and packaging of oxide fuel from and to the Cogema reprocessing plant at La Hague (France). After a general discussion of nuclear fuel and the fuel cycle, the main aspects of transport and reprocessing of oxide fuel are analysed. (Auth.)

Fuel cell water transport

Science.gov (United States)

Vanderborgh, Nicholas E.; Hedstrom, James C.

1990-01-01

The moisture content and temperature of hydrogen and oxygen gases is regulated throughout traverse of the gases in a fuel cell incorporating a solid polymer membrane. At least one of the gases traverses a first flow field adjacent the solid polymer membrane, where chemical reactions occur to generate an electrical current. A second flow field is located sequential with the first flow field and incorporates a membrane for effective water transport. A control fluid is then circulated adjacent the second membrane on the face opposite the fuel cell gas wherein moisture is either transported from the control fluid to humidify a fuel gas, e.g., hydrogen, or to the control fluid to prevent excess water buildup in the oxidizer gas, e.g., oxygen. Evaporation of water into the control gas and the control gas temperature act to control the fuel cell gas temperatures throughout the traverse of the fuel cell by the gases.

Estimating road transport fuel consumption in Ecuador

International Nuclear Information System (INIS)

Sierra, Jaime Cevallos

2016-01-01

Road transport is one of the sectors with highest energy consumptions in the planet, with large dependence of fossil fuels, and contribution for global greenhouse gas emissions. Although, Latin America is not a high-energy consumer, its share in global consumption is expected to grow, especially in the transportation sector. This make essential for developing countries the adoption of better policies to identify the vehicle groups with largest fuel demands. The present study describes the VKT technique to disaggregate road transport energy consumption by vehicle type, applied to the road transportation system of Ecuador. It also describes the procedures performed to estimate the variables required to run the model, and some of the practical applications that be used to create public policies. Results show as the biggest fuel consumers the heavy-duty freight cargo, followed by light duty vehicles. The estimation of greenhouse gas emissions evidence that road transport released 14.3 million tons of CO_2 in 2012. When fuel consumption is compared by it costs, it can be confirmed that Ecuadorean Government covered, through subsidies, for 68% of the annual fuel costs of national road transport, demonstrating the importance of restructuring these expenditures in order to achieve an efficient road transport system. - Highlights: •The vehicle-kilometers traveled has been estimated from local info. •The fuel economy has been calculated from national and international data. •The groups with higher fuel consumption has been located. •The fuel-type dependency has been estimated for each vehicle group. •Greenhouse gas emission, and fuel costs, has been estimated for local road transport.

Methods of producing transportation fuel

Science.gov (United States)

Nair, Vijay [Katy, TX; Roes, Augustinus Wilhelmus Maria [Houston, TX; Cherrillo, Ralph Anthony [Houston, TX; Bauldreay, Joanna M [Chester, GB

2011-12-27

Systems, methods, and heaters for treating a subsurface formation are described herein. At least one method for producing transportation fuel is described herein. The method for producing transportation fuel may include providing formation fluid having a boiling range distribution between -5.degree. C. and 350.degree. C. from a subsurface in situ heat treatment process to a subsurface treatment facility. A liquid stream may be separated from the formation fluid. The separated liquid stream may be hydrotreated and then distilled to produce a distilled stream having a boiling range distribution between 150.degree. C. and 350.degree. C. The distilled liquid stream may be combined with one or more additives to produce transportation fuel.

Transport of MOX fuel from Europe to Japan

International Nuclear Information System (INIS)

2002-01-01

The MOX fuel transports from Europe to Japan represent a main part in the implementing of the Japan nuclear program. They complement the 160 transports of spent fuels realized from Japan to Europe and the vitrified residues return from France to Japan. In this framework the document presents the MOX fuel, the use of the MOX fuel in reactor, the proliferation risks, the MOX fuel transport to Japan, the public health, the transport regulations, the safety and the civil liability. (A.L.B.)

Spent fuel transport in fuel cycle

International Nuclear Information System (INIS)

Labrousse, M.

1977-01-01

The transport of radioactive substances is a minor part of the fuel cycle because the quantities of matter involved are very small. However the length and complexity of the cycle, the weight of the packing, the respective distances between stations, enrichment plants and reprocessing plants are such that the problem is not negligible. In addition these transports have considerable psychological importance. The most interesting is spent fuel transport which requires exceptionally efficient packaging, especially where thermal and mechanical resistance are concerned. To meet the safety criteria necessary for the protection of both public and users it was decided to use the maximum capacity consistent with rail transport and to avoid coolant fluids under pressure. Since no single type of packing is suitable for all existing stations an effort has been made to standardise handling accessories, and future trands are towards maximum automation. A discussion on the various technical solutions available for the construction of these packing systems is followed by a description of those used for the two types of packaging ordered by COGEMA [fr

The economic impact of strengthening fuel quality regulation-reducing sulfur content in diesel fuel

International Nuclear Information System (INIS)

Chang, H.J.; Cho, G.L.; Kim, Y.D.

2006-01-01

This paper investigates the impact of strengthening vehicle emission regulation on economic activities. The government attempts to use three regulation measures to protect air quality from transportation emission. The measures include the aggregate limit (bubbles), the vehicle emission standard, and the fuel quality standard. Especially, we focus on the economic impact of reducing sulfur content in diesel fuel quality standard. Sulfur content in diesel fuel is one of the main factors in worsening local air quality. The emission from diesel vehicle accounts for 51.8% of total vehicle emission in Korea. If sulfur content reduction regulation is implemented, then the petroleum industry should build more facility to produce low sulfur content diesel, leading to additional production costs and increasing prices and decreasing outputs. We use computable general equilibrium model to analyze how the sulfur reduction regulation affects economic activities and trace out local emission reduction cost and GDP loss. And we suggest the tax-recycling mechanism to mitigate the negative economic costs due to the sulfur reduction regulation

Phenomena in thermal transport in fuels

International Nuclear Information System (INIS)

Chernatynskiy, A.; Tulenko, J.S.; Phillpot, S.R.; El-Azab, A.

2015-01-01

Thermal transport in nuclear fuels is a key performance metric that affects not only the power output, but is also an important consideration in potential accident situations. While the fundamental theory of the thermal transport in crystalline solids was extensively developed in the 1950's and 1960's, the pertinent analytic approaches contained significant simplifications of the physical processes. While these approaches enabled estimates of the thermal conductivity in bulk materials with microstructure, they were not comprehensive enough to provide the detailed guidance needed for the in-pile fuel performance. Rather, this guidance has come from data painfully accumulated over 50 years of experiments on irradiated uranium dioxide, the most widely used nuclear fuel. At this point, a fundamental theoretical understanding of the interplay between the microstructure and thermal conductivity of irradiated uranium dioxide fuel is still lacking. In this chapter, recent advances are summarised in the modelling approaches for thermal transport of uranium dioxide fuel. Being computational in nature, these modelling approaches can, at least in principle, describe in detail virtually all mechanisms affecting thermal transport at the atomistic level, while permitting the coupling of the atomistic-level simulations to the mesoscale continuum theory and thus enable the capture of the impact of microstructural evolution in fuel on thermal transport. While the subject of current studies is uranium dioxide, potential applications of the methods described in this chapter extend to the thermal performance of other fuel forms. (authors)

Fuel Mix Impacts from Transportation Fuel Carbon Intensity Standards in Multiple Jurisdictions

Science.gov (United States)

Witcover, J.

2017-12-01

Fuel carbon intensity standards have emerged as an important policy in jurisdictions looking to target transportation greenhouse gas (GHG) emissions for reduction. A carbon intensity standard rates transportation fuels based on analysis of lifecycle GHG emissions, and uses a system of deficits and tradable, bankable credits to reward increased use of fuels with lower carbon intensity ratings while disincentivizing use of fuels with higher carbon intensity ratings such as conventional fossil fuels. Jurisdictions with carbon intensity standards now in effect include California, Oregon, and British Columbia, all requiring 10% reductions in carbon intensity of the transport fuel pool over a 10-year period. The states and province have committed to grow demand for low carbon fuels in the region as part of collaboration on climate change policies. Canada is developing a carbon intensity standard with broader coverage, for fuels used in transport, industry, and buildings. This study shows a changing fuel mix in affected jurisdictions under the policy in terms of shifting contribution of transportation energy from alternative fuels and trends in shares of particular fuel pathways. It contrasts program designs across the jurisdictions with the policy, highlights the opportunities and challenges these pose for the alternative fuel market, and discusses the impact of having multiple policies alongside federal renewable fuel standards and sometimes local carbon pricing regimes. The results show how the market has responded thus far to a policy that incentivizes carbon saving anywhere along the supply chain at lowest cost, in ways that diverged from a priori policy expectations. Lessons for the policies moving forward are discussed.

Transport fuel

DEFF Research Database (Denmark)

Ronsse, Frederik; Jørgensen, Henning; Schüßler, Ingmar

2014-01-01

Worldwide, the use of transport fuel derived from biomass increased four-fold between 2003 and 2012. Mainly based on food resources, these conventional biofuels did not achieve the expected emission savings and contributed to higher prices for food commod - ities, especially maize and oilseeds...

Inspection of nuclear fuel transport in Spain

International Nuclear Information System (INIS)

Lobo Mendez, J.

1977-01-01

The experience acquired in inspecting nuclear fuel shipments carried out in Spain will serve as a basis for establishing the regulations wich must be adhered to for future transports, as the transport of nuclear fuels in Spain will increase considerably within the next years as a result of the Spanish nuclear program. The experience acquired in nuclear fuel transport inspection is described. (author) [es

Analysis of near-term spent fuel transportation hardware requirements and transportation costs

International Nuclear Information System (INIS)

Daling, P.M.; Engel, R.L.

1983-01-01

A computer model was developed to quantify the transportation hardware requirements and transportation costs associated with shipping spent fuel in the commercial nucler fuel cycle in the near future. Results from this study indicate that alternative spent fuel shipping systems (consolidated or disassembled fuel elements and new casks designed for older fuel) will significantly reduce the transportation hardware requirements and costs for shipping spent fuel in the commercial nuclear fuel cycle, if there is no significant change in their operating/handling characteristics. It was also found that a more modest cost reduction results from increasing the fraction of spent fuel shipped by truck from 25% to 50%. Larger transportation cost reductions could be realized with further increases in the truck shipping fraction. Using the given set of assumptions, it was found that the existing spent fuel cask fleet size is generally adequate to perform the needed transportation services until a fuel reprocessing plant (FRP) begins to receive fuel (assumed in 1987). Once the FRP opens, up to 7 additional truck systems and 16 additional rail systems are required at the reference truck shipping fraction of 25%. For the 50% truck shipping fraction, 17 additional truck systems and 9 additional rail systems are required. If consolidated fuel only is shipped (25% by truck), 5 additional rail casks are required and the current truck cask fleet is more than adequate until at least 1995. Changes in assumptions could affect the results. Transportation costs for a federal interim storage program could total about $25M if the FRP begins receiving fuel in 1987 or about $95M if the FRP is delayed until 1989. This is due to an increased utilization of federal interim storage facility from 350 MTU for the reference scenario to about 750 MTU if reprocessing is delayed by two years

Transport device for nuclear fuel powder

International Nuclear Information System (INIS)

Adelmann, M.

1987-01-01

The transport device for nuclear fuel powder, which does not disintegrate during transport, has a transport pipe which starts with its entry end from the floor or a closed container and opens with its outlet end at the top into a closed separation container connect via a powder filter to a suction pump. By alternate regular opening and closing of a first control valve for transport gas fitted to a transport pipe to a supply duct and a second control valve for transport gas fitted to the container to an additional supply duct, alternating plugs of nuclear fuel powder and transport gas cushions are formed and are transported to the outlet end of the transport pipe. (orig./HP) [de

Quality assurance in the transport and packaging of radioactive material

International Nuclear Information System (INIS)

Hale, J.

1995-01-01

Quality Assurance (QA) is a requirement of the International Atomic Energy Agency (IAEA) Safety Series No. 6 ''Regulations for Safe Transport of Radioactive Materials.'' It is also, increasingly, a customer requirement. British Nuclear Fuels plc (BNFL) Transport Division has established an integrated management system (including quality and safety) which is being extended to cover environmental aspects. The management system covers the design, procurement, manufacture, testing, documentation, use, maintenance, inspection and decommissioning of all packages used for the transport of radioactive materials and for interim storage. It also covers planning, programming and transport operations. These arrangements cover all modes of transport by road, rail, sea and air. The QA arrangements developed enable Transport Division to demonstrate to Competent Authorities, customers and the general public that the systems in place meet all regulatory requirements. This paper discusses what quality assurance is, why QA arrangements should be introduced and how they were established within Transport Division. Finally, the further developments in the Division's quality arrangements using the tools and techniques of Total Quality Management (TQM) and the European Foundation for Quality Management Model for Self Assessment are described

Alternatives to traditional transportation fuels 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-01

Interest in alternative transportation fuels (ATF`s) has increased in recent years due to the drives for cleaner air and less dependence upon foreign oil. This report, Alternatives to Traditional Transportation Fuels 1996, provides information on ATFs, as well as the vehicles that consume them.

Multi-fuel reformers for fuel cells used in transportation. Phase 1: Multi-fuel reformers

Science.gov (United States)

1994-05-01

DOE has established the goal, through the Fuel Cells in Transportation Program, of fostering the rapid development and commercialization of fuel cells as economic competitors for the internal combustion engine. Central to this goal is a safe feasible means of supplying hydrogen of the required purity to the vehicular fuel cell system. Two basic strategies are being considered: (1) on-board fuel processing whereby alternative fuels such as methanol, ethanol or natural gas stored on the vehicle undergo reformation and subsequent processing to produce hydrogen, and (2) on-board storage of pure hydrogen provided by stationary fuel processing plants. This report analyzes fuel processor technologies, types of fuel and fuel cell options for on-board reformation. As the Phase 1 of a multi-phased program to develop a prototype multi-fuel reformer system for a fuel cell powered vehicle, the objective of this program was to evaluate the feasibility of a multi-fuel reformer concept and to select a reforming technology for further development in the Phase 2 program, with the ultimate goal of integration with a DOE-designated fuel cell and vehicle configuration. The basic reformer processes examined in this study included catalytic steam reforming (SR), non-catalytic partial oxidation (POX) and catalytic partial oxidation (also known as Autothermal Reforming, or ATR). Fuels under consideration in this study included methanol, ethanol, and natural gas. A systematic evaluation of reforming technologies, fuels, and transportation fuel cell applications was conducted for the purpose of selecting a suitable multi-fuel processor for further development and demonstration in a transportation application.

Transportation 2000. Spent fuel transportation trends in the new millenium

International Nuclear Information System (INIS)

Blee, David; Viebrock, James; Patterson, John

1999-01-01

The paper will provide a comparison of foreign research reactor spent fuel transportation today verses the assumptions used by the Department of Energy in the Environmental Impact Statement. In addition, it will suggest changes that are likely to occur in transportation logistics through the remainder of the U.S. spent fuel returns program. Cask availability, certification status, shipment strategy, cost issues, and public acceptance are among the topical areas that will be examined. Transportation requirements will be assessed in light of current participation in the returns program and the tendency for shipment plans to shift toward spent fuel return toward the end of the 13 year period of eligibility. (author)

Effects of fueling profiles on plasma transport

International Nuclear Information System (INIS)

Houlberg, W.A.; Mense, A.T.; Attenberger, S.E.; Milora, S.L.

1977-01-01

The effects of cold particle fueling profiles on particle and energy transport in an ignition sized tokamak plasma are investigated in this study with a one-dimensional, multifluid transport model. A density gradient driven trapped particle microinstability model for plasma transport is used to demonstrate potential effects of fueling profiles on ignition requirements. Important criteria for the development of improved transport models under the conditions of shallow particle fueling profiles are outlined. A discrete pellet fueling model indicates that large fluctuations in density and temperature may occur in the outer regions of the plasma with large, shallowly penetrating pellets, but fluctuations in the pressure profile are small. The hot central core of the plasma remains unaffected by the large fluctuations near the plasma edge

Comparison of the Transportation Risks Resulting from Accidents during the Transportation of the Spent Fuel

International Nuclear Information System (INIS)

Jeong Jong Tae; Cho, Dong Kuen; Choi, Heui Joo; Choi, Jong Won

2007-01-01

The safe, environmentally sound and publicly acceptable disposal of high level wastes and spent fuels is becoming a very important issue. The operational safety assessment of a repository including a transportation safety assessment is a fundamental part in order to achieve this goal. According to the long term management strategy for spent fuels in Korea, they will be transported from the spent fuel pools in each nuclear power plant to the central interim storage facility (CISF) which is to start operation in 2016. Therefore, we have to determine the safe and economical logistics for the transportation of these spent fuels by considering their transportation risks and costs. In this study, we developed four transportation scenarios by considering the type of transportation casks and transport means in order to suggest safe and economical transportation logistics for spent fuels. Also, we estimated and compared the transportation risks resulting from the accidents during the transportation of spent fuels for these four transportation scenarios

Spent fuel and HLW transportation the French experience

International Nuclear Information System (INIS)

Giraud, J.P.; Charles, J.L.

1995-01-01

With 53 nuclear power plants in operation at EDF and a fuel cycle with recycling policy of the valuable materials, COGEMA is faced with the transport of a wide range of radioactive materials. In this framework, the transport activity is a key link in closing the fuel cycle. COGEMA has developed a comprehensive Transport Organization System dealing with all the sectors of the fuel cycle. The paper will describe the status of transportation of spent fuel and HLW in France and the experience gathered. The Transport Organization System clearly defines the role of all actors where COGEMA, acting as the general coordinator, specifies the tasks to be performed and brings technical and commercial support to its various subcontractors: TRANSNUCLEAIRE, specialized in casks engineering and transport operations, supplies packaging and performs transport operations, LEMARECHAL and CELESTIN operate transport by truck in the Vicinity of the nuclear sites while French Railways are in charge of spent fuel transport by train. HLW issued from the French nuclear program is stored for 30 years in an intermediate storage installation located at the La Hague reprocessing plant. Ultimately, these canisters will be transported to the disposal site. COGEMA has set up a comprehensive transport organization covering all operational aspects including adapted procedures, maintenance programs and personnel qualification

Worldwide spent fuel transportation logistics

International Nuclear Information System (INIS)

Best, R.E.; Garrison, R.F.

1978-01-01

This paper presents an overview of the worldwide transportation requirements for spent fuel. Included are estimates of numbers and types of shipments by mode and cask type for 1985 and the year 2000. In addition, projected capital and transportation costs are presented. For the year 1977 and prior years inclusive, there is a cumulative worldwide requirement for approximately 300 MTU of spent fuel storage at away-from-reactor (AFR) facilities. The cumulative requirements for years through 1985 are projected to be nearly 10,000 MTU, and for the years through 2000 the requirements are conservatively expected to exceed 60,000 MTU. These AFR requirements may be related directly to spent fuel transportation requirements. In total nearly 77,000 total cask shipments of spent fuel will be required between 1977 and 2000. These shipments will include truck, rail, and intermodal moves with many ocean and coastal water shipments. A limited number of shipments by air may also occur. The US fraction of these is expected to include 39,000 truck shipments and 14,000 rail shipments. European shipments to regional facilities are expected to be primarily by rail or water mode and are projected to account for 16,000 moves. Pacific basin shipments will account for 4500 moves. The remaining are from other regions. Over 400 casks will be needed to meet the transportation demands. Capital investment is expected to reach $800,000,000 in 1977 dollars. Cumulative transport costs will be a staggering $4.4 billion dollars

Transport device of spent fuel

International Nuclear Information System (INIS)

Watanabe, Takashi.

1976-01-01

Object: To provide a transport device of spent fuel particularly used in a fast breeder, which can enhance accessibility to travelling mechanism portions and exchangeability thereof to facilitate maintenance in the event of failure. Structure: On a travelling floor, which has a function to shield radioactive rays, extending in a direction of transporting spent fuel and being formed with a break passing through in a direction wall thickness, a travelling body is moved along the break. The travelling body has a support rod member mounted thereon, and the support rod member is moved within the break, the support rod member having a fuel support pocket suspended therefrom. (Furukawa, Y.)

BNFL's new spent fuel transport flask - Excellox 8

International Nuclear Information System (INIS)

McWilliam, D.S.

2002-01-01

Since British Nuclear Fuels plc (BNFL) was formed in 1971 its transport service has safely moved spent light water reactor fuel from many locations abroad to its fuel handling plants at Sellafield in the UK. To support this business a number of types of flasks have been designed and used. One of the types used has been the Excellox family of water-filled flasks. To support future business opportunities a new flask, designed to meet the requirements of the new IAEA transport regulations TS-R-1 (ST-1, Revised), has been developed. The flask will be a type B(U)F. This new flask design will maximise fuel carrying capacity to minimise transport costs. The design capacity of the new Excellox 8 flask is to be 12 pressurised water reactor or 32 boiling water reactor fuel assemblies. The objective of this BNFL project is to provide another economic spent nuclear fuel transport system, in support of BNFL transport business. (author)

Interdependencies between transport fuel demand, efficiency and quality: An application to Austria

International Nuclear Information System (INIS)

Goerlich, Roland; Wirl, Franz

2012-01-01

This paper focuses on the interdependencies between technical efficiencies and energy demand which are often either treated in isolation or do not get the sufficient attention in the literature. More precisely, this paper uses technical efficiencies as one crucial determinant of energy demand in order to integrate at least two issues that are usually investigated separately from each other: the rebound effect resulting from improved technical efficiencies and the asymmetry of energy demand. In this regard, our paper sets out a theoretical framework which has the following implications: higher efficiency increases service demand (first order rebound), low fuel prices and higher efficiency increases the demand for quality (second order) which in turn increases service demand further (third order); ceteris paribus, energy price shocks should increase scrapping rates; fuel prices direct the R and D expenditures of car producers; those on engine efficiency are irreversible, which has the consequence that energy price elasticities depend on the history of energy prices rather than being asymmetrical. Derived implications are subsequently tested on Austrian data. In particular, the purchasing decision diesel versus gasoline powered cars allows to refute the myth that consumers apply high implicit rates for discounting the future benefit from efficient cars. - Research Highlights: ►Dependencies between efficiency, fuel price, quality and fuel demand are modelled. ►Austrian data supports model implications for the defined rounds of rebounds. ►R and D efforts are directed by fuel prices surpassing a threshold on large markets. ►Consumers apply low implicit discount rates for future benefits from efficient cars. ►Effects of policy instruments (fuel efficiency standard, taxes, etc.) are discussed.

Transportation fuels of the future?

International Nuclear Information System (INIS)

Piel, W.J.

2001-01-01

Society is putting more emphasis on the mobile transportation sector to achieve future goals of sustainability and a cleaner environment. To achieve these goals, does society need to jump to a new combination of fuel and vehicle technology or can we just continue to improve on the current fuels and drive train technology that has powered us the past 70 or more years? Do we need to move to more exotic energy conversion technology (fuel cell vehicles?), or can improving fuel properties further allow us to continue using combustion engines to power our vehicles? What fuel properties can still be improved in gasoline and diesel? Besides removing sulfur, should there be less aromatics in fuels? Should aromatics be eliminated? Is there a role for oxygenates in gasoline and diesel? Do blending oxygenates in fuels help or hinder in achieving the environmental goals? Can we and should we reduce our dependency on crude oil for transportation energy? Why have not the previous government-sponsored Alternative Fuel programs displaced crude oil? The marketplace will determine which fuel and vehicle technology combination will eventually be used in the future. Does the information we know today give us insight to this future? This paper will attempt to address some of the key issues and questions on the role fuels may play in that marketplace decision

Fuels and Combustion | Transportation Research | NREL

Science.gov (United States)

Fuels and Combustion Fuels and Combustion This is the March 2015 issue of the Transportation and , combustion strategy, and engine design hold the potential to maximize vehicle energy efficiency and performance of low-carbon fuels in internal combustion engines with a whole-systems approach to fuel chemistry

Transportation of spent MTR fuels

Energy Technology Data Exchange (ETDEWEB)

Raisonnier, D.

1997-08-01

This paper gives an overview of the various aspects of MTR spent fuel transportation and provides in particular information about the on-going shipment of 4 spent fuel casks to the United States. Transnucleaire is a transport and Engineering Company created in 1963 at the request of the French Atomic Energy Commission. The company followed the growth of the world nuclear industry and has now six subsidiaries and affiliated companies established in countries with major nuclear programs.

Transportation of spent MTR fuels

International Nuclear Information System (INIS)

Raisonnier, D.

1997-01-01

This paper gives an overview of the various aspects of MTR spent fuel transportation and provides in particular information about the on-going shipment of 4 spent fuel casks to the United States. Transnucleaire is a transport and Engineering Company created in 1963 at the request of the French Atomic Energy Commission. The company followed the growth of the world nuclear industry and has now six subsidiaries and affiliated companies established in countries with major nuclear programs

DOE perspective on fuel cells in transportation

Energy Technology Data Exchange (ETDEWEB)

Kost, R.

1996-04-01

Fuel cells are one of the most promising technologies for meeting the rapidly growing demand for transportation services while minimizing adverse energy and environmental impacts. This paper reviews the benefits of introducing fuel cells into the transportation sector; in addition to dramatically reduced vehicle emissions, fuel cells offer the flexibility than use petroleum-based or alternative fuels, have significantly greater energy efficiency than internal combustion engines, and greatly reduce noise levels during operation. The rationale leading to the emphasis on proton-exchange-membrane fuel cells for transportation applications is reviewed as are the development issues requiring resolution to achieve adequate performance, packaging, and cost for use in automobiles. Technical targets for power density, specific power, platinum loading on the electrodes, cost, and other factors that become increasingly more demanding over time have been established. Fuel choice issues and pathways to reduced costs and to a renewable energy future are explored. One such path initially introduces fuel cell vehicles using reformed gasoline while-on-board hydrogen storage technology is developed to the point of allowing adequate range (350 miles) and refueling convenience. This scenario also allows time for renewable hydrogen production technologies and the required supply infrastructure to develop. Finally, the DOE Fuel Cells in Transportation program is described. The program, whose goal is to establish the technology for fuel cell vehicles as rapidly as possible, is being implemented by means of the United States Fuel Cell Alliance, a Government-industry alliance that includes Detroit`s Big Three automakers, fuel cell and other component suppliers, the national laboratories, and universities.

Transporting spent nuclear fuel: an overview

International Nuclear Information System (INIS)

1986-03-01

Although high-level radioactive waste from both commercial and defense activities will be shipped to the repository, this booklet focuses on various aspects of transporting commercial spent fuel, which accounts for the majority of the material to be shipped. The booklet is intended to give the reader a basic understanding of the following: the reasons for transportation of spent nuclear fuel, the methods by which it is shipped, the safety and security precautions taken for its transportation, emergency response procedures in the event of an accident, and the DOE program to develop a system uniquely appropriate to NWPA transportation requirements

Transportation of radioactive wastes from nuclear fuel cycles

International Nuclear Information System (INIS)

1979-09-01

This paper discusses current and foreseen radioactive waste transportation systems as they apply to the INFCE Working Group 7 study. The types of wastes considered include spent fuel, which is treated as a waste in once-through fuel cycles; high-, medium-, and low-level waste; and gaseous waste. Regulatory classification of waste quantities and containers applicable to these classifications are discussed. Radioactive wastes are presently being transported in a safe and satisfactory manner. None of the INFCE candidate fuel cycles pose any extraordinary problems to future radioactive waste transportation and such transportation will not constitute a decisive factor in the choice of a preferred fuel cycle

The transportation of PuO2 and MOX fuel and management of irradiated MOX fuel

International Nuclear Information System (INIS)

Dyck, H.P.; Rawl, R.; Durpel, L. van den

2000-01-01

Information is given on the transportation of PuO 2 and mixed-oxide (MOX) fuel, the regulatory requirements for transportation, the packages used and the security provisions for transports. The experience with and management of irradiated MOX fuel and the reprocessing of MOX fuel are described. Information on the amount of MOX fuel irradiated is provided. (author)

Fuels: market, quality, emissions in France

International Nuclear Information System (INIS)

Philippon, A.

1997-01-01

Here is a study about the automobile fuels market. From the market trends, we find the evolution of fuels quality; but in front of the concurrence and with the imbalance between diesel fuels and gasoline fuels, the improvement in fuels quality that requires investments does not increase as well as the air quality should necessitate. (N.C.)

Comparison of the transportation risks for the spent fuel in Korea for different transportation scenarios

International Nuclear Information System (INIS)

Jeong, Jongtae; Cho, D.K.; Choi, H.J.; Choi, J.W.

2011-01-01

According to the long term management strategy for spent fuels in Korea, they will be transported from the spent fuel pools in each nuclear power plant to the central interim storage facility (CISF) which is to start operation in 2016. At the start of the operation of the final repository (FR), by the year 2065, transport will then take place between the CISF and the FR. Therefore, we have to determine the safe and economical logistics for the transportation of these spent fuels by considering their transportation risks and costs. In this study, we developed four transportation scenarios for a maritime transportation by considering the type of transportation casks and transport means in order to suggest safe and economical transportation logistics for the spent fuels in Korea. And, we estimated and compared the transportation risks for these four transportation scenarios. Also, we estimated and compared the transportation risks resulting from accidents during the transportation of PWR and PHWR spent fuels by road trailers from the CISF and the FR. From the results of this study, we found that risks resulting from accidents during the transportation of the spent fuels have a very low radiological risk activity with a manageable safety and health consequences. The results of this study can be used as basic data for the development of safe and economical logistics for a transportation of the spent fuels in Korea by considering the transportation costs for the four scenarios which will be needed in the near future.

THERMAL COMPOSITE COATINGS IMPROVING QUALITY OF TECHNICAL MEANS OF TRANSPORT

Directory of Open Access Journals (Sweden)

Andrzej POSMYK

2015-06-01

Full Text Available The paper presents the thermal properties of composite insulating material designed for producing of technical means of transport. This material can be coated on most of engineering materials. The matrix of this material is an acrylic resin ant non porous ceramic microspheres made of alumina are the reinforcing phase. Thanks to that into the spheres almost vacuum (0,13 Pa dominants and a big amount of spheres pro thickness unit is it possible to achieve low thermal conductivity. Usage of these coatings for producing of cooling cabins on vehicles let us to reduce of fuel for maintain of given temperature. Usage of these coatings in planes flying on high altitudes (temperature up to -60 allows to reduce of fuel consumption for heating. It has an important influence on transport quality and quality costs.

Transport of encapsulated nuclear fuels

International Nuclear Information System (INIS)

Broman, Ulrika; Dybeck, Peter; Ekendahl, Ann-Mari

2005-12-01

The transport system for encapsulated fuel is described, including a preliminary drawing of a transport container. In the report, the encapsulation plant is assumed to be located to Oskarshamn, and the repository to Oskarshamn or Forsmark

Transportation of irradiated fuel elements

International Nuclear Information System (INIS)

Preece, A.H.

1980-01-01

The report falls under the headings: introduction (explaining the special interest of the London Borough of Brent, as forming part of the route for transportation of irradiated fuel elements); nuclear power (with special reference to transport of spent fuel and radioactive wastes); the flask aspect (design, safety regulations, criticisms, tests, etc.); the accident aspect (working manual for rail staff, train formation, responsibility, postulated accident situations); the emergency arrangements aspect; the monitoring aspect (health and safety reports); legislation; contingency plans; radiation - relevant background information. (U.K.)

An improved assembly for the transport of fuel elements

International Nuclear Information System (INIS)

Myers, G.

1979-01-01

An improved assembly for the transport and storage of radioactive nuclear fuel elements is described. The fuel element transport canister is of the type in which the fuel elements are submerged in liquid with a self regulating ullage system, so that the fuel elements are always submerged in the liquid even when the assembly is used in one orientation during loading and another orientation during transportation. (UK)

Alternatives to traditional transportation fuels 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-01

This report provides information on transportation fuels other than gasoline and diesel, and the vehicles that use these fuels. The Energy Information Administration (EIA) provides this information to support the U.S. Department of Energy`s reporting obligations under Section 503 of the Energy Policy Act of 1992 (EPACT). The principal information contained in this report includes historical and year-ahead estimates of the following: (1) the number and type of alterative-fueled vehicles (AFV`s) in use; (2) the consumption of alternative transportation fuels and {open_quotes}replacement fuels{close_quotes}; and (3) the number and type of alterative-fueled vehicles made available in the current and following years. In addition, the report contains some material on special topics. The appendices include a discussion of the methodology used to develop the estimates (Appendix A), a map defining geographic regions used, and a list of AFV suppliers.

Control system of fuel transporting device

International Nuclear Information System (INIS)

Yokota, Minoru.

1981-01-01

Purpose: To effectively avoid an obstacle in a fuel transporting device by reading the outputs of absolute position detectors mounted on movable trucks, controlling the movements of the trucks, and thereby smoothly and accurately positioning the fuel transporting device at predetermined position and providing a contact detector thereat. Method: The outputs from absolute position detectors which are mounted on a longitudinally movable truck and a laterally movable truck are input to an input/output control circuit. The input/output control circuit serves to compare, the position a fuel transporting device is to be moved to, with the present position on the basis of said input detection signal and a command signal from an operator console, to calculate the amount of movement to be driven, to produce an operation signal therefor to a control panel, and to drive and control the drive motors which are respectively mounted on the trucks for the fuel transfer device. On the other hand, in case that the transfer device comes into contact with an obstacle, the contact detector will immediately operate to produce a stop command through the control panel to the transporting device, and avoid a collision with the obstacle. (Yoshino, Y.)

Liquid-fueled SOFC power sources for transportation

Science.gov (United States)

Myles, K. M.; Doshi, R.; Kumar, R.; Krumpelt, M.

Traditionally, fuel cells have been developed for space or stationary terrestrial applications. As the first commercial 200-kW systems were being introduced by ONSI and Fuji Electric, the potentially much larger, but also more challenging, application in transportation was beginning to be addressed. As a result, fuel cell-powered buses have been designed and built, and R&D programs for fuel cell-powered passenger cars have been initiated. The engineering challenge of eventually replacing the internal combustion engine in buses, trucks, and passenger cars with fuel cell systems is to achieve much higher power densities and much lower costs than obtainable in systems designed for stationary applications. At present, the leading fuel cell candidate for transportation applications is, without question, the polymer electrolyte fuel cell (PEFC). Offering ambient temperature start-up and the potential for a relatively high power density, the polymer technology has attracted the interest of automotive manufacturers worldwide. But the difficulties of fuel handling for the PEFC have led to a growing interest in exploring the prospects for solid oxide fuel cells (SOFCs) operating on liquid fuels for transportation applications. Solid oxide fuel cells are much more compatible with liquid fuels (methanol or other hydrocarbons) and are potentially capable of power densities high enough for vehicular use. Two SOFC options for such use are discussed in this report.

Contributions to LWR spent fuel storage and transport

International Nuclear Information System (INIS)

The papers included in this document describe the aspects of spent LWR fuel storage and transport-behaviour of spent fuel during storage; use of compact storage packs; safety of storage; design of storage facilities AR and AFR; description of transport casks and transport procedures

Ordinance concerning the filing of transport of nuclear fuel materials

International Nuclear Information System (INIS)

1987-01-01

This Order provides provisions concerning nuclear fuel substances requiring notification (nuclear fuel substance, material contaminated with nuclear fuel substances, fissionable substances, etc.), procedure for notification (to prefectural public safety commission), certificate of transpot (issued via public safety commission), instructions (speed of vehicle for transporting nuclear fuel substances, parking of vehicle, place for loading and unloading of nuclear fuel substances, method for loading and unloading, report to police, measures for disaster prevention during transport, etc.), communication among members of public safety commission (for smooth transport), notification of alteration of data in transport certificate (application to be submitted to public safety commission), application of reissue of transport certificate, return of transport certificate, inspection concerning transport (to be performed by police), submission of report (to be submitted by refining facilities manager, processing facilities manager, nuclear reactor manager, master of foreign nuclear powered ship, reprocessing facilities manager, waste disposal facilities manager; concerning stolen or missing nuclear fuel substances, traffic accident, unusual leakage of nuclear fuel substances, etc.). (Nogami, K.)

Nuclear-electrolytic hydrogen as a transportation fuel

International Nuclear Information System (INIS)

DeLuchi, M.A.

1989-01-01

Hydrogen is a very attractive transportation fuel in three important ways: it is the least polluting fuel that can be used in an internal combustion engine, it produces no greenhouse gases, and it is potentially available anywhere there is water and a clean source of power. The prospect of a clean, widely available transportation fuel has motivated much of the research on hydrogen fuels. This paper is a state-of-the art review of the production, storage, performance, environmental impacts, safety, and cost of nuclear-electrolytic hydrogen for highway vehicles

EDF energy generation UK transport of irradiated fuel

Energy Technology Data Exchange (ETDEWEB)

James, R. [EDF Energy, London, (United Kingdom)

2015-07-01

This paper give an overview of irradiated fuel transport in the UK. It describes the design of irradiated fuel flask used by EDF Energy; operational experience and good practices learnt from over 50 years of irradiated fuel transport. The AGRs can store approximately 9 months generation of spent fuel, hence the ability to transport irradiated fuel is vital. Movements are by road to the nearest railhead, typically less than 2 miles and then by rail to Sellafield, up to 400 miles, for reprocessing or long term storage. Road and rail vehicles are covered. To date in the UK: over 30,000 Magnox flask journeys and over 15,000 AGR A2 flask journeys have been carried out.

Thermal model of spent fuel transport cask

International Nuclear Information System (INIS)

Ahmed, E.E.M.; Rahman, F.A.; Sultan, G.F.; Khalil, E.E.

1996-01-01

The investigation provides a theoretical model to represent the thermal behaviour of the spent fuel elements when transported in a dry shipping cask under normal transport conditions. The heat transfer process in the spent fuel elements and within the cask are modeled which include the radiant heat transfer within the cask and the heat transfer by thermal conduction within the spent fuel element. The model considers the net radiant method for radiant heat transfer process from the inner most heated element to the surrounding spent elements. The heat conduction through fuel interior, fuel-clad interface and on clad surface are also presented. (author) 6 figs., 9 refs

Rationale for continuing R&D in direct coal conversion to produce high quality transportation fuels

Energy Technology Data Exchange (ETDEWEB)

Srivastava, R.D.; McIlvried, H.G. [Burns and Roe Services Corp., Pittsburgh, PA (United States); Gray, D. [Mitre Corp, McLean, VA (United States)] [and others

1995-12-31

For the foreseeable future, liquid hydrocarbon fuels will play a significant role in the transportation sector of both the United States and the world. Factors favoring these fuels include convenience, high energy density, and the vast existing infrastructure for their production and use. At present the U.S. consumes about 26% of the world supply of petroleum, but this situation is expected to change because of declining domestic production and increasing competition for imports from countries with developing economies. A scenario and time frame are developed in which declining world resources will generate a shortfall in petroleum supply that can be allieviated in part by utilizing the abundant domestic coal resource base. One option is direct coal conversion to liquid transportation fuels. Continued R&D in coal conversion technology will results in improved technical readiness that can significantly reduce costs so that synfuels can compete economically in a time frame to address the shortfall.

Transporting fuel debris from TMI-2 to INEL

International Nuclear Information System (INIS)

Quinn, G.J.; Burton, H.M.; Bixby, W.W.; McIntosh, T.W.; McGoff, O.J.; Barkonic, R.J.; Henrie, J.O.

1986-06-01

Transportation of the damaged fuel from Unit 2 of Three Mile Island (TMI-2) presented noteworthy technical challenges involving complex institutional issues. The program resulted from both a need to package and remove the accident debris and also the opportunity to receive and study damaged core components. These combined to establish the safe transport of the TMI-2 fuel debris as a high priority for many diverse organizations. The capability of the sending and receiving facilities to handle spent fuel transport casks in the most cost-effective manner was assessed and resulted in the development by Nuclear Packaging Inc. (NuPac) of the NuPac 125-B rail cask. This paper reviews the technical challenges in preparation of the TMI-2 core debris for transport from TMI-2 to the Idaho National Engineering Laboratory (INEL) and receipt and storage of that material at INEL. Challenges discussed include design and testing of fuel debris canisters; design, fabrication and licensing of a new rail cask for spent fuel transport; cask loading operations, equipment and facilities at TMI-2; transportation logistics; and, receipt, storage and core examination operations at INEL. 10 refs

Effects of fueling profiles on plasma transport

International Nuclear Information System (INIS)

Mense, A.T.; Houlberg, W.A.; Attenberger, S.E.; Milora, S.L.

1978-04-01

A one-dimensional (1-D), multifluid transport model is used to investigate the effects of particle fueling profiles on plasma transport in an ignition-sized tokamak (TNS). Normal diffusive properties of plasmas will likely maintain the density at the center of the discharge even if no active fueling is provided there. This significantly relaxes the requirements for fuel penetration. Not only is lower fuel penetration easier to achieve, but it may have the advantage of reducing or eliminating density gradient-driven trapped particle microinstabilities. Simulation of discrete pellet fueling indicates that relatively low velocity (approximately 10 3 m/sec) pellets may be sufficient to fuel a TNS-sized device (approximately 1.25-m minor radius), to produce a relatively broad, cool edge region of plasma which should reduce the potential for sputtering, and also to reduce the likelihood of trapped particle mode dominated transport. Low penetrating pellets containing up to 10 to 20 percent of the total plasma ions can produce fluctuations in density and temperature at the plasma edge, but the pressure profile and fusion alpha production remain almost constant

Alternative transport fuels: supply, consumption and conservation

International Nuclear Information System (INIS)

Trindade, S.C.

1990-01-01

Road-based passenger and freight transport almost exclusively uses petroleum/hydrocarbon fuels in the fluid form. These fuels will probably continue to be major transport fuels well into the 21st century. As such there is need to prolong their use which can be done through: (1) conservation of fuel by increasing efficiency of internal combustion engines, and (2) conversion of natural gas, coal and peat, and biomass into alternate fuels such as ethanol, methanol, CNG, LNG, LPG, low heat-content (producer) gas and vegetable oils. Research, development and demonstration (RD and D) priorities in supply, consumption and conservation of these alternate fuels are identified and ranked in the context of situation prevailing in Brazil. Author has assigned the highest priority for research in the impact of pricing, economic, fiscal and trade policies, capital allocation criteria and institutional and legislative framework. It has also been emphasised that an integrated or systems approach is mandatory to achieve net energy gains in transport sector. (M.G.B.). 33 refs., 11 tabs., 4 figs

Risk assessment in spent fuel storage and transportation

International Nuclear Information System (INIS)

Pandimani, S.

1989-01-01

Risk assessment in various stages of nuclear fuel cycle is still an active area of Nuclear safety studies. From the results of risk assessment available in literature, it can be determined that the risk resulting from shipments of plutonium and spent-fuel are much greater than that resulting from the transport of other materials within the nuclear fuel cycle. In India spent fuels are kept in Spent Fuel Storage Pool (SFSP) for about 240-400 days, which is relatively a longer period compared to the usual 120 days as recommended by regulatory authorities. After cooling spent fuels are transported to the reprocessing sites which are mostly situated close to the plants. India has two high level waste treatment facilities, one PREFRE (Plutonium Reprocessing and Fuel Recycling) at Tarapur and the other one, a unit of Nuclear Fuel Complex at Hyderabad. This paper presents the risk associated with spent fuel storage and transportation for the Indian conditions. All calculations are based on a typical CANDU reactor system. Simple fault tree models are evolved for SFSP and for Transportation Accident Mode (TAM) for both road and rail. Fault tree quantification and risk assessment are done to each of these models. All necessary data for SFSP are taken mostly from Reactor Safety Study, (1975). Similarly, the data for rail TAM are taken from Annual Statistical Statements, (1987-8) and that for road TAM from Special Issue on Motor Vehicle Accident Statistics in India, (1986). Simulation method is used wherever necessary. Risk is also estimated for normal/accident free transport

Fuel cycle and quality control

International Nuclear Information System (INIS)

Stoll, W.

1979-01-01

The volume of the fuel cycle is described in its economic importance and its through put, as it is envisaged for the Federal Republic of Germany. Definitions are given for quality continuing usefulness of an object and translated into quality criteria. Requirements on performance of fuel elements are defined. The way in which experimental results are translated into mass production of fuel rods, is described. The economic potential for further quality effort is derived. Future ways of development for quality control organisation and structure are outlined. (Auth.)

French experience in research reactor fuel transportation

International Nuclear Information System (INIS)

Raisonnier, Daniele

1996-01-01

Since 1963 Transnucleaire has safely performed a large number of national and international transports of radioactive material. Transnucleaire has also designed and supplied suitable packaging for all types of nuclear fuel cycle radioactive material from front-end and back-end products and for power or for research reactors. Transportation of spent fuel from power reactors are made on a regular and industrial basis, but this is not yet the case for the transport of spent fuel coming from research reactors. Each shipment is a permanent challenge and requires a reactive organization dealing with all the transportation issues. This presentation will explain the choices made by Transnucleaire and its associates to provide and optimize the corresponding services while remaining in full compliance with the applicable regulations and customer requirements. (author)

Irradiated nuclear fuel transport from Japan to Europe

International Nuclear Information System (INIS)

Kavanagh, M.T.; Shimoyama, S.

1976-01-01

Irradiated nuclear fuel has been transported from Japan to Europe since 1969, although U.K. experience goes back almost two decades. Both magnox and oxide fuel have been transported, and the technical requirements associated with each type of fuel are outlined. The specialized ships used by British Nuclear Fuels Limited (BNFL) for this transport are described, as well as the ships being developed for future use in the Japan trade. The ship requirements are related to the regulatory position both in the United Kingdom and internationally, and the Japanese regulatory requirements are described. Finally, specific operational experience of a Japanese reactor operator is described

Spent fuels transportation coming from Australia; Transport de combustible use en provenance d'Australie

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

Maritime transportation of spent fuels from Australia to France fits into the contract between COGEMA and ANSTO, signed in 1999. This document proposes nine information cards in this domain: HIFAR a key tool of the nuclear, scientific and technological australian program; a presentation of the ANSTO Australian Nuclear Science and Technology Organization; the HIFAR spent fuel management problem; the COGEMA expertise in favor of the research reactor spent fuel; the spent fuel reprocessing at La Hague; the transports management; the transport safety (2 cards); the regulatory framework of the transports. (A.L.B.)

Fuel-cycle greenhouse gas emissions impacts of alternative transportation fuels and advanced vehicle technologies

International Nuclear Information System (INIS)

Wang, M. Q.

1998-01-01

At an international conference on global warming, held in Kyoto, Japan, in December 1997, the United States committed to reduce its greenhouse gas (GHG) emissions by 7% over its 1990 level by the year 2012. To help achieve that goal, transportation GHG emissions need to be reduced. Using Argonne's fuel-cycle model, I estimated GHG emissions reduction potentials of various near- and long-term transportation technologies. The estimated per-mile GHG emissions results show that alternative transportation fuels and advanced vehicle technologies can help significantly reduce transportation GHG emissions. Of the near-term technologies evaluated in this study, electric vehicles; hybrid electric vehicles; compression-ignition, direct-injection vehicles; and E85 flexible fuel vehicles can reduce fuel-cycle GHG emissions by more than 25%, on the fuel-cycle basis. Electric vehicles powered by electricity generated primarily from nuclear and renewable sources can reduce GHG emissions by 80%. Other alternative fuels, such as compressed natural gas and liquefied petroleum gas, offer limited, but positive, GHG emission reduction benefits. Among the long-term technologies evaluated in this study, conventional spark ignition and compression ignition engines powered by alternative fuels and gasoline- and diesel-powered advanced vehicles can reduce GHG emissions by 10% to 30%. Ethanol dedicated vehicles, electric vehicles, hybrid electric vehicles, and fuel-cell vehicles can reduce GHG emissions by over 40%. Spark ignition engines and fuel-cell vehicles powered by cellulosic ethanol and solar hydrogen (for fuel-cell vehicles only) can reduce GHG emissions by over 80%. In conclusion, both near- and long-term alternative fuels and advanced transportation technologies can play a role in reducing the United States GHG emissions

Fuel-cycle greenhouse gas emissions impacts of alternative transportation fuels and advanced vehicle technologies.

Energy Technology Data Exchange (ETDEWEB)

Wang, M. Q.

1998-12-16

At an international conference on global warming, held in Kyoto, Japan, in December 1997, the United States committed to reduce its greenhouse gas (GHG) emissions by 7% over its 1990 level by the year 2012. To help achieve that goal, transportation GHG emissions need to be reduced. Using Argonne's fuel-cycle model, I estimated GHG emissions reduction potentials of various near- and long-term transportation technologies. The estimated per-mile GHG emissions results show that alternative transportation fuels and advanced vehicle technologies can help significantly reduce transportation GHG emissions. Of the near-term technologies evaluated in this study, electric vehicles; hybrid electric vehicles; compression-ignition, direct-injection vehicles; and E85 flexible fuel vehicles can reduce fuel-cycle GHG emissions by more than 25%, on the fuel-cycle basis. Electric vehicles powered by electricity generated primarily from nuclear and renewable sources can reduce GHG emissions by 80%. Other alternative fuels, such as compressed natural gas and liquefied petroleum gas, offer limited, but positive, GHG emission reduction benefits. Among the long-term technologies evaluated in this study, conventional spark ignition and compression ignition engines powered by alternative fuels and gasoline- and diesel-powered advanced vehicles can reduce GHG emissions by 10% to 30%. Ethanol dedicated vehicles, electric vehicles, hybrid electric vehicles, and fuel-cell vehicles can reduce GHG emissions by over 40%. Spark ignition engines and fuel-cell vehicles powered by cellulosic ethanol and solar hydrogen (for fuel-cell vehicles only) can reduce GHG emissions by over 80%. In conclusion, both near- and long-term alternative fuels and advanced transportation technologies can play a role in reducing the United States GHG emissions.

Summary of the transportation of spent fuel attitude survey

International Nuclear Information System (INIS)

Roop, E.; Price, D.L.; Paquet, V.L.

1992-01-01

The proposed repository at Yucca Mountain, Nevada will increase highway and railway transportation of spent fuel and high level nuclear wastes. The purpose of the survey was to determine the attitudes and differences in attitudes of important actors in the transportation of spent fuel. The three major areas of investigation were 1) perceived risks associated with the transportation of spent fuel, 2) confidence in the government and others responsible for transporting spent fuel, and 3) certain transportation requirements. Response was 34.3% of the original mailing and included: 193 safety personnel, 141 employees of the nuclear industry, 260 government employees, 34 native Americans, and 9 employees of environmental organizations. This paper summarizes overall and group attitudes and opinions for the three areas mentioned above. (author)

Development of nuclear spent fuel Maritime transportation scenario

International Nuclear Information System (INIS)

Yoo, Min; Kang, Hyun Gook

2014-01-01

Spent fuel transportation of South Korea is to be conducted through near sea because it is able to ship a large amount of the spent fuel far from the public comparing to overland transportation. The maritime transportation is expected to be increased and its risk has to be assessed. For the risk assessment, this study utilizes the probabilistic safety assessment (PSA) method and the notions of the combined event. Risk assessment of maritime transportation of spent fuel is not well developed in comparison with overland transportation. For the assessment, first, the transportation scenario should be developed and categorized. Categories are assorted into the locations, release aspects and exposure aspects. This study deals with accident that happens on voyage and concentrated on ship-ship collision. The collision accident scenario is generated with event tree analysis. The scenario will be exploited for the maritime transportation risk model which includes consequence and accident probability

Development of nuclear spent fuel Maritime transportation scenario

Energy Technology Data Exchange (ETDEWEB)

Yoo, Min; Kang, Hyun Gook [KAIST, Daejeon (Korea, Republic of)

2014-08-15

Spent fuel transportation of South Korea is to be conducted through near sea because it is able to ship a large amount of the spent fuel far from the public comparing to overland transportation. The maritime transportation is expected to be increased and its risk has to be assessed. For the risk assessment, this study utilizes the probabilistic safety assessment (PSA) method and the notions of the combined event. Risk assessment of maritime transportation of spent fuel is not well developed in comparison with overland transportation. For the assessment, first, the transportation scenario should be developed and categorized. Categories are assorted into the locations, release aspects and exposure aspects. This study deals with accident that happens on voyage and concentrated on ship-ship collision. The collision accident scenario is generated with event tree analysis. The scenario will be exploited for the maritime transportation risk model which includes consequence and accident probability.

Risk of transporting spent nuclear fuel by train

International Nuclear Information System (INIS)

Elder, H.K.

1981-12-01

This paper presents results of a study which analyzes the risk of transporting spent fuel by train. The risk assessment methodology consists of 4 basic steps: (1) a description of the system being analyzed; (2) identification of sequences of events that could lead to a release of material during transportation; (3) evaluation of the probability and consequences of each release sequence; and (4) assessment of the risk and evaluation of the results. The conclusion reached was that considering the substantial benefits derived from the fuel, the current spent fuel transportation system poses reasonably low risks

EU policies on car emissions and fuel quality. Reducing the climate impact from road transport

Energy Technology Data Exchange (ETDEWEB)

Christensen, Anne Raaum; Gulbrandsen, Lars H.

2012-07-01

Transport is the second biggest source of greenhouse gas (GHG) emissions in the EU, and contributes about one-quarter of the EU's total emissions of CO{sub 2}. Significant reductions in GHG emissions from transport are required if the EU is to achieve its long-term climate goals. This report examines the making and implementation of two of the regulations the EU has put in place to lower emissions from the transport sector: the EU's revised Fuel Quality Directive (Directive 2009/30/EC) and the cars/CO{sub 2} regulation (Regulation (EC) 443/2009). It was found that the relevance of various theories of policymaking in the EU varies with different policy phases. A policy-network understanding of EU policymaking is strengthened when assessing the policy-initiation phase. The Commission played a key role in this phase and drafted legislation in close collaboration with the car and oil refining industries. An intergovernmentalist understanding of EU policy-making is strengthened when assessing the decision-making phase. In this phase, member states defending the interests of their domestic industries had strong influence, but the European Parliament played an important role in this phase too, employing its power in the co-decision procedure. Finally, the implementation process is best understood as a multi-level governance process in which several actors and institutions - notably the Commission, member states, industries, and NGOs - influenced the process. (Author)

Alternative Fuels Data Center: Biodiesel Truck Transports Capitol Christmas

Science.gov (United States)

Tree Biodiesel Truck Transports Capitol Christmas Tree to someone by E-mail Share Alternative Fuels Data Center: Biodiesel Truck Transports Capitol Christmas Tree on Facebook Tweet about Alternative Fuels Data Center: Biodiesel Truck Transports Capitol Christmas Tree on Twitter Bookmark Alternative

Quality assurance of fuel elements

International Nuclear Information System (INIS)

Hoerber, J.

1980-01-01

The quality assurance activities for reactor fuel elements are based on a quality assurance system which implies the requirements resulting from the specifications, regulations of the authorities, national standards and international rules and regulations. The quality assurance related to production of reactor fuel will be shown for PWR fuel elements in all typical fabrication steps as conversion into UO 2 -powder, pelletizing, rodmanufacture and assembling. A wide range of destructive and nondestructive techniques is applied. Quality assurance is not only verified by testing techniques but also by process monitoring by means of parameter control in production and testing procedures. (RW)

Impact of Transmutation Scenarios on Fuel Transportation

International Nuclear Information System (INIS)

Saturnin, A.; Duret, B.; Allou, A.; Jasserand, F.; Fillastre, E.; Giffard, F.X.; Chabert, C.; Caron-Charles, M.; Garzenne, C.; Laugier, F.

2015-01-01

Minor actinides transmutation scenarios have been studied in the frame of the French Sustainable Radioactive Waste Management Act of 28 June 2006. Transmutation scenarios supposed the introduction of a sodium-cooled fast reactor fleet using homogeneous or heterogeneous recycling modes for the minor actinides. Americium, neptunium and curium (MA) or americium alone (Am) can be transmuted together in a homogeneous way embedded in FR-MOX fuel or incorporated in MA or Am-Bearing radial Blankets (MABB or AmBB). MA transmutation in Accelerator Driven System has also been studied while plutonium is being recycled in SFR. Assessments and comparisons of these advanced cycles have been performed considering technical and economic criteria. Transportation needs for fresh and used transmutation fuels is one of these criteria. Transmutation fuels have specific characteristics in terms of thermal load and neutron emissions. Thermal, radiation and criticality constraints have been taken into account in this study to suggest cask concepts for routine conditions of transport, to estimate the number of assemblies to be transported in a cask and the number of annual transports. Comparison with the no transmutation option, i.e. management of uranium and plutonium in SFRs, is also presented. Regarding these matters, no high difficulties appear for assemblies with limited content of Am (homogeneous or heterogeneous recycling modes). When fuels contain curium, technical transport uncertainties increase because of the important heat release requiring dividing fresh fuels and technological innovations development (MABB and ADS). (authors)

Road transport fuels in europe: the explosion of demand for diesel fuel

International Nuclear Information System (INIS)

Bensaid, B.

2004-01-01

In the last 20 years, road transport fuel consumption has more than doubled in European countries, due to strong growth on the diesel passenger car segment and in the transport of road freight. In an economy heavily dependent on oil, European authorities are seeking to promote alternative energy solutions, such as motor fuels produced from biomass

Numerical simulation of ion transport membrane reactors: Oxygen permeation and transport and fuel conversion

KAUST Repository

Hong, Jongsup

2012-07-01

Ion transport membrane (ITM) based reactors have been suggested as a novel technology for several applications including fuel reforming and oxy-fuel combustion, which integrates air separation and fuel conversion while reducing complexity and the associated energy penalty. To utilize this technology more effectively, it is necessary to develop a better understanding of the fundamental processes of oxygen transport and fuel conversion in the immediate vicinity of the membrane. In this paper, a numerical model that spatially resolves the gas flow, transport and reactions is presented. The model incorporates detailed gas phase chemistry and transport. The model is used to express the oxygen permeation flux in terms of the oxygen concentrations at the membrane surface given data on the bulk concentration, which is necessary for cases when mass transfer limitations on the permeate side are important and for reactive flow modeling. The simulation results show the dependence of oxygen transport and fuel conversion on the geometry and flow parameters including the membrane temperature, feed and sweep gas flow, oxygen concentration in the feed and fuel concentration in the sweep gas. © 2012 Elsevier B.V.

Transportation risks in the US nuclear fuel cycle

International Nuclear Information System (INIS)

Rhoads, R.E.; Andrews, W.B.

1980-01-01

Estimated risks associated with accidental releases of materials transported for each step of the nuclear fuel cycle are presented. The risk estimates include both immediate and latent fatilities caused by releases of these materials in transportation accidents. Studies of the risk of transporting yellowcake, fresh nuclear and low level wastes from the front end of the fuel cycle have not been completed. Existing information does permit estimates of the risks to be made. The estimates presented result from the very low hazards associated with release of these materials. These estimates are consistent with the results of other studies. The results show that risks from all the fuel cycle transportation steps are low. The results also indicate that the total transportation risks associated with the nuclear fuel cycle are distributed about evenly between the fuel supply end and waste management end of the cycle. Risks in the front end of the cycle result primarily from the chemical toxicity of the materials transported. The results of the risk analysis studies for transportation of nuclear fuel cycle materials are compared with the results for the three studies that have been completed for non-nuclear systems. The risk analysis methodology used in these studies identifies the complete spectrum of potential accident consequences and estimates the probability of events producing that level of consequence. The maximum number of fatalities predicted for each material is presented. A variety of risk measures have been used because of the inherent difficulties in making risk comparisons. Examination of a number of risk measures can provide additional insights and help guard against conclusions that are dependent on the way the risk information has been developed and displayed. The results indicate that the risks from transporting these materials are all relatively low in comparison to other risks in society

The quality challenge for fuel fabrication

International Nuclear Information System (INIS)

Lannegrace, J.-P.

1990-01-01

Fuel fabrication is a key segment of the nuclear fuel cycle, since safe and economic operation of reactors is highly dependent on the quality of the fuel. Achieving and controlling quality is, therefore, of paramount importance to fuel fabricators dominating nearly every aspect of the business. The quality policy, concepts and assurance system at three French plants are outlined. The need for integrated inspection, process optimization and good employee motivation is stressed. (author)

Design of a transportation cask for irradiated CANDU fuel

International Nuclear Information System (INIS)

Nash, K.E.; Gavin, M.E.

1983-01-01

A major step in the development of a large-scale transportation system for irradiated CANDU fuel is being made by Ontario Hydro in the design and construction of a demonstration cask by 1988/89. The system being designed is based on dry transportation with the eventual fully developed system providing for dry fuel loading and unloading. Research carried out to date has demonstrated that it is possible to transport irradiated CANDU fuel in a operationally efficient and simple manner without any damage which would prejudice subsequent automated fuel handling

Spent Fuel Transportation Package Performance Study - Experimental Design Challenges

International Nuclear Information System (INIS)

Snyder, A. M.; Murphy, A. J.; Sprung, J. L.; Ammerman, D. J.; Lopez, C.

2003-01-01

Numerous studies of spent nuclear fuel transportation accident risks have been performed since the late seventies that considered shipping container design and performance. Based in part on these studies, NRC has concluded that the level of protection provided by spent nuclear fuel transportation package designs under accident conditions is adequate. [1] Furthermore, actual spent nuclear fuel transport experience showcase a safety record that is exceptional and unparalleled when compared to other hazardous materials transportation shipments. There has never been a known or suspected release of the radioactive contents from an NRC-certified spent nuclear fuel cask as a result of a transportation accident. In 1999 the United States Nuclear Regulatory Commission (NRC) initiated a study, the Package Performance Study, to demonstrate the performance of spent fuel and spent fuel packages during severe transportation accidents. NRC is not studying or testing its current regulations, a s the rigorous regulatory accident conditions specified in 10 CFR Part 71 are adequate to ensure safe packaging and use. As part of this study, NRC currently plans on using detailed modeling followed by experimental testing to increase public confidence in the safety of spent nuclear fuel shipments. One of the aspects of this confirmatory research study is the commitment to solicit and consider public comment during the scoping phase and experimental design planning phase of this research

Transport of MOX fuel from Europe to Japan; Transport de combustible mox d' Europe vers le Japon

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

The MOX fuel transports from Europe to Japan represent a main part in the implementing of the Japan nuclear program. They complement the 160 transports of spent fuels realized from Japan to Europe and the vitrified residues return from France to Japan. In this framework the document presents the MOX fuel, the use of the MOX fuel in reactor, the proliferation risks, the MOX fuel transport to Japan, the public health, the transport regulations, the safety and the civil liability. (A.L.B.)

Sensor system for fuel transport vehicle

Science.gov (United States)

Earl, Dennis Duncan; McIntyre, Timothy J.; West, David L.

2016-03-22

An exemplary sensor system for a fuel transport vehicle can comprise a fuel marker sensor positioned between a fuel storage chamber of the vehicle and an access valve for the fuel storage chamber of the vehicle. The fuel marker sensor can be configured to measure one or more characteristics of one or more fuel markers present in the fuel adjacent the sensor, such as when the marked fuel is unloaded at a retail station. The one or more characteristics can comprise concentration and/or identity of the one or more fuel markers in the fuel. Based on the measured characteristics of the one or more fuel markers, the sensor system can identify the fuel and/or can determine whether the fuel has been adulterated after the marked fuel was last measured, such as when the marked fuel was loaded into the vehicle.

Studies of Lanthanide Transport in Metallic Fuel

Energy Technology Data Exchange (ETDEWEB)

Zhang, Jinsuo; Taylor, Christopher

2018-04-02

Metallic nuclear fuels were tested in fast reactor programs and performed well. However, metallic fuels have shown the phenomenon of FCCI that are due to deleterious reactions between lanthanide fission products and cladding material. As the burnup is increased, lanthanide fission products that contact with the cladding could react with cladding constituents such as iron and chrome. These reactions produce higher-melting intermetallic compounds and low-melting alloys, and weaken the mechanical integrity. The lanthanide interaction with clad in metallic fuels is recognized as a long-term, high-burnup cause of the clad failures. Therefore, one of the key concerns of using metallic fuels is the redistribution of lanthanide fission products and migration to the fuel surface. It is believed that lanthanide migration is in part due to the thermal gradient between the center and the fuel-cladding interface, but also largely in part due to the low solubility of lanthanides within the uranium-based metal fuel. PIE of EBR-II fuels shows that lanthanides precipitate directly and do not dissolve to an appreciable extent in the fuel matrix. Based on the PIE data from EBR-II, a recent study recommended a so-called “liquid-like” transport mechanism for lanthanides and certain other species. The liquid-like transport model readily accounts for redistribution of Ln, noble metal fission products, and cladding components in the fuel matrix. According to the novel mechanism, fission products can transport as solutes in liquid metals, such as liquid cesium or liquid cesium–sodium, and on pore surfaces and fracture surfaces for metals near their melting temperatures. Transport in such solutions is expected to be much more rapid than solid-state diffusion. The mechanism could explain the Ln migration to the fuel slug peripheral surface and their deposition with a sludge-like form. Lanthanides have high solubility in liquid cesium but have low solubility in liquid sodium. As a

Spent-fuel transportation - a success story

International Nuclear Information System (INIS)

Gertz, C.P.; Schoonen, D.H.; Wakeman, B.H.

1986-01-01

Spent nuclear fuel research and development (R and D) demonstrations and associated transportation activities are being performed as a part of the storage cask performance testing programs at the Idaho National Engineering Laboratory (INEL). These spent-fuel programs support the Nuclear Waste Policy Act (NWPA) and US Department of Energy (DOE) objectives for cooperative demonstrations with the utilities, testing at federal sites, and alternatives for viable transportation systems. A cooperative demonstration program with the private sector to develop dry storage technologies that the US Nuclear Regulatory Commission (NRC) can generically approve is in place as well as cost-shared dry storage R and D program at a federal facility to collect the necessary licensing data. In addition to the accomplishments in the cask performance and testing demonstrations, the long-distance transportation of a large number of spent-fuel assemblies is considered a success story. The evaluation and implementation of applicable requirements, industry perspective, and extensive planning all contributed to this achievement

Methanol commercial aviation fuel

International Nuclear Information System (INIS)

Price, R.O.

1992-01-01

Southern California's heavy reliance on petroleum-fueled transportation has resulted in significant air pollution problems within the south Coast Air Basin (Basin) which stem directly from this near total dependence on fossil fuels. To deal with this pressing issue, recently enacted state legislation has proposed mandatory introduction of clean alternative fuels into ground transportation fleets operating within this area. The commercial air transportation sector, however, also exerts a significant impact on regional air quality which may exceed emission gains achieved in the ground transportation sector. This paper addresses the potential, through the implementation of methanol as a commercial aviation fuel, to improve regional air quality within the Basin and the need to flight test and demonstrate methanol as an environmentally preferable fuel in aircraft turbine engines

Agricultural transportation fuels

International Nuclear Information System (INIS)

Anon.

1993-01-01

The recommendations on the title subject are focused on the question whether advantages and disadvantages of agricultural fuels compared to fossil fuels justify the Dutch policy promotion of the use of agricultural products as basic materials for agricultural fuels. Attention is paid to energetic, environmental and economical aspects of both fuel types. Four options to apply agricultural transportation fuels are discussed: (1) 10% bio-ethanol in euro-unleaded gasoline for engines of passenger cars, equipped with a three-way catalyst; (2) the substitution of 15% methyl tertiair butyl ether (MTBE) by ethyl tertiair butyl ether (ETBE) as a substituent for lead in unleaded super plus gasoline (Sp 98) for engines of passenger cars, equipped with a three-way catalyst; (3) 50% KME (rapeseed oil ester) in low-sulfur diesel (0.05%S D) for engines of vans without a catalyst; and (4) the substitution of 0.05% S D by bio-ethanol or KME for buses with fuel-adjusted engines, equipped with a catalyst. Also the substitution by liquefied petroleum gas (LPG), compressed natural gas (CNG) or E 95 was investigated in option four. Each of the options investigated can contribute to a reduction of the use of fossil energy and the environmental effects of the use of fossil fuels, although some environmental effects from agricultural fuels must be taken into consideration. It is recommended to seriously pay attention to the promotion of agricultural fuels, not only in the Netherlands, but also in an international context. Policy instruments to be used in the stimulation of the use of such fuels are the existing European Community subsidies on fallow lands, exemption of the European Community energy levy, and the use of tax differentiation. Large-scale demonstration projects must be started to quantify hazardous emissions and to solve still existing technical problems. 8 figs., 3 tabs., refs., 4 appendices

Considerations for the transportation of spent fuel

International Nuclear Information System (INIS)

Jefferson, R.M.

1984-01-01

In our society today the transportation of radioactive materials, and most particularly spent reactor fuel, is surrounded by considerable emotion and a wealth of information, good and bad. The transportation of these materials is viewed as unique and distinct from the transportation of other hazardous materials and as a particularly vulnerable component of the nuclear power activities of this nation. Added to this is the concept, widely held, that almost everyone is an expert on the transportation of radioactive materials. One significant contribution to this level of emotion is the notion that all roads (rail and highway), on which these goods will be transported, somehow traverse everyone's backyard. The issue of the transportation of spent fuel has thus become a political battleground. Perhaps this should not be surprising since it has all of the right characteristics for such politicization in that it is pervasive, emotional, and visible. In order that those involved in the discussion of this activity might be able to reach some rational conclusions, this paper offers some background information which might be useful to a broad range of individuals in developing their own perspectives. The intent is to address the safety of transporting spent fuel from a technical standpoint without the emotional content which is frequently a part of this argument

Classification of transportation packaging and dry spent fuel storage system components according to importance to safety

International Nuclear Information System (INIS)

McConnell, J.W., Jr; Ayers, A.L. Jr; Tyacke, M.J.

1996-02-01

This report provides a graded approach for classification of components used in transportation packaging and dry spent fuel storage systems. This approach provides a method for identifying, the classification of components according to importance to safety within transportation packagings and dry spent fuel storage systems. Record retention requirements are discussed to identify the documentation necessary to validate that the individual components were fabricated in accordance with their assigned classification. A review of the existing regulations pertaining to transportation packagings and dry storage systems was performed to identify current requirements The general types of transportation packagings and dry storage systems were identified. Discussions were held with suppliers and fabricators of packagings and storage systems to determine current practices. The methodology used in this report is based on Regulatory Guide 7.10, Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactive Material. This report also includes a list of generic components for each of the general types of transportation packagings and spent fuel storage systems. The safety importance of each component is discussed, and a classification category is assigned

Integrated risk assessment for spent fuel transportation using developed software

International Nuclear Information System (INIS)

Yun, Mi Rae; Christian, Robby; Kim, Bo Gyung; Almomani, Belal; Ham, Jae Hyun; Kang, Gook Hyun; Lee, Sang hoon

2016-01-01

As on-site spent fuel storage meets limitation of their capacity, spent fuel need to be transported to other place. In this research, risk of two ways of transportation method, maritime transportation and on-site transportation, and interim storage facility were analyzed. Easier and integrated risk assessment for spent fuel transportation will be possible by applying this software. Risk assessment for spent fuel transportation has not been researched and this work showed a case for analysis. By using this analysis method and developed software, regulators can get some insights for spent fuel transportation. For example, they can restrict specific region for preventing ocean accident and also they can arrange spend fuel in interim storage facility avoiding most risky region which have high risk from aircraft engine shaft. Finally, they can apply soft material on the floor for specific stage for on-site transportation. In this software, because we targeted Korea, we need to use Korean reference data. However, there were few Korean reference data. Especially, there was no food chain data for Korean ocean. In MARINRAD, they used steady state food chain model, but it is far from reality. Therefore, to get Korean realistic reference data, dynamic food chain model for Korean ocean need to be developed

Integrated risk assessment for spent fuel transportation using developed software

Energy Technology Data Exchange (ETDEWEB)

Yun, Mi Rae; Christian, Robby; Kim, Bo Gyung; Almomani, Belal; Ham, Jae Hyun; Kang, Gook Hyun [KAIST, Daejeon (Korea, Republic of); Lee, Sang hoon [Keimyung University, Daegu (Korea, Republic of)

2016-05-15

As on-site spent fuel storage meets limitation of their capacity, spent fuel need to be transported to other place. In this research, risk of two ways of transportation method, maritime transportation and on-site transportation, and interim storage facility were analyzed. Easier and integrated risk assessment for spent fuel transportation will be possible by applying this software. Risk assessment for spent fuel transportation has not been researched and this work showed a case for analysis. By using this analysis method and developed software, regulators can get some insights for spent fuel transportation. For example, they can restrict specific region for preventing ocean accident and also they can arrange spend fuel in interim storage facility avoiding most risky region which have high risk from aircraft engine shaft. Finally, they can apply soft material on the floor for specific stage for on-site transportation. In this software, because we targeted Korea, we need to use Korean reference data. However, there were few Korean reference data. Especially, there was no food chain data for Korean ocean. In MARINRAD, they used steady state food chain model, but it is far from reality. Therefore, to get Korean realistic reference data, dynamic food chain model for Korean ocean need to be developed.

Determination of prerequisites for the estimation of transportation cost of spent fuels

International Nuclear Information System (INIS)

Choi, Heui Joo; Lee, Jong Youl; Kim, Seong Ki; Cha, Jeong Hoon; Choi, Jong Won

2007-10-01

The cost for the spent fuel management includes the costs for the interim storage, the transportation, and the permanent disposal of the spent fuels. The scope of this report is limited to the cost for the spent fuel transportation. KAERI is developing a cost estimation method for the spent fuel transportation through a joint study with the French AREVA TN. Several prerequisites should be fixed in order to estimate the cost for the spent fuel transportation properly. In this report we produced them considering the Korean current status on the management of spent fuels. The representative characteristics of a spent fuel generated from the six nuclear reactors at the YG site were determined. Total 7,200 tons of spent fuels are projected with the lifespan of 60 years. As the transportation mode, sea transportation and road transportation is recommended considering the location of the YG site and the hypothetical Centralized Interim Storage Facility (CISF) and Final Repository (FR). The sea route and transportation time were analyzed by using a sea distance analysis program which the NORI (National Oceanographic Research Institute) supplies on a web. Based on the results of the analysis, the shipping rates were determined. The regulations related to the spent fuel transportation were reviewed. The characteristics of the transportation vessel and a trailer were suggested. The handling and transportation systems at the YG site, Centralized Interim Storage Facility, and the Final Repository were described in detail for the purpose of the cost estimation of the spent fuel transportation. From the detail description the major components of the transportation system were determined for the conceptual design. It is believed that the conceptual design of the transportation system developed in this report will be used for the analysis of transportation logistics and the cost estimation of spent fuels

Effects of alternative-fuel vehicles on air quality in Ontario, Canada

International Nuclear Information System (INIS)

Kantor, I.; Fowler, M.; Hajimiragha, A.; Canizares, C.; Elkamel, A.

2009-01-01

The economies of the developed world are increasingly including green technologies and processes that consider social, environmental and economic consequences. Hybrid electric vehicles and other fuel-efficient vehicle types can supply consumers with vehicles that decrease their ecological footprint and reduce the cost of fuel. However, one of the societal concerns often overlooked is the impact of alternative-fuel vehicle usage on the air quality in the urban environment. This paper presented a study that assessed the impact on air quality stemming from the operation of alternative fuel vehicles in urban environments. The study specifically focused on the province-wide emissions in Ontario and urban air pollution in the city of Toronto. The paper considered the life-cycle impacts of using alternative fuels for transportation purposes in terms of six major stressors for climate change, acidification and urban air quality. The two types of vehicles that were studied were plug-in hybrid electric vehicles (PHEVs) and fuel cell vehicles. Modeling of the penetration rates for both types of vehicles was completed based on the maximum capacity of the electrical grid including planned improvements. The scope of the study and discussion of health effects was first presented followed by data gathering and usage, methodology, results of supportable penetration and vehicle growth, and pollution abatement results. It was concluded that fuel cell vehicles have an advantage over, or near-equality with, PHEVs in almost every aspect of their emissions. 13 refs., 2 tabs., 10 figs

Transport of nuclear used fuel and waste materials

Energy Technology Data Exchange (ETDEWEB)

Neau, H.J. [World Nuclear Transport Institute, London (United Kingdom)

2015-07-01

20 millions consignments of radioactive materials are routinely transported annually on public roads, railways and ships. 5% of these are nuclear fuel cycle related. International Atomic Energy Agency Regulations have been in force since 1961. The sector has an excellent safety record spanning over 50 years. Back end transport covers the operations concerned with spent fuel that leaves reactors and wastes. Since 1971, there have been 70,000 shipments of used fuel (i.e. over 80,000 tonnes) with no damage to property or person. The excellent safety record spanning over 50 years praised every year by the General Conference of the International Atomic Energy Agency. More than 200 sea voyages over a distance of more than 8 million kilometres of transport of used fuel or high-level wastes.

Regulatory viewpoint on nuclear fuel quality assurance

International Nuclear Information System (INIS)

Tripp, L.E.

1976-01-01

Considerations of the importance of fuel quality and performance to nuclear safety, ''as low reasonably achievable'' release of radioactive materials in reactor effluents, and past fuel performance problems demonstrate the need for strong regulatory input, review and inspection of nuclear fuel quality assurance programs at all levels. Such a regulatory program is being applied in the United States of America by the US Nuclear Regulatory Commission. Quality assurance requirements are contained within government regulations. Guidance on acceptable methods of implementing portions of the quality assurance program is contained within Regulatory Guides and other NRC documents. Fuel supplier quality assurance program descriptions are reviewed as a part of the reactor licensing process. Inspections of reactor licensee control of their fuel vendors as well as direct inspections of fuel vendor quality assurance programs are conducted on a regularly scheduled basis. (author)

Environmental economics of lignin derived transport fuels

OpenAIRE

Obydenkova, SV; Kouris, P Panagiotis; Hensen, EJM Emiel; Heeres, Hero J; Boot, MD Michael

2017-01-01

This paper explores the environmental and economic aspects of fast pyrolytic conversion of lignin, obtained from 2G ethanol plants, to transport fuels for both the marine and automotive markets. Various scenarios are explored, pertaining to aggregation of lignin from several sites, alternative energy carries to replace lignin, transport modalities, and allocation methodology. The results highlight two critical factors that ultimately determine the economic and/or environmental fuel viability....

Transport of MOX fuel from Europe to Japan; Transport de combustible mox d' Europe vers le Japon

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

The MOX fuel transports from Europe to Japan represent a main part in the implementing of the Japan nuclear program. They complement the 160 transports of spent fuels realized from Japan to Europe and the vitrified residues return from France to Japan. In this framework the document presents the MOX fuel, the use of the MOX fuel in reactor, the proliferation risks, the MOX fuel transport to Japan, the public health, the transport regulations, the safety and the civil liability. (A.L.B.)

Intermediate review on the transportation of spent fuel assemblies

International Nuclear Information System (INIS)

2000-10-01

container if contamination is probable according to the situation in France, and the accompaniment of the transportation by HSK in addition to the accompaniment by a radioactivity protection specialist from the Paul Scherrer Institute). Another measure will be reduced (quality of the transport documentation which is to be transmitted to HSK). On the basis of data measured in Switzerland, it was established that railway staff are subjected to no noticeable radiological exposition. From the point of view of protection against radioactivity, it should therefore be possible to reduce complementary radiation protection measures. These measures, however, also serve to assure confidence. For this purpose and in accordance with the Federal Railways, HSK has decided to maintain contamination checking at the Swiss border for foreign transportation as well as continuing accompaniment by a radioactivity protection specialist, including the measurement of the radiation doses incurred by staff, of the spent fuel transports on Swiss territory. The anthropogammametric measurements are no longer required, but the possibility to undergo such measurements is kept open for the railway staff participating to the transports. The new stringency with which the transport of spent fuel is carried out must not be relaxed. The good results gained up to now have still to be confirmed. Only one transport was carried out from the Leibstadt nuclear plant and none as yet from Muehleberg. No transportation was carried out to the BNFL reprocessing facility in England. In the future there will be also spent fuel transports to the central storage facility ZWILAG in Wuerenlingen. These examples show that much experience has still to be gained before decisions concerning the reduction of the other measures can be taken on a sound basis. HSK will carry out to a new analysis of the situation in due course

Nuclear fuel management via fuel quality factor averaging

International Nuclear Information System (INIS)

Mingle, J.O.

1978-01-01

The numerical procedure of prime number averaging is applied to the fuel quality factor distribution of once and twice-burned fuel in order to evolve a fuel management scheme. The resulting fuel shuffling arrangement produces a near optimal flat power profile both under beginning-of-life and end-of-life conditions. The procedure is easily applied requiring only the solution of linear algebraic equations. (author)

Safety evaluation on MOX new fuel at marine transport

International Nuclear Information System (INIS)

Tsumune, Daisuke; Ito, Chihiro; Saegusa, Toshiari; Maruyama, Koki

2000-01-01

In the Central Research Institute of Electric Power Industry, in order to confirm effects of MOX new fuel on the public are as small as possible even when its marine transport goes down, some exposed radiation dose has previously conducted on imaginary shipwreck of marine transport on used nuclear fuel, plutonium dioxide, and high level return glass solid. Under a base of such informations, some investigations on safety on marine transport of the MOX new fuel was conducted. On September, 1999, five transport vessels of the MOX new fuel was at first transported on marine. The value of five times of estimated exposed radiation dose (max. 8.1 x 10 -8 mSv/y) corresponds to an evaluation result assumed by shipwreck in marine transport this time. As a result, it was found that the exposed radiation dose estimated on this case would be sufficiently less than an effective dose equivalent limit (1 mSv/y) of public exposure according to the recommendation of ICRP in both coastal and oceanic areas. (G.K.)

Classification of transportation packaging and dry spent fuel storage system components according to importance to safety

International Nuclear Information System (INIS)

Tyacke, M.J.; McConnell, J.W. Jr.; Ayers, A.L. Jr.; O'Connor, S.C.; Jankovich, J.P.

1996-01-01

The Idaho National Engineering Laboratory prepared a technical report for the Office of Nuclear Material Safety and Safeguards of the US Nuclear Regulatory Commission, entitled Classification of Transportation Packaging and Dry Spent Fuel Storage System Components According to Importance to Safety, NUREG/CR-6407. This paper provides the results of that report. It also presents the graded approach for classification of components used in transportation packagings and dry spent fuel storage systems. This approach provides a method for identifying the classification of components according to importance to safety within transportation packagings and dry spent fuel storage systems. Record retention requirements are discussed to identify the documentation necessary to validate that the individual components were fabricated in accordance with their assigned classification. A review of the existing regulations pertaining to transportation packagings and dry storage systems was performed to identify current requirements. The general types of transportation packagings and dry storage systems are identified. The methodology used in this paper is based on Regulatory Guide 7.10, Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactive Material. This paper also includes a list of generic components for each of the general types of transportation packagings and spent fuel storage systems, with a classification category assigned to each component. Several examples concerning the safety importance of components are presented

Transport phenomena in fuel cells : from microscale to macroscale

Energy Technology Data Exchange (ETDEWEB)

Djilali, N. [Victoria Univ., BC (Canada). Dept. of Mechanical Engineering]|[Victoria Univ., BC (Canada). Inst. for Integrated Energy Systems

2006-07-01

Proton Exchange Membrane (PEM) fuel cells rely on an array of thermofluid transport processes for the regulated supply of reactant gases and the removal of by-product heat and water. Flows are characterized by a broad range of length and time scales that take place in conjunction with reaction kinetics in a variety of regimes and structures. This paper examined some of the challenges related to computational fluid dynamics (CFD) modelling of PEM fuel cell transport phenomena. An overview of the main features, components and operation of PEM fuel cells was followed by a discussion of the various strategies used for component modelling of the electrolyte membrane; the gas diffusion layer; microporous layer; and flow channels. A review of integrated CFD models for PEM fuel cells included the coupling of electrochemical thermal and fluid transport with 3-D unit cell simulations; air-breathing micro-structured fuel cells; and stack level modelling. Physical models for modelling of transport at the micro-scale were also discussed. Results of the review indicated that the treatment of electrochemical reactions in a PEM fuel cell currently combines classical reaction kinetics with solutions procedures to resolve charged species transport, which may lead to thermodynamically inconsistent solutions for more complex systems. Proper representation of the surface coverage of all the chemical species at all reaction sites is needed, and secondary reactions such as platinum (Pt) dissolution and oxidation must be accounted for in order to model and understand degradation mechanisms in fuel cells. While progress has been made in CFD-based modelling of fuel cells, functional and predictive capabilities remain a challenge because of fundamental modelling and material characterization deficiencies in ionic and water transport in polymer membranes; 2-phase transport in porous gas diffusion electrodes and gas flow channels; inadequate macroscopic modelling and resolution of catalyst

Regulation on the transport of nuclear fuel materials by vehicles

International Nuclear Information System (INIS)

1984-01-01

The regulations applying to the transport of nuclear fuel materials by vehicles, mentioned in the law for the regulations of nuclear source materials, nuclear fuel materials and reactors. The transport is for outside of the factories and the site of enterprises by such modes of transport as rail, trucks, etc. Covered are the following: definitions of terms, places of fuel materials handling, loading methods, limitations on mix loading with other cargo, radiation dose rates concerning the containers and the vehicles, transport indexes, signs and indications, limitations on train linkage during transport by rail, security guards, transport of empty containers, etc. together with ordinary rail cargo and so on. (Mori, K.)

Fuel cell development for transportation: Catalyst development

Energy Technology Data Exchange (ETDEWEB)

Doddapaneni, N. [Sandia National Lab., Albuquerque, NM (United States)

1996-04-01

Fuel cells are being considered as alternate power sources for transportation and stationary applications. With proton exchange membrane (PEM) fuel cells the fuel crossover to cathodes causes severe thermal management and cell voltage drop due to oxidation of fuel at the platinized cathodes. The main goal of this project was to design, synthesize, and evaluate stable and inexpensive transition metal macrocyclic catalysts for the reduction of oxygen and be electrochemically inert towards anode fuels such as hydrogen and methanol.

World-wide French experience in research reactor fuel cycle transportation

International Nuclear Information System (INIS)

Raisonnier, D.

1997-01-01

Since 1963 Transnucleaire has safely performed a large number of national and international transports of radioactive material. Transnucleaire has also designed and supplied suitable packagings for all types of nuclear fuel cycle radioactive material from front-end and back-end products and for power or for research reactors. Transportation of the nuclear fuel material for power reactors is made on a regular and industrial basis. The transportation of material for the research reactor fuel cycle is quite different due to the small quantities involved, the categorisation of material and the numerous places of delivery world-wide. Adapted solutions exist, which require a reactive organisation dealing with all the transportation issues for LEU and HEU products as metal, oxide, fresh fuel elements, spent fuel elements including supply of necessary transport packaging and equipment. This presentation will: - explain the choices made by Transnucleaire and its associates to provide and optimise the corresponding services, - demonstrate the capability to achieve, through reliable partnership, transport operations involving new routes, specific equipment and new political constraints while respecting sophisticated safety and security regulations. (author)

Experience feedback from the transportation of Framatome fuel assemblies

International Nuclear Information System (INIS)

Robin, M.E.; Gaillard, G.; Aubin, C.

1998-01-01

Framatome, the foremost world nuclear fuel manufacturer, has for 25 years been delivering fuel elements from its three factories (Dessel, Romans, Pierrelatte) to the various sites in France and abroad (Germany, Sweden, Belgium, China, Korea, South Africa, Switzerland). During this period, Framatome has built up experience and expertise in fuel element transportation by road, rail and sea. In this filed, the range of constraints is very wide: safety and environmental protection constraints; constraints arising from the control and protection of nuclear materials, contractual and financial constraints, media watchdogs. Through the experience feedback from the transportation of FRAMATOME assemblies, this paper addresses all the phases in the transportation of fresh fuel assemblies. (authors)

Standardized, utility-DOE compatible, spent fuel storage-transport systems

International Nuclear Information System (INIS)

Smith, M.L.

1991-01-01

Virginia Power has developed and licensed a facility for dry storage of spent nuclear fuel in metal spent fuel storage casks. The modifications to the design of these casks necessary for licensing for both storage and transport of spent fuel are discussed along with the operational advantages of dual purpose storage-transport casks. Dual purpose casks can be used for storage at utility and DOE sites (MRS or repository) and for shipment between these sites with minimal spent fuel handling. The cost for a standardized system of casks that are compatible for use at both DOE and utility sites is discussed along with possible arrangements for sharing both the cost and benefits of dual purpose storage-transport casks

Modeling the highway transportation of spent fuel

International Nuclear Information System (INIS)

Harrison, I.G.

1986-01-01

There will be a substantial increase in the number of spent fuel shipments on the nation's highway system in the next thirty years. Most of the spent fuel will be moving from reactors to a spent fuel repository. This study develops two models that evaluate the risk and cost of moving the spent fuel. The Minimum Total Transport Risk Model (MTTRM) seeks an efficient solution for this problem by finding the minimum risk path through the network and sending all the spent fuel shipments over this one path. The Equilibrium Transport Risk Model (ETRM) finds an equitable solution by distributing the shipments over a number of paths in the network. This model decreases the risk along individual paths, but increases society's risk because the spent fuel shipments are traveling over more links in the network. The study finds that there is a trade off between path risk and societal risk. As path risk declines, societal risk rises. The cost of shipping also increases as the number of paths expand. The cost and risk of shipping spent fuel from ten reactors to four potential repository sites are evaluated using the MTTRM. The temporary monitored retrievable storage (MRS) facility in Tennessee is found to be the minimum cost and minimum risk solution. When direct shipment to the permanent sites is considered, Deaf Smith, Texas is the least cost and least incident free transport risk location. Yucca Mountain, Nevada is the least risk location when the focus is placed on the potential consequences of an accident

Transportation of spent fuel from light water reactors

International Nuclear Information System (INIS)

Bernard, H.

1993-01-01

The French 'Compagnie Generale des Matieres Nucleaires' - COGEMA - is involved in the whole nuclear fuel cycle about 20 years. Among the different parts of the cycle, the Transport of Radioactive Materials, acting as a link between the differents plants has a great importance. As nuclear material transportation is the only fuel cycle step to be performed on public grounds, the industrial task has to be performed with the utmost stringent safety criteria. COGEMA and associates is now operating a fully mature commercial activity, with some 300 spent fuel shipments per year from its reprocessing customer's reactors to the LA HAGUE plant, either by rail, road or sea. The paper will review the organization of COGEMA transportation business, the level of technology with an update of the casks used for spent fuel, and the operational experience, with a particular view of the maintenance policy. (author)

Alternative transportation fuels in the USA: government hydrogen vehicle programs

International Nuclear Information System (INIS)

Cannon, J.S.

1993-01-01

The linkage between natural gas-based transportation and hydrogen-based transportation strategies, two clean burning gaseous fuels, provides a strong policy rationale for increased government sponsorship of hydrogen vehicle research and demonstration programs. Existing federal and state government hydrogen vehicle projects are discussed in this paper: research at the NREL, alternate-fueled buses, Renewable Hydrogen for the State of Hawaii program, New York state alternative transportation fuels program, Colorado program. 9 refs

Integrated modeling for optimized regional transportation with compressed natural gas fuel

Directory of Open Access Journals (Sweden)

Hossam A. Gabbar

2016-03-01

Full Text Available Transportation represents major energy consumption where fuel is considered as a primary energy source. Recent development in the vehicle technology revealed possible economical improvements when using natural gas as a fuel source instead of traditional gasoline. There are several fuel alternatives such as electricity, which showed potential for future long-term transportation. However, the move from current situation where gasoline vehicle is dominating shows high cost compared to compressed natural gas vehicle. This paper presents modeling and simulation methodology to optimize performance of transportation based on quantitative study of the risk-based performance of regional transportation. Emission estimation method is demonstrated and used to optimize transportation strategies based on life cycle costing. Different fuel supply scenarios are synthesized and evaluated, which showed strategic use of natural gas as a fuel supply.

INTERACTION OF AIR TRANSPORTATION AND FUEL-SUPPLY COMPANIES

Directory of Open Access Journals (Sweden)

I. P. Zheleznaya

2014-01-01

Full Text Available The article describes the role of aviation fuel in the life of air transport. Fueling industry worldwide solves two main tasks - ensuring the safety and economy of air traffic. In Russia, there is one more task of airlines fuel supply. The article deals with fuel pricing taking into consideration today's realities.

An Indian perspective for transportation and storage of spent fuel

International Nuclear Information System (INIS)

Dey, P.K.

2005-01-01

The spent fuel discharged from the reactors are temporarily stored at the reactor pool. After a certain cooling time, the spent fuel is moved to the storage locations either on or off reactor site depending on the spent fuel management strategy. As India has opted for a closed fuel cycle for its nuclear energy development, reprocessing of the spent fuel, recycling of the reprocessed plutonium and uranium and disposal of the wastes from the reprocessing operations forms the spent fuel management strategy. Since the reprocessing operations are planned to match the nuclear energy programme, storage of the spent fuel in ponds are adopted prior to reprocessing. Transport of the spent fuel to the storage locations are carried out adhering to international and national guide lines. India is having 14 operating power reactors and three research reactors. The spent fuel from the two safeguarded BWRs are stored at-reactor (AR) storage pond. A separate wet storage facility away-from-reactor (AFR) has been designed, constructed and made operational since 1991 for additional fuel storage. Storage facilities are provided in ARs at other reactor locations to cater to 10 reactor-years of operation. A much lower capacity spent fuel storage is provided in reprocessing plants on the same lines of AR fuel storage design. Since the reprocessing operations are carried out on a need basis, to cater to the increased storage needs two new spent fuel storage facilities (SFSF) are being designed and constructed near the existing nuclear plant sites. India has mastered the technology for design, construction and operation of wet spent fuel storage facility meeting all the international standards Wet storage of the spent fuel is the most commonly adopted mode all over the world. Recently an alternate mode viz. dry storage has also been considered. India has designed, constructed and operated lead shielded dry storage casks and is operational at one site. A dry storage cask made of concrete

Environmental economics of lignin derived transport fuels.

Science.gov (United States)

Obydenkova, Svetlana V; Kouris, Panos D; Hensen, Emiel J M; Heeres, Hero J; Boot, Michael D

2017-11-01

This paper explores the environmental and economic aspects of fast pyrolytic conversion of lignin, obtained from 2G ethanol plants, to transport fuels for both the marine and automotive markets. Various scenarios are explored, pertaining to aggregation of lignin from several sites, alternative energy carries to replace lignin, transport modalities, and allocation methodology. The results highlight two critical factors that ultimately determine the economic and/or environmental fuel viability. The first factor, the logistics scheme, exhibited the disadvantage of the centralized approach, owing to prohibitively expensive transportation costs of the low energy-dense lignin. Life cycle analysis (LCA) displayed the second critical factor related to alternative energy carrier selection. Natural gas (NG) chosen over additional biomass boosts well-to-wheel greenhouse gas emissions (WTW GHG) to a level incompatible with the reduction targets set by the U.S. renewable fuel standard (RFS). Adversely, the process' economics revealed higher profits vs. fossil energy carrier. Copyright © 2017 The Author(s). Published by Elsevier Ltd.. All rights reserved.

Quality surveillance experience of PHWR fuel

International Nuclear Information System (INIS)

Kulkarni, P.G.; Bandyopadhyay, A.K.; Shah, B.K.

1997-01-01

Quality Surveillance activities are being carried out for PHWR fuel for over 25 years in India. A large number of fuel bundles of 19 element design have been produced and successfully irradiated. The quality surveillance practices follow the guidelines given in various Quality Assurance Codes and Guides. An independent third party surveillance is provided to cover major manufacturing and quality control operations. A system of design basis review periodic quality audit and regulatory safety review is in place. Over the years there have been modifications in the quality assurance procedures to comply with changing requirements. Also many innovative improvements have been introduced in the manufacturing procedures. Similarly quality control activities are also modified. Developments in fuel has remained a continuous activity. The paper summarizes the experience gathered over many years in this exciting process of innovation and improvement. (author)

Proceedings of the 2008 transportation technologies and fuels forum

International Nuclear Information System (INIS)

2008-01-01

As a large emitter of pollutants, the transportation industry is now seeking to develop a sustainable transportation plan for the future by developing methods of reducing emissions and improving the fuel efficiency of vehicles. This forum discussed recent innovations in vehicle transportation technologies. Industry leaders, government representatives, and researchers discussed methods of reducing greenhouse gases (GHGs) and air pollution in the transportation sector. Advanced combustion technologies were outlined, and recent developments in hybrid electric-powered vehicles were discussed. Research related to fuel cells, hydrogen fuels and biofuels was presented. The impacts of polluting vehicles on public health were also discussed. The forum was divided into the following 5 sessions: (1) setting the scene, (2) future fuels, (3) emissions, (4) EVs now, and (5) the road to the future. The sessions were followed by a panel on technology roadmaps. The forum featured 14 presentations, of which 4 have been catalogued separately for inclusion in this database. tabs., figs.

Drop analysis for structural integrity evaluation of KJRR fuel transport container

International Nuclear Information System (INIS)

Yang, Yun Young; Lim, Jong Min; Choi, Woo Seok; Lee, Ju Chan

2016-01-01

A fuel transport container for KiJang Research Reactor(KJRR) has been developed to transport fresh fuel assemblies and fission molly targets which are used for a research reactor built in Kijang. The KJRR fuel transport container is a type-A(F) container, which is defined in domestic and foreign regulations of a radioactive substance container. According to Nuclear Safety and Security Commission's notification, the container should meet the accident conditions defined in IAEA safety Standard Series, US NRC and etc. In this study, a structural integrity of the KJRR fuel transport container is evaluated by conducting computational analyses of 9-meter free drop and 1 meter puncture. It is confirmed that structural integrity of the KJRR fuel transport container can be maintained in the transportation accident condition. Hereafter, when the test model is produced, a safety test will be conducted and its result will be compared with the result of drop and puncture analyses.

Numerical simulation of ion transport membrane reactors: Oxygen permeation and transport and fuel conversion

KAUST Repository

Hong, Jongsup; Kirchen, Patrick; Ghoniem, Ahmed F.

2012-01-01

Ion transport membrane (ITM) based reactors have been suggested as a novel technology for several applications including fuel reforming and oxy-fuel combustion, which integrates air separation and fuel conversion while reducing complexity

Spent fuel transportation in the United States: commercial spent fuel shipments through December 1984

International Nuclear Information System (INIS)

1986-04-01

This report has been prepared to provide updated transportation information on light water reactor (LWR) spent fuel in the United States. Historical data are presented on the quantities of spent fuel shipped from individual reactors on an annual basis and their shipping destinations. Specifically, a tabulation is provided for each present-fuel shipment that lists utility and plant of origin, destination and number of spent-fuel assemblies shipped. For all annual shipping campaigns between 1980 and 1984, the actual numbers of spent-fuel shipments are defined. The shipments are tabulated by year, and the mode of shipment and the casks utilized in shipment are included. The data consist of the current spent-fuel inventories at each of the operating reactors as of December 31, 1984. This report presents historical data on all commercial spent-fuel transportation shipments have occurred in the United States through December 31, 1984

Power plant fuel switching and air quality in a tropical, forested environment

Science.gov (United States)

Medeiros, Adan S. S.; Calderaro, Gisele; Guimarães, Patricia C.; Magalhaes, Mateus R.; Morais, Marcos V. B.; Rafee, Sameh A. A.; Ribeiro, Igor O.; Andreoli, Rita V.; Martins, Jorge A.; Martins, Leila D.; Martin, Scot T.; Souza, Rodrigo A. F.

2017-07-01

How a changing energy matrix for electricity production affects air quality is considered for an urban region in a tropical, forested environment. Manaus, the largest city in the central Amazon Basin of Brazil, is in the process of changing its energy matrix for electricity production from fuel oil and diesel to natural gas over an approximately 10-year period, with a minor contribution by hydropower. Three scenarios of urban air quality, specifically afternoon ozone concentrations, were simulated using the Weather Research and Forecasting (WRF-Chem) model. The first scenario used fuel oil and diesel for electricity production, which was the reality in 2008. The second scenario was based on the fuel mix from 2014, the most current year for which data were available. The third scenario considered nearly complete use of natural gas for electricity production, which is the anticipated future, possibly for 2018. For each case, inventories of anthropogenic emissions were based on electricity generation, refinery operations, and transportation. Transportation and refinery operations were held constant across the three scenarios to focus on effects of power plant fuel switching in a tropical context. The simulated NOx and CO emissions for the urban region decrease by 89 and 55 %, respectively, after the complete change in the energy matrix. The results of the simulations indicate that a change to natural gas significantly decreases maximum afternoon ozone concentrations over the population center, reducing ozone by > 70 % for the most polluted days. The sensitivity of ozone concentrations to the fuel switchover is consistent with a NOx-limited regime, as expected for a tropical forest having high emissions of biogenic volatile organic compounds, high water vapor concentrations, and abundant solar radiation. There are key differences in a shifting energy matrix in a tropical, forested environment compared to other world environments. Policies favoring the burning of

Power plant fuel switching and air quality in a tropical, forested environment

Directory of Open Access Journals (Sweden)

A. S. S. Medeiros

2017-07-01

Full Text Available How a changing energy matrix for electricity production affects air quality is considered for an urban region in a tropical, forested environment. Manaus, the largest city in the central Amazon Basin of Brazil, is in the process of changing its energy matrix for electricity production from fuel oil and diesel to natural gas over an approximately 10-year period, with a minor contribution by hydropower. Three scenarios of urban air quality, specifically afternoon ozone concentrations, were simulated using the Weather Research and Forecasting (WRF-Chem model. The first scenario used fuel oil and diesel for electricity production, which was the reality in 2008. The second scenario was based on the fuel mix from 2014, the most current year for which data were available. The third scenario considered nearly complete use of natural gas for electricity production, which is the anticipated future, possibly for 2018. For each case, inventories of anthropogenic emissions were based on electricity generation, refinery operations, and transportation. Transportation and refinery operations were held constant across the three scenarios to focus on effects of power plant fuel switching in a tropical context. The simulated NOx and CO emissions for the urban region decrease by 89 and 55 %, respectively, after the complete change in the energy matrix. The results of the simulations indicate that a change to natural gas significantly decreases maximum afternoon ozone concentrations over the population center, reducing ozone by > 70 % for the most polluted days. The sensitivity of ozone concentrations to the fuel switchover is consistent with a NOx-limited regime, as expected for a tropical forest having high emissions of biogenic volatile organic compounds, high water vapor concentrations, and abundant solar radiation. There are key differences in a shifting energy matrix in a tropical, forested environment compared to other world environments. Policies

Demonstration of a transportable storage system for spent nuclear fuel

International Nuclear Information System (INIS)

Shetler, J.R.; Miller, K.R.; Jones, R.E.

1993-01-01

The purpose of this paper is to discuss the joint demonstration project between the Sacramento Municipal Utility District (SMUD) and the US Department of Energy (DOE) regarding the use of a transportable storage system for the long-term storage and subsequent transport of spent nuclear fuel. SMUD's Rancho Seco nuclear generating station was shut down permanently in June 1989. After the shutdown, SMUD began planning the decommissioning process, including the disposition of the spent nuclear fuel. Concurrently, Congress had directed the Secretary of Energy to develop a plan for the use of dual-purpose casks. Licensing and demonstrating a dual-purpose cask, or transportable storage system, would be a step toward achieving Congress's goal of demonstrating a technology that can be used to minimize the handling of spent nuclear fuel from the time the fuel is permanently removed from the reactor through to its ultimate disposal at a DOE facility. For SMUD, using a transportable storage system at the Rancho Seco Independent Spent-Fuel Storage Installation supports the goal of abandoning Rancho Seco's spent-fuel pool as decommissioning proceeds

Transport of fresh MOX fuel assemblies for the Monju initial core

International Nuclear Information System (INIS)

Kurakami, J.; Ouchi, Y.; Usami, M.

1997-01-01

Transport of fresh MOX fuel assemblies for the prototype FBR MONJU initial core started in July 1992 and ended in March 1994. As many as 205 fresh MOX fuel assemblies for an inner core, 91 assemblies for an outer core and 5 assemblies for testing) were transported in nine transport missions. The packaging for fuel assemblies, which has shielding and shock absorbing material inside, meets IAEA regulatory requirements for Type B(U) packaging including hypothetical accident conditions such as the 9 m drop test, fire test, etc. Moreover, this package design feature such advanced technologies as high performance neutron shielding material and an automatic hold-down mechanism for the fuel assemblies. Every effort was made to carry out safe transport in conjunction with the cooperation of every competent organisation. This effort includes establishment of the transport control centre, communication training, and accompanying of the radiation monitoring expert. No transport accident occurred during the transport and all the transport missions were successfully completed on schedule. (Author)

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.

Memento. Maritime transport of MOX fuels from Europe to Japan

International Nuclear Information System (INIS)

1999-07-01

The maritime transport of MOX fuels from Europe to Japan represents the last of the 3 steps of transport of the nuclear fuel reprocessing-recycling program settled between ORC (Japan), BNFL (UK) and Cogema (France). This document summarizes the different aspects of this program: the companies concerned, the physical protection measures, the US-Japan agreements (accompanying warship), the in-depth safety, the handling of MOX fuels (containers and ships), and the Japan MOX fuel needs. (J.S.)

Exorcising spent fuel transportation using comparative hazard assessment methods

International Nuclear Information System (INIS)

Pennington, Charles W.

2003-01-01

Spent fuel transportation has achieved an exemplary safety record over more than three decades within both the United States (U.S.) and the global community at large. Today, many groups are attempting to precipitate fear of spent fuel transportation within the general public by 'demonizing' this proven technology and by creating a highly charged environment of radiation phobia. The actions of these groups within the U.S. result from the confluence of the terrorist acts of September 11, 2001, and the acceptance by the President and Congress of the U.S. Department of Energy's (DOE) recommendation of Yucca Mountain as the repository site for the disposal of the nation's spent fuel. This paper offers a comparative hazard assessment demonstrating the relative safety of spent fuel transportation in the context of currently accepted practices within society to show that there are no 'demons' associated with spent fuel transportation. The paper provides an assessment of potential population exposures based on more than 25 years of transport cask analysis and testing under beyond-design-basis (BDB) event conditions, including missile attacks, with those from current accepted activities within society that produce high dose exposures to the general public. Over the last quarter of a century, several spent fuel cask test programs have produced data that allow calculation of potential releases and population doses resulting from a terrorist attack. The DOE has used this information to develop projected worst-case population exposures as part of the Final Environmental Impact Statement (FEIS) for the Yucca Mountain repository. The paper discusses these potential releases and population exposures. Additionally, the paper identifies current unregulated activities and practices within societies yielding population exposures that exceed significantly those that would result from such highly hypothetical and improbable events as a terrorist missile attack on a spent fuel

Exorcising spent fuel transportation using comparative hazard assessment methods

Energy Technology Data Exchange (ETDEWEB)

Pennington, Charles W. [NAC international, Norcross (United States)

2003-07-01

Spent fuel transportation has achieved an exemplary safety record over more than three decades within both the United States (U.S.) and the global community at large. Today, many groups are attempting to precipitate fear of spent fuel transportation within the general public by 'demonizing' this proven technology and by creating a highly charged environment of radiation phobia. The actions of these groups within the U.S. result from the confluence of the terrorist acts of September 11, 2001, and the acceptance by the President and Congress of the U.S. Department of Energy's (DOE) recommendation of Yucca Mountain as the repository site for the disposal of the nation's spent fuel. This paper offers a comparative hazard assessment demonstrating the relative safety of spent fuel transportation in the context of currently accepted practices within society to show that there are no 'demons' associated with spent fuel transportation. The paper provides an assessment of potential population exposures based on more than 25 years of transport cask analysis and testing under beyond-design-basis (BDB) event conditions, including missile attacks, with those from current accepted activities within society that produce high dose exposures to the general public. Over the last quarter of a century, several spent fuel cask test programs have produced data that allow calculation of potential releases and population doses resulting from a terrorist attack. The DOE has used this information to develop projected worst-case population exposures as part of the Final Environmental Impact Statement (FEIS) for the Yucca Mountain repository. The paper discusses these potential releases and population exposures. Additionally, the paper identifies current unregulated activities and practices within societies yielding population exposures that exceed significantly those that would result from such highly hypothetical and improbable events as a terrorist missile

Fuel manufacture and quality control

International Nuclear Information System (INIS)

Roepenack, H.; Raab, K.

1975-01-01

The different steps in fuel and fuel element manufacturing from the conversion of UF 6 to UO 2 to the assembling of the whole fuel element are shortly described. Each of this fabrication steps must satisfy well-defined quality criteria which are checked in certain analyses or tests. (RB) [de

Current status of sea transport of nuclear fuel materials and LLW in Japan

International Nuclear Information System (INIS)

Kitagawa, Hiroshi; Akiyama, Hideo

2000-01-01

Along with the basic policy of the nuclear fuel cycle of Japan, many fuel cycle facilities have been already constructed in Rokkasho-Mura, Aomori prefecture, such as the uranium enrichment plant, the low level waste disposal center and the receiving pool of the spent nuclear fuels for reprocessing. These facilities belong to the Japan Nuclear Fuel Limited. (JNFL). Domestic sea transport of the spent nuclear fuels (SF) has been carried out since 1977 to the Tokai Reprocessing Plant, and the first sea transport of the SF to the fuel cycle facility in Rokkasho-Mura was done in Oct, 1998 using a new exclusive ship 'Rokuei-Maru'. Sea transport of the low level radioactive wastes (LLW) has been carried out since 1992 to the Rokkasho LLW Disposal Center, and about 130,000 LLW drams were transported from the nuclear power plant sites. These sea transport have demonstrated the safety of the transport of the nuclear fuel cycle materials. It is hoped that the safe sea transport of the nuclear fuel materials will contribute to the more progress of the nuclear fuel cycle activities of Japan. (author)

Remarks on the transportation of spent fuel elements

International Nuclear Information System (INIS)

Krull, W.

1992-01-01

Information and data are provided on several aspects of the transportation of spent fuel elements. These aspects include contract, transportation, reprocessing batch size, and economical considerations. (author)

Quality assurance for breeder reactor fuel fabrication

International Nuclear Information System (INIS)

Marx, E.R.

1978-01-01

Fuel performance in the Fast Flux Test Facility (FFTF) depends on fabrication of fuel to rigorous quality standards. The quality program including Management, Procurement, Fabrication, Inspection, Records, and Audits is discussed as well as unique mixed oxide fuel inspections such as homogeneity inspection, analytical chemistry, and nondestructive fissile assay

Safety assessment of ammonia as a transport fuel

Energy Technology Data Exchange (ETDEWEB)

Duijm, N.J.; Markert, F.; Lundtang paulsen, Jette

2005-02-01

This report describes the safety study performed as part of the EU supported project 'Ammonia Cracking for Clean Electric Power Technology' The study addresses the following activities: safety of operation of the ammonia-powered vehicle under normal and accident (collision) conditions, safety of transport of ammonia to the refuelling stations and safety of the activities at the refuelling station (unloading and refuelling). Comparisons are made between the safety of using ammonia and the safety of other existing or alternative fuels. The conclusion is that the hazards in relation to ammonia need to be controlled by a combination of technical and regulatory measures. The most important requirements are: - Advanced safety systems in the vehicle - Additional technical measures and regulations are required to avoid releases in maintenance workshops and unauthorised maintenance on the fuel system - Road transport of ammonia to refuelling stations in refrigerated form - Sufficient safety zones between refuelling stations and residential or otherwise public areas. When these measures are applied, the use of ammonia as a transport fuel wouldnt cause more risks than currently used fuels (using current practice). (au)

Studies and research concerning BNFP. Nuclear spent fuel transportation studies

International Nuclear Information System (INIS)

Anderson, R.T.; Maier, J.B.

1979-11-01

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

Some UK experience and practice in the packaging and transport of irradiated fuel

International Nuclear Information System (INIS)

Edney, C.J.; Rutter, R.L.

1977-01-01

The origin and growth of irradiated fuel transport within and to the U.K. is described and the role of the organisations presently carrying out transport operations is explained. An explanation of the relevant U.K. regulations and laws affecting irradiated fuel transport and the role of the controlling body, the Department of the Environment is given. An explanation is given of the technical requirements for the transport of irradiated Magnox fuel and of the type of flask used, and the transport arrangements, both within the U.K. and to the U.K., from overseas is discussed. The technical requirements for the transport of C.A.G.R. fuel are outlined and the flask and transport arrangements are discussed. The transport requirements of oxide fuel from water reactors is outlined and the flask and shipping arrangements under which this fuel is brought to the U.K. from overseas is explained. The shipping arrangements are explained with particular reference to current international and national requirements. The requirements of the transport of M.T.R. fuel are discussed and the flask type explained. The expected future expansion of the transport of irradiated fuel within and to the U.K. is outlined and the proposed operating methods are briefly discussed. A summary is given of the U.K. experience and the lessons to be drawn from that experience

Emissions of greenhouse gases from the use of transportation fuels and electricity

International Nuclear Information System (INIS)

DeLuchi, M.A.

1991-11-01

This report presents estimates of full fuel-cycle emissions of greenhouse gases from using transportation fuels and electricity. The data cover emissions of carbon dioxide (CO 2 ), methane, carbon monoxide, nitrous oxide, nitrogen oxides, and nonmethane organic compounds resulting from the end use of fuels, compression or liquefaction of gaseous transportation fuels, fuel distribution, fuel production, feedstock transport, feedstock recovery, manufacture of motor vehicles, maintenance of transportation systems, manufacture of materials used in major energy facilities, and changes in land use that result from using biomass-derived fuels. The results for electricity use are in grams of CO 2 -equivalent emissions per kilowatt-hour of electricity delivered to end users and cover generating plants powered by coal, oil, natural gas, methanol, biomass, and nuclear energy. The transportation analysis compares CO 2 -equivalent emissions, in grams per mile, from base-case gasoline and diesel fuel cycles with emissions from these alternative- fuel cycles: methanol from coal, natural gas, or wood; compressed or liquefied natural gas; synthetic natural gas from wood; ethanol from corn or wood; liquefied petroleum gas from oil or natural gas; hydrogen from nuclear or solar power; electricity from coal, uranium, oil, natural gas, biomass, or solar energy, used in battery-powered electric vehicles; and hydrogen and methanol used in fuel-cell vehicles

Development of a Life Cycle Inventory of Water Consumption Associated with the Production of Transportation Fuels

Energy Technology Data Exchange (ETDEWEB)

Lampert, David J. [Argonne National Lab. (ANL), Argonne, IL (United States); Cai, Hao [Argonne National Lab. (ANL), Argonne, IL (United States); Wang, Zhichao [Argonne National Lab. (ANL), Argonne, IL (United States); Keisman, Jennifer [Argonne National Lab. (ANL), Argonne, IL (United States); Wu, May [Argonne National Lab. (ANL), Argonne, IL (United States); Han, Jeongwoo [Argonne National Lab. (ANL), Argonne, IL (United States); Dunn, Jennifer [Argonne National Lab. (ANL), Argonne, IL (United States); Sullivan, John L. [Argonne National Lab. (ANL), Argonne, IL (United States); Elgowainy, Amgad [Argonne National Lab. (ANL), Argonne, IL (United States); Wang, Michael [Argonne National Lab. (ANL), Argonne, IL (United States); Keisman, Jennifer [American Association for the Advancemetn of Science (AAAS), Washington, DC (United States)

2015-10-01

The production of all forms of energy consumes water. To meet increased energy demands, it is essential to quantify the amount of water consumed in the production of different forms of energy. By analyzing the water consumed in different technologies, it is possible to identify areas for improvement in water conservation and reduce water stress in energy-producing regions. The transportation sector is a major consumer of energy in the United States. Because of the relationships between water and energy, the sustainability of transportation is tied to management of water resources. Assessment of water consumption throughout the life cycle of a fuel is necessary to understand its water resource implications. To perform a comparative life cycle assessment of transportation fuels, it is necessary first to develop an inventory of the water consumed in each process in each production supply chain. The Greenhouse Gases, Regulated Emissions, and Energy Use in Transportation (GREET) model is an analytical tool that can used to estimate the full life-cycle environmental impacts of various transportation fuel pathways from wells to wheels. GREET is currently being expanded to include water consumption as a sustainability metric. The purpose of this report was to document data sources and methodologies to estimate water consumption factors (WCF) for the various transportation fuel pathways in GREET. WCFs reflect the quantity of freshwater directly consumed per unit production for various production processes in GREET. These factors do not include consumption of precipitation or low-quality water (e.g., seawater) and reflect only water that is consumed (i.e., not returned to the source from which it was withdrawn). The data in the report can be combined with GREET to compare the life cycle water consumption for different transportation fuels.

Safety criteria for spent-fuel transport. Final report

International Nuclear Information System (INIS)

Goldmann, K.; Gekler, W.C.

1986-10-01

The focus of this study is on the question, ''Do current regulations provide reasonable assurance of safety for a transport scenario of spent fuel, as presently anticipated by the Department of Energy, under the Nuclear Waste Policy Act.'' This question has been addressed by developing a methodology for identifying the expected frequency of Accidents Which Exceed Regulatory Conditions in Severity (AWERCS) for spent fuel transport casks and then assessing the health effects resulting from that frequency. By applying the methodology to an illustrative case of road transports, it was found that the accidental release of radioactive material from impact AWERCS would make negligible contributions to health effects associated with spent fuel transports by road. It is also concluded that the current regulatory drop test requirements in 10 CFR 71.51 which form the basis for cask design and were used to establish AWERCS screening criteria for this study are adequate, and that no basis was found to conclude that cask performance under expected road accident conditions represents an undue risk to the public

Transport Studies and Modeling in PEM Fuel Cells

Energy Technology Data Exchange (ETDEWEB)

Mittelsteadt, Cortney K. [Giner, Inc., Auburndale, MA (United States); Xu, Hui [Giner, Inc., Auburndale, MA (United States); Brawn, Shelly [Giner, Inc., Auburndale, MA (United States)

2014-07-30

This project’s aim was to develop fuel cell components (i.e. membranes, gas-diffusion media (GDM), bipolar plates and flow fields) that possess specific properties (i.e. water transport and conductivity). A computational fluid dynamics model was developed to elucidate the effect of certain parameters on these specific properties. Ultimately, the model will be used to determine sensitivity of fuel cell performance to component properties to determine limiting components and to guide research. We have successfully reached our objectives and achieved most of the milestones of this project. We have designed and synthesized a variety of hydrocarbon block polymer membranes with lower equivalent weight, structure, chemistry, phase separation and process conditions. These membranes provide a broad selection with optimized water transport properties. We have also designed and constructed a variety of devices that are capable of accurately measuring the water transport properties (water uptake, water diffusivity and electro-osmatic drag) of these membranes. These transport properties are correlated to the membranes’ structures derived from X-ray and microscopy techniques to determine the structure-property relationship. We successfully integrated hydrocarbon membrane MEAs with a current distribution board (CBD) to study the impact of hydrocarbon membrane on water transport in fuel cells. We have designed and fabricated various GDM with varying substrate, diffusivity and micro-porous layers (MPL) and characterized their pore structure, tortuosity and hydrophobicity. We have derived a universal chart (MacMullin number as function of wet proofing and porosity) that can be used to characterize various GDM. The abovementioned GDMs have been evaluated in operating fuel cells; their performance is correlated to various pore structure, tortuosity and hydrophobicity of the GDM. Unfortunately, determining a universal relationship between the MacMullin number and these properties

Analyses of the transportation of spent research reactor fuel in the United States

International Nuclear Information System (INIS)

Cashwell, J.W.; Neuhauser, K.S.

1989-01-01

The Transportation Technology Center at Sandia National Laboratories has analyzed the impacts of transportation of research reactor spent fuel from US and foreign reactors for the US Department of Energy (DOE) Office of Defense Programs. This effort represents the first comprehensive analytical evaluation of the risks of transporting high-, medium-, and low-enriched uranium spent research reactor fuel by both sea and land. Two separate shipment programs have been analyzed: the shipment of research reactor spent fuel from Taiwan to the US (Fuel Movement Program), and the return of research reactor spent fuels of US origin from foreign and domestic reactors (Research Reactor Fuel Return Program). In order to perform these analyses, a comprehensive methodology for analyzing the probabilities and consequences of transportation in coastal waters and port facilities, handling at the port, and shipment by truck to reprocessing facilities was developed. The Taiwanese fuel consists of low-burnup aluminum-clad metallic uranium research reactor spent fuel; the other fuels are primarily aluminum-clad oxide fuels. The Fuel Movement Program is ongoing, while the Fuel Return Program addresses future shipments over a ten-year period. The operational aspects of the Taiwanese shipments have been uniform, but several possible shipping configurations are possible for the Fuel Return Program shipments. Comprehensive assessments, which bound the impacts of spent fuel transport, demonstrate that when shipments are made in compliance with applicable regulations, the risks for all such transport are low. For comparison with previously licensed transport activities and to provide continuity with earlier analyses, the results for shipment of 150-day-old commercial pressurized water reactor (PWR) spent fuel are presented as part of this study

Transport insurance of unirradiated nuclear fuels

International Nuclear Information System (INIS)

Matto, H.

1985-01-01

Special conditions must be taken into account in transport insurance for nuclear materials even if the nuclear risk involved is negligible, as in shipments of unirradiated nuclear fuels. The shipwreck of the 'Mont Louis' has raised a number of open points which must be solved pragmatically within the framework of transport insurance. Some proposals are outlined in the article. (orig.) [de

Gas transport in solid oxide fuel cells

CERN Document Server

He, Weidong; Dickerson, James

2014-01-01

This book provides a comprehensive overview of contemporary research and emerging measurement technologies associated with gas transport in solid oxide fuel cells. Within these pages, an introduction to the concept of gas diffusion in solid oxide fuel cells is presented. This book also discusses the history and underlying fundamental mechanisms of gas diffusion in solid oxide fuel cells, general theoretical mathematical models for gas diffusion, and traditional and advanced techniques for gas diffusivity measurement.

Technology status review and carbon abatement potential of renewable transport fuels in the UK

Energy Technology Data Exchange (ETDEWEB)

Woods, J; Bauen, A

2003-07-01

The document reviews the technology for the production of renewable transport fuels (RTFs) and includes a discussion on the costs of the different RTF options and the role they might play in helping reduce emissions of greenhouse gases. The motivation for using RTFs in the UK are (1) to reduce transport sector costs; (2) reduce greenhouse gas emissions; (3) improve air quality; (4) improve energy security in the transport sector and (5) assist rural development through domestic production of biomass-based fuels. The RTFs of most interest at present are ethanol produced in the fermentation of sugar and starchy crops, and biodiesel from oil crops. Figures for the UK potential for RTFs are given. It is pointed out however that given the finite availability of renewable sources and the competition for other applications, the use of RTFs will need to be efficient for sustainability. The report was prepared by Imperial College London as part of the DTI New and Renewable Energy Programme.

Development and use of GREET 1.6 fuel-cycle model for transportation fuels and vehicle technologies

International Nuclear Information System (INIS)

Wang, M. Q.

2001-01-01

Since 1995, with funds from the U.S. Department of Energy's (DOE's) Office of Transportation Technologies (OTT), Argonne National Laboratory has been developing the Greenhouse gases, Regulated Emissions, and Energy use in Transportation (GREET) model. The model is intended to serve as an analytical tool for use by researchers and practitioners in estimating fuel-cycle energy use and emissions associated with alternative transportation fuels and advanced vehicle technologies. Argonne released the first version of the GREET model--GREET 1.0--in June 1996. Since then, it has released a series of GREET versions with revisions, updates, and upgrades. In February 2000, the latest public version of the model--GREET 1.5a--was posted on Argonne's Transportation Technology Research and Development Center (TTRDC) Web site (www.transportation.anl.gov/ttrdc/greet). Major publications that address GREET development are listed. These reports document methodologies, development, key default assumptions, applications, and results of the GREET model. They are also posted, along with additional materials for the GREET model, on the TTRDC Web site. For a given transportation fuel/technology combination, the GREET model separately calculates: (A)--Fuel-cycle energy consumption for the following three source categories: (1) Total energy (all energy sources), (2) Fossil fuels (petroleum, natural gas [NG], and coal), and (3) Petroleum. (B)--Fuel-cycle emissions of the following three greenhouse gases (GHGs): (1) Carbon dioxide (CO 2 ) (with a global warming potential [GWP] of 1), (2) Methane (CH 4 ) (with a GWP of 21), and (3) Nitrous oxide (N 2 O) (with a GWP of 310). (C)--Fuel-cycle emissions of the following five criteria pollutants (separated into total [T] and urban [U] emissions): (1) Volatile organic compounds (VOCs), (2) Carbon monoxide (CO), (3) Nitrogen oxides (NO x ), (4) Particulate matter with a mean aerodynamic diameter of 10 (micro)m or less (PM 10 ), and (5) Sulfur oxides

Conceptual Assessment of a Fresh Fuel Transport Package for KJRR

Energy Technology Data Exchange (ETDEWEB)

Lee, Ju-Chan; Choi, W. S.; Bang, K. S.; Yu, S. H.; Park, J. S.; Yang, Y. Y. [KAERI, Daejeon (Korea, Republic of)

2016-05-15

The IAEA and domestic regulations stipulate that the fissile material transport package be subjected to the cumulative effects of a 9 m drop, 1 m puncture, 800 ℃ thermal and water leakage tests. A fissile material transport package should be maintained the subcriticality during the normal and accident conditions for contingency of leakage of water into or out of package, rearrangement of the contents, reduction of spaces and temperature changes. KAERI has been developing a fresh fuel transport package for Kijang research reactor (KJRR). This paper describes a conceptual design and preliminary safety analysis of the transport package for KJRR. The transport package was designed for shipment of a fresh fuel and a FM (Fission Molybdenum) target. Low-enriched uranium (LEU) of U-Mo fuel with U-235 enrichment of 19.75 w/o is used as a research reactor fuel. And LEU of UAlx-Al with U-235 enrichment of 19.75 w/o is used as a FM target material. The transport package was designed for shipment of a fresh fuel and a FM target. Safety analyses were conducted on all areas, including criticality, structural, and thermal fields. In the criticality analysis, effective neutron multiplication factors were below the criticality safety limit. In the structural analysis, the maximum stress satisfied the stress requirement stipulated in the ASME code. After 9 m free drop and 1 m puncture test, there was no significant deformation of fuel basket to cause a criticality. In the thermal analysis, the maximum temperatures at each part were lower than the allowable values.

The dieselization of America: An integrated strategy for future transportation fuels

Energy Technology Data Exchange (ETDEWEB)

Eberhardt, J.J. [Dept. of Energy, Washington, DC (United States)

1997-12-31

The Diesel Cycle engine has already established itself as the engine-of-choice for the heavy duty transport industry because of its fuel efficiency, durability, and reliability. In addition, it has also been shown to be capable of using alternative fuels, albeit at efficiencies lower than that achieved with petroleum-derived diesel fuel. Alternative fuel dedicated engines have not made significant penetration of the heavy duty truck market because truck fleet operators need a cost-competitive fuel and reliable supply and fueling infrastructure. In lieu of forcing diverse fuels from many diverse domestic feedstocks onto the end-users, the Office of Heavy Vehicle Technologies envisions that a future fuels strategy for the heavy duty transport sector is one where the diverse feedstocks are utilized to provide a single fuel specification (dispensed from the existing fueling infrastructure) that would run efficiently in a single high efficiency energy conversion device, the Diesel Cycle engine. In so doing, the US Commercial transport industry may gain a measure of security from the rapid fuel price increases by relying less on a single feedstock source to meet its increasing fuel requirements.

Fuel cells in transportation

Energy Technology Data Exchange (ETDEWEB)

Erdmann, G [Technische Univ., Berlin (Germany); Hoehlein, B [Research Center Juelich (Germany)

1996-12-01

A promising new power source for electric drive systems is the fuel cell technology with hydrogen as energy input. The worldwide fuel cell development concentrates on basic research efforts aiming at improving this new technology and at developing applications that might reach market maturity in the very near future. Due to the progress achieved, the interest is now steadily turning to the development of overall systems such as demonstration plants for different purposes: electricity generation, drive systems for road vehicles, ships and railroads. This paper does not present results concerning the market potential of fuel cells in transportation but rather addresses some questions and reflections that are subject to further research of both engineers and economists. Some joint effort of this research will be conducted under the umbrella of the IEA Implementing Agreement 026 - Annex X, but there is a lot more to be done in this challenging but also promising fields. (EG) 18 refs.

Shielding Performance Measurements of Spent Fuel Transportation Container

Directory of Open Access Journals (Sweden)

SUN Hong-chao

2015-11-01

Full Text Available The safety supervision of radioactive material transportation package has been further stressed and implemented. The shielding performance measurements of spent fuel transport container is the important content of supervision. However, some of the problems and difficulties reflected in practice need to be solved, such as the neutron dose rate on the surface of package is too difficult to measure exactly, the monitoring results are not always reliable, etc. The monitoring results using different spectrometers were compared and the simulation results of MCNP runs were considered. An improvement was provided to the shielding performance measurements technique and management of spent fuel transport.

Analyses of the transportation of spent research reactor fuel in the United States

International Nuclear Information System (INIS)

Cashwell, J.W.; Neuhauser, K.S.

1989-01-01

We analyzed the impacts of transportation of research reactor spent fuel from US and foreign reactors for the US Department of Energy's (DOE) Office of Defense Programs. Two separate shipment programs were analyzed. The shipment of research reactor spent fuel from Taiwan to the US (Fuel Movement Program), and the return of research reactor spent fuels of US origin from foreign and domestic reactors (Research Reactor Fuel Return Program). To perform these analyses, a comprehensive methodology for analyzing the probabilities and consequences of transportation in coastal waters and port facilities, handling at the port, and shipment by truck to reprocessing facilities was developed. The Taiwanese fuel consists of low-burnup aluminum-clad metallic uranium research reactor spent fuel; the other fuels are primarily aluminum-clad oxide fuels. The Fuel Movement Program is ongoing, while the Fuel Return Program addresses future shipments over a ten-year period. The operational aspects of the Taiwanese shipments have been uniform, but several possible shipping configurations are possible for the Fuel Return Program shipments. The risks of transporting spent nuclear fuel and other radioactive materials by all modes have been analyzed extensively. Comprehensive assessments, which bound the impacts of spent fuel transport, demonstrate that when shipments are made in compliance with applicable regulations, the risks for all such transport are low. For comparison with previously licensed transport activities and to provide continuity with earlier analyses, the results for shipment of 150-day-old commercial pressurized water reactor (PWR) spent fuel are presented as part of this study

Safe transport of irradiated fuel by sea

International Nuclear Information System (INIS)

Miller, M.L.

1997-01-01

The development is described of a transport system dedicated to the sea transport of irradiated nuclear fuel. The background is reviewed of why shipments were required and the establishment of a specialist shipping company, Pacific Nuclear Transport Limited. A description of the ships, flasks and other equipment utilised is provided, together with details of key procedures implemented to ensure safety and customer satisfaction. (Author)

The sea transport of irradiated nuclear fuel

International Nuclear Information System (INIS)

Miller, M.L.

1995-01-01

The paper describes the development of a transport system dedicated to the sea transport of irradiated nuclear fuel. It reviews the background to why shipments were required and the establishment of a specialist shipping company, Pacific Nuclear Transport Limited. A description of the ships, flasks and other equipment utilized is provided, together with details of key procedures implemented to ensure safety and customer satisfaction

HEU and Leu FueL Shielding Comparative Study Applied for Spent Fuel Transport

International Nuclear Information System (INIS)

Margeanu, C.A.; Margeanu, S.; Barbos, D.

2009-01-01

INR Pitesti owns and operates a TRIGA dual-core Research Reactor for material testing, power reactor fuel and nuclear safety studies. The dual core concept involves the operation of a 14 MW TRIGA steady-state, high flux research and material testing reactor at one end of a large pool, and the independent operation of an annular-core pulsing reactor (TRIGA-ACPR) at the other end of the pool. The steady-state reactor is mostly used for long term testing of power reactor fuel components (pellets, pins, subassemblies and fuel assemblies) followed by post-irradiation examination. Following the general trend to replace the He fuel type (High Enriched Uranium) by Leu fuel type (Low Enriched Uranium), in the light of international agreements between IAEA and the states using He fuel in their nuclear reactors, Inr Past's have been accomplished the TRIGA research reactor core full conversion on May 2006. The He fuel repatriation in US in the frame of Foreign Research Reactor Spent Nuclear Fuel Return Programme effectively started in 1999, the final stage being achieved in summer of 2008. Taking into account for the possible impact on the human and environment, in all activities associated to nuclear fuel cycle, the spent fuel or radioactive waste characteristics must be well known. Shielding calculations basic tasks consist in radiation doses calculation, in order to prevent any risks both for personnel protection and impact on the environment during the spent fuel manipulation, transport and storage. The paper is a comparative study of Leu and He fuel utilization effects for the shielding analysis during spent fuel transport. A comparison against the measured data for He spent fuel, available from the last stage of the spent fuel repatriation, is presented. All the geometrical and material data related on the spent fuel shipping cask were considered according to the Nac-Lt Cask approved model. The shielding analysis estimates radiation doses to shipping cask wall surface

Estimated routine radiation doses to transportation workers in alternative spent-fuel transportation systems

International Nuclear Information System (INIS)

Schneider, K.J.; Smith, R.I.; Daling, P.M.; Ross, W.A.; McNair, G.W.

1988-01-01

The federal system for the management of spent fuel and high-level radioactive waste includes the acceptance by the US Department of Energy (DOE) of the spent fuel or waste loaded in casks at the reactor or other waste generators, its transportation to a repository, and its handling and final emplacement in the repository. The DOE plans to implement a transportation system that is safe, secure, efficient, and cost-effective and will meet applicable regulatory safety and security requirements. The DOE commissioned the Pacific Northwest Laboratory (PNL) to develop estimates of the routine radiation doses that would result from the operation of a system postulated using current designs and practices. From that evaluation, PNL identified activities/operations that result in the higher fraction of doses, proposed conceptual alternatives that would effectively reduce such exposures, and evaluated the cost-effectiveness of such alternatives. The study is one of a series used in making overall system design and operational decisions in the development of the DOE's spent-fuel/high-level waste transportation system. This paper contains the highlights from the PNL study of the estimated radiation doses to the transportation workers in a postulated reference transportation system and potential alternatives to that system

Comparison of fuel production costs for future transportation

DEFF Research Database (Denmark)

Ridjan, Iva; Mathiesen, Brian Vad; Connolly, David

The purpose of this poster is to provide an overview of fuel production costs for two types of synthetic fuels – methanol and methane, along with comparable costs for first and second generation biodiesel, two types of second generation bioethanol, and biogas. The model analysed is a 100% renewable...... scenario of Denmark for 2050, where the data for the transport sector has been changed to estimate the fuel production costs for eight different fuel pathways....

Remarks on the transportation of spent fuel elements

International Nuclear Information System (INIS)

Krull, W.

1986-01-01

In this chapter topics discussed are the need for contracts, a transport company and risk insurance. Also, a section on transportation covers cranes, subpressure, contamination, cask limitations, physical protection and shipping. Reprocessing discusses minimum reprocessing batch and spent fuel. Finally, economical considerations concerning transportation and reprocessing are given

Solid oxide fuel cells for transportation: A clean, efficient alternative for propulsion

International Nuclear Information System (INIS)

Kumar, R.; Krumpelt, M.; Myles, K.M.

1993-01-01

Fuel cells show great promise for providing clean and efficient transportation power. Of the fuel cell propulsion systems under investigation, the solid oxide fuel cell (SOFC) is particularly attractive for heavy duty transportation applications that have a relatively long duty cycle, such as locomotives, trucks, and barges. Advantages of the SOFC include a simple, compact system configuration; inherent fuel flexibility for hydrocarbon and alternative fuels; and minimal water management. The specific advantages of the SOFC for powering a railroad locomotive are examined. Feasibility, practicality, and safety concerns regarding SOFCs in transportation applications are discussed, as am the major R ampersand D issues

Spent fuel shipping costs for transportation logistics analyses

International Nuclear Information System (INIS)

Cole, B.M.; Cross, R.E.; Cashwell, J.W.

1983-05-01

Logistics analyses supplied to the nuclear waste management programs of the U.S. Department of Energy through the Transportation Technology Center (TTC) at Sandia National Laboratories are used to predict nuclear waste material logistics, transportation packaging demands, shipping and receiving rates and transportation-related costs for alternative strategies. This study is an in-depth analysis of the problems and contingencies associated with the costs of shipping irradiated reactor fuel. These costs are extremely variable however, and have changed frequently (sometimes monthly) during the past few years due to changes in capital, fuel, and labor costs. All costs and charges reported in this study are based on January 1982 data using existing transport cask systems and should be used as relative indices only. Actual shipping costs would be negotiable for each origin-destination combination

Macroscopic Modeling of Transport Phenomena in Direct Methanol Fuel Cells

DEFF Research Database (Denmark)

Olesen, Anders Christian

An increasing need for energy efficiency and high energy density has sparked a growing interest in direct methanol fuel cells for portable power applications. This type of fuel cell directly generates electricity from a fuel mixture consisting of methanol and water. Although this technology...... surpasses batteries in important areas, fundamental research is still required to improve durability and performance. Particularly the transport of methanol and water within the cell structure is difficult to study in-situ. A demand therefore exist for the fundamental development of mathematical models...... for studying their transport. In this PhD dissertation the macroscopic transport phenomena governing direct methanol fuel cell operation are analyzed, discussed and modeled using the two-fluid approach in the computational fluid dynamics framework of CFX 14. The overall objective of this work is to extend...

Storage, transportation and disposal system for used nuclear fuel assemblies

Science.gov (United States)

Scaglione, John M.; Wagner, John C.

2017-01-10

An integrated storage, transportation and disposal system for used fuel assemblies is provided. The system includes a plurality of sealed canisters and a cask sized to receive the sealed canisters in side by side relationship. The plurality of sealed canisters include an internal basket structure to receive a plurality of used fuel assemblies. The internal basket structure includes a plurality of radiation-absorbing panels and a plurality of hemispherical ribs generally perpendicular to the canister sidewall. The sealed canisters are received within the cask for storage and transportation and are removed from the cask for disposal at a designated repository. The system of the present invention allows the handling of sealed canisters separately or collectively, while allowing storage and transportation of high burnup fuel and damaged fuel to the designated repository.

Proposal of guidelines for selecting optimum options in packagings and transportation systems of spent fuel

International Nuclear Information System (INIS)

Saegusa, T.; Abe, H.; Fukuda, S.

1983-01-01

Type and size of spent fuel shipping packagings and packaging transport ships in spent fuel transport system would have been determined separately in response to technical requirements etc. of reactor sites and reprocessing plants. However, since more and more spent fuel will be generated from world's nuclear power plants and will be transported much frequently to reprocessing plants or storage facilities, the current spent fuel transport system will have to be necessarily reexamined from the operational and economical aspects or an optimum transport system may have to be newly determined in the near future. In the literature, a variety of options are found, particularly of spent fuel packagings. This paper listed and classified options of spent fuel packagings and packaging transport ships in the transportation systems of spent fuel on the basis of literature surveys. These options were discussed from viewpoints of designers and users and compared in terms of transport efficiency. Finally, one way to determine an optimum transport system of spent fuel was indicated considering the total transport system in the light of safety, operational efficiency and economy

Preparation of recovery fuel - assumptions, quality, technology and cost; Upparbetning av returbraenslen - foerutsaettningar, kvalite, teknik och kostnader

Energy Technology Data Exchange (ETDEWEB)

Njurell, Rolf; Gyllenhammar, Marianne [SEP Scandinavian Energy Project AB, Goeteborg (Sweden)

2000-05-01

New laws and restrictions, in Sweden and within the EU, will change the handling of waste within the next years. The combustible wastes going to landfill today, have to be dealt with in another way in the future. The knowledge about fuel preparation has been accentuated. Preparation of wastes - properly executed - will make it a useful fuel and increase energy recovery. S.E.P. Scandinavian Energy Project AB has by the assignment of the Thermal Engineering Research Institute made this survey of required conditions technology and quality costs related to fuel preparation of recovered waste like wood, paper and plastic. Only a few fuel preparation plants for recovered waste exist in Sweden today. Most of the municipalities do not have any waste treatment except for landfill. In the future regional preparation plants will most likely be built. In that way recovered wastes can be treated in a cost-effective way and be converted into useful fuel. Transportation will increase when landfills, presently in use, will close and the waste has to be transported to regional plants. Recovered fuel can be divided into two types depending on their content. Recovered Wood Fuel is what we call RWF in this report. Recovered Commercial waste Fuel containing plastic, paper, textiles etc, is called RCF in this report. To receive a suitable fuel for a special combustion plant, the nature, quality and content of the fuel must be known. The choice of preparation equipment is guided both by the type of waste and the quality of fuel needed for the combustion plant. Different contaminations in waste are presented in the report, together with technology to separate them from the fuel. The report also focuses on some type of equipment that are available for fuel preparation in different applications. In general the waste has to be shredded or crushed and the tramp iron has to be removed. If required the waste also has to be screened. The non waste incineration plants firing RWF today and intend

Determining air quality and greenhouse gas impacts of hydrogen infrastructure and fuel cell vehicles.

Science.gov (United States)

Stephens-Romero, Shane; Carreras-Sospedra, Marc; Brouwer, Jacob; Dabdub, Donald; Samuelsen, Scott

2009-12-01

Adoption of hydrogen infrastructure and hydrogen fuel cell vehicles (HFCVs) to replace gasoline internal combustion engine (ICE) vehicles has been proposed as a strategy to reduce criteria pollutant and greenhouse gas (GHG) emissions from the transportation sector and transition to fuel independence. However, it is uncertain (1) to what degree the reduction in criteria pollutants will impact urban air quality, and (2) how the reductions in pollutant emissions and concomitant urban air quality impacts compare to ultralow emission gasoline-powered vehicles projected for a future year (e.g., 2060). To address these questions, the present study introduces a "spatially and temporally resolved energy and environment tool" (STREET) to characterize the pollutant and GHG emissions associated with a comprehensive hydrogen supply infrastructure and HFCVs at a high level of geographic and temporal resolution. To demonstrate the utility of STREET, two spatially and temporally resolved scenarios for hydrogen infrastructure are evaluated in a prototypical urban airshed (the South Coast Air Basin of California) using geographic information systems (GIS) data. The well-to-wheels (WTW) GHG emissions are quantified and the air quality is established using a detailed atmospheric chemistry and transport model followed by a comparison to a future gasoline scenario comprised of advanced ICE vehicles. One hydrogen scenario includes more renewable primary energy sources for hydrogen generation and the other includes more fossil fuel sources. The two scenarios encompass a variety of hydrogen generation, distribution, and fueling strategies. GHG emissions reductions range from 61 to 68% for both hydrogen scenarios in parallel with substantial improvements in urban air quality (e.g., reductions of 10 ppb in peak 8-h-averaged ozone and 6 mug/m(3) in 24-h-averaged particulate matter concentrations, particularly in regions of the airshed where concentrations are highest for the gasoline scenario).

An evaluation of the alternative transport fuel policies for Turkey

International Nuclear Information System (INIS)

Arslan, Ridvan; Ulusoy, Yahya; Tekin, Yuecel; Suermen, Ali

2010-01-01

The search for alternative fuels and new fuel resources is a top priority for Turkey, as is the case in the majority of countries throughout the world. The fuel policies pursued by governmental or civil authorities are of key importance in the success of alternative fuel use, especially for widespread and efficient use. Following the 1973 petroleum crisis, many users in Turkey, especially in transportation sector, searched for alternative fuels and forms of transportation. Gasoline engines were replaced with diesel engines between the mid-1970s and mid-1980s. In addition, natural gas was introduced to the Turkish market for heating in the early 1990s. Liquid petroleum gas was put into use in the mid-1990s, and bio-diesel was introduced into the market for transportation in 2003. However, after long periods of indifference governmental action, guidance and fuel policies were so weak that they did not make sense. Entrepreneurs and users experienced great economical losses and lost confidence in future attempts to search for other possible alternatives. In the present study, we will look at the history of alternative fuel use in the recent past and investigate the alternative engine fuel potential of Turkey, as well as introduce possible future policies based on experience.

Reduced Gravity Studies of Soret Transport Effects in Liquid Fuel Combustion

Science.gov (United States)

Shaw, Benjamin D.

2004-01-01

Soret transport, which is mass transport driven by thermal gradients, can be important in practical flames as well as laboratory flames by influencing transport of low molecular weight species (e.g., monatomic and diatomic hydrogen). In addition, gas-phase Soret transport of high molecular weight fuel species that are present in practical liquid fuels (e.g., octane or methanol) can be significant in practical flames (Rosner et al., 2000; Dakhlia et al., 2002) and in high pressure droplet evaporation (Curtis and Farrell, 1992), and it has also been shown that Soret transport effects can be important in determining oxygen diffusion rates in certain classes of microgravity droplet combustion experiments (Aharon and Shaw, 1998). It is thus useful to obtain information on flames under conditions where Soret effects can be clearly observed. This research is concerned with investigating effects of Soret transport on combustion of liquid fuels, in particular liquid fuel droplets. Reduced-gravity is employed to provide an ideal (spherically-symmetrical) experimental model with which to investigate effects of Soret transport on combustion. The research will involve performing reduced-gravity experiments on combustion of liquid fuel droplets in environments where Soret effects significantly influence transport of fuel and oxygen to flame zones. Experiments will also be performed where Soret effects are not expected to be important. Droplets initially in the 0.5 to 1 mm size range will be burned. Data will be obtained on influences of Soret transport on combustion characteristics (e.g., droplet burning rates, droplet lifetimes, gas-phase extinction, and transient flame behaviors) under simplified geometrical conditions that are most amenable to theoretical modeling (i.e., spherical symmetry). The experiments will be compared with existing theoretical models as well as new models that will be developed. Normal gravity experiments will also be performed.

Transport equations in an enzymatic glucose fuel cell

Science.gov (United States)

Jariwala, Soham; Krishnamurthy, Balaji

2018-01-01

A mathematical model is developed to study the effects of convective flux and operating temperature on the performance of an enzymatic glucose fuel cell with a membrane. The model assumes isothermal operating conditions and constant feed rate of glucose. The glucose fuel cell domain is divided into five sections, with governing equations describing transport characteristics in each region, namely - anode diffusion layer, anode catalyst layer (enzyme layer), membrane, cathode catalyst layer and cathode diffusion layer. The mass transport is assumed to be one-dimensional and the governing equations are solved numerically. The effects flow rate of glucose feed on the performance of the fuel cell are studied as it contributes significantly to the convective flux. The effects of operating temperature on the performance of a glucose fuel cell are also modeled. The cell performances are compared using cell polarization curves, which were found compliant with experimental observations.

Experience of European LWR irradiated fuel transport: the first five hundred tonnes

International Nuclear Information System (INIS)

Curtis, H.W.

1978-01-01

The paper describes the service provided by an international company specializing in the transport of LWR irradiated fuel throughout Europe. Methods of transport used to the reprocessing plants at La Hague and Windscale include road transport of 38 te flasks over the whole route; transport of flasks between 55 and 105 te by rail, with rail-head and the reprocessing plant, where required, performed by road using heavy trailers; roll-on, roll-off sea ferries; and charter ships. Different modes of transport have been developed to cater for the various limitations on access to reactor sites arising from geographical and routing considerations. The experience of transporting more than 500 tonnes of irradiated uranium from twenty-one power reactors is used to illustrate the flexibility which the transport organization requires when the access and handling facilities are different at almost every reactor. Variations in fuel cross sections and lengths of fuel elements used in first generation reactors created the need for first generation flasks with sufficient variants to accommodate all reactor fuels but the trend now is towards standardization of flasks to perhaps two basic types. The safety record of irradiated fuel transport is examined with explanation of the means whereby this has been achieved. The problems of programming the movement of a pool of eighteen flasks for twenty-one reactors in eight countries are discussed together with the steps taken to ensure that the service operates fairly to give priority to those reactors with the greatest problems. The transport of irradiated fuel across several national frontiers is an international task which requires an international company. The transport of European irradiated fuel can be presented as an example of international collaboration which works

Probabilistic safety analysis of transportation of spent fuel

International Nuclear Information System (INIS)

Subramaniam, Chitra

1999-11-01

The report presents the results of the study carried out to estimate the accident risk involved in the transport of spent fuel from Rajasthan Atomic Power Station near Kota to the fuel reprocessing plant at Tarapur. The technique of probabilistic safety analysis is used. The fuel considered is the Indian pressurised heavy water reactor fuel with a minimum cooling period of 485 days. The spent fuel is transported in a cuboidal, naturally-cooled shipping cask over a distance of 822 km by rail. The Indian rail accident statistics are used to estimate the basic rail accident frequency. The possible ways in which a release of radioactive material can occur from the spent fuel cask are identified by the fault tree analysis technique. The release sequences identified are classified into eight accident severity categories, and release fractions are assigned to each. The consequences resulting from the release are estimated by the computer code RADTRAN 4. Results of the risk analysis indicate that the accident risk values are very low and hence acceptable. Parametric studies show that the risk would continue to be small even if the controlling parameters were to simultaneously take extreme adverse values. (author)

Fuel cell assembly with electrolyte transport

Science.gov (United States)

Chi, Chang V.

1983-01-01

A fuel cell assembly wherein electrolyte for filling the fuel cell matrix is carried via a transport system comprising a first passage means for conveying electrolyte through a first plate and communicating with a groove in a second plate at a first point, the first and second plates together sandwiching the matrix, and second passage means acting to carry electrolyte exclusively through the second plate and communicating with the groove at a second point exclusive of the first point.

Experience of European irradiated fuel transport - the first four hundred tonnes

International Nuclear Information System (INIS)

Curtis, H.W.

1977-01-01

The paper describes the successful integration of the experience of its three shareholders into an international company providing an irradiated fuel transport service throughout Europe. The experience of transporting more than 400 tonnes of irradiated uranium from fifteen power reactors is used to illustrate the flexibility which the transport organisation requires when the access and handling facilities are different at almost every reactor. Variations in fuel cross sections and lengths of fuel elements used in first generation reactors created the need for first generation flasks with sufficient variants to accommodate all reactor fuels but the trend now is towards standardisation of flasks to perhaps two basic types. Increases in fuel rating have raised the flask shielding and heat dissipation requirements and have influenced the design of later flasks. More stringent criticality acceptance criteria have tended to reduce the flask capacity below the maximum number of elements which could physically be contained. Reprocessing plant acceptance criteria initiated because of the presence of substantial quantities of loose crud released in the flask and the need to transport substantial numbers of failed elements have also reduced the flask capacity. Different modes of transport have been developed to cater for the various limitations on access to reactor sites arising from geographical and routing considerations. The safety record of irradiated fuel transport is examined with explanation of the means whereby this has been achieved. The problems of programming the movement of a pool of flasks for fifteen reactors in eight countries are discussed together with the steps taken to ensure that the service operates fairly to give priority to those reactors with the greatest problems. The transport of European irradiated fuel can be presented as an example of international collaboration which works

Transportation of high-level waste and spent fuel

International Nuclear Information System (INIS)

Carlson, J.H.; Lake, W.H.; Thompson, J.H.

1993-01-01

The Office of Civilian Radioactive Waste Management (OCRWM) transportation program is a multifaceted undertaking to transport spent nuclear fuel from commercial reactors to temporary and permanent storage facilities commencing in 1998. One of the significant ingredients necessary to achieving this goal is the development and acquisition of shipping casks. Efforts to design and acquire high capacity casks is ongoing, as are efforts to purchase casks that can be made available using current technology. By designing casks that are optimized to the specifications of the older cooler spent fuel that will be shipped, and by designing to current NRC requirements, OCRWM's new generation of spent fuel casks will be more efficient and at least as safe as current cask designs. (J.P.N.)

Method to mount defect fuel elements i transport casks

International Nuclear Information System (INIS)

Borgers, H.; Deleryd, R.

1996-01-01

Leaching or otherwise failed fuel elements are mounted in special containers that fit into specially designed chambers in a transportation cask for transport to reprocessing or long-time storage. The fuel elements are entered into the container under water in a pool. The interior of the container is dried before transfer to the cask. Before closing the cask, its interior, and the exterior of the container are dried. 2 figs

An evaluation of the policy and techno-economic factors affecting the potential for biogas upgrading for transport fuel use in the UK

International Nuclear Information System (INIS)

Patterson, Tim; Esteves, Sandra; Dinsdale, Richard; Guwy, Alan

2011-01-01

Gaseous biofuels including biomethane, which has been shown to be more environmentally beneficial than liquid biofuels, should contribute to meeting the challenging UK targets set for the supplying of biofuels to the road transport fuel market. Under the Renewable Transport Fuel Obligations the financial incentives for the supply of biofuels have been volatile, e.g. 2008/2009 saw Renewable Transport Fuel Certificate values fall to zero. Any shortfall from the maximum value has significant implications for all biofuels. It is demonstrated that biomethane can be produced at a cost which is competitive with liquid biofuels and fossil fuels within the UK. Technologies such as water scrubbing, pressure swing adsorption and physical and chemical absorption are available to upgrade biogas generated by anaerobic digestion of organic wastes to transport fuel quality, and technologies such as membrane separation and cryogenic distillation are being modified for such an application. The manufacture and sale of biomethane as a transport fuel is also financially competitive with Combined Heat and Power. One limiting factor may be the additional cost of purchasing and maintaining biomethane fuelled vehicles. Support in this area could lead to the rapid expansion of biomethane transport fuel infrastructure and bring significant long term environmental and economic advantages. - Research highlights: → A technical summary of commercially available biogas upgrading technologies is made. → An assessment of energetic, environmental and economic performance is included. → Proposed financial subsidies for biomethane transport fuel are investigated. → Biomethane can be financially competitive with liquid biofuels. → The enhanced environmental performance of biomethane should be reflected by the level of subsidy.

Ordinance concerning the filing of transport of nuclear fuel materials

International Nuclear Information System (INIS)

1979-01-01

The ordinance is defined under the law for the regulations of nuclear source materials, nuclear fuel materials and reactors and the order for execution of the law. Any person who reports the transport of nuclear fuel materials shall file four copies of a notification according to the form attached to the public safety commission of the prefecture in charge of the dispatching place. When the transportation extends over the area in charge of another public safety commission, the commission which has received the notice shall report without delay date and route of the transport, kind and quantity of nuclear fuel materials and other necessary matters to the commission concerned and hear from the latter opinions on the items informed. The designation by the ordinance includes speed of the vehicle loaded with nuclear fuel materials, disposition of an accompanying car, arrangement of the line of the loaded vehicle and accompanying and other escorting cars, location of the parking, place of unloading and temporary storage, etc. Reports concerning troubles and measures taken shall be filed in ten days to the public safety commission which has received the notification, when accidents occur on the way, such as: theft or loss of nuclear fuel materials; traffic accident; irregular leaking of nuclear fuel materials and personal trouble by the transport. (Okada, K.)

One approach to accepting and transporting spent fuel from early-generation reactors with short fuel assemblies

International Nuclear Information System (INIS)

Peterson, R.W.; Bentz, E.J. Jr.; Bentz, C.B.

1993-01-01

In the early days of development of commercial nuclear power reactors in the U.S., the overall length and uranium loading of the fuel assemblies were considerably less than those of later generation facilities. In turn, some of these early facilities were designed for handling shorter casks than currently-certified casks. The spent fuel assemblies from these facilities are nearly all standard fuel within the definition in the Standard Contract (10 CFR 961) between the utilities and the U.S. Department of Energy (DOE) (the Big Rock Point fuel cross-section is outside the standard fuel dimension), and the utilities involved hold early delivery rights under DOE's oldest-fuel-first (OFF) allocation scenario. However, development of casks suitable for satisfying the acceptance and transportation requirements of some of these facilities is not currently underway in the DOE Cask System Development Program (CSDP). While the total MTU of these fuels is relatively small compared to the total program, the number of assemblies to be transported is significant, especially in the early years of operation according to the OFF allocation scenario. We therefore perceive a need for DOE to develop an approach and to implement plans to satisfy the unique acceptance and transportation requirements of these facilities. One such approach is outlined below. (author)

European experience in the transport of irradiated light-water reactor fuel

International Nuclear Information System (INIS)

Curtis, H.W.

1979-01-01

Various methods of transport of irradiated fuel flasks in Europe are described. While many problems in the transport of heavy flasks have been solved some remain and new ones have appeared. Some of these problems are the accumulation of crud on the surface of fuel elements, the problems of failed fuel, stringent criticality criteria, the ''sweating out'' of contaminated flasks, the access, road or rail, to reactor sites, and the maintenance of the transport vehicles. Some future trends in the direction of heavy flasks in the range of 75 to 100 tonnes are indicated

Advanced methods of quality control in nuclear fuel fabrication

International Nuclear Information System (INIS)

Onoufriev, Vladimir

2004-01-01

Under pressure of current economic and electricity market situation utilities implement more demanding fuel utilization schemes including higher burn ups and thermal rates, longer fuel cycles and usage of Mo fuel. Therefore, fuel vendors have recently initiated new R and D programmes aimed at improving fuel quality, design and materials to produce robust and reliable fuel. In the beginning of commercial fuel fabrication, emphasis was given to advancements in Quality Control/Quality Assurance related mainly to product itself. During recent years, emphasis was transferred to improvements in process control and to implementation of overall Total Quality Management (TQM) programmes. In the area of fuel quality control, statistical control methods are now widely implemented replacing 100% inspection. This evolution, some practical examples and IAEA activities are described in the paper. The paper presents major findings of the latest IAEA Technical Meetings (TMs) and training courses in the area with emphasis on information received at the TM and training course held in 1999 and other latest publications to provide an overview of new developments in process/quality control, their implementation and results obtained including new approaches to QC

Transportation of failed or damaged foreign research reactor spent nuclear fuel

International Nuclear Information System (INIS)

Messick, Charles E.; Mustin, Tracy P.; Massey, Charles D.

1999-01-01

Since initiating the Foreign Research Reactor Spent Nuclear Fuel (FRR SNF) Acceptance Program in 1996, the Program has had to deal with difficult issues associated with the transportation of failed or damaged spent fuel. In several instances, problems with failed or damaged fuel have prevented the acceptance of the fuel at considerable cost to both the Department of Energy and research reactor operators. In response to the problems faced by the Acceptance Program, DOE has undertaken significant steps to better define the spent fuel acceptance criteria. DOE has worked closely with the U.S. Nuclear Regulatory Commission to address failed or damaged research reactor spent fuel causing a degradation of the fuel assembly exposing fuel meat and to identify cask certificate issues which must be resolved by cask owners and foreign regulatory authorities. The specific issues and implementation challenges associated with the transport of MTR type FRR SNF will be discussed. The information presented will include U.S. Nuclear Regulatory Commission regulatory issues, cask certificate issues, technical constraints, implementation status, and lessons learned. Specific information will also be provided on the latest efforts to revise DOE's Appendix B, Transport Package (Cask) Acceptance Criteria. The information presented in this paper will be of interest to foreign research reactor operators, shippers, and cask vendors in evaluating the condition of their fuel to ensure it can be transported in accordance with appropriate cask certificate requirements. (author)

A Study of Transport Airplane Crash-Resistant Fuel Systems

National Research Council Canada - National Science Library

Robertson, S

2002-01-01

...), of transport airplane crash-resistant fuel system (CRFS). The report covers the historical studies related to aircraft crash fires and fuel containment concepts undertaken by the FAA, NASA, and the U.S...

Regional analysis of renewable transportation fuels - production and consumption

Science.gov (United States)

Liu, Xiaoshuai

The transportation sector contributes more than a quarter of total U.S. greenhouse gas emissions. Replacing fossil fuels with renewable fuels can be a key solution to mitigate GHG emissions from the transportation sector. Particularly, we have focused on land-based production of renewable fuels from landfills and brownfield in the southeastern region of the United States. These so call marginal lands require no direct land-use change to avoid environmental impact and, furthermore, have rendered opportunities for carbon trading and low-carbon intensity business. The resources potential and production capacity were derived using federal and state energy databases with the aid of GIS techniques. To maximize fuels production and land-use efficiency, a scheme of co-location renewable transportation fuels for production on landfills was conducted as a case study. Results of economic modeling analysis indicate that solar panel installed on landfill sites could generate a positive return within the project duration, but the biofuel production within the landfill facility is relatively uncertain, requiring proper sizing of the onsite processing facility, economic scale of production and available tax credits. From the consumers' perspective, a life-cycle cost analysis has been conducted to determine the economic and environmental implications of different transportation choices by consumers. Without tax credits, only the hybrid electric vehicles have lifetime total costs equivalent to a conventional vehicles differing by about 1 to 7%. With tax credits, electric and hybrid electric vehicles could be affordable and attain similar lifetime total costs as compared to conventional vehicles. The dissertation research has provided policy-makers and consumers a pathway of prioritizing investment on sustainable transportation systems with a balance of environmental benefits and economic feasibility.

Quality analysis in pressurized water reactor fuel

International Nuclear Information System (INIS)

Darolles, J.F.

1975-01-01

An integrated system which has been set up to administrate and analyze the quality is described. This system is in actual operation. The basic principles for quality analysis system are traceability, i.e., identification, location and history of fuel components and quality evaluation during manufacturing. The quality analysis system operates in the following areas: data recording and transmission, data processing, quality file generation. The interest of such a system may be noted particularly in manufacturing, for the constitution of quality files, the design of products and the processing of data from irradiated fuel assemblies [fr

Emissions and Air Quality Impacts of Freight Transportation

Science.gov (United States)

Bickford, Erica

Diesel freight vehicles (trucks + trains) are responsible for 20% of all U.S. nitrogen oxide (NOx) and 3% of fine particulate (PM2.5) emissions - pollutants that are harmful to human health. Freight tonnage is also projected to double over the next several decades, reaching 30 billion tons by 2050, increasing freight transport activity. Air quality impacts from increased activity, trade-offs between activity and vehicle technology improvements, as well as where to make infrastructure investments that encourage sustainable freight growth, are important considerations for transportation and air quality managers. To address these questions, we build a bottom-up roadway-by-roadway freight truck inventory (WIFE) and employ it to quantify emissions impacts of swapping biodiesel blends into the Midwest diesel freight truck fleet, and investigate emissions and air quality impacts of truck-to-rail freight modal shifts in the Midwest. We also evaluate the spatial and seasonal freight performance of WIFE modeled in a regional photochemical model (CMAQ) against satellite retrievals of nitrogen dioxide (NO2) from the Ozone Monitoring Instrument (OMI). Results show that spatial and seasonal distribution of biodiesel affects regional emissions impacts. Summer high-blend deployment yields a larger annual emissions reduction than year-round low-blend deployment, however, technological improvements in vehicle emissions controls between 2009 and 2018 dwarf the impacts of biodiesel. Truck-to-rail modal shift analysis found 40% of daily freight truck VMT could be shifted to rail freight, causing a 26% net reduction in NOx emissions, and 31% less carbon dioxide (CO2) emissions. Despite significant emissions impacts, air quality modeling results showed mostly localized near roadway air quality improvements, with small regional net changes; yet, federal regulation of CO2 emissions and/or rising costs of diesel fuel could motivate shifting freight to more fuel efficient rail. Evaluation of

Towards sustainable urban transportation: Test, demonstration and development of fuel cell and hybrid-electric buses

International Nuclear Information System (INIS)

Folkesson, Anders

2008-05-01

Several aspects make today's transport system non-sustainable: - Production, transport and combustion of fossil fuels lead to global and local environmental problems. - Oil dependency in the transport sector may lead to economical and political instability. - Air pollution, noise, congestion and land-use may jeopardise public health and quality of life, especially in urban areas. In a sustainable urban transport system most trips are made with public transport because high convenience and comfort makes travelling with public transport attractive. In terms of emissions, including noise, the vehicles are environmentally sustainable, locally as well as globally. Vehicles are energy-efficient and the primary energy stems from renewable sources. Costs are reasonable for all involved, from passengers, bus operators and transport authorities to vehicle manufacturers. The system is thus commercially viable on its own merits. This thesis presents the results from three projects involving different concept buses, all with different powertrains. The first two projects included technical evaluations, including tests, of two different fuel cell buses. The third project focussed on development of a series hybrid-bus with internal combustion engine intended for production around 2010. The research on the fuel cell buses included evaluations of the energy efficiency improvement potential using energy mapping and vehicle simulations. Attitudes to hydrogen fuel cell buses among passengers, bus drivers and bus operators were investigated. Safety aspects of hydrogen as a vehicle fuel were analysed and the use of hydrogen compared to electrical energy storage were also investigated. One main conclusion is that a city bus should be considered as one energy system, because auxiliaries contribute largely to the energy use. Focussing only on the powertrain is not sufficient. The importance of mitigating losses far down an energy conversion chain is emphasised. The Scania hybrid fuel cell

Arrival condition of spent fuel after storage, handling, and transportation

International Nuclear Information System (INIS)

Bailey, W.J.; Pankaskie, P.J.; Langstaff, D.C.; Gilbert, E.R.; Rising, K.H.; Schreiber, R.E.

1982-11-01

This report presents the results of a study conducted to determine the probable arrival condition of spent light-water reactor (LWR) fuel after handling and interim storage in spent fuel storage pools and subsequent handling and accident-free transport operations under normal or slightly abnormal conditions. The objective of this study was to provide information on the expected condition of spent LWR fuel upon arrival at interim storage or fuel reprocessing facilities or at disposal facilities if the fuel is declared a waste. Results of a literature survey and data evaluation effort are discussed. Preliminary threshold limits for storing, handling, and transporting unconsolidated spent LWR fuel are presented. The difficulty in trying to anticipate the amount of corrosion products (crud) that may be on spent fuel in future shipments is also discussed, and potential areas for future work are listed. 95 references, 3 figures, 17 tables

L. Transportation of fuel and wastes

International Nuclear Information System (INIS)

1976-01-01

The principles applied to the transport of nuclear fuels and wastes have been founded on the more general provisions governing the transport of radioactive materials. Safe shipment of radioactive materials has historically been sought by specifying required characteristics in the shipping packages and establishing minimum acceptable levels of package integrity. The reason for this is that in the course of transport by road, rail, sea, or air, consignments of radioactive material are in close proximity to members of the public, and in many cases they are loaded or unloaded by transport workers who have had no special training or experience in the handling of such substances. The procedures adopted to ensure transport safety have worked satisfactorily. Both in the USA and the UK, the industry and regulatory authorities have established outstanding safety records in shipping radioactive materials over a period of thirty years. It is claimed that there have been no injuries due to the radioactive nature of the shipments, nor has there been a release of nuclear materials serious enough to be a threat of death or injury. Admittedly, about 95% of the 800,000 shipments estimated in the USA each year involve small quantities for use in industry, medicine, agriculture and education. However the principals underlying the safe packaging of these and reactor fuels are the same, and there is little reason to doubt that a similar safety record can be maintained

CONTAINMENT ANALYSIS METHODOLOGY FOR TRANSPORT OF BREACHED CLAD ALUMINUM SPENT FUEL

Energy Technology Data Exchange (ETDEWEB)

Vinson, D.

2010-07-11

Aluminum-clad, aluminum-based spent nuclear fuel (Al-SNF) from foreign and domestic research reactors (FRR/DRR) is being shipped to the Savannah River Site and placed in interim storage in a water basin. To enter the United States, a cask with loaded fuel must be certified to comply with the requirements in the Title 10 of the U.S. Code of Federal Regulations, Part 71. The requirements include demonstration of containment of the cask with its contents under normal and accident conditions. Many Al-SNF assemblies have suffered corrosion degradation in storage in poor quality water, and many of the fuel assemblies are 'failed' or have through-clad damage. A methodology was developed to evaluate containment of Al-SNF even with severe cladding breaches for transport in standard casks. The containment analysis methodology for Al-SNF is in accordance with the methodology provided in ANSI N14.5 and adopted by the U. S. Nuclear Regulatory Commission in NUREG/CR-6487 to meet the requirements of 10CFR71. The technical bases for the inputs and assumptions are specific to the attributes and characteristics of Al-SNF received from basin and dry storage systems and its subsequent performance under normal and postulated accident shipping conditions. The results of the calculations for a specific case of a cask loaded with breached fuel show that the fuel can be transported in standard shipping casks and maintained within the allowable release rates under normal and accident conditions. A sensitivity analysis has been conducted to evaluate the effects of modifying assumptions and to assess options for fuel at conditions that are not bounded by the present analysis. These options would include one or more of the following: reduce the fuel loading; increase fuel cooling time; reduce the degree of conservatism in the bounding assumptions; or measure the actual leak rate of the cask system. That is, containment analysis for alternative inputs at fuel-specific conditions and

Transportation and air quality

International Nuclear Information System (INIS)

Roseland, M.

1992-01-01

In the greater Vancouver regional district (GVRD), some 80% of the annual production of 600,000 tonnes of air pollutants come from motor vehicles. Three critical air quality issues in the GVRD are discussed: local air pollution, ozone layer depletion, and greenhouse gas emissions, all of which are fundamentally linked to transportation. Overall air quality in the GVRD has been judged acceptable by current federal standards, but ground-level ozone has exceeded maximum tolerable levels at some locations and concentrations of suspended particulates are above maximum acceptable levels. Serious deterioration in air quality has been predicted unless a concerted effort is made to manage air quality on an airshed-wide basis. The GVRD is developing Canada's first Air Management Plan with the goal of halving atmospheric emissions by 2000. GVRD transportation priorities stress public transit, walking, cycling, car pooling, and reducing of travel demand; however, the viability of such strategies depends on decisions made outside the transportation sector. Restricted authority and jurisdiction also hinder GVRD goals; the regional level of government has no authority over highways or transit and only has authority for pollution control in some parts of the Fraser Valley. Airshed quality management, using the Los Angeles example, is seen as a possible direction for future GVRD policymaking in the transportation sector. A single regional planning agency with responsibility for transportation, land use, and air quality management appears as the best option for an integrated approach to solve multiple problems. 19 refs

standards used for quality control of nuclear fuels

International Nuclear Information System (INIS)

Guereli, L; Can, S.

1997-01-01

Nuclear fuels and fuel materials are subject to stringent restrictions as to their quality. The standards and regulations that apply vary according to reactor type and country and the standards are stated in the quality assurance documents. The concept of quality assurance has altered the conventional quality control tests and procedures, defining which control tests are to be applied and how. Although most of the tests and measurements allow the determination of tolerances to be decided according to the agreement between the buyer and the seller, exacting procedures apply to which instruments and equipment are used for these tests and measurements, how these instruments are standardized.Detailed explanations of test methods and their documentation is a requirement in all standards. The purpose of this work is to study which standards, tests and measurements apply to the nuclear fuel production. Only the standards that apply to various stages of the nuclear fuel production (powder preparation, pellet production, fuel element and fuel assembly fabrication) are reviewed. Process and documentation control, design and licensing requirements and the frequency of inspections are quality assurance subjects. Some ASTM standards are given as examples

Considerations in the selection of transport modes for spent nuclear fuel shipments

International Nuclear Information System (INIS)

Daling, P.M.; McNair, G.W.; Andrews, W.B.

1985-07-01

This paper discusses the factors associated with selecting a particular transport mode for spent fuel shipments. These factors include transportation costs, economics of potential transportation accidents, risk/safety of spent fuel transportation, routing alternatives, shipping cask handling capabilities, and shipping cask availability. Data needed to estimate transportation costs and risks are presented and discussed. The remaining factors are discussed qualitatively and can be used as guidance for selecting a particular transport mode. 15 refs., 3 tabs

Commercializing an alternate transportation fuel: lessons learned from NGV

International Nuclear Information System (INIS)

Flynn, P.C.

2001-01-01

An alternate transportation fuel, compressed natural gas, was adopted in Canada in the mid-1980s due to the unique conditions present at the time. The factors that had an impact on the limited acceptance of the fuel, keeping its rate of adoption below the critical point were examined in this paper. It was revealed that a lack of infrastructure to support converted vehicles was the deciding factor. Existing refueling stations failed to become profitable, preventing further investment in refueling facilities and resulting in depressed sales of converted vehicles. Excessive parts markup by conversion dealers was another major hurdle, as was exaggerated claims for environmental and economic benefits. In addition, promotional programs were poorly designed. In the late 1980s, the relative values of oil and natural gas shifted, lowering the momentum from sales of conversions. The consequence was major players leaving the market and natural gas remained on the fringe in both Canada and the United States. Different alternate transportation fuels, including electricity and hydrogen, are being favored by new technologies and driving forces. The growth to commercial viability for those fuels will likely be influenced by some of the factors that played a role in the fate of natural gas as a transportation fuel. 4 refs., 1 fig

Dynamic analysis and application of fuel elements pneumatic transportation in a pebble bed reactor

International Nuclear Information System (INIS)

Liu, Hongbing; Du, Dong; Han, Zandong; Zou, Yirong; Pan, Jiluan

2015-01-01

Almost 10,000 spherical fuel elements are transported pneumatically one by one in the pipeline outside the core of a pebble bed reactor every day. Any failure in the transportation will lead to the shutdown of the reactor, even safety accidents. In order to ensure a stable and reliable transportation, it's of great importance to analyze the motion and force condition of the fuel element. In this paper, we focus on the dynamic analysis of the pneumatic transportation of the fuel element and derive kinetic equations. Then we introduce the design of the transportation pipeline. On this basis we calculate some important data such as the velocity of the fuel element, the force between the fuel element and the pipeline and the efficiency of the pneumatic transportation. Then we analyze these results and provide some suggestions for the design of the pipeline. The experiment was carried out on an experimental platform. The velocities of the fuel elements were measured. The experimental results were consistent with and validated the theoretical analysis. The research may offer the basis for the design of the transportation pipeline and the optimization of the fuel elements transportation in a pebble bed reactor. - Highlights: • The kinetic equations of the fuel element in pneumatic transportation are derived. • The dynamic characteristics of the fuel element are analyzed. • Some important parameters are calculated based on the kinetic equations. • The experimental results were consistent with the analysis and verified the analysis. • This paper may offer an important guide to the research of a pebble bed reactor

Transportation of failed or damaged foreign research reactor spent nuclear fuel

International Nuclear Information System (INIS)

Messick, C.E.; Mustin, T.P.; Massey, C.D.

1998-01-01

Since resuming the Foreign Research Reactor Spent Nuclear Fuel (FRR SNF) Acceptance Program in 1996, the Program has had to deal with difficult issues associated with the transportation of failed or damaged spent fuel. In several instances, problems with failed or damaged fuel have prevented the acceptance of the fuel at considerable cost to both the Department of Energy (DOE) and research reactor operators. In response to the problems faced by the Acceptance Program, DOE has undertaken significant steps to better define the spent fuel acceptance criteria. DOE has worked closely with the U.S. Nuclear Regulatory Commission to address failed or damaged research reactor spent fuel and to identify cask certificate issues which must be resolved by cask owners and foreign regulatory authorities. The specific issues associated with the transport of Materials Testing Reactor (MTR)-type FRR SNF will be discussed. The information presented will include U.S. Nuclear Regulatory Commission regulatory issues, cask certificate issues, technical constraints, and lessons learned. Specific information will also be provided on the latest efforts to revise DOE's Appendix B, Transport Package (Cask) Acceptance Criteria. The information presented in this paper will be important to foreign research reactor operators, shippers, and cask vendors, so that appropriate amendments to the Certificate of Compliance for spent fuel casks can be submitted in a timely manner to facilitate the safe and scheduled transport of FRR SNF

Summary report on transportation of nuclear fuel materials in Japan : transportation infrastructure, threats identified in open literature, and physical protection regulations.

Energy Technology Data Exchange (ETDEWEB)

Cochran, John Russell; Ouchi, Yuichiro (Japan Atomic Energy Agency, Japan); Furaus, James Phillip; Marincel, Michelle K.

2008-03-01

This report summarizes the results of three detailed studies of the physical protection systems for the protection of nuclear materials transport in Japan, with an emphasis on the transportation of mixed oxide fuel materials1. The Japanese infrastructure for transporting nuclear fuel materials is addressed in the first section. The second section of this report presents a summary of baseline data from the open literature on the threats of sabotage and theft during the transport of nuclear fuel materials in Japan. The third section summarizes a review of current International Atomic Energy Agency, Japanese and United States guidelines and regulations concerning the physical protection for the transportation of nuclear fuel materials.

Transport of volatile fission products in the fuel-to-sheath gap of defective fuel elements during normal and reactor accident conditions

International Nuclear Information System (INIS)

Lewis, B.J.; Bonin, H.W.

1995-01-01

An analytical treatment has been used to model the vapour transport of radioactive fission products released into the fuel-to-sheath gap of defective nuclear fuel elements. The model accounts for both diffusive and bulk-convective transport. Convective transport becomes important as a result of a significant release of gaseous fission products into the gap during a high-temperature reactor accident. However, during normal reactor operation, diffusion is shown to be the dominant process of transport. The model is based on an analysis of several in-reactor tests with operating defective fuel elements, and high-temperature annealing experiments with irradiated fuel specimens. ((orig.))

Present status and prospect of spent fuel transportation

International Nuclear Information System (INIS)

Adachi, H.

1987-01-01

Problems linked with spent fuel transportation in Japan, where there are 35 NPPs in operation, are considered. Every year about 500 t U are shipped to fuel reprocessing plants in Japan, as well as in France and UK. Four kinds of casks: HZ, EXCELLOX, TN and TK - are used for this purpose. By the mid-1990's it is suggested to build in Japan fuel reprocessing plant with capacity of 800 t U per year

The single SNR fuel assembly container (ESBB) to transport unirradiated SNR 300 fuel assemblies

International Nuclear Information System (INIS)

Hilbert, F.; Hottenrott, G.

1998-01-01

In this paper a new type B(U) package design is presented. The Single SNR Fuel Assembly Container (ESBB) is designed for the transport and storage of a single SNR 300 fuel assembly. This package is the main component for the future interim storage of the fuel assemblies in heavy storage casks. Its benefits are that it is compatible with the Category I transport system of Nuclear Cargo + Service NCS) used in Germany and that it can be easily handled at the current storage locations as well as in an interim storage facility. In total 205 fuel assemblies are currently stored in Hanau, Germany and Dounreay, U.K. Former studies have shown, that heavy transport and storage casks can be handled there only with considerable efforts. But the required category I transport to an interim storage is not reasonably feasible. To overcome these problems the ESBB was designed. It consists of a stainless steel tube with welded bottom, a welded plug as closure system and shock absorbers 26 packages at maximum can be transported in one batch with the NCS security vehicle. The safety analysis shows that the package complies with IAEA 1996. Standard calculations methods and computer codes like HEATING 7.2 (Childs 1993) have been used for the analysis. Criticality safety assessment is based on conservative assumptions as required in IAEA 1996. Drop tests carried out by BAM will be used to verify the design. These tests are scheduled for mid 1998. For the validation of the design prototypes have already been manufactured. Handling tests show that the design complies with the requirements. Preliminary drop tests show that the certification drop tests will be passed positively. (authors)

Basic planning of a newly built exclusive ship for spent fuel transport

International Nuclear Information System (INIS)

Obara, I.; Sasao, T.; Akiyama, H.; Kybota, T.

1998-01-01

A commercial reprocessing plant is under construction at the Fuel Cycle Facilities in Rokkasho-mura, Aomori Prefecture. To prepare for the transport of spent nuclear fuels (SF) from all Japanese nuclear power stations to this reprocessing plant, the need for an exclusive transport ship was recognized. Nuclear Fuel Transport Co. Ltd. (NFT), in cooperation with electric power utilities planned the construction of such a ship over a period of several years. During this period NFT developed new types of cask to transport high burn-up spent fuels to the reprocessing plant. Six kinds of casks were developed and 40 units are now under fabrication. The ship was designed to carry a maximum of 20 units. Based on the Irradiated Nuclear Fuel (INF) Code adopted by the International Maritime Organization (IMO), the Japanese Ministry of Transport (MoT) issued new domestic regulations in September, 1995 which covered design criteria for ships carrying Irradiated Nuclear Fuels. The new SF transport ship is the first one to which this new regulation was applied. Although the ship will only ply the coastal routes of Japan, she has been designed to conform with all the international requirements for the Class-3 of the INF Code. In May 1995, Nuclear Fuel Shipping Co. Ltd (NFS), a wholly-owned subsidiary of NFT, concluded a contract with Mitsui Engineering and Shipbuilding Co., Ltd. for the construction of the exclusive transport ship. The keel was laid in November 1995. The ship was launched in april 1996 and named 'Rokuei-Maru'. At the end of September, she was completed and delivered to the ship owner, NFS. (authors)

Two-dimensional radiation shielding optimization analysis of spent fuel transport container

International Nuclear Information System (INIS)

Tian Yingnan; Chen Yixue; Yang Shouhai

2013-01-01

The intelligent radiation shielding optimization design software platform is a one-dimensional multi-target radiation shielding optimization program which is developed on the basis of the genetic algorithm program and one-dimensional discrete ordinate program-ANISN. This program was applied in the optimization design analysis of the spent fuel transport container radiation shielding. The multi-objective optimization calculation model of the spent fuel transport container radiation shielding was established, and the optimization calculation of the spent fuel transport container weight and radiation dose rate was carried by this program. The calculation results were checked by Monte-Carlo program-MCNP/4C. The results show that the weight of the optimized spent fuel transport container decreases to 81.1% of the origin and the radiation dose rate decreases to below 65.4% of the origin. The maximum deviation between the calculated values from the program and the MCNP is below 5%. The results show that the optimization design scheme is feasible and the calculation result is correct. (authors)

Alternative Fuel Transportation Optimization Tool : Description, Methodology, and Demonstration Scenarios.

Science.gov (United States)

2015-09-01

This report describes an Alternative Fuel Transportation Optimization Tool (AFTOT), developed by the U.S. Department of Transportation (DOT) Volpe National Transportation Systems Center (Volpe) in support of the Federal Aviation Administration (FAA)....

Spent nuclear fuel transport problems

International Nuclear Information System (INIS)

Kondrat'ev, A.N.; Kosarev, Yu.A.; Yulikov, E.I.

1977-01-01

The paper considers the problems of shipping spent fuel from nuclear power stations to reprocessing plants and also the principal ways of solving these problems with a view to achieving maximum economy and safety in transport. The increase in the number of nuclear power plants in the USSR will entail an intensification of spent-fuel shipments. Higher burnup and the need to reduce cooling time call for heavier and more complex shipping containers. The problem of shipping spent fuel should be tackled comprehensively, bearing in mind the requirements of safety and economy. One solution to these problems is to develop rational and cheap designs of such containers. In addition, the world-wide trend towards more thorough protection of the environment against pollution and of the health of the population requires the devotion of constant attention to improving the reliability and safety of shipments. The paper considers the prospects for nuclear power development in the USSR and in other member countries of the CMEA (1976-1980), the composition and design of some Soviet packaging assemblies, the appropriate cooling time for spent fuel from thermal reactor power stations, procedures for reducing fuel-shipping costs, some methodological problems of container calculation and design, and finally problems of testing and checking containers on test rigs. (author)

Effects of fuel particle size distributions on neutron transport in stochastic media

International Nuclear Information System (INIS)

Liang, Chao; Pavlou, Andrew T.; Ji, Wei

2014-01-01

Highlights: • Effects of fuel particle size distributions on neutron transport are evaluated. • Neutron channeling is identified as the fundamental reason for the effects. • The effects are noticeable at low packing and low optical thickness systems. • Unit cells of realistic reactor designs are studied for different size particles. • Fuel particle size distribution effects are not negligible in realistic designs. - Abstract: This paper presents a study of the fuel particle size distribution effects on neutron transport in three-dimensional stochastic media. Particle fuel is used in gas-cooled nuclear reactor designs and innovative light water reactor designs loaded with accident tolerant fuel. Due to the design requirements and fuel fabrication limits, the size of fuel particles may not be perfectly constant but instead follows a certain distribution. This brings a fundamental question to the radiation transport computation community: how does the fuel particle size distribution affect the neutron transport in particle fuel systems? To answer this question, size distribution effects and their physical interpretations are investigated by performing a series of neutron transport simulations at different fuel particle size distributions. An eigenvalue problem is simulated in a cylindrical container consisting of fissile fuel particles with five different size distributions: constant, uniform, power, exponential and Gaussian. A total of 15 parametric cases are constructed by altering the fissile particle volume packing fraction and its optical thickness, but keeping the mean chord length of the spherical fuel particle the same at different size distributions. The tallied effective multiplication factor (k eff ) and the spatial distribution of fission power density along axial and radial directions are compared between different size distributions. At low packing fraction and low optical thickness, the size distribution shows a noticeable effect on neutron

Total quality in spent fuel pool reracking

International Nuclear Information System (INIS)

Cranston, J.S.; Bradbury, R.B.; Cacciapouti, R.J.

1993-01-01

The nuclear utility environment is one of strict cost control under prescriptive regulations and increasing public scrutiny. This paper presents the results of A Total Quality approach, by a dedicated team, that addresses the need for increased on-site spent fuel storage in this environment. Innovations to spent fuel pool reracking, driven by utilities' specific technical needs and shrinking budgets, have resulted in both product improvements and lower prices. A Total Quality approach to the entire turnkey project is taken, thereby creating synergism and process efficiency in each of the major phases of the project: design and analysis, licensing, fabrication, installation and disposal. Specific technical advances and the proven quality of the team members minimizes risk to the utility and its shareholders and provides a complete, cost effective service. Proper evaluation of spent fuel storage methods and vendors requires a full understanding of currently available customer driven initiatives that reduce cost while improving quality. In all phases of a spent fuel reracking project, from new rack design and analysis through old rack disposal, the integration of diverse experts, at all levels and throughout all phases of a reracking project, better serves utility needs. This Total Quality environment in conjunction with many technical improvements results in a higher quality product at a lower cost

Electricity as Transportation ``Fuel''

Science.gov (United States)

Tamor, Michael

2013-04-01

The personal automobile is a surprisingly efficient device, but its place in a sustainable transportation future hinges on its ability use a sustainable fuel. While electricity is widely expected to be such a ``fuel,'' the viability of electric vehicles rests on the validity of three assumptions. First, that the emissions from generation will be significantly lower than those from competing chemical fuels whether `renewable' or fossil. Second, that advances in battery technology will deliver adequate range and durability at an affordable cost. Third, that most customers will accept any functional limitations intrinsic to electrochemical energy storage. While the first two are subjects of active research and vigorous policy debate, the third is treated virtually as a given. Popular statements to the effect that ``because 70% of all daily travel is accomplished in less than 100 miles, mass deployment of 100 mile EVs will electrify 70% of all travel'' are based on collections of one-day travel reports such as the National Household Travel Survey, and so effectively ignore the complexities of individual needs. We have analyzed the day-to-day variations of individual vehicle usage in multiple regions and draw very different conclusions. Most significant is that limited EV range results in a level of inconvenience that is likely to be unacceptable to the vast majority of vehicle owners, and for those who would accept that inconvenience, battery costs must be absurdly low to achieve any economic payback. In contrast, the plug-in hybrid (PHEV) does not suffer range limitations and delivers economic payback for most users at realistic battery costs. More importantly, these findings appear to be universal in developed nations, with labor market population density being a powerful predictor of personal vehicle usage. This ``scalable city'' hypothesis may prove to a powerful predictor of the evolution of transportation in the large cities of the developing world.

Real driving emissions and fuel consumption characteristics of Istanbul public transportation

Directory of Open Access Journals (Sweden)

Ozener Orkun

2017-01-01

Full Text Available Public transportation, which uses intra city lines frequently, has vital importance on the cities air pollution. The fossil fuel based drive units, which emits pollutants, are the primary source of this interest. Also, the fuel consumption is another major concern because of economic aspects. For an efficient and clear transportation, the pollutants and fuel consumption has to be analyzed, considering the operating conditions. In this context, the Metrobus line of Istanbul city which crosses from European side to Asian side of the city was analyzed with portable emission measurement system and portable fuel consumption meter devices. The relevant bus operating data were also collected during the operation. The data were analyzed while considering the operating modes like acceleration, deceleration, and constant speed cruises. The emission factors were developed. The pollutant emissions generally decreased as the vehicle speed increased while the fuel consumption increased for the same acceleration level. These results show the importance of operating conditions and their non-linear effect on emissions and fuel consumption Istanbul public transportation.

Evaluation of next generation biomass derived fuels for the transport sector

International Nuclear Information System (INIS)

Tsita, Katerina G.; Pilavachi, Petros A.

2013-01-01

This paper evaluates next generation biomass derived fuels for the transport sector, employing the Analytic Hierarchy Process. Eight different alternatives of fuels are considered in this paper: bio-hydrogen, bio-synthetic natural gas, bio-dimethyl ether, bio-methanol, hydro thermal upgrading diesel, bio-ethanol, algal biofuel and electricity from biomass incineration. The evaluation of alternative fuels is performed according to various criteria that include economic, technical, social and policy aspects. In order to evaluate each alternative fuel, one base scenario and five alternative scenarios with different weight factors selection per criterion are presented. After deciding the alternative fuels’ scoring against each criterion and the criteria weights, their synthesis gives the overall score and ranking for all alternative scenarios. It is concluded that synthetic natural gas and electricity from biomass incineration are the most suitable next generation biomass derived fuels for the transport sector. -- Highlights: •Eight alternative fuels for the transport sector have been evaluated. •The method of the AHP was used. •The evaluation is performed according to economic, technical, social and policy criteria. •Bio-SNG and electricity from biomass incineration are the most suitable fuels

Can lignocellulosic hydrocarbon liquids rival lignocellulose-derived ethanol as a future transport fuel?

Directory of Open Access Journals (Sweden)

Yao Ding

2012-11-01

Full Text Available Although transport fuels are currently obtained mainly from petroleum, alternative fuels derived from lignocellulosic biomass (LB have drawn much attention in recent years in light of the limited reserves of crude oil and the associated environmental issues. Lignocellulosic ethanol (LE and lignocellulosic hydrocarbons (LH are two typical representatives of the LB-derived transport fuels. This editorial systematically compares LE and LB from production to their application in transport fuels. It can be demonstrated that LH has many advantages over LE relative to such uses. However, most recent studies on the production of the LB-derived transport fuels have focused on LE production. Hence, it is strongly recommended that more research should be aimed at developing an efficient and economically viable process for industrial LH production.

Study of fuel systems for LH2-fueled subsonic transport aircraft, volume 1

Science.gov (United States)

Brewer, G. D.; Morris, R. E.; Davis, G. W.; Versaw, E. F.; Cunnington, G. R., Jr.; Riple, J. C.; Baerst, C. F.; Garmong, G.

1978-01-01

Several engine concepts examined to determine a preferred design which most effectively exploits the characteristics of hydrogen fuel in aircraft tanks received major emphasis. Many candidate designs of tank structure and cryogenic insulation systems were evaluated. Designs of all major elements of the aircraft fuel system including pumps, lines, valves, regulators, and heat exchangers received attention. Selected designs of boost pumps to be mounted in the LH2 tanks, and of a high pressure pump to be mounted on the engine were defined. A final design of LH2-fueled transport aircraft was established which incorporates a preferred design of fuel system. That aircraft was then compared with a conventionally fueled counterpart designed to equivalent technology standards.

Transportation capabilities study of DOE-owned spent nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Clark, G.L.; Johnson, R.A.; Smith, R.W. [Packaging Technology, Inc., Tacoma, WA (United States); Abbott, D.G.; Tyacke, M.J. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

1994-10-01

This study evaluates current capabilities for transporting spent nuclear fuel owned by the US Department of Energy. Currently licensed irradiated fuel shipping packages that have the potential for shipping the spent nuclear fuel are identified and then matched against the various spent nuclear fuel types. Also included are the results of a limited investigation into other certified packages and new packages currently under development. This study is intended to support top-level planning for the disposition of the Department of Energy`s spent nuclear fuel inventory.

Usage Inspection of KN-12 Spent Fuel Transport Cask

International Nuclear Information System (INIS)

Lee, J. C.; Seo, K. S.; Bang, K. S.; Cho, I. J.; Kim, D. H.; Min, D. K.

2007-03-01

The usage inspection of the KN-12 spent nuclear fuel transport package was performed to receive the license for reuse. According to the Korea Atomic Energy Act, all type B transport package should receive and pass the usage inspection every five years. The KN-12 transport cask was designed to transport twelve spent PWR fuel assemblies under wet and dry conditions. The cask was developed and licensed in 2002 in accordance with the Korea and the IAEA's safe transport regulations. The areas of usage inspection include: visual inspection, nondestructive weld inspection, load test, maximum operating pressure test, leakage test, shielding test, thermal test, external surface contamination test. In the results of the usage inspection, the damage or defect could not found out and the performance of the cask was maintained according to the requirements of the regulation. Therefore, the usage inspection was successfully performed to acquire the license for the reuse

Research reactor fuel transport in the U.K

Energy Technology Data Exchange (ETDEWEB)

Panter, R [U.K. Atomic Energy Authority, Harwell (United Kingdom)

1983-09-01

This paper describes the containers currently used for transport of fresh or spent fuel elements for Research and Materials Test Reactors in the U.K., their status, operating procedures and some of the practical difficulties. In the U.K., MTR fuel cycle work is almost entirely the responsibility of the U.K. Atomic Energy Authority.

Integrated spent fuel storage and transportation system using NUHOMS

International Nuclear Information System (INIS)

Lehnert, R.; McConaghy, W.; Rosa, J.

1990-01-01

As utilities with nuclear power plants face increasing near term spent fuel store needs, various systems for dry storage such as the NUTECH Horizontal Modular Storage (NUHOMS) system are being implemented to augment existing spent fuel pool storage capacities. These decisions are based on a number of generic and utility specific considerations including both short term and long term economics. Since the US Department of Energy (DOE) is tasked by the Nuclear Waste Policy Act with the future responsibility of transporting spent fuel from commercial nuclear power plants to a Monitored Retrievable Storage (MRS) facility anchor a permanent geologic repository, the interfaces between the utilities at-reactor dry storage system and the DOE's away-from-reactor transportation system become important. This paper presents a study of the interfaces between the current at-reactor NUHOMS system and the future away-from-reactor DOE transportation system being developed under the Office of Civilian Radioactive Waste Management (OCRWM) program. 7 refs., 9 figs., 1 tab

Potential exposures and health effects from spent fuel transportation

International Nuclear Information System (INIS)

Sandquist, G.M.; Rogers, V.C.

1986-01-01

The radiation exposures and consequent health effects associated with normal operations and accidents during transportation of spent fuel have been analyzed and evaluated. This study was performed for the U.S. Department of Energy (DOE) as contributory data for response to specific public inquires regarding the Draft Environmental Assessments issued by DOE in 1984. Large quantities of spent fuel from power reactors will be shipped by truck and/or rail from the site of generation or temporary storage to nuclear waste repositories. This transportation activity has the potential for increasing radiation exposures and risks above normal background levels in the vicinity of the transportation route. For normal, accident-free transport of spent fuel, radiation exposures arise from both gamma and neutron sources within the spent fuel cask. U.S. regulations limit the radiation dose equivalent rate to 10 millirem per hour at any point 2 meters from the outer lateral surfaces of the transport vehicle. Computer program PATHRAE-T was developed and employed to determine the total, combined dose field. PATHRAE-T was used to estimate the maximum individual doses from rail cask accidents. The maximum individual exposure, primarily due to inhalation, is about 10 rem and occurs about 70 meters downwind. Ground deposited nuclides account for 99 percent of the population dose. The maximum population dose accident could result in about 22 latent health effects for the urban population. The same case rail cask accidents were also evaluated for a maximum water pathway contamination scenario. The nuclide contaminated plume was assumed to be transported over a large reservoir used for domestic and agricultural water. This accident could result in a 63,000 person-rem dose causing about 13 latent health effects in the absence of any natural and industrial processes for nuclide removal from the water

Regulations concerning the transport of nuclear fuel materials outside the works or the enterprise

International Nuclear Information System (INIS)

1979-01-01

The regulations are defined under the law for the regulations of nuclear source materials, nuclear fuel materials and reactors and the order for execution of the law. Basic concepts and terms are explained, such as: vehicle transport; easy transport; nuclear fuel material load, exclusive loading, employee, accumulative dose and exposure dose. Technical standards of vehicle transport are specified in detail on nucler fuel materials as nuclear fuel load, L,A, EM and BU type of load, nuclear fuel load of fission substances, the second and third type of fission load and materials contaminated by nuclear fuel substances to be carried not as nuclear fuel loads. Special exceptional measures to such transport and technical standards of easy transport are also designated. The application for confirmation of the transport shall be filed to the Director General of Science and Technology Agency according to the form attached with documents explaining nuclear fuel materials to be transferred, the vessel of such materials and construction, material and method of production of such a vessel, safety of nuclear materials contained, etc. Measures in dangerous situations shall be taken to fight a fire or prohibit the entrance of persons other than the staff concerned. Reports shall be presented in 10 days to the Director, when theft, loss or irregular leaking of nuclear fuel materials or personal troubles occur on the way. (Okada, K.)

Air quality effects of alternative fuels. Final report

Energy Technology Data Exchange (ETDEWEB)

Guthrie, P.; Ligocki, M.; Looker, R.; Cohen, J.

1997-11-01

To support the Alternative Fuels Utilization Program, a comparison of potential air quality effects of alternative transportation fuels is being performed. This report presents the results of Phase 1 of this program, focusing on reformulated gasoline (RFG), methanol blended with 15 percent gasoline (M85), and compressed natural gas (CNG). The fuels are compared in terms of effects on simulated future concentrations of ozone and mobile source air toxics in a photochemical grid model. The fuel comparisons were carried out for the future year 2020 and assumed complete replacement of gasoline in the projected light-duty gasoline fleet by each of the candidate fuels. The model simulations were carried out for the areas surrounding Los Angeles and Baltimore/DC, and other (non-mobile) sources of atmospheric emissions were projected according to published estimates of economic and population growth, and planned emission control measures specific to each modeling domain. The future-year results are compared to a future-year run with all gasoline vehicle emissions removed. The results of the comparison indicate that the use of M85 is likely to produce similar ozone and air toxics levels as those projected from the use of RFG. Substitution of CNG is projected to produce significantly lower levels of ozone and the mobile source air toxics than those projected for RFG or M85. The relative benefits of CNG substitution are consistent in both modeling domains. The projection methodologies used for the comparison are subject to a large uncertainty, and modeled concentration distributions depend on meteorological conditions. The quantitative comparison of fuel effects is thus likely to be sensitive to alternative assumptions. The consistency of the results for two very different modeling domains, using very different base assumptions, lends credibility to the qualitative differentiation among these fuels. 32 refs., 42 figs., 47 tabs.

Fuel transporting device in nuclear reactor

International Nuclear Information System (INIS)

Inoue, Tatsumi.

1975-01-01

Object: To obtain a support structure of an excellent quakeproof property for a fuel transporting device provided for the transportation of fuel between a reactor building and an auxiliary building in a pressure tube reactor or the like. Structure: The structure comprises an oblique transfer chute loosely penetrating the reactor building, reactor container and auxiliary building, a transfer chute support outer cylinder surrounding the transfer chute and having one end coupled to the transfer chute and other end coupled to the container, flexible seal members respectively provided on the reactor building side and on the auxiliary building side and surrounding the transfer chute and a slidable support supported on the side of the auxiliary building such that it can be in frictional contact with the outer periphery of the transfer chute. With this construction, the relative displacements of various parts caused by an earthquake or the like can be absorbed by the support outer cylinder, flexible seals and slidable support. (Ikeda, J.)

Postulated accident scenarios for the on-site transport of spent nuclear fuel

International Nuclear Information System (INIS)

Morandin, G.; Sauve, R.

2004-01-01

Once a spent fuel container is loaded with spent fuel it typically travels on-site to a processing building for permanent lid attachment. During on-site transport a lid clamp is utilized to ensure the container lid remains in place. The safe on-site transport of spent nuclear fuel must rely on the structural integrity of the transport container and system of transport. Regard for on-site traffic and safe, efficient travel routes are important and manageable with well thought-out planning. Non-manageable incidences, such as flying debris from tornado force winds or postulated blasts in proximity to the transport container, that may result in high velocity impact and shock loading on the transport system must be considered. This paper consists of simulations that consider these types of postulated accident scenarios using detailed nonlinear finite element techniques

Preliminary assessment of costs and risks of transporting spent fuel by barge

International Nuclear Information System (INIS)

Tobin, R.L.; Meshkov, N.K.; Jones, R.H.

1985-12-01

The purpose of this study is to analyze the costs and risks associated with transporting spent fuel by barge. The barge movements would be made in combination with rail movements to transport spent fuel from plants to a repository. For the purpose of this analysis, three candidate repository sites are analyzed: Yucca Mountain, Nevada, Deaf Smith, Texas, and Hanford, Washington. This report complements a report prepared by Sandia National Laboratories in 1984 that analyzes the costs and risks of transporting spent fuel by rail and by truck to nine candidate repository sites

Spent nuclear fuel and high level radioactive waste transportation. White paper

International Nuclear Information System (INIS)

1985-06-01

The High-Level Radioactive Waste Committee of the Western Interstate Energy Board has been involved in a year-long cooperative project with the US Department of Energy (DOE) to develop an information base on the transportation of spent nuclear fuel and high-level radioactive waste (HLW) so that western states can be constructive and informed participants in the repository program under the Nuclear Waste Policy Act (NWPA). The historical safety record of transportation of HLW and spent fuel is excellent; no release of these radioactive materials has ever occurred during transportation. Projected shipments under the NWPA will, however, greatly exceed current shipments in the US. For example, over the past five years, 119 metric tons of civilian spent fuel have been shipped in this country, while shipments to the first and second repository are each expected to peak at 3000 metric tons per year. The Committee believes that the successful development and operation of a national HLW/spent fuel transportation system can best be accomplished through an open process based on the common sense approach of taking all reasonable measures to minimize public risk and performing whatever actions are reasonably required to promote public acceptance. Therefore, the Committee recommends that the Department of Energy further the goals of the NWPA by developing a Comprehensive Transportation Plan which adopts a systematic, comprehensive, and integrated approach to resolving all spent fuel and HLW transportation issues in a timely manner. The suggested scope of such a plan is discussed in this White paper. Many of the suggested elements of such a plan are similar to those being developed by the Department of energy for inclusion in the Department's Transportation Institutional Plan

Quality control procedures for HTGR fuel element components

International Nuclear Information System (INIS)

Delle, W.W.; Koizlik, K.; Luhleich, H.; Nickel, H.

1976-08-01

The growing use of nuclear reactors for the production of electric power throughout the world, and the consequent increase in the number of nuclear fuel manufacturers, is giving enhanced importance to the consideration of quality assurance in the production of nuclear fuels. The fuel is the place, where the radioactive fission products are produced in the reactor and, therefore, the integrity of the fuel is of utmost importance. The first and most fundamental means of insuring that integrity is through the exercise of properly designed quality assurance programmes during the manufacture of the fuel and other fuel element components. The International Atomic Energy Agency therefore conducted an International Seminar on Nuclear Fuel Quality Assurance in Oslo, Norway from 24 till 28 May, 1976. This KFA report contains a paper which was distributed preliminary during the seminar and - in the second part - the text of the oral presentation. The paper gives a summary of the procedures available in the present state for the production control of HTGR core materials and of the meaning of the particular properties for reactor operation. (orig./UA) [de

Problems relating to international transport of nuclear fuels

International Nuclear Information System (INIS)

Timm, U.E.

1985-01-01

Owing to the tremendous geographic distances between uranium deposits of interest, to the various degrees of sophistication of nuclear industry in industrialized countries and to the close international cooperation in the field of nuclear energy, safe international transports, physical protection and transport handling play an important role. It is suggested to better coordinate the activities of nuclear power plant operators, the nuclear industry and specialized transport companies with respect to all national and international issues of nuclear fuel transports. (DG) [de

Fuel Prices as a Factor of Shaping Profitability of Road Transport in Poland

Directory of Open Access Journals (Sweden)

Marzantowicz Łukasz

2016-12-01

Full Text Available The goal of this article is to determine the relation between the price of fuel and the profitability of the company. For this purpose, the article defines the profitability of transport enterprises and points the source of the impact of changes in fuel prices on the profitability of companies in the road transport sector. The case of the ABC transport company shows the relationship between the costs incurred for the purchase of fuel and the cost of transport activities. To test the theoretical assumptions, case study method was used.

A Lifecycle Emissions Model (LEM): Lifecycle Emissions from Transportation Fuels, Motor Vehicles, Transportation Modes, Electricity Use, Heating and Cooking Fuels, and Materials, APPENDIX A: Energy Use and Emissions from the Lifecycle of Diesel-Like Fuels Derived From Biomass

OpenAIRE

Delucchi, Mark; Lipman, Timothy

2003-01-01

An Appendix to the Report, “A Lifecycle Emissions Model (LEM): Lifecycle Emissions From Transportation Fuels, Motor Vehicles, Transportation Modes, Electricity Use, Heating and Cooking Fuels, and Materialsâ€

Development and use of GREET 1.6 fuel-cycle model for transportation fuels and vehicle technologies

International Nuclear Information System (INIS)

Wang, M. Q.

2001-01-01

Since 1995, with funds from the U.S. Department of Energy's (DOE's) Office of Transportation Technologies (OTT), Argonne National Laboratory has been developing the Greenhouse gases, Regulated Emissions, and Energy use in Transportation (GREET) model. The model is intended to serve as an analytical tool for use by researchers and practitioners in estimating fuel-cycle energy use and emissions associated with alternative transportation fuels and advanced vehicle technologies. Argonne released the first version of the GREET mode--GREET 1.0--in June 1996. Since then, it has released a series of GREET versions with revisions, updates, and upgrades. In February 2000, the latest public version of the model--GREET 1.5a--was posted on Argonne's Transportation Technology Research and Development Center (TTRDC) Web site (www.transportation.anl.gov/ttrdc/greet)

Integrated Radiation Transport and Nuclear Fuel Performance for Assembly-Level Simulations

Energy Technology Data Exchange (ETDEWEB)

Clarno, Kevin T [ORNL; Hamilton, Steven P [ORNL; Philip, Bobby [ORNL; Berrill, Mark A [ORNL; Sampath, Rahul S [ORNL; Allu, Srikanth [ORNL; Pugmire, Dave [ORNL; Dilts, Gary [Los Alamos National Laboratory (LANL); Banfield, James E [ORNL

2012-02-01

The Advanced Multi-Physics (AMP) Nuclear Fuel Performance code (AMPFuel) is focused on predicting the temperature and strain within a nuclear fuel assembly to evaluate the performance and safety of existing and advanced nuclear fuel bundles within existing and advanced nuclear reactors. AMPFuel was extended to include an integrated nuclear fuel assembly capability for (one-way) coupled radiation transport and nuclear fuel assembly thermo-mechanics. This capability is the initial step toward incorporating an improved predictive nuclear fuel assembly modeling capability to accurately account for source-terms and boundary conditions of traditional (single-pin) nuclear fuel performance simulation, such as the neutron flux distribution, coolant conditions, and assembly mechanical stresses. A novel scheme is introduced for transferring the power distribution from the Scale/Denovo (Denovo) radiation transport code (structured, Cartesian mesh with smeared materials within each cell) to AMPFuel (unstructured, hexagonal mesh with a single material within each cell), allowing the use of a relatively coarse spatial mesh (10 million elements) for the radiation transport and a fine spatial mesh (3.3 billion elements) for thermo-mechanics with very little loss of accuracy. In addition, a new nuclear fuel-specific preconditioner was developed to account for the high aspect ratio of each fuel pin (12 feet axially, but 1 4 inches in diameter) with many individual fuel regions (pellets). With this novel capability, AMPFuel was used to model an entire 17 17 pressurized water reactor fuel assembly with many of the features resolved in three dimensions (for thermo-mechanics and/or neutronics), including the fuel, gap, and cladding of each of the 264 fuel pins; the 25 guide tubes; the top and bottom structural regions; and the upper and lower (neutron) reflector regions. The final, full assembly calculation was executed on Jaguar using 40,000 cores in under 10 hours to model over 162

CANDU fuel quality and how it is achieved

International Nuclear Information System (INIS)

Gacesa, M.; Quarrington, G.R.; Tarasuk, W.R.; Carrick, I.R.; Pawliw, J.; McGregor, G.; Debnam, H.R.; Proos, L.

1980-07-01

In this three part presentation CANDU fuel quality is reviewed from the point of view of a designer/operator and a fabricator. In Part 'A' fuel performance and quality considerations are discussed from the point of view of a designer-operator. In Parts 'B' and 'C' fuel quality is reviewed from the point of view of a fabricator. The presentation was divided in this way to convey the 'team effort' attitude which exists in the Canadian program; the team effort which is an essential part of the CANDU story. (auth)

Notification determining technical details concerning measures for transportation of nuclear fuel materials

International Nuclear Information System (INIS)

1977-01-01

These provisions are established on the basis of and to enforce ''The regulation for installation and operation of reactor'', ''The regulation concerning the fabricating business of nuclear fuel'' and ''The regulations concerning the reprocessing business of spent fuel''. The terms used hereinafter are according to those used in such regulations. The limit of radioactivity concentration of things contaminated by the nuclear fuel materials which are not required to be enclosed in vessels is defined in the lists attached. In the applications for the approval of the measures concerning the transport of things remarkably difficult to be enclosed in vessels, the name and the address of the applicant, the kind, quantity, form and constitution of the thing contaminated by the nuclear fuel materials to be transported, the date and route of the transport and the measures for the prevention of injuries during the transport must be written. The limit of quantity of nuclear fuel materials classifying the performance of vessels is defined respectively in the lists attached. The radiation dose rates provided for by the Director General of the Science and Technology Agency concerning transported things and transporting apparatuses are 200 millirem per hour on the surfaces of such things and containers. The nuclear fission materials specified, for which the measures for the prevention of criticality are especially required, include uranium 233, uranium 235, plutonium 238, plutonium 239, plutonium 241, and the chemical compounds of such substances, and the nuclear fuel materials containing one or two and more of such substances, excluding the nuclear fuel materials with less than 15 grams of such uranium and plutonium. (Okada, K.)

Transportation impact analysis for shipment of irradiated N-reactor fuel and associated materials

International Nuclear Information System (INIS)

Daling, P.M.; Harris, M.S.

1994-12-01

An analysis of the radiological and nonradiological impacts of highway transportation of N-Reactor irradiated fuel (N-fuel) and associated materials is described in this report. N-fuel is proposed to be transported from its present locations in the 105-KE and 105-KW Basins, and possibly the PUREX Facility, to the 327 Building for characterization and testing. Each of these facilities is located on the Hanford Site, which is near Richland, Washington. The projected annual shipping quantity is 500 kgU/yr for 5 years for a total of 2500 kgU. It was assumed the irradiated fuel would be returned to the K- Basins following characterization, so the total amount of fuel shipped was assumed to be 5000 kgU. The shipping campaign may also include the transport and characterization of liquids, gases, and sludges from the storage basins, including fuel assembly and/or canister parts that may also be present in the basins. The impacts of transporting these other materials are bounded by the impacts of transporting 5000 kgU of N-fuel. This report was prepared to support an environmental assessment of the N-fuel characterization program. The RADTRAN 4 and GENII computer codes were used to evaluate the radiological impacts of the proposed shipping campaign. RADTRAN 4 was used to calculate the routine exposures and accident risks to workers and the general public from the N-fuel shipments. The GENII computer code was used to calculate the consequences of the maximum credible accident. The results indicate that the transportation of N-fuel in support of the characterization program should not cause excess radiological-induced latent cancer fatalities or traffic-related nonradiological accident fatalities. The consequences of the maximum credible accident are projected to be small and result in no excess latent cancer fatalities

Usage Inspection of KN-12 Spent Fuel Transport Cask

Energy Technology Data Exchange (ETDEWEB)

Lee, J. C.; Seo, K. S.; Bang, K. S.; Cho, I. J.; Kim, D. H.; Min, D. K

2007-03-15

The usage inspection of the KN-12 spent nuclear fuel transport package was performed to receive the license for reuse. According to the Korea Atomic Energy Act, all type B transport package should receive and pass the usage inspection every five years. The KN-12 transport cask was designed to transport twelve spent PWR fuel assemblies under wet and dry conditions. The cask was developed and licensed in 2002 in accordance with the Korea and the IAEA's safe transport regulations. The areas of usage inspection include: visual inspection, nondestructive weld inspection, load test, maximum operating pressure test, leakage test, shielding test, thermal test, external surface contamination test. In the results of the usage inspection, the damage or defect could not found out and the performance of the cask was maintained according to the requirements of the regulation. Therefore, the usage inspection was successfully performed to acquire the license for the reuse.

Probabilistic Risk Assessment on Maritime Spent Nuclear Fuel Transportation

Energy Technology Data Exchange (ETDEWEB)

Christian, Robby; Kang, Hyun Gook [KAIST, Daejeon (Korea, Republic of)

2016-05-15

Spent nuclear fuel (SNF) management has been an indispensable issue in South Korea. Before a long term SNF solution is implemented, there exists the need to distribute the spent fuel pool storage loads. Transportation of SNF assemblies from populated pools to vacant ones may preferably be done through the maritime mode since all nuclear power plants in South Korea are located at coastal sites. To determine its feasibility, it is necessary to assess risks of the maritime SNF transportation. This work proposes a methodology to assess the risk arising from ship collisions during the transportation of SNF by sea. Its scope is limited to the damage probability of SNF packages given a collision event. The effect of transport parameters' variation to the package damage probability was investigated to obtain insights into possible ways to minimize risks. A reference vessel and transport cask are given in a case study to illustrate the methodology's application.

Ethanol as a Fuel for Road Transportation

Energy Technology Data Exchange (ETDEWEB)

Larsen, U.; Johansen, T.; Schramm, J.

2009-05-15

Bioethanol as a motor fuel in the transportation sector, mainly for road transportation, has been subject to many studies and much discussion. Furthermore, the topic involves not only the application and engine technical aspects, but also the understanding of the entire life cycle of the fuel, well-to-wheels, including economical, environmental, and social aspects. It is not, however, the aim of this report to assess every single one of these aspects. The present report aims to address the technical potential and problems as well as the central issues related to the general application of bioethanol as an energy carrier in the near future. A suitable place to start studying a fuel is at the production stage, and bioethanol has been found to have a potential to mitigate greenhouse gases, depending on the production method. This and a potential for replacing fossil fuel-based oil (and being renewable) are the main reasons why ethanol is considered and implemented. Therefore, we must focus on two central questions related to ethanol implementation: how much carbon dioxide (CO2) can be mitigated and how much fossil fuel can be replaced? A number of life cycle assessments have been performed in order to provide estimates. These assessments have generally shown that bioethanol has very good potential and can mitigate CO2 emissions very effectively, but It has also been shown that the potential for both fossil fuel replacement and CO2 mitigation is totally dependent on the method used to produce the fuel. Bioethanol can be made from a wide range of biomass resources, not all equally effective at mitigating CO2 emissions and replacing fossil fuel. The Brazilian ethanol experience has in many ways shown the way for the rest of the world, not least in the production stage. Brazil was the first and biggest producer of bioethanol, but the United States, China, India, and European Union have since then increased their production dramatically. Overall, bioethanol represents the

Alternative transportation fuels: Financing issues

International Nuclear Information System (INIS)

Squadron, W.F.; Ward, C.O.; Brown, M.H.

1992-06-01

A multitude of alternative fuels could reduce air pollution and the impact of oil price shocks. Only a few of these fuels are readily available and inexpensive enough to merit serious consideration over the coming five years. In New York City, safety regulations narrow the field still further by eliminating propane. As a result, this study focuses on the three alternative fuels readily available in New York City: compressed natural gas, methanol, and electricity. Each has significant environmental benefits and each has different cost characteristics. With the Clean Air Act and the National Energy Strategy highlighting the country's need to improve urban air quality and move away from dependence on imported fuels, fleets may soon have little choice but to convert to altemative fuels. Given the potential for large infrastructure and vehicle costs, these fleets may have difficulty finding the capital to make that conversion. Ultimately, then, it will be the involvement of the private sector that will determine the success of alternative fuels. Whether it be utilities, fuel distributors or suppliers, private financing partners or others, it is critical that altemative fuels programs be structured and planned to attract their involvement. This report examines financing methods that do not involve government subsidies. It also explores financing methods that are specific to alternative fuels. Bond issues and other mechanisms that are used for conventional vehicles are not touched upon in this report. This report explores ways to spread the high cost of alternative fuels among a number of parties within the private sector. The emphasis is on structuring partnerships that suit methanol, electric, or natural gas vehicle fleets. Through these partnerships, alternative fuels may ultimately compete effectively against conventional vehicle fuels

Spent fuel transportation regulatory and institutional issues

International Nuclear Information System (INIS)

Lippek, H.E.

1978-01-01

The problems that could result from state and local governments and other groups with relation to regulations concerning the transportation of spent nuclear fuels are discussed. The powers of the individual states as spelled out in the Clean Air Act Amendments of 1977 are set forth in some detail. The possibility of transportation employees gaining a position to demand and receive more stringent protections from hazards of radiation is pointed out

Assessment of health risks brought about by transportation of spent fuel

International Nuclear Information System (INIS)

Suolanen, V.; Lautkaski, R.; Rossi, J.

1999-03-01

In the study health risks caused by transportation of spent fuel from Olkiluoto and from Loviisa NPP's to the planned disposal site have been evaluated. The Olkiluoto NPP is owned by Teollisuuden Voima Oy (TVO) and the Loviisa NPP, situated at Haestholmen, by Fortum Power and Heat Oy. According to the base scenario of 40 years use of the current NPP's the total amount of spent fuel will be 1840 tU (TVO) and 860 tU (Fortum). Annually, 110 tU on the average and at most 250 tU will be transported to the disposal site. The considered transportation routes are from Olkiluoto to Haestholmen, from Olkiluoto to Kivetty, from Olkiluoto to Romuvaara, from Haestholmen to Olkiluoto, from Haestholmen to Kivetty and from Haestholmen to Romuvaara. The considered transportation modes are truck, rail or ship, or combinations of these modes. Each transportation route has been divided into homogenised sequences with respect to population density and/or route type. Total amount of analysed route options were 40, some route sequences are overlapping. Radiation exposures to the population along the routes have been calculated in normal, incident and accident situations during transportation. Occupational radiation doses to the personnel have been estimated for normal transportation only. The consequences of normal transportation have been evaluated based on RADTRAN-model, developed by the Sandia National Laboratories. As incidents, stopping of spent fuel transportation for an exceptionally long period of time, and in another case contamination of outer surface of spent fuel cask have been considered. Expected collective doses and health risks of transportation accidents connected to the routes have been calculated with RADTRAN-model. Single hypothetical transport accidents with pessimistic release assumptions have been further analysed in more detail with the ARANO-model, developed by VTT (Technical Research Centre of Finland). (orig.)

Transport of Spent Nuclear Fuels, High and Intermediate Level Wastes: A Continuous Challenge

International Nuclear Information System (INIS)

Otton, C.; Blachet, L.

2009-01-01

For more than 45 years TN International has been involved in the radioactive materials transportation field. Since the beginning the used nuclear fuel transportation has been its core business. During all these years TN International, now part of AREVA, has been able to anticipate and fulfil the needs for new transport or storage casks design to fit the nuclear industry evolutions. A whole fleet of casks able to transport all the materials of the nuclear fuel cycle has been developed. In this presentation we will focus on the casks for the spent fuel, high level waste and intermediate level waste transportation. Answering to the constant evolution of the nuclear industry transport needs is a challenge that TN International faces routinely. Concerning the spent nuclear fuel transportation, TN International has developed in the early 80's a fleet of TN12 type casks fitted with several types of baskets able to safely transport all the spent fuel from the nuclear power plant or the research laboratories to AREVA La Hague plant. The current challenge is the design of a new transport cask generation taking into account the needs of the industry for the next 30 years. The replacement of the TN12 cask generation is to be scheduled as the regulations have changed and the fuel characteristics have evolved. The new generation of casks will take into account all the technical evolutions made during the TN12 thirty years of use. MOX spent fuel has now its dedicated cask: the TN112 which certificate of approval has been obtained in July 2008. This cask is able to transport 12 MOX spent fuel elements with a short cooling time. The first loading of the cask has been performed in 2008 in the EDF nuclear power plant of Saint-Laurent-des-Eaux. Concerning the high level waste such as the La Hague vitrified residues a whole fleet of casks has been developed such as the TN 28 VT dedicated to transport, the TN81 and TN85 dedicated to transport and storage. These casks have permitted the

Homogeneity of blended nuclear fuel powders after pneumatic transport

International Nuclear Information System (INIS)

Smeltzer, E.E.; Skriba, M.C.; Lyon, W.L.

1982-01-01

A study of the pneumatic transport of fine (approx. 1μm) cohesive nuclear fuel powders was conducted for the U.S. Department of Energy to demonstrate the feasibility of this method of transport and to develop a design data base for use in a large scale nuclear fuel production facility. As part of this program, a considerable effort was directed at following the homogeneity of blended powders. Since different reactors require different enrichments, blending and subsequent transport are critical parts of the fabrication sequence. The various materials used represented analogs of a wide range of powders and blends that could be expected in a commercial mixed oxide fabrication facility. All UO 2 powders used were depleted and a co-precipitated master mix of (U, Th)O 2 was made specifically for this program, using thorium as an analog for plutonium. In order to determine the effect of pneumatic transport on a blended powder, samples were taken from a feeder vessel before each test, and from a receiver vessel and a few line sections after each transfer test. The average difference between the before and after degree of non-homogeneity was < 1%, for the 21 tests considered. This shows that overall, the pneumatic transport of blended, fine nuclear fuel powders is possible, with only minor unblending occurring

Transport safety of irradiated fuel; Seguridad en el transporte de combustible irradiado.

Energy Technology Data Exchange (ETDEWEB)

Rosa Giménez, R. de la

2016-07-01

The complication of the transport of spent fuel is significant not only because of the danger of the transported good itself but also for the size of the package. The number of this kind of expeditions are supposed to increase considerably in the coming years, for that reason is necessary for specialized companies such as ETSA be prepared. To this end, ETSA has already implemented most of the measures necessary to ensure safety - security of transport, not only during its execution but throughout the preparation.

Ecological aspects of water coal fuel transportation and application

Directory of Open Access Journals (Sweden)

Anna SHVORNIKOVA

2010-01-01

Full Text Available This paper deals with the aspects of influence of transportation process and burning of water coal fuel on an ecological condition of environment. Also mathematical dependences between coal ash level and power consumption for transportation are presented.

Microalgal and terrestrial transport biofuels to displace fossil fuels

NARCIS (Netherlands)

Reijnders, L.

2009-01-01

Terrestrial transport biofuels differ in their ability to replace fossil fuels. When both the conversion of solar energy into biomass and the life cycle inputs of fossil fuels are considered, ethanol from sugarcane and biodiesel from palm oil do relatively well, if compared with ethanol from corn,

Production process and quality control for the HTTR fuel

International Nuclear Information System (INIS)

Yoshimuta, S.; Suzuki, N.; Kaneko, M.; Fukuda, K.

1991-01-01

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

Microalgal and Terrestrial Transport Biofuels to Displace Fossil Fuels

Directory of Open Access Journals (Sweden)

Lucas Reijnders

2009-02-01

Full Text Available Terrestrial transport biofuels differ in their ability to replace fossil fuels. When both the conversion of solar energy into biomass and the life cycle inputs of fossil fuels are considered, ethanol from sugarcane and biodiesel from palm oil do relatively well, if compared with ethanol from corn, sugar beet or wheat and biodiesel from rapeseed. When terrestrial biofuels are to replace mineral oil-derived transport fuels, large areas of good agricultural land are needed: about 5x108 ha in the case of biofuels from sugarcane or oil palm, and at least 1.8-3.6x109 ha in the case of ethanol from wheat, corn or sugar beet, as produced in industrialized countries. Biofuels from microalgae which are commercially produced with current technologies do not appear to outperform terrestrial plants such as sugarcane in their ability to displace fossil fuels. Whether they will able to do so on a commercial scale in the future, is uncertain.

A quality assurance programme for reload fuel for light-water reactors

International Nuclear Information System (INIS)

Nilson, R.

1976-01-01

The Exxon Nuclear quality assurance programme for the design and fabrication of reload fuel for light-water reactors is described. The programme is based on the 18 quality assurance criteria used for the design and construction of nuclear facilities in the United States of America, but is broadened considerably to reflect other inputs and experiences unique to nuclear fuel production. The government and utility interfaces with the fuel supplier in the area of quality assurance, and future trends, for example, the development of topical quality assurance reports, are also discussed. Quality assurance is discussed in terms of three fundamental categories: management control, engineering assurance and quality control. Examples of specific design, processing and inspection considerations which relate to known fuel failure mechanisms are discussed. The results of irradiated fuel examinations to date have shown that certain fuel failure mechanisms can be alleviated by the considerations described and that fuel of the requisite quality can be consistently produced. (author)

Transport of oxide spent fuel. Industrial experience of COGEMA

International Nuclear Information System (INIS)

Lenail, B.

1983-01-01

COGEMA is ruling all transports of spent fuel to La Hague reprocessing plant. The paper summarizes some aspects of the experience gained in this field (road, rail and sea transports) and describes the standards defined by COGEMA as regards transport casks. These standards are as follows: - casks of dry type, - casks of the maximum size compatible with rail transports, - capability to be unloaded with standardized equipment and following standard procedures

A complete NUHOMS {sup registered} solution for storage and transport of high burnup spent fuel

Energy Technology Data Exchange (ETDEWEB)

Bondre, J. [Transnuclear, Inc. (AREVA Group), Fremont, CA (United States)

2004-07-01

The discharge burnups of spent fuel from nuclear power plants keep increasing with plants discharging or planning to discharge fuel with burnups in excess of 60,000 MWD/MTU. Due to limited capacity of spent fuel pools, transfer of older cooler spent fuel from fuel pool to dry storage, and very limited options for transport of spent fuel, there is a critical need for dry storage of high burnup, higher heat load spent fuel so that plants could maintain their full core offload reserve capability. A typical NUHOMS {sup registered} solution for dry spent fuel storage is shown in the Figure 1. Transnuclear, Inc. offers two advanced NUHOMS {sup registered} solutions for the storage and transportation of high burnup fuel. One includes the NUHOMS {sup registered} 24PTH system for plants with 90.7 Metric Ton (MT) crane capacity; the other offers the higher capacity NUHOMS {sup registered} 32PTH system for higher crane capacity. These systems include NUHOMS {sup registered} - 24PTH and -32PTH Transportable Canisters stored in a concrete storage overpack (HSM-H). These canisters are designed to meet all the requirements of both storage and transport regulations. They are designed to be transported off-site either directly from the spent fuel pool or from the storage overpack in a suitable transport cask.

Experience with quality assurance in fuel design and manufacturing

International Nuclear Information System (INIS)

Holzer, R.; Nilson, F.

1984-01-01

The Quality Assurance/Quality Control activities for nuclear fuel design and manufacturing described here are coordinated under a common ''Quality Assurance System For Fuel Assemblies and Associated Core Components'' which regulates the QA-functions of the development, design and manufacturing of fuel assemblies independent of the organizational assignment of the contributing technical groups. Some essential characteristics of the system are shown, using examples from design control, procurement, manufacturing and qualification of special processes. The experience is very good, it allowed a flexible and well controlled implementation of design and manufacturing innovations and contributed to the overall good fuel behavior. (orig.)

Analysis of transport phenomena and electrochemical reactions in a micro PEM fuel cell

Energy Technology Data Exchange (ETDEWEB)

Sadiq Al-Baghdadi, Maher A.R. [Fuel Cell Research Center, International Energy and Environment Foundation, Najaf, P.O.Box 39 (Iraq)

2013-07-01

Micro-fuel cells are considered as promising electrochemical power sources in portable electronic devices. The presence of microelectromechanical system (MEMS) technology makes it possible to manufacture the miniaturized fuel cell systems. The majority of research on micro-scale fuel cells is aimed at micro-power applications. Performance of micro-fuel cells are closely related to many factors, such as designs and operating conditions. CFD modeling and simulation for heat and mass transport in micro PEM fuel cells are being used extensively in researches and industrial applications to gain better understanding of the fundamental processes and to optimize the micro fuel cell designs before building a prototype for engineering application. In this research, full three-dimensional, non-isothermal computational fluid dynamics model of a micro proton exchange membrane (PEM) fuel cell has been developed. This comprehensive model accounts for the major transport phenomena such as convective and diffusive heat and mass transfer, electrode kinetics, transport and phase-change mechanism of water, and potential fields in a micro PEM fuel cell. The model explains many interacting, complex electrochemical, and transport phenomena that cannot be studied experimentally. Three-dimensional results of the species profiles, temperature distribution, potential distribution, and local current density distribution are presented and analysed, with the focus on the physical insight and fundamental understanding.

Portable Fuel Quality Analyzer

Science.gov (United States)

2014-01-27

other transportation industries, such as trucking. The PFQA could also be used in fuel blending operations performed at petroleum, ethanol and biodiesel plants. ...Report Documentation Page Form ApprovedOMB No. 0704-0188 Public reporting burden for the collection of information is estimated to average 1 hour per...24476 12. DISTRIBUTION/AVAILABILITY STATEMENT Approved for public release; distribution unlimited 13. SUPPLEMENTARY NOTES 14. ABSTRACT The

Transport systems - solid indigenous fuels. [Identification of fuel transport problems in Sweden]. Transportsystem foer fasta inhemska braenslen

Energy Technology Data Exchange (ETDEWEB)

Colliander, J

1985-12-01

The following problems have been indentified: - A rational structure of transporting requires an established and relatively open market. - The necessary rolling stock for fuel conveyance by rail is not available. - Roads have to be improved and new roads have to be built. Railways with low load now might get a motivation for reinforcement. - Because of the irregular spread of consumption storing and terminals problems will arise and increase the cost of transport. - Terminals and stores are situated at a convenient place for one single enterprice. On a far-away aim this will not be rational.

Alternative Fuels Data Center: Fleet Application for School Transportation

Science.gov (United States)

Propane Buses Jan. 26, 2016 Video thumbnail for Biodiesel Offers an Easy Alternative for Fleets Biodiesel thumbnail for Biodiesel Fuels Education in Alabama Biodiesel Fuels Education in Alabama May 1, 2012 Video School Transportation Videos on YouTube Video thumbnail for New Hampshire Cleans up with Biodiesel Buses

Quality management and quality assurance in the manufacture of nuclear fuel elements: new trends and challenges

International Nuclear Information System (INIS)

Baur, K.

1998-01-01

Modern instruments for quality assurance are applied with increasing success also in the area of fuel element supply. This new philosophy of quality management is characterized by a clear focus on processes and a commitment to continuous quality improvement. How can these new quality concepts, the application of which is desired by the companies operating nuclear power plants, be implemented and find acceptance? Is it possible that error prevention in place of error correction can increase the quality of fuel elements and at the same time reduce costs? What instruments are available to solve problems specific to fuel element technology? Efforts currently under way to answer these questions are described, particularly with regard to cooperation with fuel element suppliers. Within this context, a new guideline 'Quality System for Fuel Elements' has been developed. (orig.) [de

Quality evaluation of the nuclear fuel manufactured in Romania before 1990

International Nuclear Information System (INIS)

Budan, O.; Galeriu, C.A.; Pascu, A.; Bailescu, A.; Andrei, G.

1997-01-01

Nuclear fuel fabricated in Romania before June 1990 was stored and was not licensed for the use in reactor. A preliminary appraisal performed by AECL and Zircatec experts in 1990, considered this fuel as being of suspect quality. Taking into consideration that Nuclear Fuel Plant was qualified to produce CANDU-6 fuel, only after 1990, RENEL-GEN authorized FCN to evaluate the actual quality of the stock fuel, in 1996. A documented evaluation program was developed and implemented. Stock production of each year was considered as one fuel bundle lot. Quality verification was done on statistical basis. Random sampling was applied, with the condition that each production week was represented in the sample. The results show that the fuel quality is not acceptable for in-reactor use. Recovery solutions for the stock fuel were established and already applied. An independent review of the program, results and recovery solutions, made by AECL confirmed the consistency of the work performed by FCN for stock fuel quality evaluation. (author)

Economics of radioactive material transportation in the light-water reactor nuclear fuel cycle

International Nuclear Information System (INIS)

Dupree, S.A.; O'Malley, L.C.

1980-10-01

This report presents estimates of certain transportation costs, in 1979 dollars, associated with Light-Water Reactor (LWR) once-through and recycle fuel cycles. Shipment of fuel, high-level waste and low-level waste was considered. Costs were estimated for existing or planned transportation systems and for recommended alternate systems, based on the assumption of mature fuel cycles. The annual radioactive material transportation costs required to support a nominal 1000-MW(e) LWR in a once-through cycle in which spent fuel is shipped to terminal storage or disposal were found to be approx. $490,000. Analogous costs for an average reactor operating in a fuel cycle with uranium and plutonim recycle were determined to be approx. $770,000. These results assume that certain recommended design changes will occur in radioactive material shipping systems as a mature fuel cycle evolves

Transport and storage of spent fuel in Germany - possibilities for more safety

International Nuclear Information System (INIS)

Brennecke, P.; Fasten, Ch.; Nitsche, F.

2004-01-01

The safe transport of spent fuel from nuclear power plants in Germany is ensured by compliance with the dangerous goods transport regulations of class 7 which are fully consistent with the IAEA Transport Regulations and in parallel with the regulations of the German Atomic Energy Act. The purpose of this paper is to give an overview of this legal basis and the appropriate regulations applicable to spent fuel transport in Germany. Some aspects of the status and the future development of spent fuel shipments are described including experiences since resumption of those shipments in 2001. Furthermore, the status of licensing of on-site interim storage, assessments of an terrorist attack as well as consequences resulting from changes in energy policy are given

Alternative Fuels in Transportation : Workforce needs and opportunities in support of reducing reliance on petroleum fuels

Science.gov (United States)

2016-01-01

An overreliance on foreign oil and the negative impacts of using petroleum fuels on the worlds climate have prompted energy policies that support the diversification of transport fuels and aggressive work to transition to non-petroleum options. Th...

Programmatic and technical requirements for the FMDP fresh MOX fuel transport package

International Nuclear Information System (INIS)

Ludwig, S.B.; Michelhaugh, R.D.; Pope, R.B.

1997-12-01

This document is intended to guide the designers of the package to all pertinent regulatory and other design requirements to help ensure the safe and efficient transport of the weapons-grade (WG) fresh MOX fuel under the Fissile Materials Disposition Program. To accomplish the disposition mission using MOX fuel, the unirradiated MOX fuel must be transported from the MOX fabrication facility to one or more commercial reactors. Because the unirradiated fuel contains large quantities of plutonium and is not sufficient radioactive to create a self-protecting barrier to deter the material from theft, DOE intends to use its fleet of safe secure trailers (SSTs) to provide the necessary safeguards and security for the material in transit. In addition to these requirements, transport of radioactive materials must comply with regulations of the Department of Transportation and the Nuclear Regulatory Commission (NRC). In particular, NRC requires that the packages must meet strict performance requirements. The requirements for shipment of MOX fuel (i.e., radioactive fissile materials) specify that the package design is certified by NRC to ensure the materials contained in the packages are not released and remain subcritical after undergoing a series of hypothetical accident condition tests. Packages that pass these tests are certified by NRC as a Type B fissile (BF) package. This document specifies the programmatic and technical design requirements a package must satisfy to transport the fresh MOX fuel assemblies

Production Costs of Alternative Transportation Fuels. Influence of Crude Oil Price and Technology Maturity

Energy Technology Data Exchange (ETDEWEB)

Cazzola, Pierpaolo; Morrison, Geoff; Kaneko, Hiroyuki; Cuenot, Francois; Ghandi, Abbas; Fulton, Lewis

2013-07-01

This study examines the production costs of a range of transport fuels and energy carriers under varying crude oil price assumptions and technology market maturation levels. An engineering ''bottom-up'' approach is used to estimate the effect of the input cost of oil and of various technological assumptions on the finished price of these fuels. In total, the production costs of 20 fuels are examined for crude oil prices between USD 60 and USD 150 per barrel. Some fuel pathways can be competitive with oil as their production, transport and storage technology matures, and as oil price increases. Rising oil prices will offer new opportunities to switch to alternative fuels for transport, to diversify the energy mix of the transport sector, and to reduce the exposure of the whole system to price volatility and potential distuption of supply. In a time of uncertainty about the leading vehicle technology to decarbonize the transport sector, looking at the fuel cost brings key information to be considered to keep mobility affordable yet sustainable.

The role of bio-fuels in satisfying US transportation fuel demands

Energy Technology Data Exchange (ETDEWEB)

Akinci, Berk; Fitch, Jonathan V. [Department of Electrical Engineering, Worcester Polytechnic Institute, 100 Institute Road, Worcester, MA 01609 (United States); Kassebaum, Paul G. [Department of Mechanical Engineering, Worcester Polytechnic Institute, 100 Institute Road, Worcester, MA 01609 (United States); Thompson, Robert W. [Department of Chemical Engineering, Worcester Polytechnic Institute, 100 Institute Road, Worcester, MA 01609 (United States)

2008-09-15

In spite of the abundant interest in conversion of agricultural products into useful energy carriers, there have been relatively few studies assessing the magnitude of the impact these fuels can make on satisfying US energy demands. There have been fewer studies of unintended consequences stemming from these enterprises, although several research groups have begun questioning the appropriate levels of subsidies provided to individuals and companies to stimulate production of bio-fuels. In this paper, the production capacities for bio-fuels - ethanol and biodiesel - are evaluated for their potential impact on the US energy market. Several ramifications of these technologies are reviewed. This study concludes that ethanol or biodiesel production do not appear scalable to make a significant difference on the US fossil fuel demand for transportation. Aspects of this study point to systemic changes that may be required in lifestyles and attitudes toward energy consumption. Finally, comments regarding US energy policies are included to stimulate discussion. (author)

The role of bio-fuels in satisfying US transportation fuel demands

International Nuclear Information System (INIS)

Akinci, Berk; Kassebaum, Paul G.; Fitch, Jonathan V.; Thompson, Robert W.

2008-01-01

In spite of the abundant interest in conversion of agricultural products into useful energy carriers, there have been relatively few studies assessing the magnitude of the impact these fuels can make on satisfying US energy demands. There have been fewer studies of unintended consequences stemming from these enterprises, although several research groups have begun questioning the appropriate levels of subsidies provided to individuals and companies to stimulate production of bio-fuels. In this paper, the production capacities for bio-fuels-ethanol and biodiesel-are evaluated for their potential impact on the US energy market. Several ramifications of these technologies are reviewed. This study concludes that ethanol or biodiesel production do not appear scalable to make a significant difference on the US fossil fuel demand for transportation. Aspects of this study point to systemic changes that may be required in lifestyles and attitudes toward energy consumption. Finally, comments regarding US energy policies are included to stimulate discussion

Develpment of quality assurance manual for fabrication of DUPIC fuel

Energy Technology Data Exchange (ETDEWEB)

Lee, Young Gun; Lee, J. W.; Kim, S. S. and others

2001-09-01

The Quality Assurance Manual for the fabrication of DUPIC fuel with high quality was developed. The Quality Assurance Policy established by this manual is to assure that the DUPIC fuel element supplied to customer conform to the specified requirements of customer, applicable codes and standards. The management of KAERI is committed to implementation and maintenance of the program described by this manual. This manual describes the quality assurance program for DUPIC fuel fabrication to comply with CAN3-Z299.2-85 to the extent as needed and appropriate. This manual describes the methods which DUPIC Fuel Development Team(DFDT) personnel must follow to achieve and assure high quality of our product. This manual also describes the quality management system applicable to the activities performed at DFDT.

Develpment of quality assurance manual for fabrication of DUPIC fuel

International Nuclear Information System (INIS)

Lee, Young Gun; Lee, J. W.; Kim, S. S. and others

2001-09-01

The Quality Assurance Manual for the fabrication of DUPIC fuel with high quality was developed. The Quality Assurance Policy established by this manual is to assure that the DUPIC fuel element supplied to customer conform to the specified requirements of customer, applicable codes and standards. The management of KAERI is committed to implementation and maintenance of the program described by this manual. This manual describes the quality assurance program for DUPIC fuel fabrication to comply with CAN3-Z299.2-85 to the extent as needed and appropriate. This manual describes the methods which DUPIC Fuel Development Team(DFDT) personnel must follow to achieve and assure high quality of our product. This manual also describes the quality management system applicable to the activities performed at DFDT

10 CFR 51.52 - Environmental effects of transportation of fuel and waste-Table S-4.

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Environmental effects of transportation of fuel and waste... Environmental effects of transportation of fuel and waste—Table S-4. Under § 51.50, every environmental report... detailed analysis of the environmental effects of transportation of fuel and wastes to and from the reactor...

The Role of Distribution Infrastructure and Equipment in the Life-cycle Air Emissions of Liquid Transportation Fuels

Science.gov (United States)

Strogen, Bret Michael

component. In order to apply the new emission factors to policy-relevant scenarios, a projection is made for the fleet inventory of infrastructure components necessary to distribute 21 billion gallons of ethanol (the 2022 federal mandate for advanced biofuels under the Energy Independence and Security Act of 2007) derived entirely from Miscanthus grass, for comparison to the baseline petroleum system. Due to geographic, physical and chemical properties of biomass and alcohols, the distribution system for Miscanthus-based ethanol is more capital- and energy-intensive than petroleum per unit of fuel energy delivered. The transportation of biofuels away from producer regions poses environmental, health, and economic trade-offs that are herein evaluated using a simplified national distribution network model. In just the last ten years, ethanol transportation within the contiguous United States is estimated to have increased more than ten-fold in total t-km as ethanol has increasingly been transported away from Midwest producers due to air quality regulations pertaining to gasoline, renewable fuel mandates, and the 10% blending limit (i.e., the E10 blend wall). From 2004 to 2009, approximately 10 billion t-km of ethanol transportation are estimated to have taken place annually for reasons other than the E10 blend wall, leading to annual freight costs greater than $240 million and more than 300,000 tonnes of CO2-e emissions and significant emissions of criteria air pollutants from the combustion of more than 90 million liters of diesel. Although emissions from distribution activities are small when normalized to each unit of fuel, they are large in scale. Archetypal fuel distribution routes by rail and by truck are created to evaluate the significance of mode choice and route location on the severity of public health impacts from locomotive and truck emissions, by calculating the average PM2.5 pollution intake fraction along each route. Exposure to pollution resulting from

Energy system aspects of hydrogen as an alternative fuel in transport

International Nuclear Information System (INIS)

Ramesohl, Stephan; Merten, Frank

2006-01-01

Considering the enormous ecological and economic importance of the transport sector the introduction of alternative fuels-together with drastic energy efficiency gains-will be a key to sustainable mobility, nationally as well as globally. However, the future role of alternative fuels cannot be examined from the isolated perspective of the transport sector. Interactions with the energy system as a whole have to be taken into account. This holds both for the issue of availability of energy sources as well as for allocation effects, resulting from the shift of renewable energy from the stationary sector to mobile applications. With emphasis on hydrogen as a transport fuel for private passenger cars, this paper discusses the energy systems impacts of various scenarios introducing hydrogen fueled vehicles in Germany. It identifies clear restrictions to an enhanced growth of clean hydrogen production from renewable energy sources (RES). Furthermore, it points at systems interdependencies that call for a priority use of RES electricity in stationary applications. Whereas hydrogen can play an increasing role in transport after 2030 the most important challenge is to exploit short-mid-term potentials of boosting car efficiency

Existing experimental criticality data applicable to nuclear-fuel-transportation systems

International Nuclear Information System (INIS)

Bierman, S.R.

1983-02-01

Analytical techniques are generally relied upon in making criticality evaluations involving nuclear material outside reactors. For these evaluations to be accepted the calculations must be validated by comparison with experimental data for a known set of conditions having physical and neutronic characteristics similar to those conditions being evaluated analytically. The purpose of this report is to identify those existing experimental data that are suitable for use in verifying criticality calculations on nuclear fuel transportation systems. In addition, near term needs for additional data in this area are identified. Of the considerable amount of criticality data currently existing, that are applicable to non-reactor systems, those particularly suitable for use in support of nuclear material transportation systems have been identified and catalogued into the following groups: (1) critical assemblies of fuel rods in water; (2) critical assemblies of fuel rods in water containing soluble neutron absorbers; (3) critical assemblies containing solid neutron absorber; (4) critical assemblies of fuel rods in water with heavy metal reflectors; and (5) critical assemblies of fuel rods in water with irregular features. A listing of the current near term needs for additional data in each of the groups has been developed for future use in planning criticality research in support of nuclear fuel transportation systems. The criticality experiments needed to provide these data are briefly described and identified according to priority and relative cost of performing the experiments

Experience with fuel damage caused by abnormal conditions in handling and transporting operations

International Nuclear Information System (INIS)

Bailey, W.J.

1983-01-01

Pacific Northwest Laboratory (PNL) conducted a study to determine the expected condition of spent USA light-water reactor (LWR) fuel upon arrival at interim storage or fuel reprocessing facilities or, if fuel is declared a waste, at disposal facilities. Initial findings were described in an earlier PNL paper at PATRAM '80 and in a report. Updated findings are described in this paper, which includes an evaluation of information obtained from the literature and a compilation of cases of known or suspected damage to fuel as a result of handling and/or transporting operations. To date, PNL has evaluated 123 actual cases (98 USA and 25 non-USA). Irradiated fuel was involved in all but 10 of the cases. From this study, it is calculated that the frequency of unusual occurrences involving fuel damage from handling and transporting operations has been low. The damage that did occur was generally minor. The current base of experience with fuel handling and transporting operations indicates that nearly all of these unusual occurrences had only a minor or negligible effect on spent fuel storage facility operations

Sustainable fuel for the transportation sector.

Science.gov (United States)

Agrawal, Rakesh; Singh, Navneet R; Ribeiro, Fabio H; Delgass, W Nicholas

2007-03-20

A hybrid hydrogen-carbon (H(2)CAR) process for the production of liquid hydrocarbon fuels is proposed wherein biomass is the carbon source and hydrogen is supplied from carbon-free energy. To implement this concept, a process has been designed to co-feed a biomass gasifier with H(2) and CO(2) recycled from the H(2)-CO to liquid conversion reactor. Modeling of this biomass to liquids process has identified several major advantages of the H(2)CAR process. (i) The land area needed to grow the biomass is transportation sector. (ii) Whereas the literature estimates known processes to be able to produce approximately 30% of the United States transportation fuel from the annual biomass of 1.366 billion tons, the H(2)CAR process shows the potential to supply the entire United States transportation sector from that quantity of biomass. (iii) The synthesized liquid provides H(2) storage in an open loop system. (iv) Reduction to practice of the H(2)CAR route has the potential to provide the transportation sector for the foreseeable future, using the existing infrastructure. The rationale of using H(2) in the H(2)CAR process is explained by the significantly higher annualized average solar energy conversion efficiency for hydrogen generation versus that for biomass growth. For coal to liquids, the advantage of H(2)CAR is that there is no additional CO(2) release to the atmosphere due to the replacement of petroleum with coal, thus eliminating the need to sequester CO(2).

Aircraft transporting container for nuclear fuel

International Nuclear Information System (INIS)

Kurakami, Jun-ichi; Kubo, Minoru.

1991-01-01

The present invention concerns an air craft transporting container for nuclear fuels. A sealing container that seals a nuclear fuel container and constitutes a sealed boundary for the transporting container is incorporated in an inner container. Shock absorbers are filled for absorbing impact shock energy in the gap between the inner container and the sealing container. The inner container is incorporated with wooden impact shock absorbers being filled so that it is situated in a substantially central portion of an external container. Partitioning cylinders are disposed coaxially in the cylindrical layer filled with wooden impact shock absorbers at an intermediate portion between the outer and the inner containers. Further, a plurality of longitudinally intersecting partitioning disks are disposed each at a predetermined distance in right and left cylindrical wooden impact shock absorbing layers which are in contact with the end face of the inner container. Accordingly, the impact shock energy can be absorbed by the wooden impact shock absorbers efficiently by a plurality of the partitioning disks and the partitioning cylinders. (I.N.)

Transporting spent fuel and reactor waste in Sweden experience from 5 years of operation

International Nuclear Information System (INIS)

Dybeck, P.; Gustafsson, B.

1990-01-01

This paper reports that since the Final Repository for Reactor Waste, SFR, was taken into operation in 1988, the SKB sea transportation system is operating at full capacity by transporting spent fuel and now also reactor waste from the 12 Swedish reactors to CLAB and SFR. Transports from the National Research Center, Studsvik to the repository has recently also been integrated in the system. CLAB, the central intermediate storage for spent fuel, has been in operation since 1985. The SKB Sea Transportation System consists today of the purpose built ship M/s Sigyn, 10 transport casks for spent fuel, 2 casks for spent core components, 27 IP-2 shielded steel containers for reactor waste and 5 terminal vehicles. During an average year about 250 tonnes of spent fuel and 3 -- 4000 m 3 of reactor waste are transported to CLAB and SFR respectively, corresponding to around 30 sea voyages

Mechanical Fatigue Testing of High Burnup Fuel for Transportation Applications

Energy Technology Data Exchange (ETDEWEB)

Wang, Jy-An John [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wang, Hong [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2015-05-01

This report describes testing designed to determine the ability of high burnup (HBU) (>45 GWd/MTU) spent fuel to maintain its integrity under normal conditions of transportation. An innovative system, Cyclic Integrated Reversible-bending Fatigue Tester (CIRFT), has been developed at Oak Ridge National Laboratory (ORNL) to test and evaluate the mechanical behavior of spent nuclear fuel (SNF) under conditions relevant to storage and transportation. The CIRFT system is composed of a U-frame equipped with load cells for imposing the pure bending loads on the SNF rod test specimen and measuring the in-situ curvature of the fuel rod during bending using a set up with three linear variable differential transformers (LVDTs).

Mechanical Fatigue Testing of High-Burnup Fuel for Transportation Applications

Energy Technology Data Exchange (ETDEWEB)

Wang, Jy-An John [ORNL; Wang, Hong [ORNL

2015-05-01

This report describes testing designed to determine the ability of high burnup (HBU) (>45 GWd/MTU) spent fuel to maintain its integrity under normal conditions of transportation. An innovative system, Cyclic Integrated Reversible-bending Fatigue Tester (CIRFT), has been developed at Oak Ridge National Laboratory (ORNL) to test and evaluate the mechanical behavior of spent nuclear fuel (SNF) under conditions relevant to storage and transportation. The CIRFT system is composed of a U-frame equipped with load cells for imposing the pure bending loads on the SNF rod test specimen and measuring the in-situ curvature of the fuel rod during bending using a set up with three linear variable differential transformers (LVDTs).

Transport fuel demand responses to fuel price and income projections : Comparison of integrated assessment models

NARCIS (Netherlands)

Edelenbosch, O. Y.; van Vuuren, Detlef; Bertram, C.; Carrara, S.; Emmerling, J.; Daly, H.; Kitous, A.; McCollum, D. L.; Saadi Failali, N.

Income and fuel price pathways are key determinants in projections of the energy system in integrated assessment models. In recent years, more details have been added to the transport sector representation in these models. To better understand the model dynamics, this manuscript analyses transport

An economic analysis of transportation fuel policies in Brazil: Fuel choice, land use, and environmental impacts

International Nuclear Information System (INIS)

Nuñez, Hector M.; Önal, Hayri

2016-01-01

Brazil uses taxes, subsidies, and blending mandates as policy instruments to manage and stabilize its transportation fuel markets. The fuel sector has been very dynamic in recent years due to frequent policy adjustments and variable market conditions. In this paper, we use a price endogenous economic simulation model to analyze the impacts of such policy adjustments under various challenging conditions in the global ethanol and sugar markets. Our analysis specifically focuses on Brazilian producers' supply responses, consumers' driving demand and fuel choice, ethanol trade, land use, greenhouse gas emissions, and social welfare. The model results show that (i) under a low ethanol blending rate, conventional vehicles would be driven significantly less while flex-fuel and ethanol-dedicated vehicles would not be affected significantly; (ii) lowering the fuel taxes adversely affects the competitiveness of sugarcane ethanol against gasoline blends, thus lowering producers' surplus; and (iii) while a reduction in fuel taxes is advantageous in terms of overall social welfare, it has serious environmental impacts by increasing the GHG emissions from transportation fuels consumed in Brazil. - Highlights: • We examine the economic and environmental impacts of Brazilian fuel policies. • We also analyze impacts under different sugar and ethanol markets conditions. • Lowering blending rate reduces distance driven by conventional cars. • Lowering fuel tax rates affects competitiveness of ethanol against gasoline blend. • Reducing fuel tax rates has dramatic environmental impacts by increasing emissions.

Energy and the transport sector. [For countries with no fossil fuels

Energy Technology Data Exchange (ETDEWEB)

Olson, P E

1979-01-01

This article describes the current energy situation from both the global viewpoint and the viewpoint of countries with no indigenous sources of fossil fuels. The lack of fossil fuels necessitates a substitution with indigenous sources of energy, where feasible. Long-distance railway transport is a self-evident element in the expanding transport sector. In view of the proven high energy efficiency of electric railway systems, there is every incentive for a more active investment policy in railway electrification. This applies to both medium-distance transportation of freight and passengers and different electric mass transit systems.

Regulations concerning the transport of nuclear fuel materials outside the works or the enterprise

International Nuclear Information System (INIS)

1981-01-01

This rule is established under the provisions of the law concerning the regulation of nuclear raw materials, nuclear fuel materials and nuclear reactors and the ordinance for its execution, and to enforce the law. Basic terms are defined, such as vehicle transport, simplified transport, nuclear fuel transport goods, exclusive loading, worker, cumulative dose and exposure radiation dose. Nuclear fuel transport goods are classified into types of L, A, BM and BU according to their radioactivities. Radiation dose rate shall not exceed 0.5 milli-rem an hour on the surface of the type L, and 200 milli-rem an hour on the surface of the type A. For the type BM, the rate shall not surpass 1,000 milli-rem an hour at the distance of 1 meter from the surface in the special test conditions. The transport goods of fissile materials must not reach criticality on the way, but also shall conform to the stipulated technical standards. The particular things contaminated by nuclear fuel materials can be transported without specifying as nuclear fuel transport goods, and their radiation dose rate shall not go beyond 0.5 milli-rem an hour on the surface. The transport by special measures, the technical standards of simplified transport and measures to be taken in danger in transit are defined, respectively.(Okada, K.)

Greenhouse gas emissions from the production and use of alternative transport fuels

International Nuclear Information System (INIS)

Le Cornu, J.K.

1990-01-01

A number of the commonly proposed alternative transport fuels were ranked according to both the cumulative greenhouse gas emissions and the production costs incurred between the recovery of the prime resource and the fuel's end use by the Australian transport fleet. An examination of the emissions of each greenhouse gas at each production stage confirmed the common presumption that the low levels of secondary greenhouse gas emissions involved contribute little to the overall greenhouse impact of a fuel's production and use. From a greenhouse point of view the transport fuels studied could be reasonable well ranked by considering their carbon dioxide emissions alone. A possible exception may apply in the case of the compressed natural gas option, which may need to separate consideration of the effect of fugitive emissions of methane from gas distribution systems. An assumption involved in reaching this result was that nitrous oxide emissions, on which there was inadequate hard data, would not form more than 1% of the total nitrogen oxide emissions. At such an emission level it could contribute up to 5% of a fuel's total greenhouse impact. It is concluded that apart from some small niche opportunities, there is no Australian alternative transport fuel option whose production cost and greenhouse impact makes it one which policy should favour over other fuels. It is stressed that this is no more than a preliminary scouting study of generic options, which addresses only greenhouse issues. 17 refs., 1 tab., 8 figs

Advanced reactors and novel reactions for the conversion of triglyceride based oils into high quality renewable transportation fuels

Science.gov (United States)

Linnen, Michael James

Sustainable energy continues to grow more important to all societies, leading to the research and development of a variety of alternative and renewable energy technologies. Of these, renewable liquid transportation fuels may be the most visible to consumers, and this visibility is further magnified by the long-term trend of increasingly expensive petroleum fuels that the public consumes. While first-generation biofuels such as biodiesel and fuel ethanol have been integrated into the existing fuel infrastructures of several countries, the chemical differences between them and their petroleum counterparts reduce their effectiveness. This gives rise to the development and commercialization of second generation biofuels, many of which are intended to have equivalent properties to those of their petroleum counterparts. In this dissertation, the primary reactions for a second-generation biofuel process, known herein as the University of North Dakota noncatalytic cracking process (NCP), have been studied at the fundamental level and improved. The NCP is capable of producing renewable fuels and chemicals that are virtually the same as their petroleum counterparts in performance and quality (i.e., petroleum-equivalent). In addition, a novel analytical method, FIMSDIST was developed which, within certain limitations, can increase the elution capabilities of GC analysis and decrease sample processing times compared to other high resolution methods. These advances are particularly useful for studies of highly heterogeneous fuel and/or organic chemical intermediates, such as those studied for the NCP. However the data from FIMSDIST must be supplemented with data from other methods such as for certain carboxylic acid, to provide accurate, comprehensive results, From a series of TAG cracking experiments that were performed, it was found that coke formation during cracking is most likely the result of excessive temperature and/or residence time in a cracking reactor. Based on this

Environmental economics of lignin derived transport fuels

NARCIS (Netherlands)

Obydenkova, Svetlana V.; Kouris, Panos D.; Hensen, Emiel J. M.; Heeres, Hero J.; Boot, Michael D.

2017-01-01

This paper explores the environmental and economic aspects of fast pyrolytic conversion of lignin, obtained from 2G ethanol plants, to transport fuels for both the marine and automotive markets. Various scenarios are explored, pertaining to aggregation of lignin from several sites, alternative

Leveling the playing field of transportation fuels: Accounting for indirect emissions of natural gas

International Nuclear Information System (INIS)

Sexton, Steven; Eyer, Jonathan

2016-01-01

Natural gas transportation fuels are credited in prior studies with greenhouse gas emissions savings relative to petroleum-based fuels and relative to the total emissions of biofuels. These analyses, however, overlook a source of potentially large indirect emissions from natural gas transportation fuels, namely the emissions from incremental coal-fired generation caused by price-induced substitutions away from natural-gas-fired electricity generation. Because coal-fired generation emits substantially more greenhouse gases and criteria air pollutants than natural-gas-fired generation, this indirect coal-use change effect diminishes potential emissions savings from natural gas transportation fuels. Estimates from a parameterized multi-market model suggest the indirect coal-use change effect rivals in magnitude the indirect land-use change effect of biofuels and renders natural gas fuels as carbon intensive as petroleum fuels. - Highlights: •Natural gas used in transport causes indirect emissions in the electricity sector. •These emissions result from increased coal use in electricity generation. •They rival in magnitude indirect land use change (ILUC) emissions of biofuels. •Natural gas fuels are estimated to be as carbon intensive as the petroleum fuels. •Policy ignores indirect emissions from natural gas.

Life cycle analysis of transportation fuel pathways

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-02-24

The purpose of this work is to improve the understanding of the concept of life cycle analysis (LCA) of transportation fuels and some of its pertinent issues among non-technical people, senior managers, and policy makers. This work should provide some guidance to nations considering LCA-based policies and to people who are affected by existing policies or those being developed. While the concept of employing LCA to evaluate fuel options is simple and straightforward, the act of putting the concept into practice is complex and fraught with issues. Policy makers need to understand the limitations inherent in carrying out LCA work for transportation fuel systems. For many systems, even those that have been employed for a 100 years, there is a lack of sound data on the performance of those systems. Comparisons between systems should ideally be made using the same tool, so that differences caused by system boundaries, allocation processes, and temporal issues can be minimized (although probably not eliminated). Comparing the results for fuel pathway 1 from tool A to those of fuel system 2 from tool B introduces significant uncertainty into the results. There is also the question of the scale of system changes. LCA will give more reliable estimates when it is used to examine small changes in transportation fuel pathways than when used to estimate large scale changes that replace current pathways with completely new pathways. Some LCA tools have been developed recently primarily for regulatory purposes. These tools may deviate from ISO principles in order to facilitate simplicity and ease of use. In a regulatory environment, simplicity and ease of use are worthy objectives and in most cases there is nothing inherently wrong with this approach, particularly for assessing relative performance. However, the results of these tools should not be confused with, or compared to, the results that are obtained from a more complex and rigorous ISO compliant LCA. It should be

A methodology for the evaluation of fuel rod failures under transportation accidents

International Nuclear Information System (INIS)

Rashid, J.Y.R.; Machiels, A.J.

2004-01-01

Recent studies on long-term behavior of high-burnup spent fuel have shown that under normal conditions of stor-age, challenges to cladding integrity from various postulated damage mechanisms, such as delayed hydride crack-ing, stress-corrosion cracking and long-term creep, would not lead to any significant safety concerns during dry storage, and regulatory rules have subsequently been established to ensure that a compatible level of safety is maintained. However, similar safety assurances for spent fuel transportation have not yet been developed, and further studies are currently being conducted to evaluate the conditions under which transportation-related safety issues can be resolved. One of the issues presently under evaluation is the ability and the extent of the fuel as-semblies to maintain non-reconfigured geometry during transportation accidents. This evaluation may determine whether, or not, the shielding, confinement, and criticality safety evaluations can be performed assuming initial fuel assembly geometries. The degree to which spent fuel re-configuration could occur during a transportation accident would depend to a large degree on the number of fuel rod failures and the type and geometry of the failure modes. Such information can only be developed analytically, as there is no direct experimental data that can provide guidance on the level of damage that can be expected. To this end, the paper focuses on the development of a modeling and analysis methodology that deals with this general problem on a generic basis. First consideration is given to defining acci-dent loading that is equivalent to the bounding, although analytically intractable, hypothetical transportation acci-dent of a 9-meter drop onto essentially unyielding surface, which is effectively a condition for impact-limiters de-sign. Second, an analytically robust material constitutive model, an essential element in a successful structural analysis, is required. A material behavior model

Effects of AFR storage location on spent fuel transportation

International Nuclear Information System (INIS)

Joy, D.S.; Shappert, L.B.

1979-01-01

In order to assess the impact of Away-From-Reactor (AFR) siting on the spent fuel transportation system, five different sites were studied: Argonne, Oak Ridge, Savannah River, Idaho Falls, and Richland. Transportation costs, cask fleet sizes, and radiation exposures received by transportation workers and the general public were calculated for each site. Results show that the eastern three sites are best. 5 figures, 5 tables

k-eff of the Bn-350 reactor fuel by transportation

International Nuclear Information System (INIS)

Lado, A. V.; Romanenko, O. G.; Tazhibaeva, I. L.

2001-01-01

There is packaging of nuclear fuel on the BN-350 fast breeder reactor, Actau, now. The analysis of criticality while this procedure was done in the Safety Analysis Report . Keeping in mind the planning displacement of the fuel to a site of long-term storage, the criticality assessment of the fuel packed into transportation cask carried out in this paper

Transfer of radioactive materials in the fuel cycle. Transportation systems, transportation volume and radiation protection

International Nuclear Information System (INIS)

Schwarz, G.

1997-01-01

No other aspect of the carriage of hazardous goods has been provoking such long-lived concern in the general public and in the press during the last few years as the transport of spent nuclear fuels and high-level radioactive wastes to the storage facility at Gorleben. One reason for this controversy, besides clear-cut opposition in principal against such transfer activities, is the fact that there is an information gap, so that large parts of the population are not well informed about the relevant legal safety requirements and obligations governing such transports. The article therefore tries to fill this gap, presenting information on the number and necessity of transports of radioactive materials in the nuclear fuel cycle, the relevant scenarios, the transportation systems and packing and shielding requirements, as well as information on the radiological classification and hazardousness of waste forms. (Orig.) [de

Ultraclean Fuels Production and Utilization for the Twenty-First Century: Advances toward Sustainable Transportation Fuels

Energy Technology Data Exchange (ETDEWEB)

Fox, Elise B.; Liu, Zhong-Wen; Liu, Zhao-Tie

2013-11-21

Ultraclean fuels production has become increasingly important as a method to help decrease emissions and allow the introduction of alternative feed stocks for transportation fuels. Established methods, such as Fischer-Tropsch, have seen a resurgence of interest as natural gas prices drop and existing petroleum resources require more intensive clean-up and purification to meet stringent environmental standards. This review covers some of the advances in deep desulfurization, synthesis gas conversion into fuels and feed stocks that were presented at the 245th American Chemical Society Spring Annual Meeting in New Orleans, LA in the Division of Energy and Fuels symposium on "Ultraclean Fuels Production and Utilization".

Waste heat recovery for transport trucks using thermally regenerative fuel cells

Energy Technology Data Exchange (ETDEWEB)

Carrier, A.; Wechsler, D.; Whitney, R.; Jessop, P. [Queen' s Univ., Kingston, ON (Canada). Dept. of Chemistry; Davis, B.R. [Queen' s-RMC Fuel Cell Research Centre, Kingston, ON (Canada)

2009-07-01

Carbon emissions associated with transportation can be reduced by increasing the fuel efficiency of transport trucks. This can be achieved with thermally regenerative fuel cells that transform the waste heat from the engine block into electricity. In order to operate such a fuel cell, one needs a fluid which rapidly, reversibly, and selectively undergoes dehydrogenation. Potential fluids have been screened for their ability to dehydrogenate and then rehydrogenate at the appropriate temperatures. An examination of the thermodynamics, kinetics, and selectivities of these processes have shown that the challenge involving hydrogenolysis at high temperature must be addressed. This paper discussed the economics of thermally regenerative fuel cells and the advantages and disadvantages of the identified fluids, and of such systems in general.

Thermal analysis on NAC-STC spent fuel transport cask under different transport conditions

Energy Technology Data Exchange (ETDEWEB)

Xu, Yumei [Institute of Process Equipment, Zhejiang University, Hangzhou (China); Yang, Jian, E-mail: zdhjkz@zju.edu.cn [Institute of Process Equipment, Zhejiang University, Hangzhou (China); Xu, Chao; Wang, Weiping [Institute of Process Equipment, Zhejiang University, Hangzhou (China); Ma, Zhijun [Department of Material Engineering, South China University of Technology, Guangzhou (China)

2013-12-15

Highlights: • Spent fuel cask was investigated as a whole instead of fuel assembly alone. • The cask was successfully modeled and meshed after several simplifications. • Equivalence method was used to calculate the properties of parts. • Both the integral thermal field and peak values are captured to verify safety. • The temperature variations of key parts were also plotted. - Abstract: Transport casks used for conveying spent nuclear fuel are inseparably related to the safety of the whole reprocessing system for spent nuclear fuel. Thus they must be designed according to rigorous safety standards including thermal analysis. In this paper, for NAC-STC cask, a finite element model is established based on some proper simplifications on configurations and the heat transfer mechanisms. Considering the complex components and gaps, the equivalence method is presented to define their material properties. Then an equivalent convection coefficient is introduced to define boundary conditions. Finally, the temperature field is captured and analyzed under both normal and accident transport conditions by using ANSYS software. The validity of numerical calculation is given by comparing its results with theoretical calculation. Obtaining the integral distribution laws of temperature and peak temperature values of all vital components, the security of the cask can be evaluated and verified.

Chemical and toxicological characterization of exhaust emissions from alternative fuels for urban public transport

International Nuclear Information System (INIS)

Turrio Baldassarri, L.; Conti, R.; Crebelli, B.; Iamicelli, A.L.; De Berardis, M.; Gambino, A.L.; Iannaccone, S.

2008-01-01

The Istituto Superiore di Sanita (ISS, the National Institute of Health of Italy) and the Istituto dei Motori (IM) of the Consiglio Nazionale delle Ricerche (CNR, National Research Council) have carried out this study, jointly funded by the two institutes together with the Ministry of Environment. The chemical and toxicological characteristics of emissions from two urban bus engines were studied: a diesel engine fueled with both diesel oil and bio diesel blend and an equivalent spark-ignition one fuelled with compressed natural gas, operating in steady-state conditions. Regulated and unregulated pollutants, such as carcinogenic polycyclic aromatic hydrocarbons and nitrated derivatives, carbonyl compounds and light aromatic hydrocarbons were quantified. Mutagenicity of the emissions was evaluated by the Salmonella typhimurium/mammalian microsome assay. The effect of the fuels under study on the size distribution of particulate matter was also evaluated. The impact of diesel-powered transport on urban air quality, and the potential benefits for human health deriving from the use of natural gas for public transport, are discussed [it

Human error prediction and countermeasures based on CREAM in spent nuclear fuel (SNF) transportation

International Nuclear Information System (INIS)

Kim, Jae San

2007-02-01

Since the 1980s, in order to secure the storage capacity of spent nuclear fuel (SNF) at NPPs, SNF assemblies have been transported on-site from one unit to another unit nearby. However in the future the amount of the spent fuel will approach capacity in the areas used, and some of these SNFs will have to be transported to an off-site spent fuel repository. Most SNF materials used at NPPs will be transported by general cargo ships from abroad, and these SNFs will be stored in an interim storage facility. In the process of transporting SNF, human interactions will involve inspecting and preparing the cask and spent fuel, loading the cask onto the vehicle or ship, transferring the cask as well as storage or monitoring the cask. The transportation of SNF involves a number of activities that depend on reliable human performance. In the case of the transport of a cask, human errors may include spent fuel bundle misidentification or cask transport accidents among others. Reviews of accident events when transporting the Radioactive Material (RAM) throughout the world indicate that human error is the major causes for more than 65% of significant events. For the safety of SNF transportation, it is very important to predict human error and to deduce a method that minimizes the human error. This study examines the human factor effects on the safety of transporting spent nuclear fuel (SNF). It predicts and identifies the possible human errors in the SNF transport process (loading, transfer and storage of the SNF). After evaluating the human error mode in each transport process, countermeasures to minimize the human error are deduced. The human errors in SNF transportation were analyzed using Hollnagel's Cognitive Reliability and Error Analysis Method (CREAM). After determining the important factors for each process, countermeasures to minimize human error are provided in three parts: System design, Operational environment, and Human ability

MX 8: the next generation high capacity system for the transport of fresh MOX fuel

International Nuclear Information System (INIS)

Potelle, F.; Issard, H.

1998-01-01

The choice of reprocessing policy was made a long time ago in France, leading to the development of an advanced Pu recycling industry. In 1987, Saint Laurent was the first French reactor to be loaded with fresh MOX fuel. Transnucleaire, then in charge of transport packaging development, created the FS 69 concept, derived from the classical RCC concept for the transport of UO 2 fresh fuel. On the other hand, Cogema, as the main actor in the field of fuel cycle and thus in transport matters, developed the associated security truck and security caisson in order to provide the transport system with the acceptable Physical Protection devices required by French Authorities. As a whole, the security truck and the FS 69 have now been used for more than ten years with a remarkable level of efficiency and safety. Indeed, more than 600 fresh MOX fuel elements have been delivered, without any incident, both regarding safety or fuel integrity requirements. But, as a matter of fact, the replacement of FS 69 transport system is now scheduled for several reasons. First of all, the burnups achieved with UO 2 fuel progressed together with its enrichment within the last ten years, and the MOX 'equivalence' also implies that its Pu content be increased to enhance its reactor performances: from 5.25 % of Pu content today, the MOX fuel will reach 7% tomorrow, and almost 10% the day after tomorrow. Lastly, the reprocessing/recycling policy has been confirmed and amplified, leading to an increasing number of 'moxified' reactors. As a consequence, the French utility (EDF), the fuel designer (Fragema, the joint venture between Framatome and Cogema), the fuel manufacturer (Cogema), and the transporter (Transnucleaire) joined in a specific working group devoted to the development of the MX 8, the next generation high capacity system for the land transport of MOX fuel. (authors)

On direct and indirect methanol fuel cells for transportation applications

Energy Technology Data Exchange (ETDEWEB)

Gottesfield, S.

1996-04-01

Research on direct oxidation methanol fuel cells (DMFCs) and polymer electrolyte fuel cells (PEFCs) is discussed. Systems considered for transportation applications are addressed. The use of platinum/ruthenium anode electrocatalysts and platinum cathode electrocatalysts in polymer electrolyte DMFCs has resulted in significant performance enhancements.

Life cycle assessment of Jatropha biodiesel as transportation fuel in rural India

Energy Technology Data Exchange (ETDEWEB)

Achten, Wouter M.J. [Katholieke Universiteit Leuven, Division Forest, Nature and Landscape, Celestijnenlaan 200 E-2411, BE-3001 Leuven (Belgium); World Agroforestry Centre (ICRAF) Regional Office for South Asia, CG Block, 1st Floor, National Agricultural Science Centre, Dev Prakash Shastri Marg, Pusa, New Delhi 110 012 (India); Almeida, Joana [Katholieke Universiteit Leuven, Division Forest, Nature and Landscape, Celestijnenlaan 200 E-2411, BE-3001 Leuven (Belgium); Grupo de Disciplinas da Ecologia da Hidrosfera, Faculdade de Ciencias e Tecnologia, FCT, Universidade Nova de Lisboa, 2829-516 Caparica (Portugal); Fobelets, Vincent; Bolle, Evelien; Muys, Bart [Katholieke Universiteit Leuven, Division Forest, Nature and Landscape, Celestijnenlaan 200 E-2411, BE-3001 Leuven (Belgium); Mathijs, Erik [Katholieke Universiteit Leuven, Division Agricultural and Food Economics, Celestijnenlaan 200 E-2411, BE-3001 Leuven (Belgium); Singh, Virendra P. [World Agroforestry Centre (ICRAF) Regional Office for South Asia, CG Block, 1st Floor, National Agricultural Science Centre, Dev Prakash Shastri Marg, Pusa, New Delhi 110 012 (India); Tewari, Dina N. [Utthan NGO, Centre for Sustainable Development and Poverty Alleviation, 18-A, Auckland Road, Civil Lines, Allahabad 211 001 (India); Verchot, Louis V. [Centre for International Forestry Research, P.O. Box 0113 BOCBD, Bogor 16000 (Indonesia)

2010-12-15

Since 2003 India has been actively promoting the cultivation of Jatropha on unproductive and degraded lands (wastelands) for the production of biodiesel suitable as transportation fuel. In this paper the life cycle energy balance, global warming potential, acidification potential, eutrophication potential and land use impact on ecosystem quality is evaluated for a small scale, low-input Jatropha biodiesel system established on wasteland in rural India. In addition to the life cycle assessment of the case at hand, the environmental performance of the same system expanded with a biogas installation digesting seed cake was quantified. The environmental impacts were compared to the life cycle impacts of a fossil fuel reference system delivering the same amount of products and functions as the Jatropha biodiesel system under research. The results show that the production and use of Jatropha biodiesel triggers an 82% decrease in non-renewable energy requirement (Net Energy Ratio, NER = 1.85) and a 55% reduction in global warming potential (GWP) compared to the reference fossil-fuel based system. However, there is an increase in acidification (49%) and eutrophication (430%) from the Jatropha system relative to the reference case. Although adding biogas production to the system boosts the energy efficiency of the system (NER = 3.40), the GWP reduction would not increase (51%) due to additional CH{sub 4} emissions. For the land use impact, Jatropha improved the structural ecosystem quality when planted on wasteland, but reduced the functional ecosystem quality. Fertilizer application (mainly N) is an important contributor to most negative impact categories. Optimizing fertilization, agronomic practices and genetics are the major system improvement options. (author)

Life cycle assessment of Jatropha biodiesel as transportation fuel in rural India

International Nuclear Information System (INIS)

Achten, Wouter M.J.; Almeida, Joana; Fobelets, Vincent; Bolle, Evelien; Mathijs, Erik; Singh, Virendra P.; Tewari, Dina N.; Verchot, Louis V.; Muys, Bart

2010-01-01

Since 2003 India has been actively promoting the cultivation of Jatropha on unproductive and degraded lands (wastelands) for the production of biodiesel suitable as transportation fuel. In this paper the life cycle energy balance, global warming potential, acidification potential, eutrophication potential and land use impact on ecosystem quality is evaluated for a small scale, low-input Jatropha biodiesel system established on wasteland in rural India. In addition to the life cycle assessment of the case at hand, the environmental performance of the same system expanded with a biogas installation digesting seed cake was quantified. The environmental impacts were compared to the life cycle impacts of a fossil fuel reference system delivering the same amount of products and functions as the Jatropha biodiesel system under research. The results show that the production and use of Jatropha biodiesel triggers an 82% decrease in non-renewable energy requirement (Net Energy Ratio, NER = 1.85) and a 55% reduction in global warming potential (GWP) compared to the reference fossil-fuel based system. However, there is an increase in acidification (49%) and eutrophication (430%) from the Jatropha system relative to the reference case. Although adding biogas production to the system boosts the energy efficiency of the system (NER = 3.40), the GWP reduction would not increase (51%) due to additional CH 4 emissions. For the land use impact, Jatropha improved the structural ecosystem quality when planted on wasteland, but reduced the functional ecosystem quality. Fertilizer application (mainly N) is an important contributor to most negative impact categories. Optimizing fertilization, agronomic practices and genetics are the major system improvement options.

Current issues in the transport of radioactive waste and spent fuel: work by the World Nuclear Transport Institute

Energy Technology Data Exchange (ETDEWEB)

Neau, H-J.; Bonnardel-Azzarelli, B. [World Nuclear Transport Inst., London (United Kingdom)

2014-07-01

Various kinds of radioactive waste are generated from nuclear power and fuel cycle facilities. These materials have to be treated, stored and eventually sent to a repository site. Transport of wastes between these various stages is crucial for the sustainable utilization of nuclear energy. The IAEA Regulations for the Safe Transport of Radioactive Material (SSR-6) have, for many decades, provided a safe and efficient framework for radioactive materials transport and continue to do so. However, some shippers have experienced that in the transport of certain specific radioactive wastes, difficulties can be encountered. For example, some materials produced in the decommissioning of nuclear facilities are unique in terms of composition or size and can be difficult to characterize as surface contaminated objects (SCO) or homogeneous. One way WNTI (World Nuclear Transport Institute) helps develop transport methodologies is through the use of Industry Working Groups, bringing together WNTI members with common interests, issues and experiences. The Back-End Transport Industry Working Group focuses on the following issues currently. - Characterization of Waste: techniques and methods to classify wastes - Large Objects: slightly contaminated large objects (ex. spent steam generators) transport - Dual Use Casks: transportable storage casks for spent nuclear fuels, including the very long term storage of spent fuel - Fissile Exceptions: new fissile exceptions provisions of revised TS-R-1 (SSR-6) The paper gives a broad overview of current issues for the packaging and transport of radioactive wastes and the associated work of the WNTI. (author)

Transport and supply logistics of biomass fuels: Vol. 1. Supply chain options for biomass fuels

Energy Technology Data Exchange (ETDEWEB)

Allen, J; Browne, M; Palmer, H; Hunter, A; Boyd, J

1996-10-01

The study which forms part of a wider project funded by the Department of Trade and Industry, looks at the feasibility of generating electricity from biomass-fuelled power stations. Emphasis is placed on supply availabilty and transport consideration for biomass fuels such as wood wastes from forestry, short rotation coppice products, straw, miscanthus (an energy crop) and farm animal slurries. The study details the elements of the supply chain for each fuel from harvesting to delivery at the power station. The delivered cost of each fuel, the environmental impact of the biomass fuel supply and other relevant non-technical issues are addressed. (UK)

Analysis of the risk of transporting spent nuclear fuel by train

Energy Technology Data Exchange (ETDEWEB)

Elder, H.K.

1981-09-01

This report uses risk analyses to analyze the safety of transporting spent nuclear fuel for commercial rail shipping systems. The rail systems analyzed are those expected to be used in the United States when the total electricity-generating capacity by nuclear reactors is 100 GW in the late 1980s. Risk as used in this report is the product of the probability of a release of material to the environment and the consequences resulting from the release. The analysis includes risks in terms of expected fatalities from release of radioactive materials due to transportation accidents involving PWR spent fuel shipped in rail casks. The expected total risk from such shipments is 1.3 x 10/sup -4/ fatalities per year. Risk spectrums are developed for shipments of spent fuel that are 180 days and 4 years out-of-reactor. The risk from transporting spent fuel by train is much less (by 2 to 4 orders of magnitude) than the risk to society from other man-caused events such as dam failure.

Sustainable Transportation: Accelerating Widespread Adoption of Energy Efficient Vehicles & Fuels (Brochure)

Energy Technology Data Exchange (ETDEWEB)

2014-12-01

While energy efficient transportation strategies have the potential to simultaneously slash oil consumption and reduce greenhouse gas (GHG) emissions, a truly sustainable solution will require more than just putting drivers behind the wheels of new fuel-efficient cars. As the only national laboratory dedicated 100% to renewable energy and energy efficiency, the National Renewable Energy Laboratory (NREL) accelerates widespread adoption of high-performance, low-emission, energy-efficient passenger and freight vehicles, as well as alternative fuels and related infrastructure. Researchers collaborate closely with industry, government, and research partners, using a whole-systems approach to design better batteries, drivetrains, and engines, as well as thermal management, energy storage, power electronic, climate control, alternative fuel, combustion, and emission systems. NREL's sustainable transportation research, development, and deployment (RD&D) efforts are not limited to vehicles, roads, and fueling stations. The lab also explores ways to save energy and reduce GHGs by integrating transportation technology advancements with renewable energy generation, power grids and building systems, urban planning and policy, and fleet operations.

Transport and storage of spent nuclear fuel

International Nuclear Information System (INIS)

Lung, M.; Lenail, B.

1987-01-01

From a safety standpoint, spent fuel is clearly not ideal for permanent disposal and reprocessing is the best method of preparing wastes for long-term storage in a repository. Furthermore, the future may demonstrate that some fission products recovered in reprocessing have economic applications. Many countries have in fact reached the point at which the recycling of plutonium and uranium from spent fuel is economical in LWR's. Even in countries where this is not yet evident, (i.e., the United States), the French example shows that the day will come when spent fuel will be retrieved for reprocessing and recycle. It is highly questionable whether spent fuel will ever be considered and treated as waste in the same sense as fission products and processed as such, i.e., packaged in a waste form for permanent disposal. Even when recycled fuel material can no longer be reused in LWR's because of poor reactivity, it will be usable in FBR's. Based on the considerable experience gained by SGN and Cogema, this paper has provided practical discussion and illustrations of spent fuel transport and storage of a very important step in the nuclear fuel management process. The best of spent fuel storage depends on technical, economic and policy considerations. Each design has a role to play and we hope that the above discussion will help clarify certain issues

Catalytic Conversion of Bio-oil to Fuel for Transportation

DEFF Research Database (Denmark)

Mortensen, Peter Mølgaard

identied as a prospective route to bio-fuels. The upgrading is most favorably done by hydrodeoxygenation (HDO), producing bio-fuels at a quality equivalent to conventional fossil fuels. The topic of this Ph.D. thesis has been the development of active and stable catalysts for this reaction. In the search...

Transport control of forest fuels by fleet manager, mobile terminals and GPS

International Nuclear Information System (INIS)

Sikanen, Lauri; Asikainen, Antti; Lehikoinen, Mikko

2005-01-01

Chip transportation is undertaken by private transportation enterprises that are contracted by a larger wood fuel trader. Compared with industrial roundwood supply the volumes and value of wood fuel supply are markedly lower. As a result, the possibilities to invest in information systems for transport management are limited. New portable, wireless communication techniques and internet-based systems for fleet management enable more cost-efficient control systems with low investment costs in hard and software and also low operating costs. Mobile handsets with GPS, digital road map display and global positioning systems (GPS) or general purpose radio service data transfer protocol can be used as mobile terminals in chippers and trucks. In addition, transport management personnel can use them to locate in-forest wood fuel storage piles into the map database as well as point suitable routing to the storage piles. In a pilot study, conducted in Central Finland, an internet based management tool, Arbonaut Fleet ManagerTM, was tailored for forest fuel supply chain management and trailed for three months. It was found that use of mobile handsets with GPS and map display assisted especially in exact location of in-forest wood fuel storage piles by managers. They assisted also trucks and chippers in navigation to storages and landings, but the screen was too small for reading during driving. The management system was found helpful in stock accounting and GPS-based vehicle tracking gave transportation distances directly for invoicing

Development of a transport cask for spent fuel elements of research reactors

International Nuclear Information System (INIS)

Quintana, F.; Saliba, R.O.; Furnari, J.C.; Mourao, R.P; Leite da Silva, L.; Novara, O.; Alexandre Miranda, C.; Mattar Neto, M.

2012-01-01

This article presents an overview of the development of a research reactor spent fuel transport cask. Through a project funded by the IAEA, Argentina, Brazil and Chile have collaborated to enhance regional capacity in the management of spent fuel elements from research reactors operated in the region. A packaging for the transport of research reactors spent fuel was developed. It was designed by a team of researchers from the countries mentioned and a 1:2 scale model for MTR type fuel was constructed in Argentina and subsequently tested in CDTN facilities in Belo Horizonte, Brazil. There were three test sequences to test the cask for normal transport and hypothetical accident conditions. It has successfully passed the tests and the overall performance was considered satisfactory. As part of the licensing process, a test sequence with the presence of regulatory authorities is scheduled for December, 2012 (author)

Criticality safety requirements for transporting EBR-II fuel bottles stored at INTEC

International Nuclear Information System (INIS)

Lell, R. M.; Pope, C. L.

2000-01-01

Two carrier/shipping cask options are being developed to transport bottles of EBR-II fuel elements stored at INTEC. Some fuel bottles are intact, but some have developed leaks. Reactivity control requirements to maintain subcriticality during the hypothetical transport accident have been examined for both transport options for intact and leaking bottles. Poison rods, poison sleeves, and dummy filler bottles were considered; several possible poison materials and several possible dummy filler materials were studied. The minimum number of poison rods or dummy filler bottles has been determined for each carrier for transport of intact and leaking bottles

Transport experience of NH-25 spent fuel shipping cask for post irradiation examination

International Nuclear Information System (INIS)

Mori, Ryuji

1982-01-01

Since the Japan Atomic Energy Research Institute and Nippon Nuclear Fuel Development Co. hot laboratories are located far off from the port which can handle spent fuel shipping casks, it is necessary to use a trailer-mounted cask which can be transported by public roads, bridges and intersections for the transportation of spent fuel specimens to these hot laboratories. Model NH-25 shipping cask was designed, manufactured and oualification tested to meet Japanese regulations and was officially registered as a BM type cask. The NH-25 cask accomodates two BWR fuel assemblies, one PWR assembly or one ATR fuel assembly using interchangeable inner containers. The cask weight is 29.2 t. The cask has three concentric stainless steel shells. Gamma shielding is lead cast between the inner shell and the intermediate shell. Neutro n shielding consists of ethylene-glycol-aqueous solution layer formed between the intermediate shell and the outer shell. The NH-25 cask now has been in operation for 2.5 yr. It was used for the transportation of spent fuel assemblies from six LWR power plants to the port on shipping cask carrier ''Hinouramaru'' on the sea, as well as from the port to the hot laboratory on a trailer. The capability of safe handling and transporting of spent fuel assemblies has been well demonstrated. (author)

Transport phenomena in alkaline direct ethanol fuel cells for sustainable energy production

Science.gov (United States)

An, L.; Zhao, T. S.

2017-02-01

Alkaline direct ethanol fuel cells (DEFC), which convert the chemical energy stored in ethanol directly into electricity, are one of the most promising energy-conversion devices for portable, mobile and stationary power applications, primarily because this type of fuel cell runs on a carbon-neutral, sustainable fuel and the electrocatalytic and membrane materials that constitute the cell are relatively inexpensive. As a result, the alkaline DEFC technology has undergone a rapid progress over the last decade. This article provides a comprehensive review of transport phenomena of various species in this fuel cell system. The past investigations into how the design and structural parameters of membrane electrode assemblies and the operating parameters affect the fuel cell performance are discussed. In addition, future perspectives and challenges with regard to transport phenomena in this fuel cell system are also highlighted.

Foundations for the definition of MOX fuel quality requirements

International Nuclear Information System (INIS)

Bairiot, H.; Deramaix, P.; Vanderborck, Y.

1991-01-01

The quality of uranium-plutonium mixed oxide (MOX) fuel, as of any nuclear fuel, depends on the design optimization and on the fabrication process stability. The design optimization is essentially based on feed-back from irradiation experience through engineering assessment of the results; the stability of the process is necessary to justify minimal uncertainty margins in the fuel design. Since MOX fuel is quite similar to UO 2 fuel, the lessons learned from UO 2 fuels can complement the MOX experimental data base. MOX is however different from UO 2 fuel in some respects, among others: the industrial fabrication scale is a factor 10 lower than for UO 2 fuel, the fuel enrichment process takes place in the manufacturing plant, the radioactivity of Pu imposes handling constraints, Pu ages quite rapidly, altering its isotopic composition during storage, the incorporation of Pu alters the material physics and neutronic characteristics of the fuel. In this perspective, the paper outlines some quality attributes for which MOX fuel may or even must depart form UO 2 fuel. (orig.)

METHANOL PRODUCTION FROM BIOMASS AND NATURAL GAS AS TRANSPORTATION FUEL

Science.gov (United States)

Two processes are examined for production of methanol. They are assessed against the essential requirements of a future alternative fuel for road transport: that it (i) is producible in amounts comparable to the 19 EJ of motor fuel annually consumed in the U.S., (ii) minimizes em...

Conclusions and recommendations. [for problems in energy situation, air transportation, and hydrogen fuel

Science.gov (United States)

1973-01-01

Conclusions and recommendations are presented for an analysis of the total energy situation; the effect of the energy problem on air transportation; and hydrogen fuel for aircraft. Properties and production costs of fuels, future prediction for energy and transportation, and economic aspects of hydrogen production are appended.

Radioactive waste management decommissioning spent fuel storage. V. 3. Waste transport, handling and disposal spent fuel storage

International Nuclear Information System (INIS)

1985-01-01

As part of the book entitled Radioactive waste management decommissioning spent fuel storage, vol. 3 dealts with waste transport, handling and disposal, spent fuel storage. Twelve articles are presented concerning the industrial aspects of nuclear waste management in France [fr

Virginia Power and Department of Energy spent fuel transportation experience

International Nuclear Information System (INIS)

Ruska, M.D.; Schoonen, D.H.

1986-12-01

Spent fuel assemblies for the Spent Fuel Storage Cask Testing Program conducted by EG and G Idaho, Inc., at the Idaho National Engineering Laboratory (INEL) were transported to the INEL. A total of 69 spent fuel assemblies (23 shipments) were shipped from Virginia Power's nuclear power plant at Surry, Virginia, to the INEL between July 1985 and June 1986 to fill and test three spent fuel storage casks. The shipments were made over the highway system in Transnuclear, Inc., TN-8L shipping casks on specially constructed trailers. The shipments were moved by diesel tractors owned and operated by Tri-State Motor Transit Company of Joplin, Missouri. The gross vehicle weight for each shipment was 112,000 lb, which was a major consideration when selecting routes for the shipments. Cooperative negotiations with officials for the 17 states involved obtained authorization to transport through their states. The shipping campaign was successfully completed through close communication and cooperation and careful planning and operation by all organizations involved

Parallel processing of neutron transport in fuel assembly calculation

International Nuclear Information System (INIS)

Song, Jae Seung

1992-02-01

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

Coordination of ministerial actions regarding the use of liquefied natural gas (LNG) as fuel. LNG, a European component of the energy transition in road freight transport

International Nuclear Information System (INIS)

Maler, Philippe; Erhardt, Jean-Bernard; Ourliac, Jean-Paul

2015-09-01

This report is the third of a series dealing with the coordination of ministerial actions in favor of the use of liquefied natural gas (LNG) as fuel in transports. LNG is an important potential substitute to diesel fuel in road transport and would allow significant abatement of nitrogen oxides emissions. Bio-LNG is ten times less polluting than fossil fuel LNG and thus important efforts are to be made in bio-LNG R and D. An important work has been carried out for adapting EU regulations and standards to LNG vehicles and LNG supply developments. This report presents, first, a summary of the report's recommendations and the aim of this coordination study, and, then, treats more thoroughly of the different coordination aspects: 1 - European framework of energy transition in the road freight transport (differences with maritime transport, CO 2 emissions abatement, trucks pollution and fuel quality standards, trucks technical specifications and equipment, fuel taxes in EU countries); 2 - European policy and national actions in favour of LNG development for road transport (LNG as alternate fuel, the Paris agreement, the French national energy plan); 3 - Environmental benefits of LNG in road transport (public health impacts, nitrogen oxides abatement, divergent views and expertise, LNG and CO 2 abatement measures, bio-LNG environmental evaluation; 4 - LNG development actors in road transport and the administrative coordination (professional organizations, public stakeholders, LNG topics information dissemination at the Ministry); 5 - LNG development in road transport at the worldwide, European and national scales; 6 - European regulations and standards allowing trucks LNG fueling and circulation (standard needs, users information, regulation works); 7 - Common rules to define and implement for personnel training; 8 - reflexion on LNG taxation; 9 - support policy for a road transport LNG supply chain (infrastructures, European financing, lessons learnt from maritime

Assessment of the environmental benefits of transport and stationary fuel

International Nuclear Information System (INIS)

Bauen, A.; Hart, D.

2000-01-01

Fuel cells (FCs) offer significant environmental benefits over competing technologies and hence the environment is a strong driving force behind the development of FC systems for transport and stationary applications. This paper provides a comprehensive comparison of FC and competing systems, and points out strengths and weaknesses of the different FC systems, suggesting areas for improvement. The results presented build on earlier work [D. Hart, G. Hoermandinger, Initial assessment of the environmental characteristics of fuel cells and competing technologies, ETSU F/02/00111/REP/1, ETSU, Harwell, UK, 1997.] and provide a detailed analysis of a wider range of systems, The analysis takes the form of a model, which compares system emissions (global, regional and local pollutants) and energy consumption on a full fuel cycle basis. It considers a variety of primary energy sources, intermediate fuel supply steps and FC systems for transport and stationary end-uses. These are compared with alternative systems for transport and stationary applications. Energy and pollutant emission reductions of FC systems compared to alternative vehicle technology vary considerably, though all FC technologies show reduction in energy use and CO 2 emissions of at least 20%; as well as reductions of several orders of magnitude in regulated pollutants compared to the base-case vehicle. The location of emissions is also of importance, with most emissions in the case of FC vehicles occurring in the fuel supply stage. The energy, CO 2 and regulated emissions advantages of FC systems for distributed and baseload electricity are more consistent than for transport applications, with reductions in regulated pollutants generally larger than one order of magnitude compared to competing technologies. For CHP applications, the advantages of FC systems with regard to regulated pollutants remain large. However, energy and CO 2 emission advantages are reduced, depending largely on the assumptions made

Regulations for safe transport of spent fuels from nuclear power plants in CMEA member countries. Part III

International Nuclear Information System (INIS)

Zizka, B.

1978-11-01

The regulations for safe transport of spent fuel from nuclear power plants in the CMEA member countries consist of general provisions, technical requirements for spent fuel transport, transport conditions, procedures for submitting reports on transport, regulations for transport and protection of radioactive material to be transported, procedures for customs clearance, technical and organizational measures for the prevention of hypothetical accidents and the elimination of their consequences. The bodies responsible for spent fuel transport in the CMEA member countries are listed. (J.B.)

The management of the Spend Fuel Pool Water Quality (1996-2007)

Energy Technology Data Exchange (ETDEWEB)

Kim, Tae Hwan; Lee, Eui Gyu; Choi, Ho Young; Choi, Mun Jo; Kim, Hyung Wook; Lee, Mun; Lee, Choong Sung; Hur, Soon Ock; Ahn, Guk Hun

2008-12-15

The water quality management of spent fuel storage pool water quality in HANARO is important to prevent the corrosion of nuclear fuel and reactor structure material. The condition of the spent fuel storage pool water has been monitored by measuring the electrical conductivity of the spent fuel storage pool purification system and pH periodically. The status of the spent fuel storage pool water quality management was investigated by using the measured data. taken from 1996 to 2007. In general, the electrical conductivity of the spent fuel storage pool water have been managed within 1 {mu}S/cm which is an operation target of HANARO.

Analysis of the transportation logistics for spent nuclear fuel in Korea

International Nuclear Information System (INIS)

Lee, Hyo Jik; Ko, Won Il; Seo, Ki Seok

2010-01-01

As a part of the back-end fuel cycle, transportation of spent nuclear fuel (SNF) from nuclear power plants (NPP s ) to a fuel storage facility is very important in establishing a nuclear fuel cycle. In Korea, the accumulated amount of SNF in the NPP pools is troublesome since the temporary storage facilities at these NPP pools are expected to be full of SNF within ten years. Therefore, Korea cannot help but plan for the construction of an interim storage facility to solve this problem in the near future. Especially, a decision on several factors, such as where the interim storage facility should be located, how many casks a transport ship can carry at a time and how many casks are initially required, affect the configuration of the transportation system. In order to analyze the various possible candidate scenarios, we assumed four cases for the interim storage facility location, three cases for the load capacity that a transport ship can carry and two cases for the total amount of casks used for transportation. First, this study considered the currently accumulated amount of SNF in Korea, and the amount of SNF generated from NPP s until all NPP s are shut down. Then, how much SNF per year must be transported from theNPP s to an interim storage facility was calculated during an assumed transportation period. Second, 24 candidate transportation scenarios were constructed by a combination of the decision factors. To construct viable yearly transportation schedules for the selected 24 scenarios, we created a spreadsheet program named TranScenario, which was developed by using MS EXCEL. TranScenario can help schedulers input shipping routes and allocate transportation casks. Also,TranScenario provides information on the cask distribution in the NPP s and in the interim storage facility automatically, by displaying it in real time according to the shipping routes, cask types and cask numbers that the user generates. Once a yearly transportation schedule is established

327 SNF fuel return to K-Basin quality process plan

International Nuclear Information System (INIS)

Ham, J.E.

1998-01-01

The B and W Hanford Company's (BWHC) 327 Facility, in the 300 Area of the Hanford Site, contains Spent Nuclear Fuel (SNF) single fuel element canisters (SFEC) and fuel remnant canisters (FRC) which are to be returned to K-Basin. Seven shipments of up to six fuel canisters will be loaded into the CNS 1-13G Cask and transported to 105-KE

Testing of a transport cask for research reactor spent fuel

International Nuclear Information System (INIS)

Mourao, Rogerio P.; Silva, Luiz Leite da; Miranda, Carlos A.; Mattar Neto, Miguel; Quintana, Jose F.A.; Saliba, Roberto O.; Novara, Oscar E.

2011-01-01

Since the beginning of the last decade three Latin American countries which operate research reactors - Argentina, Brazil and Chile - have been joining efforts to improve the regional capability in the management of spent fuel elements from the reactors operated in the region. As a step in this direction, a packaging for the transport of irradiated fuel from research reactors was designed by a tri-national team and a half-scale model for MTR fuel constructed in Argentina and tested in Brazil. Two test campaigns have been carried out so far, covering both normal conditions of transportation and hypothetical accident conditions. Although the specimen has not successfully performed the tests, its overall performance was considered very satisfactory, and improvements are being introduced to the design. A third test sequence is planned for 2011. (author)

HYDROGEN COMMERCIALIZATION: TRANSPORTATION FUEL FOR THE 21ST CENTURY

Energy Technology Data Exchange (ETDEWEB)

APOLONIO DEL TORO

2008-05-27

Since 1999, SunLine Transit Agency has worked with the U.S. Department of Energy (DOE), U.S. Department of Defense (DOD), and the U.S. Department of Transportation (DOT) to develop and test hydrogen infrastructure, fuel cell buses, a heavy-duty fuel cell truck, a fuel cell neighborhood electric vehicle, fuel cell golf carts and internal combustion engine buses operating on a mixture of hydrogen and compressed natural gas (CNG). SunLine has cultivated a rich history of testing and demonstrating equipment for leading industry manufacturers in a pre-commercial environment. Visitors to SunLine's "Clean Fuels Mall" from around the world have included government delegations and agencies, international journalists and media, industry leaders and experts and environmental and educational groups.

Reduction of Fuel Consumption and Exhaust Pollutant Using Intelligent Transport Systems

Directory of Open Access Journals (Sweden)

Mostofa Kamal Nasir

2014-01-01

Full Text Available Greenhouse gas emitted by the transport sector around the world is a serious issue of concern. To minimize such emission the automobile engineers have been working relentlessly. Researchers have been trying hard to switch fossil fuel to alternative fuels and attempting to various driving strategies to make traffic flow smooth and to reduce traffic congestion and emission of greenhouse gas. Automobile emits a massive amount of pollutants such as Carbon Monoxide (CO, hydrocarbons (HC, carbon dioxide (CO2, particulate matter (PM, and oxides of nitrogen (NOx. Intelligent transport system (ITS technologies can be implemented to lower pollutant emissions and reduction of fuel consumption. This paper investigates the ITS techniques and technologies for the reduction of fuel consumption and minimization of the exhaust pollutant. It highlights the environmental impact of the ITS application to provide the state-of-art green solution. A case study also advocates that ITS technology reduces fuel consumption and exhaust pollutant in the urban environment.

Reduction of Fuel Consumption and Exhaust Pollutant Using Intelligent Transport Systems

Science.gov (United States)

Nasir, Mostofa Kamal; Md Noor, Rafidah; Kalam, M. A.; Masum, B. M.

2014-01-01

Greenhouse gas emitted by the transport sector around the world is a serious issue of concern. To minimize such emission the automobile engineers have been working relentlessly. Researchers have been trying hard to switch fossil fuel to alternative fuels and attempting to various driving strategies to make traffic flow smooth and to reduce traffic congestion and emission of greenhouse gas. Automobile emits a massive amount of pollutants such as Carbon Monoxide (CO), hydrocarbons (HC), carbon dioxide (CO2), particulate matter (PM), and oxides of nitrogen (NOx). Intelligent transport system (ITS) technologies can be implemented to lower pollutant emissions and reduction of fuel consumption. This paper investigates the ITS techniques and technologies for the reduction of fuel consumption and minimization of the exhaust pollutant. It highlights the environmental impact of the ITS application to provide the state-of-art green solution. A case study also advocates that ITS technology reduces fuel consumption and exhaust pollutant in the urban environment. PMID:25032239

Reduction of fuel consumption and exhaust pollutant using intelligent transport systems.

Science.gov (United States)

Nasir, Mostofa Kamal; Md Noor, Rafidah; Kalam, M A; Masum, B M

2014-01-01

Greenhouse gas emitted by the transport sector around the world is a serious issue of concern. To minimize such emission the automobile engineers have been working relentlessly. Researchers have been trying hard to switch fossil fuel to alternative fuels and attempting to various driving strategies to make traffic flow smooth and to reduce traffic congestion and emission of greenhouse gas. Automobile emits a massive amount of pollutants such as Carbon Monoxide (CO), hydrocarbons (HC), carbon dioxide (CO2), particulate matter (PM), and oxides of nitrogen (NO x ). Intelligent transport system (ITS) technologies can be implemented to lower pollutant emissions and reduction of fuel consumption. This paper investigates the ITS techniques and technologies for the reduction of fuel consumption and minimization of the exhaust pollutant. It highlights the environmental impact of the ITS application to provide the state-of-art green solution. A case study also advocates that ITS technology reduces fuel consumption and exhaust pollutant in the urban environment.

C1 CHEMISTRY FOR THE PRODUCTION OF ULTRA-CLEAN LIQUID TRANSPORTATION FUELS AND HYDROGEN

Energy Technology Data Exchange (ETDEWEB)

Gerald P. Huffman

2004-09-30

The Consortium for Fossil Fuel Science (CFFS) is a research consortium with participants from the University of Kentucky, University of Pittsburgh, West Virginia University, University of Utah, and Auburn University. The CFFS is conducting a research program to develop C1 chemistry technology for the production of clean transportation fuel from resources such as coal and natural gas, which are more plentiful domestically than petroleum. The processes under development will convert feedstocks containing one carbon atom per molecular unit into ultra clean liquid transportation fuels (gasoline, diesel, and jet fuel) and hydrogen, which many believe will be the transportation fuel of the future. Feedstocks include synthesis gas, a mixture of carbon monoxide and hydrogen produced by coal gasification, coalbed methane, light products produced by Fischer-Tropsch (FT) synthesis, methanol, and natural gas.

Used Fuel Logistics: Decades of Experience with transportation and Interim storage solutions

Energy Technology Data Exchange (ETDEWEB)

Orban, G.; Shelton, C.

2015-07-01

Used fuel inventories are growing worldwide. While some countries have opted for a closed cycle with recycling, numerous countries must expand their interim storage solutions as implementation of permanent repositories is taking more time than foreseen. In both cases transportation capabilities will have to be developed. AREVA TN has an unparalleled expertise with transportation of used fuel. For more than 50 years AREVA TN has safely shipped more than 7,000 used fuel transport casks. The transportation model that was initially developed in the 1970s has been adapted and enhanced over the years to meet more restrictive regulatory requirements and evolving customer needs, and to address public concerns. The numerous “lessons learned” have offered data and guidance that have allowed for also efficient and consistent improvement over the decades. AREVA TN has also an extensive experience with interim dry storage solutions in many countries on-site but also is working with partners to developed consolidated interim storage facility. Both expertise with storage and transportation contribute to safe, secure and smooth continuity of the operations. This paper will describe decades of experience with a very successful transportation program as well as interim storage solutions. (Author)

Standard casks for the transport of LWR spent fuel

International Nuclear Information System (INIS)

Blum, P.

1986-01-01

During the past decade, TRANSNUCLEAIRE has developed, licensed and marketed a family of standard casks for the transport of spent fuel from LWR reactors to reprocessing plants and the ancillary equipments necessary for their operation and transport. A large number of these casks have been manufactured in different countries and are presently used for european and intercontinental transports. The main advantages of these casks are: large payload, moderate cost, reliability, standardisation facilitating fabrication, operation and spare part supply [fr

Improving the ignition quality of fuels

KAUST Repository

Sarathy, Mani

2017-06-08

Provided herein are compounds and methods of producing compounds for improving ignition quality and combustion efficiency of fuels, for example fossil fuels. In various aspects we generate highly oxygenated compounds from hydrocarbon feedstocks. The feedstock can be a branched alkane or n-alkane having a chain length greater than or equal to 6, a cycloalkane with a 5 or 6 membered ring structure, or a alkylated cycloalkane with 5 or more carbon atoms. The reactant can be fed in the gas- phase to a partial oxidation reactor (with or without a catalyst), and at a fixed temperature, mixture composition, and residence time. The reactant can be converted to a mixture of products including keto hydroperoxides, diketo hydroperoxides, keto dihydroperoxides, hydroperoxyl cyclic ethers, and alkenyl hydroperoxides. The compounds are inherently unstable and can quickly decompose to highly reactive radical species that can be used to improve the ignition quality of a fuel and advance ignition in an engine.

Improving the ignition quality of fuels

KAUST Repository

Sarathy, Mani; Wang, Zhandong; Shankar, Vijai Shankar Bhavani

2017-01-01

Provided herein are compounds and methods of producing compounds for improving ignition quality and combustion efficiency of fuels, for example fossil fuels. In various aspects we generate highly oxygenated compounds from hydrocarbon feedstocks. The feedstock can be a branched alkane or n-alkane having a chain length greater than or equal to 6, a cycloalkane with a 5 or 6 membered ring structure, or a alkylated cycloalkane with 5 or more carbon atoms. The reactant can be fed in the gas- phase to a partial oxidation reactor (with or without a catalyst), and at a fixed temperature, mixture composition, and residence time. The reactant can be converted to a mixture of products including keto hydroperoxides, diketo hydroperoxides, keto dihydroperoxides, hydroperoxyl cyclic ethers, and alkenyl hydroperoxides. The compounds are inherently unstable and can quickly decompose to highly reactive radical species that can be used to improve the ignition quality of a fuel and advance ignition in an engine.

Fueling profile sensitivities of trapped particle mode transport to TNS

International Nuclear Information System (INIS)

Mense, A.T.; Attenberger, S.E.; Houlberg, W.A.

1977-01-01

A key factor in the plasma thermal behavior is the anticipated existence of dissipative trapped particle modes. A possible scheme for controlling the strength of these modes was found. The scheme involves varying the cold fueling profile. A one dimensional multifluid transport code was used to simulate plasma behavior. A multiregime model for particle and energy transport was incorporated based on pseudoclassical, trapped electron, and trapped ion regimes used elsewhere in simulation of large tokamaks. Fueling profiles peaked toward the plasma edge may provide a means for reducing density-gradient-driven trapped particle modes, thus reducing diffusion and conduction losses

Energy analysis and break-even distance for transportation for biofuels in comparison to fossil fuels

Science.gov (United States)

In the present analysis various forms fuel from biomass and fossil sources, their mass and energy densities, and their break-even transportation distances to transport them effectively were analyzed. This study gives an insight on how many times more energy spent on transporting the fuels to differe...

Nuclear Energy and Synthetic Liquid Transportation Fuels

Science.gov (United States)

McDonald, Richard

2012-10-01

This talk will propose a plan to combine nuclear reactors with the Fischer-Tropsch (F-T) process to produce synthetic carbon-neutral liquid transportation fuels from sea water. These fuels can be formed from the hydrogen and carbon dioxide in sea water and will burn to water and carbon dioxide in a cycle powered by nuclear reactors. The F-T process was developed nearly 100 years ago as a method of synthesizing liquid fuels from coal. This process presently provides commercial liquid fuels in South Africa, Malaysia, and Qatar, mainly using natural gas as a feedstock. Nuclear energy can be used to separate water into hydrogen and oxygen as well as to extract carbon dioxide from sea water using ion exchange technology. The carbon dioxide and hydrogen react to form synthesis gas, the mixture needed at the beginning of the F-T process. Following further refining, the products, typically diesel and Jet-A, can use existing infrastructure and can power conventional engines with little or no modification. We can then use these carbon-neutral liquid fuels conveniently long into the future with few adverse environmental impacts.

Analysis of hydrogen as a Transportation Fuel FY17 Report

Energy Technology Data Exchange (ETDEWEB)

Pratt, Richard M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Luzi, Francesco [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wilcox Freeburg, Eric D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2017-09-30

This report summarizes the results of literature reviews, surveys and analyses performed to evaluate the potential of hydrogen-fueled vehicles to be an economically viable transportation alternative. Five existing and important drivers of expanding hydrogen-fueled transportation adoption are multi-billion dollar sales reservations of Nikola Class 8 trucks, CALSTART viability analysis of hybrid-hydrogen drayage trucks in the shipyard cargo application, analysis showing economic advantages of Fuel Cell Electric Vehicles (FCEV)s over Battery Electric Vehicles (BEV)s beginning at 150-mile ranges, the announcement of a commercial 5kg electrolyzer, and commercial plans or vehicle availability by nine vehicle manufacturers of FCEV passenger vehicles. But hydrogen infrastructure availability needed to support broad adoption of hydrogen-fueled vehicles is limited to less than 50 publicly-available refueling stations, primarily in California. The demand side (consumer) economics associated with FCEV adoption showed strong economic sensitivity to the original vehicle’s fuel economy (mpg), distance traveled, and hydrogen (H2) generation costs. Seven use cases were used to evaluate the broad range of potential FCEV purchasers, including autonomous vehicle applications. Each consumer use case analysis resulted in a different hydrogen fuel cost that would be equivalent to the current fuel cost being paid by the consumer. The H2 generation costs (supply side) were sensitive to the volume of H2 supplied and H2 production costs needed to repay H2 supply facility capital costs and produce competitively-priced energy. H2FAST was used to more accurately incorporate capital, maintenance and production costs into a viable H2 supply cost to the consumer. When the H2 generation and consumer economics were combined, several applications with positive economics became clear. The availability of low-cost hydrogen pipeline connections, and therefore low-cost hydrogen, greatly benefits the

Proton exchange membrane fuel cell technology for transportation applications

Energy Technology Data Exchange (ETDEWEB)

Swathirajan, S. [General Motors R& D Center, Warren, MI (United States)

1996-04-01

Proton Exchange Membrane (PEM) fuel cells are extremely promising as future power plants in the transportation sector to achieve an increase in energy efficiency and eliminate environmental pollution due to vehicles. GM is currently involved in a multiphase program with the US Department of Energy for developing a proof-of-concept hybrid vehicle based on a PEM fuel cell power plant and a methanol fuel processor. Other participants in the program are Los Alamos National Labs, Dow Chemical Co., Ballard Power Systems and DuPont Co., In the just completed phase 1 of the program, a 10 kW PEM fuel cell power plant was built and tested to demonstrate the feasibility of integrating a methanol fuel processor with a PEM fuel cell stack. However, the fuel cell power plant must overcome stiff technical and economic challenges before it can be commercialized for light duty vehicle applications. Progress achieved in phase I on the use of monolithic catalyst reactors in the fuel processor, managing CO impurity in the fuel cell stack, low-cost electrode-membrane assembles, and on the integration of the fuel processor with a Ballard PEM fuel cell stack will be presented.

Quality assurance monitoring during nuclear fuel production in JSC 'TVEL'

International Nuclear Information System (INIS)

Filimonov, G.; Tchirkov, V.

2000-01-01

The paper describes Quality Assurance (QA) monitoring during fabrication of nuclear fuel in Russian Federation. Joint Stock Company 'TVEL', natural state monopoly of the type of holding that fabricates and supplies nuclear fuel for the NPPs of Russia, CIS and Europe, incorporates the major enterprises of the nuclear fuel cycle including JSC 'Mashinostroitelny zavod', Electrostal (fabrication of fuel pellets, rods and assemblies for different types of reactors), JSC 'Novosibirsky zavod khimconcentratov', Novosibirsk (fabrication of fuel rods and assemblies for WWER-440 and WWER-1000), JSC 'Tchepetsky mechanitchesky zavod', Tchepetsk (fabrication of Zr tubing). Monitoring of QA is an important element of Quality Management System (QMS) developed and implemented at the above-mentioned enterprises of the JSC 'TVEL' and it is performed on three levels including external and internal audits and author's supervision. Paper also describes short- and long-term policies of the JSC 'TVEL' in nuclear fuel quality field. (author)

New, innovative and sustainable transportation fuels

Energy Technology Data Exchange (ETDEWEB)

Lassi, U. (Univ. of Oulu, Dept. of Chemistry (Finland)). email: ulla.lassi@oulu.fi; Keiski, R. (Univ. of Oulu, Dept. of Process and Environmental Engineering (Finland)); Kordas, K. (Univ. of Oulu, Microelectronics and Materials Physics Laboratories (Finland)); Mikkola, J.-P. (Aabo Akademi Univ., Lab. of Industrial Chemistry and Reaction Engineering, Turku (Finland))

2009-07-01

Secondary products from the industry - e.g. by-products of food and paper/pulp industry - can be used to manufacture new liquid biofuels or fuel components. A particularly interesting alternative is provided by butanol, which can be produced from biomass, since it seems to be most suitable for replacing petrol as fuel in gasoline engines. Besides, it is very energy efficient and also suitable to be produced on an industrial scale. Production of biobutanol and other higher alcohols is studied in the research project 'New, innovative sustainable transportation fuels for mobile applications; from biocomponents to flexible liquid fuels (SusFuFlex)'. The project is carried out as a joint project between the University of Oulu and Aabo Akademi University. It is financied by the Academy of Finland in 2008-2011, within the research programme for Sustainable Energy. Research focuses on the production of higher bioalcohols and other compounds suitable as oxygenates (e.g. butanol, pentanol, mixed alcohols; e.g. glycerine ethers, glycerol carbonate). The objectives of the research are (1) to evaluate the old and novel procedures for microbiological production of butanol, higher alcohols and oxygenates as fossil fuel substitutes, (2) to develop and optimize catalytic materials and chemical reaction routes for the production of higher alcohols and other bio-derived compounds applicable as gasoline fuel and its additives, (3) to conduct a sustainability analysis of the processes to be developed, to analyze the atom economy of the new processes and to make a preliminary economical analysis, and (4) to integrate the processes and know-how developed by the research groups

Alternative Fuels Data Center: South Dakota Transportation Data for

Science.gov (United States)

Grants Ethanol and Methanol Tax Liquefied Natural Gas (LNG) Tax Biofuel Franchising Contract Regulations Natural Gas Transportation Fuel Consumption Source: State Energy Data System based on beta data converted

Impacts of Particulate Pollution from Fossil Fuel and Biomass Burnings on the Air Quality and Human Health in Southeast Asia

Science.gov (United States)

Lee, H. H.; Iraqui, O.; Gu, Y.; Yim, S. H. L.; Wang, C.

2017-12-01

Severe haze events in Southeast Asia have attracted the attention of governments and the general public in recent years, due to their impact on local economies, air quality and public health. Widespread biomass burning activities are a major source of severe haze events in Southeast Asia. On the other hand, particulate pollutants from human activities other than biomass burning also play an important role in degrading air quality in Southeast Asia. These pollutants can be locally produced or brought in from neighboring regions by long-range transport. A better understanding of the respective contributions of fossil fuel and biomass burning aerosols to air quality degradation becomes an urgent task in forming effective air pollution mitigation policies in Southeast Asia. In this study, to examine and quantify the contributions of fossil fuel and biomass burning aerosols to air quality and visibility degradation over Southeast Asia, we conducted three numerical simulations using the Weather Research and Forecasting (WRF) model coupled with a chemistry component (WRF-Chem). These simulations were driven by different aerosol emissions from: (a) fossil fuel burning only, (b) biomass burning only, and (c) both fossil fuel and biomass burning. By comparing the simulation results, we examined the corresponding impacts of fossil fuel and biomass burning emissions, separately and combined, on the air quality and visibility of the region. The results also showed that the major contributors to low visibility days (LVDs) among 50 ASEAN cities are fossil fuel burning aerosols (59%), while biomass burning aerosols provided an additional 13% of LVDs in Southeast Asia. In addition, the number of premature mortalities among ASEAN cities has increased from 4110 in 2002 to 6540 in 2008, caused primarily by fossil fuel burning aerosols. This study suggests that reductions in both fossil fuel and biomass burning emissions are necessary to improve the air quality in Southeast Asia.

FFTF metal fuel pin sodium bond quality verification

International Nuclear Information System (INIS)

Pitner, A.L.; Dittmer, J.O.

1988-12-01

The Fast Flux Test Facility (FFTF) Series III driver fuel design consists of U-10Zr fuel slugs contained in a ferritic alloy cladding. A liquid metal, sodium bond between the fuel and cladding is required to prevent unacceptable temperatures during operation. Excessive voiding or porosity in the sodium thermal bond could result in localized fuel melting during irradiation. It is therefore imperative that bond quality be verified during fabrication of these metal fuel pins prior to irradiation. This document discusses this verification

Regulatory status of burnup credit for storage and transport of spent fuel in Germany

International Nuclear Information System (INIS)

Neuber, J.C.; Schweer, H.H.; Johann, H.G.

2001-01-01

This paper describes the regulatory status of burnup credit applications to pond storage and dry-cask transport and storage of spent fuel in Germany. Burnup credit for wet storage of LWR fuel at nuclear power plants has to comply with the newly developed safety standard DIN 25471. This standard establishes the safety requirements for burnup credit criticality safety analysis of LWR fuel storage ponds and gives guidance on meeting these requirements. Licensing evaluations of dry transport systems are based on the application of the IAEA Safety Standards Series No.ST-1. However, because of the fact that burnup credit for dry-cask transport becomes more and more inevitable due to increasing initial enrichment of the fuel, and because of the increasing importance of dry-cask storage in Germany, the necessity of giving regulatory guidance on applying burnup credit to dry-cask transport and storage is seen. (author)

OPTIMIZATION METHOD AND SOFTWARE FOR FUEL COST REDUCTION IN CASE OF ROAD TRANSPORT ACTIVITY

Directory of Open Access Journals (Sweden)

György Kovács

2017-06-01

Full Text Available The transport activity is one of the most expensive processes in the supply chain and the fuel cost is the highest cost among the cost components of transportation. The goal of the research is to optimize the transport costs in case of a given transport task both by the selecting the optimal petrol station and by determining the optimal amount of the refilled fuel. Recently, in practice, these two decisions have not been made centrally at the forwarding company, but they depend on the individual decision of the driver. The aim of this study is to elaborate a precise and reliable mathematical method for selecting the optimal refuelling stations and determining the optimal amount of the refilled fuel to fulfil the transport demands. Based on the elaborated model, new decision-supporting software is developed for the economical fulfilment of transport trips.

Total quality approach at ABB Atom Nuclear Fuel - winner of the Swedish quality award 1994

International Nuclear Information System (INIS)

Moorlin, K.; Olsson, S.

1995-01-01

ABB Atom Nuclear Fuel Division received the Swedish Quality Award 1994. The company has since many years a reputation for high product quality and a well implemented quality assurance system. Since some years a total quality approach is applied. For ABB Atom, total quality means continuous improvement of all business processes keeping the customer in focus. This paper elaborates on the improvement tools used at the ABB Atom Nuclear Fuel Division and gives some detailed information of the experience. (author) 6 figs

Experiences in the application of quality control and quality assurance programmes in water reactor fuel fabrication

International Nuclear Information System (INIS)

Balaramamoorthy, K.; Vijayaraghavan, R.; Kulkarni, P.G.; Raghavan, S.V.; Bandyopadhyay, A.K.

1984-01-01

Nuclear fuel for Research Reactors and Pressurised Heavy Water Reactors (PHWRs) is being fabricated in India for a period of over two decades. The fuel is produced to conform to stringent quality control specifications. Generally, the performance of the fuel has been very good in the reactors. This is not only due to the high quality workmanship in the various stages of production but also to the meticulous care exercised in the planning and application of quality control and quality assurance procedures. For the nuclear fuel used in Water Reactors, extensive material specifications have been compiled and they are periodically reviewed and revised. The specifications cover various aspects such as metallurgical and mechanical properties, non-destructive testing, dimensional and visual standard requirements. Similarly, detailed manufacturing engineering instructions (MEIs) and quality control instructions (QCIs) have been drawn. For any deviations from the specified requirements, design concession committee considers all deviations and acceptance or rejection criteria are evolved. In this task, the design concession committee is supported by experimentation in various laboratories of the Department of Atomic Energy. The Quality Assurance procedures have been evolved over a long period of time. They generally conform to the latest code and recommended guides of IAEA regarding Quality Assurance in the manufacture of fuel. (orig.)