Options for treating high-temperature gas-cooled reactor fuel for repository disposal

International Nuclear Information System (INIS)

Lotts, A.L.; Bond, W.D.; Forsberg, C.W.; Glass, R.W.; Harrington, F.E.; Micheals, G.E.; Notz, K.J.; Wymer, R.G.

1992-02-01

This report describes the options that can reasonably be considered for disposal of high-temperature gas-cooled reactor (HTGR) fuel in a repository. The options include whole-block disposal, disposal with removal of graphite (either mechanically or by burning), and reprocessing of spent fuel to separate the fuel and fission products. The report summarizes what is known about the options without extensively projecting or analyzing actual performance of waste forms in a repository. The report also summarizes the processes involved in convert spent HTGR fuel into the various waste forms and projects relative schedules and costs for deployment of the various options. Fort St. Vrain Reactor fuel, which utilizes highly-enriched 235 U (plus thorium) and is contained in a prismatic graphite block geometry, was used as the baseline for evaluation, but the major conclusions would not be significantly different for low- or medium-enriched 235 U (without thorium) or for the German pebble-bed fuel. Future US HTGRs will be based on the Fort St. Vrain (FSV) fuel form. The whole block appears to be a satisfactory waste form for disposal in a repository and may perform better than light-water reactor (LWR) spent fuel. From the standpoint of process cost and schedule (not considering repository cost or value of fuel that might be recycled), the options are ranked as follows in order of increased cost and longer schedule to perform the option: (1) whole block, (2a) physical separation, (2b) chemical separation, and (3) complete chemical processing

Advanced Fuel Cycle Cost Basis

Energy Technology Data Exchange (ETDEWEB)

D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert; E. Schneider

2009-12-01

This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 25 cost modules—23 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, transuranic, and high-level waste.

Advanced Fuel Cycle Cost Basis

Energy Technology Data Exchange (ETDEWEB)

D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert

2007-04-01

This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 26 cost modules—24 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, and high-level waste.

Advanced Fuel Cycle Cost Basis

Energy Technology Data Exchange (ETDEWEB)

D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert; E. Schneider

2008-03-01

This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 25 cost modules—23 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, transuranic, and high-level waste.

Technology assessment of various coal-fuel options

International Nuclear Information System (INIS)

Coenen, R.; Findling, B.; Klein-Vielhauer, S.; Nieke, E.; Paschen, H.; Tangen, H.; Wintzer, D.

1991-01-01

The technology assessment (TA) study of coal-based fuels presented in this report was performed for the Federal Ministry for Research and Technology. Its goal was to support decision-making of the Federal Ministry for Research and Technology in the field of coal conversion. Various technical options of coal liquefaction have been analyzed on the basis of hard coal as well as lignite -- direct liquefaction of coal (hydrogenation) and different possibilities of indirect liquefaction, that is the production of fuels (methanol, gasoline) by processing products of coal gasification. The TA study takes into consideration the entire technology chain from coal mining via coal conversion to the utilization of coal-based fuels in road transport. The analysis focuses on costs of the various options, overall economic effects, which include effects on employment and public budgets, and on environmental consequences compared to the use of liquid fuels derived from oil. Furthermore, requirements of infrastructure and other problems of the introduction of coal-based fuels as well as prospects for the export of technologies of direct and indirect coal liquefaction have been analyzed in the study. 14 figs., 10 tabs

Performance and fuel cycle cost analysis of one Janus 30 conceptual design for several fuel element design options

Energy Technology Data Exchange (ETDEWEB)

Nurdin, Martias [Research Centre for Nuclear Techniques, National Atomic Energy Agency (Indonesia); Matos, J E; Freese, K E [RERTR Program, Argonne National Laboratory (United States)

1983-09-01

The performance and fuel cycle costs for a 25 MW, JANUS 30 reactor conceptual design by INTERATOM, Federal Republic of Germany, for BATAN, Republic of Indonesia have been studied using 19.75% enriched uranium in four fuel element design options. All of these fuel element designs have either been proposed by INTERATOM for various reactors or are currently in use with 93% enriched uranium in reactors in the Federal Republic of Germany. Aluminide, oxide, and silicide fuels were studied for selected designs using the range of uranium densities that are either currently qualified or are being developed and demonstrated internationally. These uranium densities include 1.7-2.3 g/cm{sup 3} in aluminide fuel, 1.7-3.2 g/cm{sup 3} in oxide fuel, and 2.9-6.8 g/cm{sup 3} in silicide fuel. As of November 1982) both the aluminide and the oxide fuels with about 1.7 g U/cm{sup 3} are considered to be fully-proven for licensing purposes. Irradiation screening and proof testing of fuels with uranium densities greater than 1.7 g/cm{sup 3} are currently in progress, and these tests need to be completed in order to obtain licensing authorization for routine reactor use. To assess the long-term fuel adaptation strategy as well as the present fuel acceptance, reactor performance and annual fuel cycle costs were computed for seventeen cases based on a representative end-of-cycle excess reactivity and duty factor. In addition, a study was made to provide data for evaluating the trade-off between the increased safety associated with thicker cladding and the economic penalty due to increased fuel consumption. (author)

A comparison study on radioactive waste management effectiveness in various nuclear fuel cycles

International Nuclear Information System (INIS)

Ko, Won Il; Kim, Ho Dong

2001-07-01

This study examines whether the DUPIC (Direct Use of Spent PWR Fuel In CANDU) fuel cycle make radioactive waste management more effective, by comparing it with other fuel cycles such as the PWR (Pressurized Water Reactor) once-through cycle, the HWR (Pressurized Heavy Water Reactor) once-through cycle and the thermal recycling option to use an existing PWR with MOX (Mixed Oxide) fuel. This study first focuses on the radioactive waste volume generated in all fuel cycle steps, which could be one of the measures of effectiveness of the waste management. Then the total radioactive waste disposition cost is estimated based on two units measuring; m3/GWe-yr and US$/GWe-yr. We find from the radioactive waste volume estimation that the DUPIC fuel cycle could have lower volumes for milling tailings, low level waste and spent fuel than those of other fuel cycle options. From the results of the disposition cost analysis, we find that the DUPIC waste disposition cost is the lowest among fuel cycle options. If the total waste disposition cost is used as a proxy for quantifying the easiness or difficulty in managing wastes, then the DUPIC option actually make waste management easier

PWR Core II blanket fuel disposition recommendation of storage option study

International Nuclear Information System (INIS)

Dana, C.M.

1995-01-01

After review of the options available for current storage of T Plant Fuel the recommended option is wet storage without the use of chillers. A test has been completed that verifies the maximum temperature reached is below the industrial standard for storage of spent fuel. This option will be the least costly and still maintain the fuel in a safe environment. The options that were evaluated included dry storage with and without chillers, and wet storage with and without chillers. Due to the low decay heat of the Shippingport Core II Blanket fuel assemblies the fuel pool temperature will not exceed 100 deg. F

Conversion and standardization of university reactor fuels using low-enrichment uranium - options and costs

International Nuclear Information System (INIS)

Harris, D.R.; Matos, J.E.; Young, H.H.

1985-01-01

The highly-enriched uranium (HEU) fuel used in twenty United States university reactors can be viewed as contributing to the risk of theft or diversion of weapons-useable material. The US Nuclear Regulatory Commission has issued a policy statement expressing its concern and has published a proposed rule on limiting the use of HEU in NRC-licensed non-power reactors. The fuel options, functional impacts, licensing, and scheduling of conversion and standardization of these reactor fuels to use of low-enrichment uranium (LEU) have been assessed. The university reactors span a wide range in form and function, from medium-power intense neutron sources where HEU fuel may be required, to low-power training and research facilities where HEU fuel is unnecessary. Conversion provides an opportunity to standardize university reactor fuels and improve reactor utilization in some cases. The entire program is estimated to cost about $10 million and to last about five years. Planning for conversion and standardization is facilitated by the US Department of Energy. 20 refs., 1 tab

Conversion and standardization of university reactor fuels using low-enrichment uranium - Options and costs

International Nuclear Information System (INIS)

Harris, D.R.; Matos, J.E.; Young, H.H.

1985-01-01

The highly-enriched uranium (HEU) fuel used in twenty United States university reactors can be viewed as contributing to the risk of theft or diversion of weapons-useable material. The U.S. Nuclear Regulatory Commission has issued a policy statement expressing its concern and has published a proposed rule on limiting the use of HEU in NRC-licensed non-power reactors. The fuel options, functional impacts, licensing, and scheduling of conversion and standardization of these reactor fuels to use of low-enrichment uranium (LEU) have been assessed. The university reactors span a wide range in form and function, from medium-power intense neutron sources where HEU fuel may be required, to low-power training and research facilities where HEU fuel is unnecessary. Conversion provides an opportunity to standardize university reactor fuels and improve reactor utilization in some cases. The entire program is estimated to cost about $10 million and to last about five years. Planning for conversion and standardization is facilitated by the U.S. Department of Energy. (author)

Options for cost-effectively reducing atmospheric methane concentrations from anthropogenic biomass sources

International Nuclear Information System (INIS)

Roos, K.F.; Jacobs, C.; Orlic, M.

1993-01-01

Methane is a major greenhouse gas, second only to carbon dioxide in its contribution to future global warming. Methane concentrations have more than doubled over the last two centuries and continue to rise annually. These increases are largely correlated with increasing human populations. Methane emissions from human related activities currently account for about 70 percent of annual emissions. Of these human related emissions, biomass sources account for about 75 percent and non-biomass sources about 25 percent. Because methane has a shorter lifetime than other major greenhouse gases, efforts to reduce methane emissions may fairly quickly be translated into lower atmospheric concentrations of methane and lower levels of radiative forcing. This fairly quick response would have the benefit of slowing the rate of climate change and hence allow natural ecosystems more time to adapt. Importantly, methane may be cost-effectively reduced from a number of biomass and non-biomass sources in the United States and worldwide. Methane is a valuable fuel, not just a waste by-product, and often systems may be reconfigured to reap the fuel value of the methane and more than justify the necessary expenditures. Such options for reducing methane emission from biomass sources exist for landfills, livestock manures, and ruminant livestock, and have been implemented to varying degrees in countries around the world. However, there are a number of barriers that hinder the more widespread use of technologies, including institutional, financial, regulatory, informational, and other barriers. This paper describes an array of available options that may be cost-effectively implemented to reduce methane emissions from biomass sources. This paper also discusses a number of programs that have been developed in the United States and internationally to promote the implementation of these methane reduction options and overcome existing barriers

Cost-effective and low-technology options for simulation and training in neonatology.

Science.gov (United States)

Bruno, Christie J; Glass, Kristen M

2016-11-01

The purpose of this review is to explore low-cost options for simulation and training in neonatology. Numerous cost-effective options exist for simulation and training in neonatology. Lower cost options are available for teaching clinical skills and procedural training in neonatal intubation, chest tube insertion, and pericardiocentesis, among others. Cost-effective, low-cost options for simulation-based education can be developed and shared in order to optimize the neonatal simulation training experience. Copyright © 2016 Elsevier Inc. All rights reserved.

Spent fuel reprocessing options

International Nuclear Information System (INIS)

2008-08-01

The objective of this publication is to provide an update on the latest developments in nuclear reprocessing technologies in the light of new developments on the global nuclear scene. The background information on spent fuel reprocessing is provided in Section One. Substantial global growth of nuclear electricity generation is expected to occur during this century, in response to environmental issues and to assure the sustainability of the electrical energy supply in both industrial and less-developed countries. This growth carries with it an increasing responsibility to ensure that nuclear fuel cycle technologies are used only for peaceful purposes. In Section Two, an overview of the options for spent fuel reprocessing and their level of development are provided. A number of options exist for the treatment of spent fuel. Some, including those that avoid separation of a pure plutonium stream, are at an advanced level of technological maturity. These could be deployed in the next generation of industrial-scale reprocessing plants, while others (such as dry methods) are at a pilot scale, laboratory scale or conceptual stage of development. In Section Three, research and development in support of advanced reprocessing options is described. Next-generation spent fuel reprocessing plants are likely to be based on aqueous extraction processes that can be designed to a country specific set of spent fuel partitioning criteria for recycling of fissile materials to advanced light water reactors or fast spectrum reactors. The physical design of these plants must incorporate effective means for materials accountancy, safeguards and physical protection. Section four deals with issues and challenges related to spent fuel reprocessing. The spent fuel reprocessing options assessment of economics, proliferation resistance, and environmental impact are discussed. The importance of public acceptance for a reprocessing strategy is discussed. A review of modelling tools to support the

Fuel cycle cost comparisons with oxide and silicide fuels

Energy Technology Data Exchange (ETDEWEB)

Matos, J E; Freese, K E [RERTR Program, Argonne National Laboratory (United States)

1983-09-01

This paper addresses fuel cycle cost comparisons for a generic 10 MW reactor with HEU aluminide fuel and with LEU oxide and silicide fuels in several fuel element geometries. The intention of this study is to provide a consistent assessment of various design options from a cost point of view. The status of the development and demonstration of the oxide and silicide fuels are presented in several papers in these proceedings. Routine utilization of these fuels with the uranium densities considered here requires that they are successfully demonstrated and licensed. Thermal-hydraulic safety margins, shutdown margins, mixed cores, and transient analyses are not addressed here, but analyses of these safety issues are in progress for a limited number of the most promising design options. Fuel cycle cost benefits could result if a number of reactors were to utilize fuel elements with the same number or different numbers of the same standard fuel plate. Data is presented to quantify these potential cost benefits. This analysis shows that there are a number of fuel element designs using LEU oxide or silicide fuels that have either the same or lower total fuel cycle costs than the HEU design. Use of these fuels with the uranium densities considered requires that they are successfully demonstrated and licensed. All safety criteria for the reactor with these fuel element designs need to be satisfied as well. With LEU oxide fuel, 31 g U/cm{sup 3} 1 and 0.76 mm--thick fuel meat, elements with 18-22 plates 320-391 g {sup 235}U) result in the same or lower total costs than with the HEU element 23 plates, 280 g {sup 235}U). Higher LEU loadings (more plates per element) are needed for larger excess reactivity requirements. However, there is little cost advantage to using more than 20 of these plates per element. Increasing the fuel meat thickness from 0.76 mm to 1.0 mm with 3.1 g U/cm{sup 3} in the design with 20 plates per element could result in significant cost reductions if the

Nuclear spent fuel management. Experience and options

International Nuclear Information System (INIS)

1986-01-01

Spent nuclear fuel can be stored safely for long periods at relatively low cost, but some form of permanent disposal will eventually be necessary. This report examines the options for spent fuel management, explores the future prospects for each stage of the back-end of the fuel cycle and provides a thorough review of past experience and the technical status of the alternatives. Current policies and practices in twelve OECD countries are surveyed

CANDU fuel cycle options in Korea

International Nuclear Information System (INIS)

Boczar, P.G.; Fehrenbach, P.J.; Meneley, D.A.

1996-04-01

The easiest first step in CANDU fuel-cycle evolution may be the use of slightly enriched uranium (SEU), including recovered uranium from reprocessed LWR spent fuel. Relatively low enrichment (up to 1.2%) will result in a twoto three-fold reduction in the quantity of spent fuel per unit energy production, reductions in fuel-cycle costs, and greater flexibility in the design of new reactors. The CANFLEX (CANDU FLEXible) fuel bundle would be the optimal fuel carrier. A country that has both CANDU and PWR reactors can exploit the natural synergism between these two reactor types to minimize overall waste production, and maximize energy derived from the fuel. This synergism can be exploited through several different fuel cycles. A high burnup CANDU MOX fuel design could be used to utilize plutonium from conventional reprocessing or more advanced reprocessing options (such as co-processing). DUPIC (Direct Use of Spent PWR Fuel In CANDU) represents a recycle option that has a higher degree of proliferation resistance than does conventional reprocessing, since it uses only dry processes for converting spent PWR fuel into CANDU fuel, without separating the plutonium. Good progress is being made in the current KAERI, AECL, and U.S. Department of State program in demonstrating the technical feasibility of DUPIC. In the longer term, CANDU reactors offer even more dramatic synergistic fuel cycles with PWR or FBR reactors. If the objective of a national fuel-cycle program is the minimization of actinide waste or destruction of long-lived fission products, then studies have shown the superiority of CANDU reactors in meeting this objective. Long-term energy security can be assured either through the thorium cycle or through a CANDU 1 FBR system, in which the FBR would be operated as a 'fuel factory,' providing the fissile material to power a number of lower-cost, high efficiency CANDU reactors. In summary, the CANDU reactor's simple fuel design, high neutron economy, and on

Impacts of nuclear fuel cycle costs on nuclear power generating costs

International Nuclear Information System (INIS)

Bertel, E.; Naudet, G.

1989-01-01

Fuel cycle costs are one of the main parameters to evaluate the competitiveness of various nuclear strategies. The historical analysis based on the French case shows the good performances yet achieved in mastering elementary costs in order to limit global fuel cycle cost escalation. Two contrasted theoretical scenarios of costs evolution in the middle and long term have been determined, based upon market analysis and technological improvements expected. They are used to calculate the global fuel cycle costs for various fuel management options and for three strategies of nuclear deployment. The results illustrate the stability of the expected fuel cycle costs over the long term, to be compared to the high incertainty prevailing for fossil fueled plants. The economic advantages of advanced technologies such as MOX fueled PWRs are underlined

Sustainability Features of Nuclear Fuel Cycle Options

Directory of Open Access Journals (Sweden)

Stefano Passerini

2012-09-01

Full Text Available The nuclear fuel cycle is the series of stages that nuclear fuel materials go through in a cradle to grave framework. The Once Through Cycle (OTC is the current fuel cycle implemented in the United States; in which an appropriate form of the fuel is irradiated through a nuclear reactor only once before it is disposed of as waste. The discharged fuel contains materials that can be suitable for use as fuel. Thus, different types of fuel recycling technologies may be introduced in order to more fully utilize the energy potential of the fuel, or reduce the environmental impacts and proliferation concerns about the discarded fuel materials. Nuclear fuel cycle systems analysis is applied in this paper to attain a better understanding of the strengths and weaknesses of fuel cycle alternatives. Through the use of the nuclear fuel cycle analysis code CAFCA (Code for Advanced Fuel Cycle Analysis, the impact of a number of recycling technologies and the associated fuel cycle options is explored in the context of the U.S. energy scenario over 100 years. Particular focus is given to the quantification of Uranium utilization, the amount of Transuranic Material (TRU generated and the economics of the different options compared to the base-line case, the OTC option. It is concluded that LWRs and the OTC are likely to dominate the nuclear energy supply system for the period considered due to limitations on availability of TRU to initiate recycling technologies. While the introduction of U-235 initiated fast reactors can accelerate their penetration of the nuclear energy system, their higher capital cost may lead to continued preference for the LWR-OTC cycle.

An analysis of international nuclear fuel supply options

Science.gov (United States)

Taylor, J'tia Patrice

. The material movement module is the largest of the three, and the two other modules that assess nonproliferation and economics of the options are dependent on its output. Proliferation resistance measures from literature are modified and incorporated in MEPAT. The module to assess the nonproliferation of the supply options allows the user to specify defining attributes for the fuel cycle processes, and determines significant quantities of materials as well as measures of proliferation resistance. The measure is dependent on user-input and material information. The economics module allows the user to specify costs associated with different processes and other aspects of the fuel cycle. The simulation tool then calculates economic measures that relate the cost of the fuel cycle to electricity production. The second part of this dissertation consists of an examination of four scenarios of fuel supply option using MEPAT. The first is a simple scenario illustrating the modules and basic functions of MEPAT. The second scenario recreates a fuel supply study reported earlier in literature, and compares MEPAT results with those reported earlier for validation. The third, and a rather realistic, scenario includes four nuclear programs with one program entering the nuclear energy market. The fourth scenario assesses the reactor options available to the Hashemite Kingdom of Jordan, which is currently assessing available options to introduce nuclear power in the country. The methodology developed and implemented in MEPAT to analyze the material, proliferation and economics of nuclear fuel supply options is expected to help simplify and assess different reactor and fuel options available to utilities, government agencies and international organizations.

Cost analysis and economic comparison for alternative fuel cycles in the heavy water cooled canadian reactor (CANDU)

International Nuclear Information System (INIS)

Yilmaz, S.

2000-01-01

Three main options in a CANDU fuel cycle involve use of: (1) natural uranium (0.711 weight percent U-235) fuel, (2) slightly enriched uranium (1.2 weight percent U-235) fuel, and (3) recovered uranium (0.83 weight percent U-235) fuel from light water reactor spent fuel. ORIGEN-2 computer code was used to identify composition of the spent fuel for each option, including the standard LWR fuel (3.3 weight percent U-235). Uranium and plutonium credit calculations were performed using ORIGEN-2 output. WIMSD-5 computer code was used to determine maximum discharge burnup values for each case. For the 3 cycles selected (natural uranium, slightly enriched uranium, recovered uranium), levelized fuel cycle cost calculations are performed over the reactor lifetime of 40 years, using unit process costs obtained from literature. Components of the fuel cycle costs are U purchase, conversion, enrichment, fabrication, SF storage, SF disposal, and reprocessing where applicable. Cost parameters whose effects on the fuel cycle cost are to be investigated are escalation ratio, discount rate and SF storage time. Cost estimations were carried out using specially developed computer programs. Share of each cost component on the total cost was determined and sensitivity analysis was performed in order to show how a change in a main cost component affects the fuel cycle cost. The main objective of this study has been to find out the most economical option for CANDU fuel cycle by changing unit prices and cost parameters

Cost effectiveness of robotics and remote tooling for occupational risk reduction at a nuclear fuel fabrication facility

Energy Technology Data Exchange (ETDEWEB)

Lochard, Jacques

1989-08-01

This case study, related to the design stage of a fuel fabrication facility, presents the evaluation of alternative options to manipulate mixed oxide fuel rods in a quality control shop. It is based on a study performed in the framework of the 'MELOX project' developed by COGEMA in France. The methodology for evaluating robotic actions is resulting from a research work part funded by the IAEA under the co-ordinated research programme on 'Comparison of cost-effectiveness of risk reduction among different energy systems', and by the commission of the European Communities under the research and training programme on radiation protection.

Cost effectiveness of robotics and remote tooling for occupational risk reduction at a nuclear fuel fabrication facility

International Nuclear Information System (INIS)

Lochard, Jacques

1989-01-01

This case study, related to the design stage of a fuel fabrication facility, presents the evaluation of alternative options to manipulate mixed oxide fuel rods in a quality control shop. It is based on a study performed in the framework of the 'MELOX project' developed by COGEMA in France. The methodology for evaluating robotic actions is resulting from a research work part funded by the IAEA under the co-ordinated research programme on 'Comparison of cost-effectiveness of risk reduction among different energy systems', and by the commission of the European Communities under the research and training programme on radiation protection

Bioenergy expansion in the EU: Cost-effective climate change mitigation, employment creation and reduced dependency on imported fuels

International Nuclear Information System (INIS)

Berndes, Goeran; Hansson, Julia

2007-01-01

Presently, the European Union (EU) is promoting bioenergy. The aim of this paper is to study the prospects for using domestic biomass resources in Europe and specifically to investigate whether different policy objectives underlying the promotion of bioenergy (cost-effective climate change mitigation, employment creation and reduced dependency on imported fuels) agree on which bioenergy options that should be used. We model bioenergy use from a cost-effectiveness perspective with a linear regionalized energy- and transport-system model and perform supplementary analysis. It is found that the different policy objectives do not agree on the order of priority among bioenergy options. Maximizing climate benefits cost-effectively is in conflict with maximizing employment creation. The former perspective proposes the use of lignocellulosic biomass in the stationary sector, while the latter requires biofuels for transport based on traditional agricultural crops. Further, from a security-of-supply perspective, the appeal of a given bioenergy option depends on how oil and gas import dependencies are weighed relative to each other. Consequently, there are tradeoffs that need to be addressed by policymakers promoting the use of bioenergy. Also, the importance of bioenergy in relation to employment creation and fuel import dependency reduction needs to be further addressed

CANDU fuel cycle options in Korea

International Nuclear Information System (INIS)

Boczar, P. G.; Fehrenbach, P. J.; Meneley, D. A.

1996-01-01

There are many reasons for countries embarking on a CANDU R program to start with the natural uranium fuel cycle. Simplicity of fuel design, ease of fabrication, and ready availability of natural uranium all help to localize the technology and to reduce reliance on foreign technology. Nonetheless, at some point, the incentives for using natural uranium fuel may be outweighed by the advantages of alternate fuel cycles. The excellent neutron economy, on-line refuelling, and simple fuel-bundle design provide an unsurpassed degree of fuel-cycle flexibility in CANDU reactors. The easiest first step in CANDU fuel-cycle evolution may be the use of slightly enriched uranium (SEU), including recovered uranium from reprocessed LWR spent fuel. Relatively low enrichment (up to 1.2%) will result in a two- to three-fold reduction in the quantity of spent fuel per unit energy production, reductions in fuel-cycle costs, and greater flexibility in the design of new reactors. The CANFLEX (CANDU FLEXible) fuel bundle would be the optimal fuel carrier. A country that has both CANDU and PWR reactors can exploit the natural synergism between these two reactor types to minimize overall waste production, and maximize energy derived from the fuel. This synergism can be exploited through several different fuel cycles. A high burnup CANDU MOX fuel design could be used to utilize plutonium from conventional reprocessing or more advanced reprocessing options (such as co-processing). DUPIC (Direct Use of Spent PWR Fuel In CANDU) represents a recycle option that has a higher degree of proliferation resistance than dose conventional reprocessing, since it uses only dry processes for converting spent PWR fuel into CANDU fuel, without separating the plutonium. Good progress is being made in the current KAERI, AECL, and U. S. Department of State program in demonstrating the technical feasibility of DUPIC. In the longer term, CANDU reactors offer even more dramatic synergistic fuel cycles with PWR or

Nuclear fuel cycle cost analysis using a probabilistic simulation technique

International Nuclear Information System (INIS)

Won, Il Ko; Jong, Won Choi; Chul, Hyung Kang; Jae, Sol Lee; Kun, Jai Lee

1998-01-01

A simple approach was described to incorporate the Monte Carlo simulation technique into a fuel cycle cost estimate. As a case study, the once-through and recycle fuel cycle options were tested with some alternatives (ie. the change of distribution type for input parameters), and the simulation results were compared with the values calculated by a deterministic method. A three-estimate approach was used for converting cost inputs into the statistical parameters of assumed probabilistic distributions. It was indicated that the Monte Carlo simulation by a Latin Hypercube Sampling technique and subsequent sensitivity analyses were useful for examining uncertainty propagation of fuel cycle costs, and could more efficiently provide information to decisions makers than a deterministic method. It was shown from the change of distribution types of input parameters that the values calculated by the deterministic method were set around a 40 th ∼ 50 th percentile of the output distribution function calculated by probabilistic simulation. Assuming lognormal distribution of inputs, however, the values calculated by the deterministic method were set around an 85 th percentile of the output distribution function calculated by probabilistic simulation. It was also indicated from the results of the sensitivity analysis that the front-end components were generally more sensitive than the back-end components, of which the uranium purchase cost was the most important factor of all. It showed, also, that the discount rate made many contributions to the fuel cycle cost, showing the rank of third or fifth of all components. The results of this study could be useful in applications to another options, such as the Dcp (Direct Use of PWR spent fuel In Candu reactors) cycle with high cost uncertainty

Economic Analysis of Different Nuclear Fuel Cycle Options

International Nuclear Information System (INIS)

Ko, W.; Gao, F.

2012-01-01

An economic analysis has been performed to compare four nuclear fuel cycle options: a once-through cycle (OT), DUPIC recycling, thermal recycling using MOX fuel in a pressurized water reactor (PWR-MOX), and sodium fast reactor recycling employing pyro processing (Pyro-SFR). This comparison was made to suggest an economic competitive fuel cycle for the Republic of Korea. The fuel cycle cost (FCC) has been calculated based on the equilibrium material flows integrated with the unit cost of the fuel cycle components. The levelized fuel cycle costs (LFCC) have been derived in terms of mills/kWh for a fair comparison among the FCCs, and the results are as follows: OT 7.35 mills/kWh, DUPIC 9.06 mills/kWh, PUREX-MOX 8.94 mills/kWh, and Pyro-SFR 7.70 mills/kWh. Due to unavoidable uncertainties, a cost range has been applied to each unit cost, and an uncertainty study has been performed accordingly. A sensitivity analysis has also been carried out to obtain the break-even uranium price (215$/kgU) for the Pyro-SFR against the OT, which demonstrates that the deployment of the Pyro-SFR may be economical in the foreseeable future. The influence of pyro techniques on the LFCC has also been studied to determine at which level the potential advantages of Pyro-SFR can be realized.

Cost-effectiveness of emergency contraception options over 1 year.

Science.gov (United States)

Bellows, Brandon K; Tak, Casey R; Sanders, Jessica N; Turok, David K; Schwarz, Eleanor B

2018-05-01

seeking emergency contraception, the model estimated direct medical costs of $1,228,000 and 137 unintended pregnancies with ulipristal acetate, compared to $1,279,000 and 150 unintended pregnancies with oral levonorgestrel, $1,376,000 and 61 unintended pregnancies with copper intrauterine devices, and $1,558,000 and 63 unintended pregnancies with oral levonorgestrel plus same-day levonorgestrel intrauterine device. The copper intrauterine device was the most cost-effective emergency contraception strategy in the majority (63.9%) of model iterations and, compared to ulipristal acetate, cost $1957 per additional pregnancy prevented. Model estimates were most sensitive to changes in the cost of the copper intrauterine device (with higher copper intrauterine device costs, oral levonorgestrel plus same-day levonorgestrel intrauterine device became the most cost-effective option) and the cost of a live birth (with lower-cost births, ulipristal acetate became the most cost-effective option). When the proportion of obese women in the population increased, the copper intrauterine device became even more most cost-effective. Over 1 year, the copper intrauterine device is currently the most cost-effective emergency contraception option. Policy makers and health care insurance companies should consider the potential for long-term savings when women seeking emergency contraception can promptly obtain whatever contraceptive best meets their personal preferences and needs; this will require removing barriers and promoting access to intrauterine devices at emergency contraception visits. Copyright © 2018 Elsevier Inc. All rights reserved.

Emission Control Cost-Effectiveness of Alternative-Fuel Vehicles

OpenAIRE

Wang, Quanlu; Sperling, Daniel; Olmstead, Janis

1993-01-01

Although various legislation and regulations have been adopted to promote the use of alternative-fuel vehicles for curbing urban air pollution problems, there is a lack of systematic comparisons of emission control cost-effectiveness among various alternative-fuel vehicle types. In this paper, life-cycle emission reductions and life-cycle costs were estimated for passenger cars fueled with methanol, ethanol, liquified petroleum gas, compressed natural gas, and electricity. Vehicle emission es...

Alternative Fuels Data Center: Biodiesel Equipment Options

Science.gov (United States)

Equipment Options to someone by E-mail Share Alternative Fuels Data Center: Biodiesel Equipment Options on Facebook Tweet about Alternative Fuels Data Center: Biodiesel Equipment Options on Twitter Bookmark Alternative Fuels Data Center: Biodiesel Equipment Options on Google Bookmark Alternative Fuels

Effect of different fuel options on performance of high-temperature PEMFC (proton exchange membrane fuel cell) systems

International Nuclear Information System (INIS)

Authayanun, Suthida; Saebea, Dang; Patcharavorachot, Yaneeporn; Arpornwichanop, Amornchai

2014-01-01

High-temperature proton exchange membrane fuel cells (HT-PEMFCs) have received substantial attention due to their high CO (carbon monoxide) tolerance and simplified water management. The hydrogen and CO fractions affect the HT-PEMFC performance and different fuel sources for hydrogen production result in different product gas compositions. Therefore, the aim of this study is to investigate the theoretical performance of HT-PEMFCs fueled by the reformate gas derived from various fuel options (i.e., methane, methanol, ethanol, and glycerol). Effects of fuel types and CO poisoning on the HT-PEMFC performance are analyzed. Furthermore, the necessity of a water-gas shift (WGS) reactor as a CO removal unit for pretreating the reformate gas is investigated for each fuel type. The methane steam reforming shows the highest possibility of CO formation, whereas the methanol steam reforming produces the lowest quantity of CO in the reformate gas. The methane fuel processing gives the maximum fraction of hydrogen (≈0.79) when the WGS reactor is included. The most suitable fuel is the one with the lowest CO poisoning effect and the maximum fuel cell performance. It is found that the HT-PEMFC system fueled by methanol without the WGS reactor and methane with WGS reactor shows the highest system efficiency (≈50%). - Highlights: • Performance of HT-PEMFC run on different fuel options is theoretically investigated. • Glycerol, methanol, ethanol and methane are hydrogen sources for the HT-PEMFC system. • Effect of CO poisoning on the HT-PEMFC performance is taken into account. • The suitable fuel for HT-PEMFC system is identified regarding the system efficiency

Evaluation of retention and disposal options for tritium in fuel reprocessing

International Nuclear Information System (INIS)

Grimes, W.R.; Hampson, D.C.; Larkin, D.J.; Skolrud, J.O.; Benjamin, R.W.

1982-08-01

Five options were evaluated as means of retaining tritium released from light-water reactor or fast breeder reactor fuel during the head-end steps of a typical Purex reprocessing scheme. Cost estimates for these options were compared with a base case in which no retention of tritium within the facility was obtained. Costs were also estimated for a variety of disposal methods of the retained tritium. The disposal costs were combined with the retention costs to yield total costs (capital plus operating) for retention and disposal of tritium under the conditions envisioned. The above costs were converted to an annual basis and to a dollars per curie retained basis. This then was used to estimate the cost in dollars per man-rem saved by retaining the tritium. Only the options that used the least expensive disposal costs could approach the $1000/man-rem cost used as a guide by the Nuclear Regulatory Commission

Benefit/cost analysis of plutonium recycle options in the United States of America

International Nuclear Information System (INIS)

Lowenberg, H.; Burnham, J.B.; Fisher, F.D.; Ray, W.H.

1977-01-01

Beginning in 1973, the USAEC started the analysis of the benefit/cost balance of Pu recycling in light-water reactors and the US Nuclear Regulatory Commission has continued this effort to the present time. A study of the United States nuclear industry from 1975 until 2000 was summarized in a final environmental statement called GESMO - Generic Environmental Statement on Mixed Oxide, NUREG-0002. Cumulative environmental and economic effects for several industry growth patterns were determined. Five alternatives were evaluated, covering the basic options of recycling uranium and plutonium; recycling uranium; and no recycling. The NRC findings, excluding consideration of proliferation and safeguards questions, are: the safety of reactors and fuel-cycle facilities are not significantly affected by recycle; excluding consideration of radiological effects, the environmental effects of recycle are slightly less than those from a non-recycle system; plutonium recycling extends uranium resources and reduces environmental impacts at the same time requiring reprocessing and Pu-handling facilities; despite uncertainties, recycling has probable economic advantages over other fuel concepts; differences in health effects attributable to recycling provide no basis for selecting a particular fuel-cycle option; no waste-management considerations appear that could be a basis for the selection of any particular option. The NRC studies on health, safety and environmental considerations of Pu recycling in the United States of America show that the differences in benefits/costs between the alternative fuel cycles are small and hence do not provide a clear basis for a decision on Pu recycle at this time. Safeguards and international proliferation implications appear to be the controlling factors in reaching a decision. President Carter's statement indefinitely deferring reprocessing and Pu recycle in the United States of America has resulted in a re-evaluation by NRC of its programme to

Reforming options for hydrogen production from fossil fuels for PEM fuel cells

Energy Technology Data Exchange (ETDEWEB)

Ersoz, Atilla; Olgun, Hayati [TUBITAK Marmara Research Center, Institute of Energy, Gebze, 41470 Kocaeli (Turkey); Ozdogan, Sibel [Marmara University Faculty of Engineering, Goztepe, 81040 Istanbul (Turkey)

2006-03-09

PEM fuel cell systems are considered as a sustainable option for the future transport sector in the future. There is great interest in converting current hydrocarbon based transportation fuels into hydrogen rich gases acceptable by PEM fuel cells on-board of vehicles. In this paper, we compare the results of our simulation studies for 100kW PEM fuel cell systems utilizing three different major reforming technologies, namely steam reforming (SREF), partial oxidation (POX) and autothermal reforming (ATR). Natural gas, gasoline and diesel are the selected hydrocarbon fuels. It is desired to investigate the effect of the selected fuel reforming options on the overall fuel cell system efficiency, which depends on the fuel processing, PEM fuel cell and auxiliary system efficiencies. The Aspen-HYSYS 3.1 code has been used for simulation purposes. Process parameters of fuel preparation steps have been determined considering the limitations set by the catalysts and hydrocarbons involved. Results indicate that fuel properties, fuel processing system and its operation parameters, and PEM fuel cell characteristics all affect the overall system efficiencies. Steam reforming appears as the most efficient fuel preparation option for all investigated fuels. Natural gas with steam reforming shows the highest fuel cell system efficiency. Good heat integration within the fuel cell system is absolutely necessary to achieve acceptable overall system efficiencies. (author)

Reforming options for hydrogen production from fossil fuels for PEM fuel cells

Science.gov (United States)

Ersoz, Atilla; Olgun, Hayati; Ozdogan, Sibel

PEM fuel cell systems are considered as a sustainable option for the future transport sector in the future. There is great interest in converting current hydrocarbon based transportation fuels into hydrogen rich gases acceptable by PEM fuel cells on-board of vehicles. In this paper, we compare the results of our simulation studies for 100 kW PEM fuel cell systems utilizing three different major reforming technologies, namely steam reforming (SREF), partial oxidation (POX) and autothermal reforming (ATR). Natural gas, gasoline and diesel are the selected hydrocarbon fuels. It is desired to investigate the effect of the selected fuel reforming options on the overall fuel cell system efficiency, which depends on the fuel processing, PEM fuel cell and auxiliary system efficiencies. The Aspen-HYSYS 3.1 code has been used for simulation purposes. Process parameters of fuel preparation steps have been determined considering the limitations set by the catalysts and hydrocarbons involved. Results indicate that fuel properties, fuel processing system and its operation parameters, and PEM fuel cell characteristics all affect the overall system efficiencies. Steam reforming appears as the most efficient fuel preparation option for all investigated fuels. Natural gas with steam reforming shows the highest fuel cell system efficiency. Good heat integration within the fuel cell system is absolutely necessary to achieve acceptable overall system efficiencies.

Spent LWR fuel storage costs: reracking, AR basins, and AFR basins

International Nuclear Information System (INIS)

1980-01-01

Whenever possible, fuel storage requirements will be met by reracking existing reactor basins and/or transfer of fuel to available space in other reactor basins. These alternatives represent not only the lowest cost storage options but also the most timely. They are recognized to face environmental and regulatory obstacles. However, such obstacles should be less severe than those that would be encountered with AR or AFR basin storage. When storage requirements cannot be met by the first two options, the least costly alternative for most utilities will be use of a Federal AFR. Storage costs of $100,000 to $150,000 MTU at a AFR are less costly than charges of up to $320,000/MTU that could be incurred by the use of AR basins. AFR storage costs do not include transportation from the reactor to the AFR. This cost would be paid by the utility separately. Only when a utility requires annual storage capacity for 100 MTU of spent fuel can self-storage begin to compete with AFR costs. The large reactor complexes discharging these fuel quantities are not currently those that require relief from fuel storage problems

Cost-effective policy instruments for greenhouse gas emission reduction and fossil fuel substitution through bioenergy production in Austria

International Nuclear Information System (INIS)

Schmidt, Johannes; Leduc, Sylvain; Dotzauer, Erik; Schmid, Erwin

2011-01-01

Climate change mitigation and security of energy supply are important targets of Austrian energy policy. Bioenergy production based on resources from agriculture and forestry is an important option for attaining these targets. To increase the share of bioenergy in the energy supply, supporting policy instruments are necessary. The cost-effectiveness of these instruments in attaining policy targets depends on the availability of bioenergy technologies. Advanced technologies such as second-generation biofuels, biomass gasification for power production, and bioenergy with carbon capture and storage (BECCS) will likely change the performance of policy instruments. This article assesses the cost-effectiveness of energy policy instruments, considering new bioenergy technologies for the year 2030, with respect to greenhouse gas emission (GHG) reduction and fossil fuel substitution. Instruments that directly subsidize bioenergy are compared with instruments that aim at reducing GHG emissions. A spatially explicit modeling approach is used to account for biomass supply and energy distribution costs in Austria. Results indicate that a carbon tax performs cost-effectively with respect to both policy targets if BECCS is not available. However, the availability of BECCS creates a trade-off between GHG emission reduction and fossil fuel substitution. Biofuel blending obligations are costly in terms of attaining the policy targets. - Highlights: → Costs of energy policies and effects on reduction of CO 2 emissions and fossil fuel consumption. → Particular focus on new bioenergy production technologies such as second generation biofuels. → Spatially explicit techno-economic optimization model. → CO 2 tax: high costs for reducing fossil fuel consumption if carbon capture and storage is available. → Biofuel policy: no significant reductions in CO 2 emissions or fossil fuel consumption.

ENVI Model Development for Korean Nuclear Spent Fuel Options Analysis

Energy Technology Data Exchange (ETDEWEB)

Chang, Sunyoung; Jeong, Yon Hong; Han, Jae-Jun; Lee, Aeri; Hwang, Yong-Soo [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2015-10-15

The disposal facility of the spent nuclear fuel will be operated from 2051. This paper presents the ENVI code developed by GoldSim Software to simulate options for managing spent nuclear fuel (SNF) in South Korea. The ENVI is a simulator to allow decision-makers to assist to evaluate the performance for spent nuclear fuel management. The multiple options for managing the spent nuclear fuel including the storage and transportation are investigated into interim storage, permanent disposal in geological repositories and overseas and domestic reprocessing. The ENVI code uses the GoldSim software to simulate the logistics of the associated activities. The result by the ENVI model not only produces the total cost to compare among the multiple options but also predict the sizes and timings of different facilities required. In order to decide the policy for spent nuclear management this purpose of this paper is to draw the optimum management plan to solve the nuclear spent fuel issue in the economical aspects. This paper is focused on the development of the ENVI's logic and calculations to simulate four options(No Reprocessing, Overseas Reprocessing, Domestic Reprocessing, and Overseas and Domestic Reprocessing) for managing the spent nuclear fuel in South Korea. The time history of the spent nuclear fuel produced from both the existing and future NPP's can be predicted, based on the Goldsim software made available very user friendly model. The simulation result will be used to suggest the strategic plans for the spent nuclear fuel management.

ENVI Model Development for Korean Nuclear Spent Fuel Options Analysis

International Nuclear Information System (INIS)

Chang, Sunyoung; Jeong, Yon Hong; Han, Jae-Jun; Lee, Aeri; Hwang, Yong-Soo

2015-01-01

The disposal facility of the spent nuclear fuel will be operated from 2051. This paper presents the ENVI code developed by GoldSim Software to simulate options for managing spent nuclear fuel (SNF) in South Korea. The ENVI is a simulator to allow decision-makers to assist to evaluate the performance for spent nuclear fuel management. The multiple options for managing the spent nuclear fuel including the storage and transportation are investigated into interim storage, permanent disposal in geological repositories and overseas and domestic reprocessing. The ENVI code uses the GoldSim software to simulate the logistics of the associated activities. The result by the ENVI model not only produces the total cost to compare among the multiple options but also predict the sizes and timings of different facilities required. In order to decide the policy for spent nuclear management this purpose of this paper is to draw the optimum management plan to solve the nuclear spent fuel issue in the economical aspects. This paper is focused on the development of the ENVI's logic and calculations to simulate four options(No Reprocessing, Overseas Reprocessing, Domestic Reprocessing, and Overseas and Domestic Reprocessing) for managing the spent nuclear fuel in South Korea. The time history of the spent nuclear fuel produced from both the existing and future NPP's can be predicted, based on the Goldsim software made available very user friendly model. The simulation result will be used to suggest the strategic plans for the spent nuclear fuel management

Evaluation of fuel cycle options for plutonium utilization: 1977 study. Final report

International Nuclear Information System (INIS)

Pardue, W.M.; Madia, W.J.; Pobereskin, M.; Tripplett, M.B.; Waddell, J.D.

1977-05-01

This is the third in a series of three reports on the analysis of plutonium recycle. Analyses are based upon an October, 1976, middle case ERDA forecast of nuclear growth which predicts 510 GWe of nuclear capacity in the year 2000. Four fuel cycle options were reviewed, ranging from no LWR recycle of uranium of plutonium to recycle options both with and without breeder reactors. A special effort was devoted to the review of various estimates of the costs of reprocessing nuclear fuels, with a resulting value of $190/kg of heavy metal (deflated 1975 dollars). The associated range is estimated to $125/kg to $250/kg. Sensitivity analysis of reprocessing costs, uranium consumption, average generation costs, and total discounted costs of electricity indicate that the long-term economic advantages of plutonium recycle are quite conclusive. Nuclear scenarios which project low growth rates and which delay the start of recycle and introduction of a breeder reactor postpone the apparent economic advantages

Life cycle assessment of mobility options using wood based fuels--comparison of selected environmental effects and costs.

Science.gov (United States)

Weinberg, Jana; Kaltschmitt, Martin

2013-12-01

An environmental assessment and a cost analysis were conducted for mobility options using electricity, hydrogen, ethanol, Fischer-Tropsch diesel and methane derived from wood. Therefore, the overall life cycle with regard to greenhouse gas emissions, acidifying emissions and fossil energy demand as well as costs is analysed. The investigation is carried out for mobility options in 2010 and gives an outlook to the year 2030. Results show that methane utilization in the car is beneficial with regard to environmental impacts (e.g. 58.5 g CO2-eq./km) and costs (23.1 €-ct./km) in 2010, especially in comparison to hydrogen usage (132.4 g CO2-eq./km and 63.9 €-ct./km). The electric vehicle construction has high environmental impacts and costs compared to conventional vehicles today, but with technical improvements and further market penetration, battery electric vehicles can reach the level of concepts with combustion engines in future applications (e.g. cost decrease from 38.7 to 23.4 €-ct./km). Copyright © 2013 Elsevier Ltd. All rights reserved.

Study Of The Fuel Cycle Effect To The Electricity Generating Cost

International Nuclear Information System (INIS)

Salimy, D. H.

1998-01-01

The nuclear fuel cycle cost contributes relatively small fraction to the total nuclear power generation cost, I.e. about 15 to 30%, compared to the fuel cost in the coal-generated electricity (40-60%). Or in the oil-generated electricity (70-80%). This situation will give effect that the future generation cost is much less sensitive to the changes in the fuel prince than in the case of fossil fuel power plants. The study has shown that by assuming a 100% increase in the natural uranium price, the total nuclear fuel cycle cost would increase only by about 27% and in turn it contributes about 29% increase to the total nuclear fuel cycle cost. As a result, it contributes only 4 to 8% increase in the nuclear energy generation cost. As a comparison, if the same situation should occur to fossil fuel plants, the assumed fuel price increase would have increased the electricity generating cost by about 40-65% for coal-fired plants, and about 70-85% for oil-fired plants. This study also has assesses the economic aspects of the electricity generating cots for nuclear power plant (NPP) and the coal power plant. For an NPP the most affecting factor is the investment cost, while for the coal power plant, the major factor influencing the total cost is the price/cost of the fuel

Uranium Resource Availability Analysis of Four Nuclear Fuel Cycle Options

International Nuclear Information System (INIS)

Youn, S. R.; Lee, S. H.; Jeong, M. S.; Kim, S. K.; Ko, W. I.

2013-01-01

Making the national policy regarding nuclear fuel cycle option, the policy should be established in ways that nuclear power generation can be maintained through the evaluation on the basis of the following aspects. To establish the national policy regarding nuclear fuel cycle option, that must begin with identification of a fuel cycle option that can be best suited for the country, and the evaluation work for that should be proceeded. Like all the policy decision, however, a certain nuclear fuel cycle option cannot be superior in all aspects of sustain ability, environment-friendliness, proliferation-resistance, economics, technologies, which make the comparison of the fuel cycle options very complicated. For such a purpose, this paper set up four different fuel cycle of nuclear power generation considering 2nd Comprehensive Nuclear Energy Promotion Plan(CNEPP), and analyzed material flow and features in steady state of all four of the fuel cycle options. As a result of an analysis on material flow of each nuclear fuel cycle, it was analyzed that Pyro-SFR recycling is most effective on U resource availability among four fuel cycle option. As shown in Figure 3, OT cycle required the most amount of U and Pyro-SFR recycle consumed the least amount of U. DUPIC recycling, PWR-MOX recycling, and Pyro-SFR recycling fuel cycle appeared to consumed 8.2%, 12.4%, 39.6% decreased amount of uranium respectively compared to OT cycle. Considering spent fuel can be recycled as potential energy resources, U and TRU taken up to be 96% is efficiently used. That is, application period of limited uranium natural resources can be extended, and it brings a great influence on stable use of nuclear energy

Assessment of Startup Fuel Options for a Test or Demonstration Fast Reactor

Energy Technology Data Exchange (ETDEWEB)

Carmack, Jon [Idaho National Lab. (INL), Idaho Falls, ID (United States); Hayes, Steven [Idaho National Lab. (INL), Idaho Falls, ID (United States); Walters, L. C. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-09-01

This document explores startup fuel options for a proposed test/demonstration fast reactor. The fuel options considered are the metallic fuels U-Zr and U-Pu-Zr and the ceramic fuels UO₂ and UO₂-PuO₂ (MOX). Attributes of the candidate fuel choices considered were feedstock availability, fabrication feasibility, rough order of magnitude cost and schedule, and the existing irradiation performance database. The reactor-grade plutonium bearing fuels (U-Pu-Zr and MOX) were eliminated from consideration as the initial startup fuels because the availability and isotopics of domestic plutonium feedstock is uncertain. There are international sources of reactor grade plutonium feedstock but isotopics and availability are also uncertain. Weapons grade plutonium is the only possible source of Pu feedstock in sufficient quantities needed to fuel a startup core. Currently, the available U.S. source of (excess) weapons-grade plutonium is designated for irradiation in commercial light water reactors (LWR) to a level that would preclude diversion. Weapons-grade plutonium also contains a significant concentration of gallium. Gallium presents a potential issue for both the fabrication of MOX fuel as well as possible performance issues for metallic fuel. Also, the construction of a fuel fabrication line for plutonium fuels, with or without a line to remove gallium, is expected to be considerably more expensive than for uranium fuels. In the case of U-Pu-Zr, a relatively small number of fuel pins have been irradiated to high burnup, and in no case has a full assembly been irradiated to high burnup without disassembly and re-constitution. For MOX fuel, the irradiation database from the Fast Flux Test Facility (FFTF) is extensive. If a significant source of either weapons-grade or reactor-grade Pu became available (i.e., from an international source), a startup core based on Pu could be reconsidered.

Comparative cost-effectiveness of Option B+ for prevention of mother-to-child transmission of HIV in Malawi.

Science.gov (United States)

Tweya, Hannock; Keiser, Olivia; Haas, Andreas D; Tenthani, Lyson; Phiri, Sam; Egger, Matthias; Estill, Janne

2016-03-27

To estimate the cost-effectiveness of prevention of mother-to-child transmission (MTCT) of HIV with lifelong antiretroviral therapy (ART) for pregnant and breastfeeding women ('Option B+') compared with ART during pregnancy or breastfeeding only unless clinically indicated ('Option B'). Mathematical modelling study of first and second pregnancy, informed by data from the Malawi Option B+ programme. Individual-based simulation model. We simulated cohorts of 10 000 women and their infants during two subsequent pregnancies, including the breastfeeding period, with either Option B+ or B. We parameterized the model with data from the literature and by analysing programmatic data. We compared total costs of antenatal and postnatal care, and lifetime costs and disability-adjusted life-years of the infected infants between Option B+ and Option B. During the first pregnancy, 15% of the infants born to HIV-infected mothers acquired the infection. With Option B+, 39% of the women were on ART at the beginning of the second pregnancy, compared with 18% with Option B. For second pregnancies, the rates MTCT were 11.3% with Option B+ and 12.3% with Option B. The incremental cost-effectiveness ratio comparing the two options ranged between about US$ 500 and US$ 1300 per DALY averted. Option B+ prevents more vertical transmissions of HIV than Option B, mainly because more women are already on ART at the beginning of the next pregnancy. Option B+ is a cost-effective strategy for PMTCT if the total future costs and lost lifetime of the infected infants are taken into account.

Cost-effectiveness analysis of Option B+ for HIV prevention and treatment of mothers and children in Malawi.

Science.gov (United States)

Fasawe, Olufunke; Avila, Carlos; Shaffer, Nathan; Schouten, Erik; Chimbwandira, Frank; Hoos, David; Nakakeeto, Olive; De Lay, Paul

2013-01-01

The Ministry of Health in Malawi is implementing a pragmatic and innovative approach for the management of all HIV-infected pregnant women, termed Option B+, which consists of providing life-long antiretroviral treatment, regardless of their CD4 count or clinical stage. Our objective was to determine if Option B+ represents a cost-effective option. A decision model simulates the disease progression of a cohort of HIV-infected pregnant women receiving prophylaxis and antiretroviral therapy, and estimates the number of paediatric infections averted and maternal life years gained over a ten-year time horizon. We assess the cost-effectiveness from the Ministry of Health perspective while taking into account the practical realities of implementing ART services in Malawi. If implemented as recommended by the World Health Organization, options A, B and B+ are equivalent in preventing new infant infections, yielding cost effectiveness ratios between US$ 37 and US$ 69 per disability adjusted life year averted in children. However, when the three options are compared to the current practice, the provision of antiretroviral therapy to all mothers (Option B+) not only prevents infant infections, but also improves the ten-year survival in mothers more than four-fold. This translates into saving more than 250,000 maternal life years, as compared to mothers receiving only Option A or B, with savings of 153,000 and 172,000 life years respectively. Option B+ also yields favourable incremental cost effectiveness ratios (ICER) of US$ 455 per life year gained over the current practice. In Malawi, Option B+ represents a favorable policy option from a cost-effectiveness perspective to prevent future infant infections, save mothers' lives and reduce orphanhood. Although Option B+ would require more financial resources initially, it would save societal resources in the long-term and represents a strategic option to simplify and integrate HIV services into maternal, newborn and child

North American natural gas outlook : does gas remain a fuel option for oil sands?

International Nuclear Information System (INIS)

George, R.R.

2003-01-01

This paper presents a North America natural gas outlook from Purvin and Gertz, an international energy consulting firm that has 30 years experience in providing strategic, commercial and technical advice to the petroleum industry. In particular, this presentation focuses on natural gas market fundamentals and how they may impact on oil sands development. It includes charts and graphs depicting NYMEX natural gas outlooks to July, 2009 and examines how supply will react to major changes in Canada's supply portfolio. It was noted that oil sands development is a driver for natural gas demand in Alberta. The existing regional gas pipeline infrastructure was presented and the market impact on upgrader options was discussed. The author suggests that if gas prices are too high, there are other fuel options for steam and power generation. These include bitumen, asphalt, coke, coal and nuclear. However, these options have additional costs, uncertainties and environmental issues. A key factor for success would be to have a clear understanding of the benefits and risks between these fuel options. 1 tab., 9 figs

Advanced Fuel Cycle Cost Basis – 2017 Edition

Energy Technology Data Exchange (ETDEWEB)

Dixon, B. W. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Ganda, F. [Argonne National Lab. (ANL), Argonne, IL (United States); Williams, K. A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Hoffman, E. [Argonne National Lab. (ANL), Argonne, IL (United States); Hanson, J. K. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2017-09-29

This report, commissioned by the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the DOE Nuclear Technology Research and Development (NTRD) Program (previously the Fuel Cycle Research and Development (FCRD) and the Advanced Fuel Cycle Initiative (AFCI)). The report describes the NTRD cost basis development process, reference information on NTRD cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for numerous fuel cycle cost modules (modules A-O) as well as cost modules for a number of reactor types (R modules). The fuel cycle cost modules were developed in the areas of natural uranium mining and milling, thorium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, managed decay storage, recycled product storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, transuranic, and high-level waste. Since its inception, this report has been periodically updated. The last such internal document was published in August 2015 while the last external edition was published in December of 2009 as INL/EXT-07-12107 and is available on the Web at URL: www.inl.gov/technicalpublications/Documents/4536700.pdf. This current report (Sept 2017) is planned to be reviewed for external release, at which time it will replace the 2009 report as an external publication. This information is used in the ongoing evaluation of nuclear fuel cycles by the NE NTRD program.

Burnable poison option for DUPIC fuel

International Nuclear Information System (INIS)

Choi, Hang Bok; Cupta, H. P.

1996-08-01

The mechanisms of positive coolant void reactivity of CANDU natural uranium and DUPIC fuel have been studied. The design study of DUPIC fuel was performed using the burnable poison material in the center pin to reduce the coolant void reactivity. The amount of burnable poison was determined such that the prompt inverse period of DUPIC fuel upon full coolant voiding is the same as that of natural uranium fuel at equilibrium burnup. A parametric study on various burnable poisons has shown that natural dysprosium has more merit over other materials because it uniformly controls the void reactivity throughout the burnup with reasonable amount of poison. Additional studies on the option of using scattering or absorber material in the center pin position and the option using variable fuel density were performed. In any case of option using variable fuel density were performed. In any case of options to reduce the void reactivity, it was found that either the discharge burnup and/or the relative linear pin power are sacrificed. A preliminary study was performed for the evaluation of reference DUPIC fuel performance especially represented by Stress Corrosion Cracking(SCC) parameters which is mainly influenced by the refueling operations. For the reference 2-bundle shift refueling scheme, the predicted ramped power and power increment of the reference DUPIC fuel are below the SCC thresholds of CANDU natural uranium fuel. For a 4-bundle shift refueling scheme, the envelopes of element ramped power and power increment upon refueling are 8% and 44% higher than those of a 2-bundle shift refueling scheme on the average, respectively, but still have margins to the failure thresholds of natural uranium fuel. 23 tabs., 25 figs., 20 refs. (Author)

Long-term issues associated with spent nuclear power fuel management options

International Nuclear Information System (INIS)

Jae-Sol, Lee; Kosaku, Fukuda; Burcl, R.; Bell, M.

2003-01-01

Spent fuel management is perceived as one of the crucial issues to be resolved for sustainable utilisation of nuclear power. In the last decades, spent fuel management policies have shown diverging tendencies among the nuclear power production countries - a group has adhered to reprocessing- recycle and another has turned to direct disposal, while the rest of the countries have not taken decision yet, often with ''wait and see'' position. Both the closed and open fuel cycle options for spent fuel management have been subject to a number of debates with pros and cons on various issues such as proliferation risk, environmental impact, etc. The anticipation for better technical solutions that would mitigate those issues has given rise to the renewal of interest in partitioning and transmutation of harmful nuclides to be disposed of, and in a broader context, the recent initiatives for development of innovative nuclear systems. The current trend toward globalization of market economy, which has already brought important impacts on nuclear industry, might have a stimulating effect on regional-international co-operations for cost-effective efforts to mitigate some of those long-term issues associated with spent fuel management. (author)

Fuel cycle cost uncertainty from nuclear fuel cycle comparison

International Nuclear Information System (INIS)

Li, J.; McNelis, D.; Yim, M.S.

2013-01-01

This paper examined the uncertainty in fuel cycle cost (FCC) calculation by considering both model and parameter uncertainty. Four different fuel cycle options were compared in the analysis including the once-through cycle (OT), the DUPIC cycle, the MOX cycle and a closed fuel cycle with fast reactors (FR). The model uncertainty was addressed by using three different FCC modeling approaches with and without the time value of money consideration. The relative ratios of FCC in comparison to OT did not change much by using different modeling approaches. This observation was consistent with the results of the sensitivity study for the discount rate. Two different sets of data with uncertainty range of unit costs were used to address the parameter uncertainty of the FCC calculation. The sensitivity study showed that the dominating contributor to the total variance of FCC is the uranium price. In general, the FCC of OT was found to be the lowest followed by FR, MOX, and DUPIC. But depending on the uranium price, the FR cycle was found to have lower FCC over OT. The reprocessing cost was also found to have a major impact on FCC

Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - IV: DUPIC Fuel Cycle Cost

International Nuclear Information System (INIS)

Ko, Won Il; Choi, Hangbok; Yang, Myung Seung

2001-01-01

This study examines the economics of the DUPIC fuel cycle using unit costs of fuel cycle components estimated based on conceptual designs. The fuel cycle cost (FCC) was calculated by a deterministic method in which reference values of fuel cycle components are used. The FCC was then analyzed by a Monte Carlo simulation to get the uncertainty of the FCC associated with the unit costs of the fuel cycle components. From the deterministic analysis on the equilibrium fuel cycle model, the DUPIC FCC was estimated to be 6.21 to 6.34 mills/kW.h for DUPIC fuel options, which is a little smaller than that of the once-through FCC by 0.07 to 0.27 mills/kW.h. Considering the uncertainty (0.40 to 0.44 mills/kW.h) of the FCC estimated by the Monte Carlo simulation method, the cost difference between the DUPIC and once-through fuel cycle is negligible. On the other hand, the material balance calculation has shown that the DUPIC fuel cycle can save natural uranium resources by ∼20% and reduce the spent fuel arising by ∼65% compared with the once-through fuel cycle. In conclusion, the DUPIC fuel cycle is comparable with the once-through fuel cycle from the viewpoint of FCC. In the future, it should be important to consider factors such as the environmental benefit owing to natural uranium savings, the capability of reusing spent pressurized water reactor fuel, and the safeguardability of the fuel cycle when deciding on an advanced nuclear fuel cycle option

An Adjusted Discount Rate Model for Fuel Cycle Cost Estimation

Energy Technology Data Exchange (ETDEWEB)

Kim, S. K.; Kang, G. B.; Ko, W. I. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2013-10-15

Owing to the diverse nuclear fuel cycle options available, including direct disposal, it is necessary to select the optimum nuclear fuel cycles in consideration of the political and social environments as well as the technical stability and economic efficiency of each country. Economic efficiency is therefore one of the significant evaluation standards. In particular, because nuclear fuel cycle cost may vary in each country, and the estimated cost usually prevails over the real cost, when evaluating the economic efficiency, any existing uncertainty needs to be removed when possible to produce reliable cost information. Many countries still do not have reprocessing facilities, and no globally commercialized HLW (High-level waste) repository is available. A nuclear fuel cycle cost estimation model is therefore inevitably subject to uncertainty. This paper analyzes the uncertainty arising out of a nuclear fuel cycle cost evaluation from the viewpoint of a cost estimation model. Compared to the same discount rate model, the nuclear fuel cycle cost of a different discount rate model is reduced because the generation quantity as denominator in Equation has been discounted. Namely, if the discount rate reduces in the back-end process of the nuclear fuel cycle, the nuclear fuel cycle cost is also reduced. Further, it was found that the cost of the same discount rate model is overestimated compared with the different discount rate model as a whole.

An Adjusted Discount Rate Model for Fuel Cycle Cost Estimation

International Nuclear Information System (INIS)

Kim, S. K.; Kang, G. B.; Ko, W. I.

2013-01-01

Owing to the diverse nuclear fuel cycle options available, including direct disposal, it is necessary to select the optimum nuclear fuel cycles in consideration of the political and social environments as well as the technical stability and economic efficiency of each country. Economic efficiency is therefore one of the significant evaluation standards. In particular, because nuclear fuel cycle cost may vary in each country, and the estimated cost usually prevails over the real cost, when evaluating the economic efficiency, any existing uncertainty needs to be removed when possible to produce reliable cost information. Many countries still do not have reprocessing facilities, and no globally commercialized HLW (High-level waste) repository is available. A nuclear fuel cycle cost estimation model is therefore inevitably subject to uncertainty. This paper analyzes the uncertainty arising out of a nuclear fuel cycle cost evaluation from the viewpoint of a cost estimation model. Compared to the same discount rate model, the nuclear fuel cycle cost of a different discount rate model is reduced because the generation quantity as denominator in Equation has been discounted. Namely, if the discount rate reduces in the back-end process of the nuclear fuel cycle, the nuclear fuel cycle cost is also reduced. Further, it was found that the cost of the same discount rate model is overestimated compared with the different discount rate model as a whole

Closing the fuel cycle: A superior option for India

International Nuclear Information System (INIS)

Balu, K.; Purushotham, D.S.C.; Kakodkar, A.

1999-01-01

The closed fuel cycle option with reprocessing and recycle of uranium and plutonium (U and Pu) for power generation allows better utilization of the uranium resources. On its part, plutonium is a unique energy source. During the initial years of nuclear fuel cycle activities, reprocessing and recycle of uranium and plutonium for power generation was perceived by many countries to be among the best of long term strategies for the management of spent fuel. But, over the years, some of the countries have taken a position that once-through fuel cycle is both economical and proliferation-resistant. However, such perceptions do vary as a function of economic growth and energy security of a given country. This paper deals with techno-economic perspectives of reprocessing and recycling in the Indian nuclear power programme. Experience of developing Mixed Oxide UO 2 -PuO 2 (MOX) fuel and its actual use in a power reactor (BWR) is presented. The paper further deals with the use of MOX in PHWRs in the future and current thinking, in the Indian context, in respect of advanced fuel cycles for the future. From environmental safety considerations, the separation of long-lived isotopes and minor actinides from high level waste (HLW) would enhance the acceptability of reprocessing and recycle option. The separated actinides are suitable for recycling with MOX fuel. However, the advanced fuel cycles with such recycling of Uranium and transuranium elements call for additional sophisticated fuel cycle activities which are yet to be mastered. India is interested in both uranium and thorium fuel cycles. This paper describes the current status of the Indian nuclear power scenario with reference to the program on reactors, reprocessing and radioactive waste management, plutonium recycle options, thorium-U233 fuel cycle studies and investigations on partitioning of actinides from Purex HLW as relevant to PHWR spent fuels. (author)

Tradeoffs in fuel cycle performance for most promising options - 15346

International Nuclear Information System (INIS)

Taiwo, T.; Kim, T.K.; Feng, B.; Stauff, N.; Hoffman, E.; Ganda, F.; Todosow, M.; Brown, N.; Raitses, G.; Gehin, J.; Powers, J.; Youinou, G.; Hiruta, H.; Wigeland, R.

2015-01-01

A recent Evaluation and Screening (E/S) study of nuclear fuel cycle options was conducted by grouping all potential options into 40 Evaluation Groups (EGs) based on similarities in fundamental physics characteristics and fuel cycle performance. Through a rigorous evaluation process considering benefit and challenge metrics, 4 of these EGs were identified by the E/S study as 'most promising'. All 4 involve continuous recycle of U/Pu or U/TRU with natural uranium feed in fast critical reactors. However, these most promising EGs also include fuel cycle groups with variations on feed materials, neutron spectra, and reactor criticality. Therefore, the impacts of the addition of natural thorium fuel feed to a system that originally only used natural uranium fuel feed, using an intermediate spectrum instead of a fast spectrum, and using externally-driven systems versus critical reactors were evaluated. It was found that adding thorium to the natural uranium feed mixture leads to lower burnup, higher mass flows, and degrades fuel cycle benefit metrics (waste management, resource utilization, etc.) for fuel cycles that continuously recycle U/Pu or U/TRU. Adding thorium results in fissions of 233 U instead of just 239 Pu and in turn results in a lower average number of neutrons produced per absorption (η) for the fast reactor system. For continuous recycling systems, the lower η results in lower excess reactivity and subsequently lower achievable fuel burnup. This in turn leads to higher mass flows (fabrication, reprocessing, disposal, etc.) to produce a given amount of energy and subsequent lower metrics performance. The investigated fuel cycle options with intermediate spectrum reactors also exhibited degraded performance in the benefit metrics compared to fast spectrum reactors. Similarly, this is due to lower η values as the spectrum softens. The best externally-driven systems exhibited similar performance as fast critical reactors in terms of mass flows

77 FR 19278 - Informational Meeting on Nuclear Fuel Cycle Options

Science.gov (United States)

2012-03-30

... DEPARTMENT OF ENERGY Informational Meeting on Nuclear Fuel Cycle Options AGENCY: Office of Fuel... activities leading to a comprehensive evaluation and screening of nuclear fuel cycle options in 2013. At this... fuel cycle options developed for the evaluation and screening provides a comprehensive representation...

Spent-fuel storage: a private sector option

International Nuclear Information System (INIS)

Thomas, J.A.; Ross, S.R.

1983-01-01

The investigation was performed to delineate the legal and financial considerations for establishing private sector support for the planning and development of an independent spent-fuel storage facility (ISFSF). The preferred institutional structure was found to be one in which a not-for-profit corporation contracts with a limited partnership to handle the spent fuel. The limited partnership acquires the necessary land and constructs the ISFSF facility and then leases the facility to the not-for-profit corporation, which acquires spent-fuel rods from the utilities. The DOE must agree to purchase the spent-fuel rods at the expiration of term and warrant continued operation of the facility if policy changes at the federal level force the removal of the rods prior to completion of the contracted storage cycle. The DOE planning base estimate of spent-fuel storage requirements indicates a market potential adequate to support 10,000 MTU or more of spent-fuel storage prior to the time a government repository is available to accept spent fuel around the turn of the century. The estimated construction cost of a 5000-MTU water basin facility is $552 million. The total capital requirements to finance such a facility are estimated to be $695 million, based on an assumed capital structure of 70 percent debt and 30 percent equity. The estimated total levelized cost of storage, including operating costs, for the assumed 17-year life of the facility is $223 per kilogram of uranium. This is equivalent to a slightly less than one mill per kilowatt-hour increase in nuclear fuel costs at the nuclear power station that was the source of the spent fuel. In conclusion, within the context of the new Nuclear Waste Policy Act of 1982, the study points to both the need for and the advantages of private sector support for one or more ISFSFs and establishes a workable mechanism for the recovery of the costs of owning and operating such facilities. 3 figures, 4 tables

Considerations Regarding ROK Spent Nuclear Fuel Management Options

International Nuclear Information System (INIS)

Braun, Chaim; Forrest, Robert

2013-01-01

In this paper we discuss spent fuel management options in the Republic of Korea (ROK) from two interrelated perspectives: Centralized dry cask storage and spent fuel pyroprocessing and burning in sodium fast reactors (SFRs). We argue that the ROK will run out of space for at-reactors spent fuel storage by about the year 2030 and will thus need to transition centralized dry cask storage. Pyroprocessing plant capacity, even if approved and successfully licensed and constructed by that time, will not suffice to handle all the spent fuel discharged annually. Hence centralized dry cask storage will be required even if the pyroprocessing option is successfully developed by 2030. Pyroprocessing is but an enabling technology on the path leading to fissile material recycling and burning in future SFRs. In this regard we discuss two SFR options under development in the U. S.: the Super Prism and the Travelling Wave Reactor (TWR). We note that the U. S. is further along in reactor development than the ROK. The ROK though has acquired more experience, recently in investigating fuel recycling options for SFRs. We thus call for two complementary joint R and D project to be conducted by U. S. and ROK scientists. One leading to the development of a demonstration centralized away-from-reactors spent fuel storage facility. The other involve further R and D on a combined SFR-fuel cycle complex based on the reactor and fuel cycle options discussed in the paper

A qualitative assessment of climate adaptation options and some estimates of adaptation costs

International Nuclear Information System (INIS)

Van Ierland, E.C.; De Bruin, K.; Dellink, R.B.; Ruijs, A.

2007-02-01

The Routeplanner project aims to provide a 'systematic assessment' of potential adaptation options to respond to climate change in the Netherlands in connection to spatial planning. The study is the result of a policy oriented project that took place between May and September 2006. The aim of the current study is to provide a 'qualitative assessment' of the direct and indirect effects of adaptation options and to provide an assessment of some of the costs and benefits of adaptation options. The present report presents and summarizes the results of all phases of the study: an inventory of adaptation options, a qualitative assessment of the effects of the adaptation options for the Netherlands in the long run, a database which allows to rank the various options according to a set of criteria and a relative ranking on the basis of these criteria. Finally, the report also contains the best available information on costs and benefits of various adaptation options. However, while conducting the study the project team observed that reliable information in this respect is in many cases still lacking and an urgent need exists for more detailed studies on costs and benefits of adaptation options and the design of the best options to cope with climate change

Obesity-related health impacts of fuel excise taxation- an evidence review and cost-effectiveness study.

Science.gov (United States)

Brown, V; Moodie, M; Cobiac, L; Mantilla Herrera, A M; Carter, R

2017-05-04

Reducing automobile dependence and improving rates of active transport may reduce the impact of obesogenic environments, thereby decreasing population prevalence of obesity and other diseases where physical inactivity is a risk factor. Increasing the relative cost of driving by an increase in fuel taxation may therefore be a promising public health intervention for obesity prevention. A scoping review of the evidence for obesity or physical activity effect of changes in fuel price or taxation was undertaken. Potential health benefits of an increase in fuel excise taxation in Australia were quantified using Markov modelling to simulate obesity, injury and physical activity related health impacts of a fuel excise taxation intervention for the 2010 Australian population. Health adjusted life years (HALYs) gained and healthcare cost savings from diseases averted were estimated. Incremental cost-effectiveness ratios (ICERs) were reported and results were tested through sensitivity analysis. Limited evidence on the effect of policies such as fuel taxation on health-related behaviours currently exists. Only three studies were identified reporting associations between fuel price or taxation and obesity, whilst nine studies reported associations specifically with physical activity, walking or cycling. Estimates of the cross price elasticity of demand for public transport with respect to fuel price vary, with limited consensus within the literature on a probable range for the Australian context. Cost-effectiveness modelling of a AUD0.10 per litre increase in fuel excise taxation using a conservative estimate of cross price elasticity for public transport suggests that the intervention would be cost-effective from a limited societal perspective (237 HALYs gained, AUD2.6 M in healthcare cost savings), measured against a comparator of no additional increase in fuel excise. Under "best case" assumptions, the intervention would be more cost-effective (3181 HALYs gained, AUD34.2�

Radiological impacts of spent nuclear fuel management options

International Nuclear Information System (INIS)

Riotte, H.; Lazo, T.; Mundigl, S.

2000-01-01

An important technical study on radiological impacts of spent nuclear fuel management options, recently completed by the NEA, is intended to facilitate informed international discussions on the nuclear fuel cycle. The study compares the radiological impacts on the public and on nuclear workers resulting from two approaches to handling spent fuel from nuclear power plants: - the reprocessing option, that includes the recycling of spent uranium fuel, the reuse of the separated plutonium in MOX fuel, and the direct disposal of spent MOX fuel; and the once-through option, with no reprocessing of spent fuel, and its direct disposal. Based on the detailed research of a group of 18 internationally recognised experts, under NEA sponsorship, the report concludes that: The radiological impacts of both the reprocessing and the non-reprocessing fuel cycles studied are small, well below any regulatory dose limits for the public and for workers, and insignificantly low as compared with exposures caused by natural radiation. The difference in the radiological impacts of the two fuel cycles studied does not provide a compelling argument in favour of one option or the other. The study also points out that other factors, such as resource utilisation efficiency, energy security, and social and economic considerations would tend to carry more weight than radiological impacts in decision-making processes. (authors)

Economic Analysis of Several Nuclear Fuel Cycles

International Nuclear Information System (INIS)

Ko, Won Il; Gao, Fanxing; Kim, Sung Ki

2012-01-01

appropriate for an estimate on the costs of energy given the various technologies. Levelized fuel cycle cost (LFCC) and levelized generation cost (LGC) have offered effective indicators for economic comparison among nuclear fuel cycles and were adopted to compare the fuel cycle options considered in this study. The unpredictable change of the unit costs of several key components due to the uncertainties can lead to considerable differences in levelized costs among the fuel cycle alternatives. To take these unavoidable uncertainties into account, a wide scale was applied to each unit cost and a distribution of levelized cost was also obtained

Cost-effectiveness of available treatment options for patients suffering from severe COPD in the UK: a fully incremental analysis

Directory of Open Access Journals (Sweden)

Hertel N

2012-03-01

Full Text Available Nadine Hertel1, Robert W Kotchie1, Yevgeniy Samyshkin1, Matthew Radford1, Samantha Humphreys2, Kevin Jameson21IMS Consulting Group, London, UK; 2MSD Ltd, Hoddesdon, UKPurpose: Frequent exacerbations which are both costly and potentially life-threatening are a major concern to patients with chronic obstructive pulmonary disease (COPD, despite the availability of several treatment options. This study aimed to assess the lifetime costs and outcomes associated with alternative treatment regimens for patients with severe COPD in the UK setting.Patients and methods: A Markov cohort model was developed to predict lifetime costs, outcomes, and cost-effectiveness of various combinations of a long-acting muscarinic antagonist (LAMA, a long-acting beta agonist (LABA, an inhaled corticosteroid (ICS, and roflumilast in a fully incremental analysis. Patients willing and able to take ICS, and those refusing or intolerant to ICS were analyzed separately. Efficacy was expressed as relative rate ratios of COPD exacerbation associated with alternative treatment regimens, taken from a mixed treatment comparison. The analysis was conducted from the UK National Health Service (NHS perspective. Parameter uncertainty was explored using one-way and probabilistic sensitivity analysis.Results: Based on the results of the fully incremental analysis a cost-effectiveness frontier was determined, indicating those treatment regimens which represent the most cost-effective use of NHS resources. For ICS-tolerant patients the cost-effectiveness frontier suggested LAMA as initial treatment. Where patients continue to exacerbate and additional therapy is required, LAMA + LABA/ICS can be a cost-effective option, followed by LAMA + LABA/ICS + roflumilast (incremental cost-effectiveness ratio [ICER] versus LAMA + LABA/ICS: £16,566 per quality-adjusted life-year [QALY] gained. The ICER in ICS-intolerant patients, comparing LAMA + LABA + roflumilast versus LAMA + LABA, was £13

A qualitative assessment of climate adaptation options and some estimates of adaptation costs

International Nuclear Information System (INIS)

Van Ierland, E.C.; De Bruin, K.; Dellink, R.B.; Ruijs, A.

2006-12-01

The Routeplanner project aims to provide a 'systematic assessment' of potential adaptation options to respond to climate change in the Netherlands in connection to spatial planning. The study is the result of a policy oriented project that took place between May and September 2006. The aim of the current study is to provide a 'qualitative assessment' of the direct and indirect effects of adaptation options and to provide an assessment of some of the costs and benefits of adaptation options. The present report presents and summarizes the results of all phases of the study: an inventory of adaptation options, a qualitative assessment of the effects of the adaptation options for the Netherlands in the long run, a database which allows to rank the various options according to a set of criteria and a relative ranking on the basis of these criteria. Finally, the report also contains the best available information on costs and benefits of various adaptation options.

Does a renewable fuel standard for biofuels reduce climate costs?

Energy Technology Data Exchange (ETDEWEB)

Greaker, Mads; Hoel, Michael; Rosendahl, Knut Einar

2012-07-01

Recent contributions have questioned whether biofuels policies actually lead to emissions reductions, and thus lower climate costs. In this paper we make two contributions to the literature. First, we study the market effects of a renewable fuel standard. Opposed to most previous studies we model the supply of fossil fuels taking into account that fossil fuels is a non-renewable resource. Second, we model emissions from land use change explicitly when we evaluate the climate effects of the renewable fuel standard. We find that extraction of fossil fuels most likely will decline initially as a consequence of the standard. Thus, if emissions from biofuels are sufficiently low, the standard will have beneficial climate effects. Furthermore, we find that the standard tends to reduce total fuel (i.e., oil plus biofuels) consumption initially. Hence, even if emissions from biofuels are substantial, climate costs may be reduced. Finally, if only a subset of countries introduce a renewable fuel standard, there will be carbon leakage to the rest of the world. However, climate costs may decline as global extraction of fossil fuels is postponed.(Author)

Obesity-related health impacts of fuel excise taxation- an evidence review and cost-effectiveness study

Directory of Open Access Journals (Sweden)

V. Brown

2017-05-01

Full Text Available Abstract Background Reducing automobile dependence and improving rates of active transport may reduce the impact of obesogenic environments, thereby decreasing population prevalence of obesity and other diseases where physical inactivity is a risk factor. Increasing the relative cost of driving by an increase in fuel taxation may therefore be a promising public health intervention for obesity prevention. Methods A scoping review of the evidence for obesity or physical activity effect of changes in fuel price or taxation was undertaken. Potential health benefits of an increase in fuel excise taxation in Australia were quantified using Markov modelling to simulate obesity, injury and physical activity related health impacts of a fuel excise taxation intervention for the 2010 Australian population. Health adjusted life years (HALYs gained and healthcare cost savings from diseases averted were estimated. Incremental cost-effectiveness ratios (ICERs were reported and results were tested through sensitivity analysis. Results Limited evidence on the effect of policies such as fuel taxation on health-related behaviours currently exists. Only three studies were identified reporting associations between fuel price or taxation and obesity, whilst nine studies reported associations specifically with physical activity, walking or cycling. Estimates of the cross price elasticity of demand for public transport with respect to fuel price vary, with limited consensus within the literature on a probable range for the Australian context. Cost-effectiveness modelling of a AUD0.10 per litre increase in fuel excise taxation using a conservative estimate of cross price elasticity for public transport suggests that the intervention would be cost-effective from a limited societal perspective (237 HALYs gained, AUD2.6 M in healthcare cost savings, measured against a comparator of no additional increase in fuel excise. Under “best case” assumptions, the intervention

Radiological aspects of postfission waste management for light-water reactor fuel cycle options

Energy Technology Data Exchange (ETDEWEB)

Shipler, D B; Nelson, I C [Battelle Pacific Northwest Laboratories, Richland, WA (United States)

1978-12-01

A generic environmental impact statement on the management of radioactive postfission wastes from various light-water reactor fuel cycles in the United States has been prepared. The environmental analysis for post-fission waste management includes an examination of radiological impacts related to different waste treatment, storage, transportation, and disposal options at the process level. Effects addressed include effluents from plants, and radiological impacts from facility operation (routine and accidents), and decommissioning. Environmental effects are combined for fuel reprocessing plants, mixed-oxide fuel fabrication plants, and waste repositories. Radiological effects are also aggregated for several fuel cycle options over the period 1980 and 2050. Fuel cycles analyzed are (1) once-through cycle in which spent reactor fuel is cooled in water basins for at least 6-1/2 years and then disposed of in deep geologic repositories; (2) spent fuel reprocessing in which uranium only and uranium and plutonium is recycled and solidified high level waste, fuel residues, and non-high-level transuranic wastes are disposed of in deep geologic repositories; and (3) deferred cycle that calls for storage of spent fuel at Federal spent fuel storage facilities until the year 2000 at which time a decision is made whether to dispose of spent fuel as a waste or to reprocess the fuel to recover uranium and plutonium. Key environmental issues for decision-making related to waste management alternatives and fuel cycle options are highlighted. (author)

Life cycle assessment of automobile/fuel options.

Science.gov (United States)

MacLean, Heather L; Lave, Lester B

2003-12-01

We examine the possibilities for a "greener" car that would use less material and fuel, be less polluting, and would have a well-managed end-of-life. Light-duty vehicles are fundamental to our economy and will continue to be for the indefinite future. Any redesign to make these vehicles greener requires consumer acceptance. Consumer desires for large, powerful vehicles have been the major stumbling block in achieving a "green car". The other major barrier is inherent contradictions among social goals such as fuel economy, safety, low emissions of pollutants, and low emissions of greenhouse gases, which has led to conflicting regulations such as emissions regulations blocking sales of direct injection diesels in California, which would save fuel. In evaluating fuel/vehicle options with the potential to improve the greenness of cars [diesel (direct injection) and ethanol in internal combustion engines, battery-powered, gasoline hybrid electric, and hydrogen fuel cells], we find no option dominates the others on all dimensions. The principles of green design developed by Anastas and Zimmerman (Environ. Sci. Technol. 2003, 37, 94A-101A) and the use of a life cycle approach provide insights on the key sustainability issues associated with the various options.

Comparative cost-effectiveness of Option B+ for prevention of mother to child transmission of HIV in Malawi: Mathematical modelling study

Science.gov (United States)

Tweya, Hannock; Keiser, Olivia; Haas, Andreas D.; Tenthani, Lyson; Phiri, Sam; Egger, Matthias; Estill, Janne

2016-01-01

Objective To estimate the cost-effectiveness of prevention of mother to child transmission (MTCT) of HIV with lifelong antiretroviral therapy (ART) for pregnant and breastfeeding women (‘Option B+’) compared to ART during pregnancy or breastfeeding only unless clinically indicated (‘Option B’). Design Mathematical modelling study of first and second pregnancy, informed by data from the Malawi Option B+ programme. Methods Individual-based simulation model. We simulated cohorts of 10,000 women and their infants during two subsequent pregnancies, including the breastfeeding period, with either Option B+ or B. We parameterised the model with data from the literature and by analysing programmatic data. We compared total costs of ante-natal and post-natal care, and lifetime costs and disability-adjusted life-years (DALYs) of the infected infants between Option B+ and Option B. Results During the first pregnancy, 15% of the infants born to HIV-infected mothers acquired the infection. With Option B+, 39% of the women were on ART at the beginning of the second pregnancy, compared to 18% with Option B. For second pregnancies, the rates MTCT were 11.3% with Option B+ and 12.3% with Option B. The incremental cost-effectiveness ratio comparing the two options ranged between about US$ 500 and US$ 1300 per DALY averted. Conclusion Option B+ prevents more vertical transmissions of HIV than Option B, mainly because more women are already on ART at the beginning of the next pregnancy. Option B+ is a cost-effective strategy for PMTCT if the total future costs and lost lifetime of the infected infants are taken into account. PMID:26691682

A fuel cycle cost study with HEU and LEU fuels

International Nuclear Information System (INIS)

Matos, J.E.; Freese, K.E.

1985-01-01

Fuel cycle costs are compared for a range of 235 U loadings with HEU and LEU fuels using the IAEA generic 10 MW reactor as an example. If LEU silicide fuels are successfully demonstrated and licensed, the results indicate that total fuel cycle costs can be about the same or lower than those with the HEU fuels that are currently used in most research reactors. (author)

A fuel cycle cost study with HEU and LEU fuels

Energy Technology Data Exchange (ETDEWEB)

Matos, J E; Freese, K E [Argonne National Laboratory, Argonne, IL (United States)

1985-07-01

Fuel cycle costs are compared for a range of {sup 235}U loadings with HEU and LEU fuels using the IAEA generic 10 MW reactor as an example. If LEU silicide fuels are successfully demonstrated and licensed, the results indicate that total fuel cycle costs can be about the same or lower than those with the HEU fuels that are currently used in most research reactors. (author)

A cost analysis of Colorado's 1991-92 oxygenated fuels program

International Nuclear Information System (INIS)

Manderino, L.A.; Bowles, S.L.

1993-01-01

This paper discusses the methodology used to conduct a cost analysis of Colorado's 1991-92 Oxygenated Fuels Program. This program requires the use of oxygenated fuels during the winter season in Denver and surrounding areas. The cost analysis was conducted as part of an overall cost-effectiveness study of the 1991-92 program conducted by PRC Environmental Management, Inc. (PRC). The paper, however, focuses on cost analysis and does not consider potential benefits of the program. The study analyzed costs incurred by different segments of society, including government, industry, and consumers. Because the analysis focused on a specific program year, neither past nor future costs were studied. The discussion of government costs includes the agencies interviewed and the types of costs associated with government administration and enforcement of the program. The methodology used to calculate costs to private industry is also present. The study examined the costs to fuel refineries, pipelines, and blenders, as well as fuel retailers and automobile fleet operators. Finally, the paper discusses the potential costs incurred by the consumer purchasing oxygenated fuels. Costs associated with issues such as vehicle driveability, automobile parts durability and performance, and fuel economy are also examined. A summary of all costs by category is presented along with an analysis of the major cost components. These include costs which are sensitive to specific circumstances and which may vary among programs

Nuclear Fuel Cycle Options Catalog: FY16 Improvements and Additions

Energy Technology Data Exchange (ETDEWEB)

Price, Laura L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Barela, Amanda Crystal [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Schetnan, Richard Reed [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Walkow, Walter M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-08-31

The United States Department of Energy, Office of Nuclear Energy, Fuel Cycle Technology Program sponsors nuclear fuel cycle research and development. As part of its Fuel Cycle Options campaign, the DOE has established the Nuclear Fuel Cycle Options Catalog. The catalog is intended for use by the Fuel Cycle Technologies Program in planning its research and development activities and disseminating information regarding nuclear energy to interested parties. The purpose of this report is to document the improvements and additions that have been made to the Nuclear Fuel Cycle Options Catalog in the 2016 fiscal year.

Nuclear Fuel Cycle Options Catalog FY15 Improvements and Additions.

Energy Technology Data Exchange (ETDEWEB)

Price, Laura L. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Barela, Amanda Crystal [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Schetnan, Richard Reed [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Walkow, Walter M. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

2015-11-01

The United States Department of Energy, Office of Nuclear Energy, Fuel Cycle Technology Program sponsors nuclear fuel cycle research and development. As part of its Fuel Cycle Options campaign, the DOE has established the Nuclear Fuel Cycle Options Catalog. The catalog is intended for use by the Fuel Cycle Technologies Program in planning its research and development activities and disseminating information regarding nuclear energy to interested parties. The purpose of this report is to document the improvements and additions that have been made to the Nuclear Fuel Cycle Options Catalog in the 2015 fiscal year.

U.S. weapons-usable plutonium disposition policy: Implementation of the MOX fuel option

Energy Technology Data Exchange (ETDEWEB)

Woods, A.L. [ed.] [Amarillo National Resource Center for Plutonium, TX (United States); Gonzalez, V.L. [Texas A and M Univ., College Station, TX (United States). Dept. of Political Science

1998-10-01

A comprehensive case study was conducted on the policy problem of disposing of US weapons-grade plutonium, which has been declared surplus to strategic defense needs. Specifically, implementation of the mixed-oxide fuel disposition option was examined in the context of national and international nonproliferation policy, and in contrast to US plutonium policy. The study reveals numerous difficulties in achieving effective implementation of the mixed-oxide fuel option including unresolved licensing and regulatory issues, technological uncertainties, public opposition, potentially conflicting federal policies, and the need for international assurances of reciprocal plutonium disposition activities. It is believed that these difficulties can be resolved in time so that the implementation of the mixed-oxide fuel option can eventually be effective in accomplishing its policy objective.

U.S. weapons-useable plutonium disposition policy: Implementation of the MOX fuel option

International Nuclear Information System (INIS)

Woods, A.L.; Gonzalez, V.L.

1998-10-01

A comprehensive case study was conducted on the policy problem of disposing of US weapons-grade plutonium, which has been declared surplus to strategic defense needs. Specifically, implementation of the mixed-oxide fuel disposition option was examined in the context of national and international nonproliferation policy, and in contrast to US plutonium policy. The study reveals numerous difficulties in achieving effective implementation of the mixed-oxide fuel option including unresolved licensing and regulatory issues, technological uncertainties, public opposition, potentially conflicting federal policies, and the need for international assurances of reciprocal plutonium disposition activities. It is believed that these difficulties can be resolved in time so that the implementation of the mixed-oxide fuel option can eventually be effective in accomplishing its policy objective

Global warming and urban smog: The cost effectiveness of CAFE standards and alternative fuels

International Nuclear Information System (INIS)

Krupnick, A.J.; Walls, M.A.; Collins, C.T.

1992-01-01

This paper evaluates alternative transportation policies for reducing greenhouse gas emissions and ozone precursors. The net cost-effectiveness -- i.e., the cost per ton of greenhouse gas reduced, adjusted for ozone reduction benefits -- of substituting methanol, compressed natural gas (CNG), and reformulated gasoline for conventional gasoline is assessed and compared with the cost-effectiveness of raising the corporate average fuel economy (CAFE) standard to 38 miles per gallon. Computing this open-quotes netclose quotes cost-effectiveness is one way of measuring the joint environmental benefits that these alternatives provide. Greenhouse gas emissions are assessed over the entire fuel cycle and include not only carbon dioxide emissions, but also methane, carbon monoxide, and nitrous oxide emissions. In computing cost-effectiveness, we account for the so-called open-quotes rebound effectclose quotes -- the impact on vehicle-miles traveled of higher or lower fuel costs. CNG is found to be the most cost-effective of these alternatives, followed by increasing the CAFE standard, substituting methanol for gasoline, and substituting reformulated for conventional gasoline. Including the ozone reduction benefits does not change the rankings of the alternatives, but does make the alternative fuels look better relative to increasing the CAFE standard. Incorporating the rebound effect greatly changes the magnitude of the estimates but does not change the rankings of the alternatives. None of the alternatives look cost-effective should a carbon tax of $35 per ton be passes (the proposal in the Stark bill, H.R. 1086), and only CNG under optimistic assumptions looks cost-effective if a tax of $100 per ton of carbon is passed

Economic evaluation of multilateral nuclear fuel cycle approach

International Nuclear Information System (INIS)

Takashima, Ryuta; Kuno, Yusuke; Omoto, Akira; Tanaka, Satoru

2011-01-01

Recently previous works have shown that multilateral nuclear fuel cycle approach has benefits not only of non-proliferation but also of cost effectiveness. This is because for most facilities in nuclear fuel cycle, there exist economies of scale, which has a significant impact on the costs of nuclear fuel cycle. Therefore, the evaluation of economic rationality is required as one of the evaluation factors for the multilateral nuclear fuel cycle approach. In this study, we consider some options with respect to multilateral approaches to nuclear fuel cycle in Asian-Pacific region countries that are proposed by the University of Tokyo. In particular, the following factors are embedded into each type: A) no involvement of assurance of services, B) provision of assurance of services including construction of new facility, without transfer of ownership, and C) provision of assurance of service including construction of new joint facilities with ownership transfer of facilities to multilateral nuclear fuel cycle approach. We show the overnight costs taking into account install and operation of nuclear fuel cycle facilities for each option. The economic parameter values such as uranium price, scale factor, and market output expansion influences the total cost for each option. Thus, we show how these parameter values and economic risks affect the total overnight costs for each option. Additionally, the international facilities could increase the risk of transportation for nuclear material compared to national facilities. We discuss the potential effects of this transportation risk on the costs for each option. (author)

Design Evolution Study - Aging Options

International Nuclear Information System (INIS)

McDaniel, P.

2002-01-01

The purpose of this study is to identify options and issues for aging commercial spent nuclear fuel received for disposal at the Yucca Mountain Mined Geologic Repository. Some early shipments of commercial spent nuclear fuel to the repository may be received with high-heat-output (younger) fuel assemblies that will need to be managed to meet thermal goals for emplacement. The capability to age as much as 40,000 metric tons of heavy metal of commercial spent nuclear he1 would provide more flexibility in the design to manage this younger fuel and to decouple waste receipt and waste emplacement. The following potential aging location options are evaluated: (1) Surface aging at four locations near the North Portal; (2) Subsurface aging in the permanent emplacement drifts; and (3) Subsurface aging in a new subsurface area. The following aging container options are evaluated: (1) Complete Waste Package; (2) Stainless Steel inner liner of the waste package; (3) Dual Purpose Canisters; (4) Multi-Purpose Canisters; and (5) New disposable canister for uncanistered commercial spent nuclear fuel. Each option is compared to a ''Base Case,'' which is the expected normal waste packaging process without aging. A Value Engineering approach is used to score each option against nine technical criteria and rank the options. Open issues with each of the options and suggested future actions are also presented. Costs for aging containers and aging locations are evaluated separately. Capital costs are developed for direct costs and distributable field costs. To the extent practical, unit costs are presented. Indirect costs, operating costs, and total system life cycle costs will be evaluated outside of this study. Three recommendations for aging commercial spent nuclear fuel--subsurface, surface, and combined surface and subsurface are presented for further review in the overall design re-evaluation effort. Options that were evaluated but not recommended are: subsurface aging in a new

Options contracts in the nuclear fuel industry

International Nuclear Information System (INIS)

Fuller, D.M.

1995-01-01

This article discusses options trading in the nuclear fuels industry. Although there now exists no formal options market in the nuclear industry, flexibilities, or embedded options, are actually quite common in the long-term supply contracts. The value of these flexibilities can be estimated by applying the methods used to evaluate options. The method used is the Black-Scholes Model, and it is applied to a number of examples

Cost Probability Analysis of China's Nuclear Fuel Cycle Transition

International Nuclear Information System (INIS)

Gao, R. X.; Ko, W. I.; Lee, S. H.

2015-01-01

The Chinese government has already determined to develop the closed nuclear fuel cycle, its long-term roadmap of spent fuel management has not been decided yet. Currently, it seems that China's booming economy gives abundant financial assurance to develop nuclear programs in full play according to its near-term national plans. However, the viability and sustainability of nuclear power always depends critically on its economics. Therefore, it is necessary to conduct a well focused cost-benefit and objective analysis of China's ongoing nuclear power programs with the future prospects. In this study, we conduct a comparative analysis of electricity generation cost in four reference nuclear fuel cycle transition scenarios by 2050. Direct disposal is assumed to produce the cheapest LCT as low as 62.688 mills/kWh compared to the other options. However, after performing a relative uncertainty study, the results show that the capital cost of reactor is the key cost component which leads to the cost gap

Cost Probability Analysis of China's Nuclear Fuel Cycle Transition

Energy Technology Data Exchange (ETDEWEB)

Gao, R. X. [Univ. of Science and Technology, Daejeon (Korea, Republic of); Ko, W. I.; Lee, S. H. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-05-15

The Chinese government has already determined to develop the closed nuclear fuel cycle, its long-term roadmap of spent fuel management has not been decided yet. Currently, it seems that China's booming economy gives abundant financial assurance to develop nuclear programs in full play according to its near-term national plans. However, the viability and sustainability of nuclear power always depends critically on its economics. Therefore, it is necessary to conduct a well focused cost-benefit and objective analysis of China's ongoing nuclear power programs with the future prospects. In this study, we conduct a comparative analysis of electricity generation cost in four reference nuclear fuel cycle transition scenarios by 2050. Direct disposal is assumed to produce the cheapest LCT as low as 62.688 mills/kWh compared to the other options. However, after performing a relative uncertainty study, the results show that the capital cost of reactor is the key cost component which leads to the cost gap.

Options for converting excess plutonium to feed for the MOX fuel fabrication facility

Energy Technology Data Exchange (ETDEWEB)

Watts, Joe A [Los Alamos National Laboratory; Smith, Paul H [Los Alamos National Laboratory; Psaras, John D [Los Alamos National Laboratory; Jarvinen, Gordon D [Los Alamos National Laboratory; Costa, David A [Los Alamos National Laboratory; Joyce, Jr., Edward L [Los Alamos National Laboratory

2009-01-01

The storage and safekeeping of excess plutonium in the United States represents a multibillion-dollar lifecycle cost to the taxpayers and poses challenges to National Security and Nuclear Non-Proliferation. Los Alamos National Laboratory is considering options for converting some portion of the 13 metric tons of excess plutonium that was previously destined for long-term waste disposition into feed for the MOX Fuel Fabrication Facility (MFFF). This approach could reduce storage costs and security ri sks, and produce fuel for nuclear energy at the same time. Over the course of 30 years of weapons related plutonium production, Los Alamos has developed a number of flow sheets aimed at separation and purification of plutonium. Flow sheets for converting metal to oxide and for removing chloride and fluoride from plutonium residues have been developed and withstood the test oftime. This presentation will address some potential options for utilizing processes and infrastructure developed by Defense Programs to transform a large variety of highly impure plutonium into feedstock for the MFFF.

A review on future trends of LWR fuel cycle costs

International Nuclear Information System (INIS)

Tamiya, S.; Otomo, T.; Meguro, T.

1977-01-01

In the cost estimations in the past, the main components of fuel cycle were mining and milling, uranium enrichment and fuel fabrication, and reprocessing charge deemed to be recovered by plutonium credit. Since the oil crisis, every component of fuel cycle cost has gone up in recent years as well as the construction cost of a power station. Recent analysis shows that the costs in the back end of fuel cycle are much higher than those anticipated several years ago, although their contribution to the electricity generating cost by nuclear would be small. The situation of the back end of the fuel cycle has been quite changed in recent years, and there are still many uncertainties in this field, that is, regulatory requirements for reprocessing plant such as safety, safeguards, environmental protection and high level waste management. So, it makes it more difficult to estimate the investment in this sector of fuel cycle, therefore, to estimate the cost of this sector. The institutional problems must be cleared in relation to the ultimate disposal of high level waste, too. Co-location of some parts of fuel cycle facilities may also affect on the fuel cycle costs. In this paper a review is made of the future trend of nuclear fuel cycle cost of LWR based on the recent analysis. Those factors which affect the fuel cycle costs are also discussed. In order to reduce the uncertainties of the cost estimations as soon as possible, the necessity is emphasized to discuss internationally such items as the treatment and disposal of high level radioactive wastes, siting issues of a reprocessing plant, physical protection of plutonium and the effects of plutonium on the environment

Global warming and urban smog: Cost-effectiveness of CAFE standards and alternative fuels

International Nuclear Information System (INIS)

Krupnick, A.J.; Walls, M.A.; Collins, C.T.

1993-01-01

In this paper we estimate the cost-effectiveness, in terms of reducing greenhouse gas emissions, of increasing the corporate average fuel economy (CAFE) standard to 38 miles per gallon and substituting methanol, compressed natural gas (CNG), and reformulated gasoline for conventional gasoline. Greenhouse gas emissions are assessed over the entire fuel cycle and include carbon dioxide, methane, carbon monoxide, and nitrous oxide emissions. To account for joint environmental benefits, the cost per ton of greenhouse gas reduced is adjusted for reductions in volatile organic compound (VOC) emissions, an ozone precursor. CNG is found to be the most cost-effective of these alternatives, followed by increasing the CAFE standard, substituting methanol for gasoline, and substituting reformulated for conventional gasoline. Including the VOC benefits does not change the ranking of the alternatives, but does make the alternative fuels look better relative to increasing the CAFE standard. None of the alternatives look cost-effective should a carbon tax of $35 per ton be passed, and only CNG under optimistic assumptions looks cost-effective with a tax of $100 per ton of carbon. 35 refs., 4 figs., 6 tabs

POEM is a cost-effective procedure: cost-utility analysis of endoscopic and surgical treatment options in the management of achalasia.

Science.gov (United States)

Miller, Heidi J; Neupane, Ruel; Fayezizadeh, Mojtaba; Majumder, Arnab; Marks, Jeffrey M

2017-04-01

Achalasia is a rare motility disorder of the esophagus. Treatment is palliative with the goal of symptom remission and slowing the progression of the disease. Treatment options include per oral endoscopic myotomy (POEM), laparoscopic Heller myotomy (LM) and endoscopic treatments such as pneumatic dilation (PD) and botulinum toxin type A injections (BI). We evaluate the economics and cost-effectiveness of treating achalasia. We performed cost analysis for POEM, LM, PD and BI at our institution from 2011 to 2015. Cost of LM was set to 1, and other procedures are presented as percentage change. Cost-effectiveness was calculated based on cost, number of interventions required for optimal results for dilations and injections and efficacy reported in the current literature. Incremental cost-effectiveness ratio was calculated by a cost-utility analysis using quality-adjusted life year gained, defined as a symptom-free year in a patient with achalasia. Average number of interventions required was 2.3 dilations or two injections for efficacies of 80 and 61 %, respectively. POEM cost 1.058 times the cost of LM, and PD and BI cost 0.559 and 0.448 times the cost of LM. Annual cost per cure over a period of 4 years for POEM, and LM were consistently equivalent, trending the same as PD although this has a lower initial cost. The cost per cure of BI remains stable over 3 years and then doubles. The cost-effectiveness of POEM and LM is equivalent. Myotomy, either surgical or endoscopic, is more cost-effective than BI due to high failure rates of the economical intervention. When treatment is being considered BI should be utilized in patients with less than 2-year life expectancy. Pneumatic dilations are cost-effective and are an acceptable approach to treatment of achalasia, although myotomy has a lower relapse rate and is cost-effective compared to PD after 2 years.

Least cost options for life extension

Energy Technology Data Exchange (ETDEWEB)

Davis, F.; Bradaric, M. [Bechtel Corp., San Francisco, CA (United States)

1995-12-01

Rehabilitation of existing electric generating capacity offers one of the most cost-effective ways of meeting near-term power needs in many Eastern and Central European countries. In particular, the uncertainty associated with other supply sources and severe capital constraints tends to favor investments which maximize the utilization of existing fossil-fired equipment. However, it is critical that least-cost planning principles, including the consideration of environmental impacts, be applied to the economic analysis of rehabilitation options. This paper draws on Bechtel`s experience in applying least-cost planning to plant rehabilitation studies in Bulgaria, Romania and Slovakia. The examples provided illustrate the importance of least-cost planning and the effect of the value placed on environmental emissions.

Fuel economy and life-cycle cost analysis of a fuel cell hybrid vehicle

Science.gov (United States)

Jeong, Kwi Seong; Oh, Byeong Soo

The most promising vehicle engine that can overcome the problem of present internal combustion is the hydrogen fuel cell. Fuel cells are devices that change chemical energy directly into electrical energy without combustion. Pure fuel cell vehicles and fuel cell hybrid vehicles (i.e. a combination of fuel cell and battery) as energy sources are studied. Considerations of efficiency, fuel economy, and the characteristics of power output in hybridization of fuel cell vehicle are necessary. In the case of Federal Urban Driving Schedule (FUDS) cycle simulation, hybridization is more efficient than a pure fuel cell vehicle. The reason is that it is possible to capture regenerative braking energy and to operate the fuel cell system within a more efficient range by using battery. Life-cycle cost is largely affected by the fuel cell size, fuel cell cost, and hydrogen cost. When the cost of fuel cell is high, hybridization is profitable, but when the cost of fuel cell is less than 400 US$/kW, a pure fuel cell vehicle is more profitable.

The effects of rising energy costs and transportation mode mix on forest fuel procurement costs

International Nuclear Information System (INIS)

Rauch, Peter; Gronalt, Manfred

2011-01-01

Since fossil fuels have been broadly recognized as a non-renewable energy source that threatens the climate, sustainable and CO 2 neutral energy sources - such as forest fuels - are being promoted in Europe, instead. With the expeditiously growing forest fuel demand, the strategic problem of how to design a cost-efficient distribution network has evolved. This paper presents an MILP model, comprising decisions on modes of transportation and spatial arrangement of terminals, in order to design a forest fuel supply network for Austria. The MILP model is used to evaluate the impacts of rising energy costs on procurement sources, transport mix and procurement costs on a national scale, based on the example of Austria. A 20% increase of energy costs results in a procurement cost increase of 7%, and another 20% increase of energy costs would have similar results. While domestic waterways become more important as a result of the first energy cost increase, rail only does so after the second. One way to decrease procurement costs would be to reduce the share of empty trips with truck and trailer. Reducing this share by 10% decreases the average procurement costs by up to 20%. Routing influences the modal split considerably, and the truck transport share increases from 86% to 97%, accordingly. Increasing forest fuel imports by large CHPs lowers domestic competition and also enables smaller plants to cut their procurement costs. Rising forest fuel imports via ship will not significantly decrease domestic market shares, but they will reduce procurement costs considerably. (author)

Cost effectiveness of option B plus for prevention of mother-to-child transmission of HIV in resource-limited countries: evidence from Kumasi, Ghana.

Science.gov (United States)

VanDeusen, Adam; Paintsil, Elijah; Agyarko-Poku, Thomas; Long, Elisa F

2015-03-18

Achieving the goal of eliminating mother-to-child HIV transmission (MTCT) necessitates increased access to antiretroviral therapy (ART) for HIV-infected pregnant women. Option B provides ART through pregnancy and breastfeeding, whereas Option B+ recommends continuous ART regardless of CD4 count, thus potentially reducing MTCT during future pregnancies. Our objective was to compare maternal and pediatric health outcomes and cost-effectiveness of Option B+ versus Option B in Ghana. A decision-analytic model was developed to simulate HIV progression in mothers and transmission (in utero, during birth, or through breastfeeding) to current and all future children. Clinical parameters, including antenatal care access and fertility rates, were estimated from a retrospective review of 817 medical records at two hospitals in Ghana. Additional parameters were obtained from published literature. Modeled outcomes include HIV infections averted among newborn children, quality-adjusted life-years (QALYs), and cost-effectiveness ratios. HIV-infected women in Ghana have a lifetime average of 2.3 children (SD 1.3). Projected maternal life expectancy under Option B+ is 16.1 years, versus 16.0 years with Option B, yielding a gain of 0.1 maternal QALYs and 3.2 additional QALYs per child. Despite higher initial ART costs, Option B+ costs $785/QALY gained, a value considered very cost-effective by World Health Organization benchmarks. Widespread implementation of Option B+ in Ghana could theoretically prevent up to 668 HIV infections among children annually. Cost-effectiveness estimates remained favorable over robust sensitivity analyses. Although more expensive than Option B, Option B+ substantially reduces MTCT in future pregnancies, increases both maternal and pediatric QALYs, and is a cost-effective use of limited resources in Ghana.

Radiological impacts of spent nuclear fuel management options. A comparative study

International Nuclear Information System (INIS)

2000-01-01

Given its potential significance for public health and the environment, the impact of radioactive releases during important steps of nuclear energy production must be considered when selecting among different fuel cycles. With this in mind, the OECD Nuclear Energy Agency (NEA) has undertaken a comparative study to the radiological impacts of two main fuel cycle options : one with and one without reprocessing of spent nuclear fuel. The study compares the respective impacts of the two options based on generic models and assumptions as well as actual data. It concludes that the difference between them is not significant. A wealth of recent data assembled and evaluated by an international expert team is provided in annex. (authors)

The next generation of urban MACCs. Reassessing the cost-effectiveness of urban mitigation options by integrating a systemic approach and social costs

International Nuclear Information System (INIS)

Saujot, Mathieu; Lefèvre, Benoit

2016-01-01

Many cities are implementing policies and climate action plans. Yet local climate policies suffer from a lack of scientific understanding and evaluation methods able to support the definition of efficient mitigation strategies. The purpose of this paper is to build on classical approaches in the energy policy field that exist at the national and international level to propose an urban MACCs methodology able to fulfill this lack and inform local debates. The methodology is an extension of static “expert-based” MACCs; it combines a land use transport integrated model and an abatement cost methodology that integrates co-benefits, and takes into account the spatial and systemic dimensions of cities. The methodology is implemented for the transportation sector of a mid-sized European city (Grenoble, France). Our results present the cost-effectiveness and political feasibility of several proposed measures. We find that the inclusion of co-benefits can profoundly change the cost-benefit assessment of transport mitigation options. Moreover we underline the key parameters determining the cost-effectiveness ranking of mitigation options. These urban MACCs aim to serve as a bridge between urban planning and mitigation policies and can thus contribute to strengthen and align sustainable and climate change agendas at the local level. - Highlights: •Local climate policies lack scientific understanding for prioritizing mitigation actions. •We develop a method to evaluate cost-effectiveness of urban transportation actions. •This method combines urban modeling and MACCs to inform urban planning. •Abatement costs from its application to a mid-sized city are presented. •The impact of the inclusion of co-benefits is analyzed.

Comparison of options for distributed generation in India

International Nuclear Information System (INIS)

Banerjee, Rangan

2006-01-01

There is renewed interest in distributed generation (DG). This paper reviews the different technological options available for DG, their current status and evaluates them based on the cost of generation and future potential in India. The non-renewable options considered are internal combustion engines fuelled by diesel, natural gas and microturbines and fuel cells fired by natural gas. The renewable technologies considered are wind, solar photovoltaic, biomass gasification and bagasse cogeneration. The cost of generation is dependent on the load factor and the discount rate. Gas engines and Bagasse based cogeneration are found to be the most cost effective DG options while wind and biomass gasifier fired engines are viable under certain conditions. PEM Fuel cells and micro turbines based on natural gas need a few demonstrations projects and cost reductions before becoming viable. A strategy involving pilot projects, tracking of costs and dissemination of information is likely to result in DG meeting 10% of India's power needs by 2012

Nuclear-fuel-cycle costs. Consolidated Fuel-Reprocessing Program

International Nuclear Information System (INIS)

Burch, W.D.; Haire, M.J.; Rainey, R.H.

1981-01-01

The costs for the back-end of the nuclear fuel cycle, which were developed as part of the Nonproliferation Alternative Systems Assessment Program (NASAP), are presented. Total fuel-cycle costs are given for the pressurized-water reactor once-through and fuel-recycle systems, and for the liquid-metal fast-breeder-reactor system. These calculations show that fuel-cycle costs are a small part of the total power costs. For breeder reactors, fuel-cycle costs are about half that of the present once-through system. The total power cost of the breeder-reactor system is greater than that of light-water reactor at today's prices for uranium and enrichment

Benefit/cost analysis of plutonium recycle options in the United States

International Nuclear Information System (INIS)

Lowenberg, H.; Burnham, J.B.; Fisher, F.; Ray, W.H.

1977-01-01

Predictable effects of the recycle of plutonium and uranium recovered from spent LWR fuels were assessed in a final environmental statement (GESMO). Five alternative dispositions of LWR-produced plutonium ranging from prompt recycle of recovered plutonium and uranium to no recovery and no recycle are compared. The assessments consider cumulative effects for the period 1975 through 2000, and are centered on a conservative low growth rate resulting in about 500 LWR's in the U.S. in 2000. A more optimistic growth projection resulting in about 800 LWR's in 2000 is also analyzed in order to assess the effects of industry size upon the impacts. Demands for fuel cycle services were calculated with an ERDA program, NUFUEL, which was modified to include penalties for 236 U and 242 Pu. Unit cost data, including a simulation of market place reaction to supply-demand functions for uranium costs, were combined with the NUFUEL demand data in an economics code, NUCOST. Environmental impacts were also based upon NUFUEL demand data and were developed using a model plant industry concept. Using the most likely unit costs with a 10% discount rate, present worth incentives for prompt recycle over no recycle of $3.2 billion for the lower growth and about $6 billion for the higher growth were indicated. Present worth costs of delays in recycle of up to 5 years were less than $1 billion. Sensitivity of the economic assessments to unit cost variations and discount rates were also evaluated. Environmental impacts other than radiological were lowest for prompt Pu recycle and highest for no recycle. Radiological impacts for the total world wide total body exposure from U.S. industry for the 26 year period were estimated to be: - No recycle-8.2 million person-rem; U only recycle-9.5 million person-rem; Pu and U recycle-8.8 million person-rem. Comparison of the decreased radiological impact of the no recycle option with its increased costs relative to prompt plutonium recycle resulted in a

Greenhouse gas abatement in Senegal. A case study of least-cost options

International Nuclear Information System (INIS)

Amous, S.; Revet, D.; Sokona, Y.

1994-01-01

The first stage of the study was to make a preliminary inventory of greenhouse gas (GHG) emissions for the base year 1988. Following this seven no regret technical options for emission reduction were investigated and the costs calculated, allowing the identification of three least-cost options. The three least-cost options must be implemented first because of their negative costs. The economic benefits of both abatement scenarios are characterized by a negative global cost whatever the discount rate is. (author)

Final Report on Two-Stage Fast Spectrum Fuel Cycle Options

International Nuclear Information System (INIS)

Yang, Won Sik; Lin, C. S.; Hader, J. S.; Park, T. K.; Deng, P.; Yang, G.; Jung, Y. S.; Kim, T. K.; Stauff, N. E.

2016-01-01

This report presents the performance characteristics of two ''two-stage'' fast spectrum fuel cycle options proposed to enhance uranium resource utilization and to reduce nuclear waste generation. One is a two-stage fast spectrum fuel cycle option of continuous recycle of plutonium (Pu) in a fast reactor (FR) and subsequent burning of minor actinides (MAs) in an accelerator-driven system (ADS). The first stage is a sodium-cooled FR fuel cycle starting with low-enriched uranium (LEU) fuel; at the equilibrium cycle, the FR is operated using the recovered Pu and natural uranium without supporting LEU. Pu and uranium (U) are co-extracted from the discharged fuel and recycled in the first stage, and the recovered MAs are sent to the second stage. The second stage is a sodium-cooled ADS in which MAs are burned in an inert matrix fuel form. The discharged fuel of ADS is reprocessed, and all the recovered heavy metals (HMs) are recycled into the ADS. The other is a two-stage FR/ADS fuel cycle option with MA targets loaded in the FR. The recovered MAs are not directly sent to ADS, but partially incinerated in the FR in order to reduce the amount of MAs to be sent to the ADS. This is a heterogeneous recycling option of transuranic (TRU) elements

Final Report on Two-Stage Fast Spectrum Fuel Cycle Options

Energy Technology Data Exchange (ETDEWEB)

Yang, Won Sik [Purdue Univ., West Lafayette, IN (United States); Lin, C. S. [Purdue Univ., West Lafayette, IN (United States); Hader, J. S. [Purdue Univ., West Lafayette, IN (United States); Park, T. K. [Purdue Univ., West Lafayette, IN (United States); Deng, P. [Purdue Univ., West Lafayette, IN (United States); Yang, G. [Purdue Univ., West Lafayette, IN (United States); Jung, Y. S. [Purdue Univ., West Lafayette, IN (United States); Kim, T. K. [Argonne National Lab. (ANL), Argonne, IL (United States); Stauff, N. E. [Argonne National Lab. (ANL), Argonne, IL (United States)

2016-01-30

This report presents the performance characteristics of two “two-stage” fast spectrum fuel cycle options proposed to enhance uranium resource utilization and to reduce nuclear waste generation. One is a two-stage fast spectrum fuel cycle option of continuous recycle of plutonium (Pu) in a fast reactor (FR) and subsequent burning of minor actinides (MAs) in an accelerator-driven system (ADS). The first stage is a sodium-cooled FR fuel cycle starting with low-enriched uranium (LEU) fuel; at the equilibrium cycle, the FR is operated using the recovered Pu and natural uranium without supporting LEU. Pu and uranium (U) are co-extracted from the discharged fuel and recycled in the first stage, and the recovered MAs are sent to the second stage. The second stage is a sodium-cooled ADS in which MAs are burned in an inert matrix fuel form. The discharged fuel of ADS is reprocessed, and all the recovered heavy metals (HMs) are recycled into the ADS. The other is a two-stage FR/ADS fuel cycle option with MA targets loaded in the FR. The recovered MAs are not directly sent to ADS, but partially incinerated in the FR in order to reduce the amount of MAs to be sent to the ADS. This is a heterogeneous recycling option of transuranic (TRU) elements

Use of spikants in HTGR fuel and their effect on costs

International Nuclear Information System (INIS)

Brooks, L.H.

1979-05-01

The costs of fresh fuel fabrication have been estimated for flowsheets that have spikant added (Co-60) at various points. The costs are compared with refabricated and fresh fuel fabrication costs. It is shown that the costs increase as the spikant is added nearer to the plant feed point. The least cost is achieved by adding a detachable spikant to the finished fuel element. The highest cost is incurred when the spikant is fed in with the plant feed. This cost is greater than that for refabricated fuel because extra process cells are necessary to prepare the spikant and, in addition, the gamma flux from the Co-60 is much greater than from U-232 and greater precautions have to be taken

Fuel alternatives for oil sands development - the nuclear option

Energy Technology Data Exchange (ETDEWEB)

Bock, D [Atomic Energy of Canada Ltd., Mississauga, ON (Canada); Donnelly, J K

1996-12-31

Currently natural gas is the fuel of choice in all oil sand developments. Alberta sources of hydrocarbon based fuels are large but limited. Canadian nuclear technology was studied as a possible alternative for providing steam for the deep commercial in situ oil sand projects which were initiated over ten years ago. Because the in situ technology of that time required steam at pressures in excess of 10 MPa, the nuclear option required the development of new reactor technology, or the use of steam compressors, which was not economical. The current SAGD (steam assisted gravity drainage) technology requires steam at pressures of less than 5 MPa, which is in the reach of existing Canadian nuclear technology. The cost of supplying steam for a SAGD in situ project using a CANDU 3 nuclear reactor was developed. The study indicates that for gas prices in excess of $2.50 per gigajoule, replacing natural gas fuel with a nuclear reactor is economically feasible for in situ projects in excess of 123 thousand barrels per day. (author). 9 refs., 3 tabs., 12 figs.

Fuel alternatives for oil sands development - the nuclear option

International Nuclear Information System (INIS)

Bock, D.; Donnelly, J.K.

1995-01-01

Currently natural gas is the fuel of choice in all oil sand developments. Alberta sources of hydrocarbon based fuels are large but limited. Canadian nuclear technology was studied as a possible alternative for providing steam for the deep commercial in situ oil sand projects which were initiated over ten years ago. Because the in situ technology of that time required steam at pressures in excess of 10 MPa, the nuclear option required the development of new reactor technology, or the use of steam compressors, which was not economical. The current SAGD (steam assisted gravity drainage) technology requires steam at pressures of less than 5 MPa, which is in the reach of existing Canadian nuclear technology. The cost of supplying steam for a SAGD in situ project using a CANDU 3 nuclear reactor was developed. The study indicates that for gas prices in excess of $2.50 per gigajoule, replacing natural gas fuel with a nuclear reactor is economically feasible for in situ projects in excess of 123 thousand barrels per day. (author). 9 refs., 3 tabs., 12 figs

K Basin spent fuel sludge treatment alternatives study. Volume 2, Technical options

International Nuclear Information System (INIS)

Beary, M.M.; Honekemp, J.R.; Winters, N.

1995-01-01

Approximately 2100 metric tons of irradiated N Reactor fuel are stored in the KE and KW Basins at the Hanford Site, Richland, Washington. Corrosion of the fuel has led to the formation of sludges, both within the storage canisters and on the basin floors. Concern about the degraded condition of the fuel and the potential for leakage from the basins in proximity to the Columbia River has resulted in DOE's commitment in the Tri-Party Agreement (TPA) to Milestone M-34-00-T08 to remove the fuel and sludges by a December 2002 target date. To support the planning for this expedited removal action, the implications of sludge management under various scenarios are examined. This report, Volume 2 of two volumes, describes the technical options for managing the sludges, including schedule and cost impacts, and assesses strategies for establishing a preferred path

K Basin spent fuel sludge treatment alternatives study. Volume 1, Regulatory options

International Nuclear Information System (INIS)

Beary, M.M.; Honekemp, J.R.; Winters, N.

1995-01-01

Approximately 2100 metric tons of irradiated N Reactor fuel are stored in the KE and KW Basins at the Hanford Site, Richland, Washington. Corrosion of the fuel has led to the formation of sludges, both within the storage canisters and on the basin floors. Concern about the degraded condition of the fuel and the potential for leakage from the basins in proximity to the Columbia River has resulted in DOE's commitment in the Tri-Party Agreement (TPA) to Milestone M-34-00-T08 to remove the fuel and sludges by a December 2002 target date. To support the planning for this expedited removal action, the implications of sludge management under various scenarios are examined. Volume 1 of this two-volume report describes the regulatory options for managing the sludges, including schedule and cost impacts, and assesses strategies for establishing a preferred path

Costing the EPR Project Using the Real Options Method

International Nuclear Information System (INIS)

Epaulard, Anne; Gallon, Stephane

2001-01-01

Real options theory makes it possible to cost investments which offer flexibility but whose returns are uncertain, such as the construction in 2000 of an EPR prototype; this prototype will enable the European pressurised-water reactor (EPR) to be used to renew EDF's nuclear power stations in 2020 (flexibility) but its economic worth will then depend on the cost of the competing gas-fired power plants (uncertain return). Options theory shows that investing in EPR technology in 2000 provides sufficient flexibility in 2020 to be considered cost-effective, even though use of EPRs is unlikely by that date. The investment made in 2000 to develop EPR technology therefore actually plays the part of an option or, in other words, insurance (against the risk of high gas prices)

Controlling fuel costs: Procurement strategies and regulatory standards

International Nuclear Information System (INIS)

Einhorn, H.A.; Levi, B.I.

1992-01-01

Since the oil price shocks and inflation of the 1970s, regulatory authorities and utilities have devoted considerable attention to controlling energy costs while maintaining reliable service. Although much of this concern has been directed towards capital cost containment, increasing scrutiny has been applied to a broad range of variable costs, especially to fuel procurement expenditures. With some 40% to 65% of the electric utility industry's annual operation and maintenance expenses paid to secure fuel supplies, even a small difference in fuel costs could have a substantial impact on costs to ratepayers. This increased attention to fuel cost containment can be expected to intensify as implementation of the 1990 amendments to the Clean Air Act affects fuel purchase decisions. To assure that fuel is purchased in a responsible and cost-effective manner, some state jurisdictions have initiated periodic reviews (audits) of the procurement practices that electric utilities follow when purchasing fuel. While a utility must demonstrate how it purchases fuel, there is wide variation in interest and scope of audits among jurisdictions. In this paper, the authors review: (1) the regulatory environment within which fuel procurement and audits occur, and (2) some particularly controversial issues that will receive increasing attention as the practice of conducting fuel procurement audits spreads

Sensitivity analysis and probabilistic assessment of seawater desalination costs fueled by nuclear and fossil fuel

International Nuclear Information System (INIS)

Kavvadias, K.C.; Khamis, I.

2014-01-01

The reliable supply of water and energy is an important prerequisite for sustainable development. Desalination is a feasible option that can solve the problem of water scarcity in some areas, but it is a very energy intensive technology. Moreover, the rising cost of fossil fuel, its uncertain availability and associated environmental concerns have led to a need for future desalination plants to use other energy sources, such as renewables and nuclear. Nuclear desalination has thus the potential to be an important option for safe, economic and reliable supply of large amounts of fresh water to meet the ever-increasing worldwide water demand. Different approaches to use nuclear power for seawater desalination have been considered including utilisation of the waste heat from nuclear reactors to further reduce the cost of nuclear desalination. Various options to implement nuclear desalination relay mainly on policy making based on socio-economic and environmental impacts of available technologies. This paper examines nuclear desalination costs and proposes a methodology for exploring interactions between critical parameters. - Highlights: • The paper demonstrated desalination costs under uncertainty conditions. • Uncertainty for nuclear power prevails only during the construction period. • Nuclear desalination proved to be cheaper and with less uncertainty

Mass Flow Data Comparison for Comprehensive Fuel Cycle Options

International Nuclear Information System (INIS)

Kim, T.K.; Taiwo, T.A.; Wigeland, R.A.; Dixon, B.W.; Gehin, J.C.; Todosow, M.

2015-01-01

One of the key objectives stated in the United States Department of Energy, Nuclear Energy R and D road-map is the development of sustainable nuclear fuel cycles that improve natural resource utilisation and provide adequate capability and capacity to manage wastes produced by the fuel cycle. In order to inform this objective, an evaluation and screening of nuclear fuel cycle options has been conducted. As part of that effort, the entire fuel cycle options space was represented by 40 Evaluation Groups (EGs), and mass flow information for each of the EGs was provided by using an Analysis Example (AE). In this paper, the mass flow data of the 40 AEs are compared to inform on trends in the natural resource utilisation and nuclear waste generation. For the AEs that need enriched uranium support, the natural uranium required is high and the natural resource utilisation is generally lower than 2% regardless of the fuel cycle strategy (i.e., once-through, limited recycle, or continuous recycle). However, the utilisation could be improved by avoiding enriched uranium fuel support. The natural resource utilisation increases to more than 80% by recycling the nuclear fuel continuously without enriched uranium support. The combined mass of spent nuclear fuel (SNF) and high-level waste (HLW), i.e., SNF+HLW mass, is lower by using a continuous recycle option compared to a once-through fuel cycle option, because SNF mass is converted to mass of recycled products and only fission products and other process losses need to be disposed. The combined disposed mass of depleted uranium (DU), recovered uranium (RU) and thorium (RTh), i.e. DU+RU+RTh mass, has a similar trend to the uranium utilisation. For the AEs that need enriched uranium fuel, the DU and RU are the major fraction by mass of the DU+RU+RTh, which are two orders of magnitude higher in mass compared to those for the AEs that do not need enriched uranium fuel. (authors)

Consolidated fuel reprocessing programme: Analysis of various options for the breeder fuel cycle in the USA

International Nuclear Information System (INIS)

Stradley, J.G.; Burch, W.D.; Yook, H.R.

1986-01-01

The United States Department of Energy (DOE) has established a programme to develop innovative liquid metal reactor (LMR) designs to assist in developing future U.S. reactor strategy. The paper describes studies in progress to examine various fuel cycle strategies that relate to the reactor strategy. Three potential fuel cycle options that focus on supporting an initial 1300 MW(e) reactor station have been defined: (1) Completion and utilization of the Breeder Reprocessing Engineering Test/Secure Automated Fabrication (BRET/SAF) in the Fuels and Materials Examination Facility (FMEF) at Hanford, Washington; (2) a co-located fuel cycle facility; and (3) delayed closure of the fuel cycle for five to ten years. The BRET, designed as a development facility, has sufficient capacity to service the needs of an initial module at an LMR station. It appears feasible to increase this capacity and to utilize SAF in the FMEF to accommodate the projected output (up to 35 MtHM/year) from the 1300 MW(e) liquid-metal concepts under study. Plans developed within the United States Consolidated Management Office for an initial reactor project have envisioned that cost savings could be realized by delaying the closure of the fuel cycle as long as supplies of plutonium could be obtained relatively inexpensively. This might prove to be only five to ten years, but even that period might be long enough for the fuel cycle costs to be spread over more than one reactor rather than loaded on the initial project. This concept is being explored as is the question of the future coupling of a light water reactor reprocessing industry for plutonium supply to breeder recycle

Cost-effectiveness of public-health policy options in the presence of pretreatment NNRTI drug resistance in sub-Saharan Africa

DEFF Research Database (Denmark)

Phillips, Andrew N; Cambiano, Valentina; Nakagawa, Fumiyo

2018-01-01

BACKGROUND: There is concern over increasing prevalence of non-nucleoside reverse-transcriptase inhibitor (NNRTI) resistance in people initiating antiretroviral therapy (ART) in low-income and middle-income countries. We assessed the effectiveness and cost-effectiveness of alternative public health...... sources and considers specific drugs and resistance mutations. We used this model to generate multiple setting scenarios mimicking those in sub-Saharan Africa and considered the prevalence of pretreatment NNRTI drug resistance in 2017. We then compared effectiveness and cost-effectiveness of alternative...... policy options. We took a 20 year time horizon, used a cost effectiveness threshold of US$500 per DALY averted, and discounted DALYs and costs at 3% per year. FINDINGS: A transition to use of a dolutegravir as a first-line regimen in all new ART initiators is the option predicted to produce the most...

Repository emplacement costs for Al-clad high enriched uranium spent fuel

International Nuclear Information System (INIS)

McDonell, W.R.; Parks, P.B.

1994-01-01

A range of strategies for treatment and packaging of Al-clad high-enriched uranium (HEU) spent fuels to prevent or delay the onset of criticality in a geologic repository was evaluated in terms of the number of canisters produced and associated repository costs incurred. The results indicated that strategies in which neutron poisons were added to consolidated forms of the U-Al alloy fuel generally produced the lowest number of canisters and associated repository costs. Chemical processing whereby the HEU was removed from the waste form was also a low cost option. The repository costs generally increased for isotopic dilution strategies, because of the substantial depleted uranium added. Chemical dissolution strategies without HEU removal were also penalized because of the inert constituents in the final waste glass form. Avoiding repository criticality by limiting the fissile mass content of each canister incurred the highest repository costs

Costs of electronuclear fuel production

International Nuclear Information System (INIS)

Flaim, T.; Loose, V.

1978-07-01

The Los Alamos Scientific Laboratory (LASL) proposes to study the electronuclear fuel producer (EFP) as a means of producing fissile fuel to generate electricity. The main advantage of the EFP is that it may reduce the risks of nuclear proliferation by breeding 233 U from thorium, thereby avoiding plutonium separation. A report on the costs of electronuclear fuel production based upon two designs considered by LASL is presented. The findings indicate that the EFP design variations considered are not likely to result in electricity generation costs as low as the uranium fuel cycle used in the US today. At current estimates of annual fuel output (500 kg 233 U per EFP), the costs of electricity generation using fuel produced by the EFP are more than three times higher than generating costs using the traditional fuel cycle. Sensitivity analysis indicates that electronuclear fuel production would become cost competitive with the traditional uranium fuel cycle when U 3 O 8 (yellowcake) prices approach $1000 per pound

K Basin spent fuel sludge treatment alternatives study. Volume 2, Technical options

Energy Technology Data Exchange (ETDEWEB)

Beary, M.M.; Honekemp, J.R.; Winters, N. [Science Applications International Corp., Richland, WA (United States)

1995-01-01

Approximately 2100 metric tons of irradiated N Reactor fuel are stored in the KE and KW Basins at the Hanford Site, Richland, Washington. Corrosion of the fuel has led to the formation of sludges, both within the storage canisters and on the basin floors. Concern about the degraded condition of the fuel and the potential for leakage from the basins in proximity to the Columbia River has resulted in DOE`s commitment in the Tri-Party Agreement (TPA) to Milestone M-34-00-T08 to remove the fuel and sludges by a December 2002 target date. To support the planning for this expedited removal action, the implications of sludge management under various scenarios are examined. This report, Volume 2 of two volumes, describes the technical options for managing the sludges, including schedule and cost impacts, and assesses strategies for establishing a preferred path.

The costs and benefits of Option B+ for the prevention of mother-to-child transmission of HIV.

Science.gov (United States)

Gopalappa, Chaitra; Stover, John; Shaffer, Nathan; Mahy, Mary

2014-01-01

Most countries follow WHO 2010 guidelines for the prevention of mother-to-child transmission (PMTCT) of HIV using either Option A or B for women not yet eligible for antiretroviral therapy (ART). Both of these approaches involve the use of antiretrovirals during pregnancy and breastfeeding. Some countries have adopted a new strategy, Option B+, in which HIV-positive pregnant women are started immediately on ART and continued for life. Option B+ is more costly than Options A or B, but provides additional health benefits. In this article, we estimate the additional costs and effectiveness of Option B+. We developed a deterministic model to simulate births, breastfeeding, and HIV infection in women in four countries, Kenya, Zambia, South Africa, and Vietnam that differ in fertility rate, birth interval, age at first birth, and breastfeeding patterns, but have similar age at HIV infection. We estimated the total PMTCT costs and new child infections under Options A, B, and B+, and measured cost-effectiveness as the incremental PMTCT-related costs per child infection averted. We included adult sexual transmissions averted from ART, the corresponding costs saved, and estimated the total incremental cost per transmission (child and adult) averted. When considering PMTCT-related costs and child infections, Option B+ was the most cost-effective strategy costing between $6000 and $23 000 per infection averted compared with Option A. Option B+ averted more child infections compared with Option B in all four countries and cost less than Option B in Kenya and Zambia. When including adult sexual transmissions averted, Option B+ cost less and averted more infections than Options A and B.

Levelized cost-risk reduction prioritization of waste disposal options

International Nuclear Information System (INIS)

Wilkinson, V.K.; Young, J.M.

1992-01-01

The prioritization of solid waste disposal options in terms of reduced risk to workers, the public, and the environment has recently generated considerable governmental and public interest. In this paper we address the development of a methodology to establish priorities for waste disposal options, such as incineration, landfills, long-term storage, waste minimization, etc. The study is one result of an overall project to develop methodologies for Probabilistic Risk Assessments (PRAs) of non-reactor nuclear facilities for the US Department of Energy. Option preferences are based on a levelized cost-risk reduction analysis. Option rankings are developed as functions of disposal option cost and timing, relative long- and short-term risks, and possible accident scenarios. We examine the annual costs and risks for each option over a large number of years. Risk, in this paper, is defined in terms of annual fatalities (both prompt and long-term) and environmental restoration costs that might result from either an accidental release or long-term exposure to both plant workers and the public near the site or facility. We use event timing to weigh both costs and risks; near-term costs and risks are discounted less than future expenditures and fatalities. This technique levels the timing of cash flows and benefits by converting future costs and benefits to present value costs and benefits. We give an example Levelized Cost-Benefit Analysis of incinerator location options to demonstrate the methodology and required data

Crude Glycerol as Cost-Effective Fuel for Combined Heat and Power to Replace Fossil Fuels, Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Roberts, William L

2012-10-31

The primary objectives of this work can be summed into two major categories. Firstly, the fundamentals of the combustion of glycerol (in both a refined and unrefined form) were to be investigated, with emphasis of the development of a system capable of reliably and repeatedly combusting glycerol as well as an analysis of the emissions produced during glycerol combustion. Focus was placed on quantifying common emissions in comparison to more traditional fuels and this work showed that the burner developed was able to completely combust glycerol within a relatively wide range of operating conditions. Additionally, focus was placed on examining specific emissions in more detail, namely interesting NOx emissions observed in initial trials, acrolein and other volatile organic emissions, and particulate and ash emissions. This work showed that the combustion of crude glycerol could result in significantly reduced NOx emissions as a function of the high fuel bound oxygen content within the glycerol fuel. It also showed that when burned properly, the combustion of crude glycerol did not result in excessive emissions of acrolein or any other VOC compared to the combustion from more traditional fuels. Lastly however, this work has shown that in any practical application in which glycerol is being burned, it will be necessary to explore ash mitigation techniques due to the very high particulate matter concentrations produced during glycerol combustion. These emissions are comparable to unfiltered coal combustion and are directly tied to the biodiesel production method. The second focus of this work was directed to developing a commercialization strategy for the use of glycerol as a fuel replacement. This strategy has identified a 30 month plan for the scaling up of the laboratory scale burner into a pre-pilot scale system. Additionally, financing options were explored and an assessment was made of the economics of replacing a traditional fuel (namely natural gas) with crude

Completion of Population of and Quality Assurance on the Nuclear Fuel Cycle Options Catalog.

Energy Technology Data Exchange (ETDEWEB)

Price, Laura L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Barela, Amanda Crystal [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Walkow, Walter M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Schetnan, Richard Reed [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Arnold, Matthew Brian [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2015-12-01

An Evaluation and Screening team supporting the Fuel Cycle Technologies Program Office of the United States Department of Energy, Office of Nuclear Energy is conducting an evaluation and screening of a comprehensive set of fuel cycle options. These options have been assigned to one of 40 evaluation groups, each of which has a representative fuel cycle option [Todosow 2013]. A Fuel Cycle Data Package System Datasheet has been prepared for each representative fuel cycle option to ensure that the technical information used in the evaluation is high-quality and traceable [Kim, et al., 2013]. The information contained in the Fuel Cycle Data Packages has been entered into the Nuclear Fuel Cycle Options Catalog at Sandia National Laboratories so that it is accessible by the evaluation and screening team and other interested parties. In addition, an independent team at Savannah River National Laboratory has verified that the information has been entered into the catalog correctly. This report documents that the 40 representative fuel cycle options have been entered into the Catalog, and that the data entered into the catalog for the 40 representative options has been entered correctly.

A strategic approach to short- and long-term irradiated WWER fuel management

International Nuclear Information System (INIS)

Wilcox, P.; Conboy, T.M.

1994-01-01

A methodology is presented for comparison of alternative options for short-term and long-term irradiated fuel management. The value of this methodology is that all interested parties can take part in the analysis and derive the basis for decision-making. The methodology can answer questions as: When can uranium and plutonium recovered by reprocessing be recycled cost effectively in WWER? If reprocessing is not the short-term option chosen, is storage of irradiated fuel at the original licensed nuclear reactor site preferable to a separate storage-only-site? Are modular vault dry stores and cooling ponds which necessitate significant capital investment prior to deployment, more costly overall than their options? Should the most suitable form of irradiated fuel management be determined only by cost constraints? The key stages of the methodology are: 1) Assessing the current situation; 2) Assessing priorities; 3) Option/possible solutions; 4) Generic storage systems; 5) Cost/funding analysis; 6) Selection criteria; 7) Optioneering/evaluation. The conclusions that can be reached from this methodological approach lead to firm recommendations based on objective assessments. The methodology builds on existing expertise. It is not an imposed solution allowing an excellent exchange of knowledge and skills between the people involved

A strategic approach to short- and long-term irradiated WWER fuel management

Energy Technology Data Exchange (ETDEWEB)

Wilcox, P [BNFL International Ltd., Warrington (United Kingdom); Conboy, T M [BNFL Engineering Ltd., Manchester (United Kingdom)

1994-12-31

A methodology is presented for comparison of alternative options for short-term and long-term irradiated fuel management. The value of this methodology is that all interested parties can take part in the analysis and derive the basis for decision-making. The methodology can answer questions as: When can uranium and plutonium recovered by reprocessing be recycled cost effectively in WWER? If reprocessing is not the short-term option chosen, is storage of irradiated fuel at the original licensed nuclear reactor site preferable to a separate storage-only-site? Are modular vault dry stores and cooling ponds which necessitate significant capital investment prior to deployment, more costly overall than their options? Should the most suitable form of irradiated fuel management be determined only by cost constraints? The key stages of the methodology are: (1) Assessing the current situation; (2) Assessing priorities; (3) Option/possible solutions; (4) Generic storage systems; (5) Cost/funding analysis; (6) Selection criteria; (7) Optioneering/evaluation. The conclusions that can be reached from this methodological approach lead to firm recommendations based on objective assessments. The methodology builds on existing expertise. It is not an imposed solution allowing an excellent exchange of knowledge and skills between the people involved.

Automobiles and global warming: Alternative fuels and other options for carbon dioxide emissions reduction

International Nuclear Information System (INIS)

Sagar, A.D.

1995-01-01

Automobiles are a source of considerable pollution at the global level, including a significant fraction of the total greenhouse gas emissions. Alternative fuels have received some attention as potential options to curtail the carbon dioxide emissions from motor vehicles. This article discusses the feasibility and desirability (from a technical as well as a broader environmental perspective) of the large-scale production and use of alternative fuels as a strategy to mitigate automotive carbon dioxide emissions. Other options such as improving vehicle efficiency and switching to more efficient modes of passenger transportation are also discussed. These latter options offer an effective and immediate way to tackle the greenhouse and other pollutant emission from automobiles, especially as the limitations of currently available alternative fuels and the technological and other constraints for potential future alternatives are revealed

Is the Venner-PneuX Endotracheal Tube System A Cost-Effective Option For Post Cardiac Surgery Care?

Science.gov (United States)

Andronis, Lazaros; Oppong, Raymond A; Manga, Na'ngono; Senanayake, Eshan; Gopal, Shameer; Charman, Susan; Giri, Ramesh; Luckraz, Heyman

2018-04-27

Ventilator-associated pneumonia (VAP) is common and costly. In a recent randomized controlled trial, the Venner-PneuX (VPX) endotracheal tube system was found to be superior to standard endotracheal tubes (SET) in preventing VAP. However, VPX is considerably more expensive. We evaluated the costs and benefits of VPX to determine whether replacing SET with VPX is a cost-effective option for intensive care units. We developed a decision analytic model to compare intubation with VPX or SET for patients requiring mechanical ventilation post cardiac surgery. The model was populated with existing evidence on costs, effectiveness and quality of life. Cost-effectiveness and cost-utility analyses were conducted from an NHS hospital perspective. Uncertainty was assessed through deterministic and probabilistic sensitivity analyses. Compared to SET, VPX is associated with an expected cost saving of £738 per patient. VPX led to a small increase in quality-adjusted life years (QALYs), indicating that the device is overall less costly and more effective than SET. The probability of VPX being cost-effective at £30,000 per QALY is 97%. VPX would cease to be cost-effective if (i) it led to a risk reduction smaller than 0.02 compared to SET, (ii) the acquisition cost of VPX was as high as £890 or, (iii) the cost of treating a case of VAP was lower than £1,450. VPX resulted in improved outcomes and savings which far offset the cost of the device, suggesting that replacing SET with VPX is overall beneficial. Findings were robust to extreme values of key parameters. Copyright © 2018. Published by Elsevier Inc.

Evaluation of the recycling costs, as a disposal form of the spent nuclear fuel

International Nuclear Information System (INIS)

Ramirez S, J.R.; Alonso V, G.; Palacios, J.C.

2006-01-01

At the moment there are 2 BWR reactors operating in the Nuclear Power station of Laguna Verde in Mexico. At the end of the programmed life of the reactors (40 years) its will have completed 26 operation cycles, with will have 6712 spent fuel assemblies will be in the pools of the power station. Up to now, the decision on the destination of the high level wastes (spent nuclear fuel) it has not been determined in Mexico, the same as in other countries, adopting a politics of 'to wait to see that it happens in the world', in this respect, in the world two practical alternatives exist, one is to store the fuel in repositories designed for that end, another is reprocess the fuel to recycle the plutonium contained in it, both solutions have their particular technical and economic problematic. In this work it is evaluated from the economic point of view the feasibility of having the spent fuel, using the one recycled fuel, for that which thinks about a consistent scenario of a BWR reactor in which the fuel discharged in each operation cycle is reprocessed and its are built fuel assemblies of the MOX type to replace partly to the conventional fuel. This scenario shows an alternative to the indefinite storage of the high level radioactive waste. The found results when comparing from the economic point of view both options, show that the one recycled, even with the current costs of the uranium it is of the order of 7% more expensive that the option of storing the fuel in repositories constructed for that purpose. However the volumes of spent fuel decrease in 66%. (Author)

Comparing the social costs of biofuels and fossil fuels: A case study of Vietnam

International Nuclear Information System (INIS)

Le, Loan T.; Ierland, Ekko C. van; Zhu, Xueqin; Wesseler, Justus; Ngo, Giang

2013-01-01

Biofuel substitution for fossil fuels has been recommended in the literature and promoted in many countries; however, there are concerns about its economic viability. In this paper we focus on the cost-effectiveness of fuels, i.e., we compare the social costs of biofuels and fossil fuels for a functional unit defined as 1 km of vehicle transportation. We base our empirical results on a case study in Vietnam and compare two biofuels and their alternative fossil fuels: ethanol and gasoline, and biodiesel and diesel with a focus on the blends of E5 and E10 for ethanol, and B5 and B10 for biodiesel. At the discount rate of 4%, ethanol substitution for gasoline in form of E5 or E10 saves 33% of the social cost of gasoline if the fuel consumption of E5 and E10 is the same as gasoline. The ethanol substitution will be cost-effective if the fuel consumption of E5 and E10, in terms of L km −1 , is not exceeding the consumption of gasoline by more than 1.7% and 3.5% for E5 and E10 respectively. The biodiesel substitution would be cost-effective if the fuel consumption of B5 and B10, in terms of L km −1 compared to diesel, would decrease by more than 1.4% and 2.8% for B5 and B10 respectively at the discount rate of 4%. -- Highlights: •We examine cost-effectiveness of biofuels under efficiency levels of blends. •Cassava-based ethanol used as E5 saves 33% of social cost compared to gasoline. •Ethanol is cost-effective if E5 consumption per km is less than 1.017 times gasoline consumption. •Jatropha-based biodiesel used as B5 or B10 is currently not cost-effective in comparison to diesel. •Biodiesel would be cost-effective if B5 consumption per km would be less than 0.986 times diesel consumption

Gel-sphere-pac reactor fuel fabrication and its application to a variety of fuels

International Nuclear Information System (INIS)

Olsen, A.R.; Judkins, R.R.

1979-12-01

The gel-sphere-pac fuel fabrication option was evaluated for its possible application to commercial scale fuel fabrication for 19 fuel element designs that use oxide fuel in metal clad rods. The dry gel spheres are prepared at the reprocessing plant and are then calcined, sintered, inspected, and loaded into fuel rods and packed by low-energy vibration. A fuel smear density of 83 to 88% theoretical can be obtained. All fuel fabrication process steps were defined and evaluated from fuel receiving to finished fuel element shipping. The evaluation also covers the feasibility of the process, the current status of technology, estimates of the required time and cost to develop the technology to commercial status, and the safety and licensability of commercial scale plants. The primary evaluation was for a Light-Water Reactor fuel element containing (U,Pu)O 2 fuel. The other 18 fuel element types - 3 for Light-Water Reactors, 1 for a Heavy-Water Reactor, 1 for a Gas-Cooled Fast Reactor, 7 for Liquid-Metal-Cooled Fast Breeder Reactors, and 3 pairs for Light-Water Prebreeder and Breeder Reactors - were compared with the Light-Water Reactor. The gel-sphere-pac option was found applicable to 17 of the 19 element types; the characteristics of a commercial scale plant were defined for these for making cost estimates for such plants. The evaluation clearly shows the gel-sphere-pac process to be a viable fuel fabrication option. Estimates indicate a significant potential fabrication cost advantage for the gel-sphere-pac process if a remotely operated and remotely maintained fuel fabrication plant is required

Lookback Option Pricing with Fixed Proportional Transaction Costs under Fractional Brownian Motion.

Science.gov (United States)

Sun, Jiao-Jiao; Zhou, Shengwu; Zhang, Yan; Han, Miao; Wang, Fei

2014-01-01

The pricing problem of lookback option with a fixed proportion of transaction costs is investigated when the underlying asset price follows a fractional Brownian motion process. Firstly, using Leland's hedging method a partial differential equation satisfied by the value of the lookback option is derived. Then we obtain its numerical solution by constructing a Crank-Nicolson format. Finally, the effectiveness of the proposed form is verified through a numerical example. Meanwhile, the impact of transaction cost rate and volatility on lookback option value is discussed.

NPP fuel cycle and assessment of possible options for long-term fuel supply

International Nuclear Information System (INIS)

Ignatenko, E.I.; Lebedev, V.M.; Davidenko, N.N.

1999-01-01

The purpose of this paper is to present some results of the analysis of the possible options for Russian NPPs fuel supply. In the classical consideration these are four fuel cycles: uranium cycle based on natural uranium, this cycle has several economical advantages with the use of CANDU type reactors with a heavy-water moderator; uranium cycle based on enriched uranium, it is a basis for the current and future nuclear power; uranium-thorium fuel cycle with capabilities which are very promising but unfortunately difficult to implement in practice; plutonium-uranium cycle, in terms of its potential capabilities it is an excellent option, but it is extremely difficult to implement it in practice due to a high activity and toxicity of nuclear materials under recycle. The nuclear power of Russia is currently aimed at using the cheapest fuel resources, that is first of all, uranium reprocessed from industrial reactor fuel and slag-heaps accumulated on the past in isotope-separation plant sites. These resources are enough for the Russian large-scale nuclear power to be developed [ru

Fuel options for the fuel cell vehicle: hydrogen, methanol or gasoline?

International Nuclear Information System (INIS)

Thomas, C.E.; James, B.D.; Lomax, F.D. Jr.; Kuhn, I.F. Jr.

2000-01-01

Fuel cell vehicles can be powered directly by hydrogen or, with an onboard chemical processor, other liquid fuels such as gasoline or methanol. Most analysts agree that hydrogen is the preferred fuel in terms of reducing vehicle complexity, but one common perception is that the cost of a hydrogen infrastructure would be excessive. According to this conventional wisdom, the automobile industry must therefore develop complex onboard fuel processors to convert methanol, ethanol or gasoline to hydrogen. We show here, however, that the total fuel infrastructure cost to society including onboard fuel processors may be less for hydrogen than for either gasoline or methanol, the primary initial candidates currently under consideration for fuel cell vehicles. We also present the local air pollution and greenhouse gas advantages of hydrogen fuel cell vehicles compared to those powered by gasoline or methanol. (Author)

Policy options to contain healthcare costs: a review and classification

NARCIS (Netherlands)

Stadhouders, N.W.; Koolman, X.; Tanke, M.A.C.; Maarse, H.; Jeurissen, P.P.T.

2016-01-01

Containing health care costs has been a challenge for most OECD member states. We classify 2250 cost containment policies in forty-one groups of policy options. This conceptual framework might act as a toolkit for policymakers that seek to develop strategies for cost control; and for researchers

Investigation into fuel pin reshuffling options in PWR in-core fuel management for enhancement of efficient use of nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Daing, Aung Tharn, E-mail: atdaing@khu.ac.kr; Kim, Myung Hyun, E-mail: mhkim@khu.ac.kr

2014-07-01

Highlights: • This paper discusses an alternative option, fuel pin reshuffling for maximization of cycle energy production. • The prediction results of isotopic compositions of each burnt pin are verified. • The operating performance is analyzed at equilibrium core with fuel pin reshuffling. • The possibility of reuse of spent fuel pins for reduction of fresh fuel assemblies is investigated. - Abstract: An alternative way to enhance efficient use of nuclear fuel is investigated through fuel pin reshuffling options within PWR fuel assembly (FA). In modeling FA with reshuffled pins, as prerequisite, the single pin calculation method is proposed to estimate the isotopic compositions of each pin of burnt FA in the core-wide environment. Subsequently, such estimation has been verified by comparing with the neutronic performance of the reference design. Two scenarios are concerned, i.e., first scenario was targeted on the improvement of the uniform flux spatial distribution and on the enhancement of neutron economy by simply reshuffling the existing fuel pins in once-burnt fuel assemblies, and second one was focused on reduction of fresh fuel loading and discharged fuel assemblies with more economic incentives by reusing some available spent fuel pins still carrying enough reactivity that are mechanically sound ascertained. In scenario-1, the operating time was merely somewhat increased for few minutes when treating eight FAs by keeping enough safety margins. The scenario-2 was proved to reduce four fresh FAs loading without largely losing any targeted parameters from the safety aspect despite loss of 14 effective full power days for operation at reference plant full rated power.

Impact of Nuclear Energy Futures on Advanced Fuel Cycle Options

International Nuclear Information System (INIS)

Dixon, B.W.; Piet, S.J.

2004-01-01

The Nuclear Waste Policy Act requires the Secretary of Energy to inform Congress before 2010 on the need for a second geologic repository for spent nuclear fuel. By that time, the spent fuel discharged from current commercial reactors will exceed the statutory limit of the first repository. There are several approaches to eliminate the need for another repository in this century. This paper presents a high-level analysis of these spent fuel management options in the context of a full range of possible nuclear energy futures. The analysis indicates the best option to implement varies depending on the nuclear energy future selected

Impact of advanced fuel cycle options on waste management policies

International Nuclear Information System (INIS)

Gordelier, Stan; Cavedon, Jean-Marc

2006-01-01

OECD/NEA has performed a study on the impact of advanced fuel cycle options on waste management policies with 33 experts from 12 member countries, 1 non-member country and 2 international organizations. The study extends a series of previous ones on partitioning and transmutation (P and T) issues, focusing on the performance assessments for repositories of high-level waste (HLW) arising from advanced fuel cycles. This study covers a broader spectrum than previous studies, from present industrial practice to fully closed cycles via partially closed cycles (in terms of transuranic elements); 9 fuel cycle schemes and 4 variants. Elements of fuel cycles are considered primarily as sources of waste, the internal mass flows of each scheme being kept for the sake of mass conservation. The compositions, activities and heat loads of all waste flows are also tracked. Their impact is finally assessed on the waste repository concepts. The study result confirms the findings from the previous NEA studies on P and T on maximal reduction of the waste source term and maximal use of uranium resources. In advanced fuel cycle schemes the activity of the waste is reduced by burning first plutonium and then minor actinides and also the uranium consumption is reduced, as the fraction of fast reactors in the park is increased to 100%. The result of the repository performance assessments, analysing the effect of different HLW isotopic composition on repository performance and on repository capacity, shows that the maximum dose released to biosphere at any time in normal conditions remains, for all schemes and for all the repository concepts examined, well below accepted radiation protection thresholds. The major impact is on the detailed concept of the repositories, through heat load and waste volume. Advanced fuel cycles could allow a repository to cover waste produced from 5 to 20 times more electricity generation than PWR once-through cycle. Given the flexibility of the advanced fuel

Diversification of fuel costs accounting for load variation

International Nuclear Information System (INIS)

Ruangpattana, Suriya; Preckel, Paul V.; Gotham, Douglas J.; Muthuraman, Kumar; Velástegui, Marco; Morin, Thomas L.; Uhan, Nelson A.

2012-01-01

A practical mathematical programming model for the strategic fuel diversification problem is presented. The model is designed to consider the tradeoffs between the expected costs of investments in capacity, operating and maintenance costs, average fuel costs, and the variability of fuel costs. In addition, the model is designed to take the load curve into account at a high degree of resolution, while keeping the computational burden at a practical level. The model is illustrated with a case study for Indiana's power generation system. The model reveals that an effective means of reducing the volatility of the system-level fuel costs is through the reduction of dependence on coal-fired generation with an attendant shift towards nuclear generation. Model results indicate that about a 25% reduction in the standard deviation of the generation costs can be achieved with about a 20–25% increase in average fuel costs. Scenarios that incorporate costs for carbon dioxide emissions or a moratorium on nuclear capacity additions are also presented. Highlights: ► We propose a fuel price risk management model for generation investments accounting for load shape. ► The formulation incorporates a highly refined load curve while maintaining tractability. ► We demonstrate the model for planning generation investments in the state of Indiana for 2025. ► Scenarios reflect charges for CO 2 emissions and a moratorium on new nuclear power.

Fuel cycle cost study with HEU and LEU fuels

International Nuclear Information System (INIS)

Matos, J.E.; Freese, K.E.

1984-01-01

Fuel cycle costs are compared for a range of 235 U loadings with HEU and LEU fuels using the IAEA generic 10 MW reactor as an example. If LEU silicide fuels are successfully demonstrated and licensed, the results indicate that total fuel cycle costs can be about the same or lower than those with the HEU fuels that are currently used in most research reactors

A multi-attribute approach to the rationalization of radiation protection options

International Nuclear Information System (INIS)

Lombard, J.; Oudiz, A.

1979-01-01

Application of the ALARA principle requires the use of quantitative methods such as cost-benefit, cost-effectiveness, multi-attribute and other analyses. An example is presented of the application of a multi-attribute analysis in connection with the determination of ALARA levels for the light-water fuel cycle. Thirty-nine processing options for waste from different fuel cycle facilities have been identified. These are categorized on the basis of cost, of performance in terms of reduction of collective and individual detriment and, finally, of a subjective index of data reliability. Multi-attribute analysis can be used for classifying options on the basis of these four criteria. In particular, a method known as ''total outclassing analysis'' can be used for initial classification of options independently of the ''implicit value of human life''. The value of total outclassing analysis lies in the fact that it can be used for a classification of options which takes collective and individual detriment simultaneously into account. It thus represents a satisfactory synthesis of the individual approach (critical groups) and the collective approach. A finer classification can be obtained by carrying out a non-total outclassing analysis (ELECTRE method). At this stage the weighting of criteria becomes a necessity. The results, however, are fairly insensitive to modification of the ''implicit value of human life''. Generally, the study shows traditional radiation protection options to be justified, especially where the trapping of iodine in reactors is concerned, and stresses the value of retaining noble gases in reprocessing plants

Comparing the social costs of biofuels and fossil fuels: A case study of Vietnam

NARCIS (Netherlands)

Thanh, le L.; Ierland, van E.C.; Zhu, X.; Wesseler, J.H.H.; Ngo, G.

2013-01-01

Biofuel substitution for fossil fuels has been recommended in the literature and promoted in many countries; however, there are concerns about its economic viability. In this paper we focus on the cost-effectiveness of fuels, i.e., we compare the social costs of biofuels and fossil fuels for a

Spent fuel storage - dry storage options and issues

International Nuclear Information System (INIS)

Akins, M.J.

2007-01-01

The increase in the number of nuclear energy power generation facilities will require the ability to store the spent nuclear fuel for a long period until the host countries develop reprocessing or disposal options. Plants have storage pools which are closely associated with the operating units. These are excellent for short term storage, but require active maintenance and operations support which are not desirable for the long term. Over the past 25 years, dry storage options have been developed and implemented throughout the world. In recent years, protection against terrorist attack has become an increasing source of design objectives for these facilities, as well as the main nuclear plant. This paper explores the current design options of dry storage cask systems and examines some of the current design issues for above ground , in-ground, or below-ground storage of spent fuel in dry casks. (author)

Methodology for estimating reprocessing costs for nuclear fuels

International Nuclear Information System (INIS)

Carter, W.L.; Rainey, R.H.

1980-02-01

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

An Improved Quantum-Behaved Particle Swarm Optimization Method for Economic Dispatch Problems with Multiple Fuel Options and Valve-Points Effects

Directory of Open Access Journals (Sweden)

Hong-Yun Zhang

2012-09-01

Full Text Available Quantum-behaved particle swarm optimization (QPSO is an efficient and powerful population-based optimization technique, which is inspired by the conventional particle swarm optimization (PSO and quantum mechanics theories. In this paper, an improved QPSO named SQPSO is proposed, which combines QPSO with a selective probability operator to solve the economic dispatch (ED problems with valve-point effects and multiple fuel options. To show the performance of the proposed SQPSO, it is tested on five standard benchmark functions and two ED benchmark problems, including a 40-unit ED problem with valve-point effects and a 10-unit ED problem with multiple fuel options. The results are compared with differential evolution (DE, particle swarm optimization (PSO and basic QPSO, as well as a number of other methods reported in the literature in terms of solution quality, convergence speed and robustness. The simulation results confirm that the proposed SQPSO is effective and reliable for both function optimization and ED problems.

A cost-benefit analysis of spent fuel management

International Nuclear Information System (INIS)

Lamorlette, G.

2001-01-01

The back end of the fuel cycle is an area of economic risk for utilities having nuclear power plants to generate electricity. A cost-benefit analysis is a method by which utilities can evaluate advantages and drawbacks of alternative back end fuel cycle strategies. The present paper analyzes how spent fuel management can influence the risks and costs incurred by a utility over the lifetime of its power plants and recommends a recycling strategy. (author)

Cost-effective design of ringwall storage hybrid power plants: A real options analysis

International Nuclear Information System (INIS)

Weibel, Sebastian; Madlener, Reinhard

2015-01-01

Highlights: • Economic viability, optimal size, and siting of a hybrid ringwall hydro power plant. • Real options analysis for optimal investment timing and stochastic storage volumes. • Stochastic PV and solar power production affects optimal size of the storage device. • Monte Carlo simulation is used for wind/solar power, el. price, and investment cost. • Numerical computations for two different hybrid ringwall storage plant scenarios. - Abstract: We study the economic viability and optimal sizing and siting of a hybrid plant that combines a ringwall hydro storage system with wind and solar power plants (ringwall storage hybrid power plant, RSHPP). A real options model is introduced to analyze the economics of an onshore RSHPP, and in particular of the varying storage volume in light of the stochastic character of wind and solar power, as well as the optimal investment timing under uncertainty. In fact, many uncertainties arise in such a project. Energy production is determined by the stochastic character of wind and solar power, and affects the optimal size of the storage device. Monte Carlo simulation is performed to analyze the following sources of uncertainty: (i) wind intensity and solar irradiation; (ii) future electricity price; and (iii) investment costs. The results yield the optimal size of the storage device; the energy market on which the operator should sell the electricity generated; numerical examples for two different RSHPP scenarios; and a real options model for analyzing the opportunity to defer the project investment and thus to exploit the value of waiting

Steam and partial oxidation reforming options for hydrogen production from fossil fuels for PEM fuel cells

Directory of Open Access Journals (Sweden)

Yousri M.A. Welaya

2012-06-01

Full Text Available Proton exchange membrane fuel cell (PEM generates electrical power from air and from hydrogen or hydrogen rich gas mixtures. Therefore, there is an increasing interest in converting current hydrocarbon based marine fuels such as natural gas, gasoline, and diesel into hydrogen rich gases acceptable to the PEM fuel cells on board ships. Using chemical flow sheeting software, the total system efficiency has been calculated. Natural gas appears to be the best fuel for hydrogen rich gas production due to its favorable composition of lower molecular weight compounds. This paper presents a study for a 250 kW net electrical power PEM fuel cell system utilizing a partial oxidation in one case study and steam reformers in the second. This study has shown that steam-reforming process is the most competitive fuel processing option in terms of fuel processing efficiency. Partial oxidation process has proved to posses the lowest fuel processing efficiency. Among the options studied, the highest fuel processing efficiency is achieved with natural gas steam reforming system.

Fast Reactor Fuel Cycle Cost Estimates for Advanced Fuel Cycle Studies

International Nuclear Information System (INIS)

Harrison, Thomas

2013-01-01

Presentation Outline: • Why Do I Need a Cost Basis?; • History of the Advanced Fuel Cycle Cost Basis; • Description of the Cost Basis; • Current Work; • Fast Reactor Fuel Cycle Applications; • Sample Fuel Cycle Cost Estimate Analysis; • Future Work

Cost and performance of fossil fuel power plants with CO2 capture and storage

International Nuclear Information System (INIS)

Rubin, Edward S.; Chen, Chao; Rao, Anand B.

2007-01-01

CO 2 capture and storage (CCS) is receiving considerable attention as a potential greenhouse gas (GHG) mitigation option for fossil fuel power plants. Cost and performance estimates for CCS are critical factors in energy and policy analysis. CCS cost studies necessarily employ a host of technical and economic assumptions that can dramatically affect results. Thus, particular studies often are of limited value to analysts, researchers, and industry personnel seeking results for alternative cases. In this paper, we use a generalized modeling tool to estimate and compare the emissions, efficiency, resource requirements and current costs of fossil fuel power plants with CCS on a systematic basis. This plant-level analysis explores a broader range of key assumptions than found in recent studies we reviewed for three major plant types: pulverized coal (PC) plants, natural gas combined cycle (NGCC) plants, and integrated gasification combined cycle (IGCC) systems using coal. In particular, we examine the effects of recent increases in capital costs and natural gas prices, as well as effects of differential plant utilization rates, IGCC financing and operating assumptions, variations in plant size, and differences in fuel quality, including bituminous, sub-bituminous and lignite coals. Our results show higher power plant and CCS costs than prior studies as a consequence of recent escalations in capital and operating costs. The broader range of cases also reveals differences not previously reported in the relative costs of PC, NGCC and IGCC plants with and without CCS. While CCS can significantly reduce power plant emissions of CO 2 (typically by 85-90%), the impacts of CCS energy requirements on plant-level resource requirements and multi-media environmental emissions also are found to be significant, with increases of approximately 15-30% for current CCS systems. To characterize such impacts, an alternative definition of the 'energy penalty' is proposed in lieu of the

ORCOST-2, PWR, BWR, HTGR, Fossil Fuel Power Plant Cost and Economics

International Nuclear Information System (INIS)

Fuller, L.C.; Myers, M.L.

1975-01-01

1 - Description of problem or function: ORCOST2 estimates the cost of electrical energy production from single-unit steam-electric power plants. Capital costs and operating and maintenance costs are calculated using base cost models which are included in the program for each of the following types of plants: PWR, BWR, HTGR, coal, oil, and gas. The user may select one of several input/output options for calculation of capital cost, operating and maintenance cost, levelized energy costs, fixed charge rate, annual cash flows, cumulative cash flows, and cumulative discounted cash flows. Options include the input of capital cost and/or fixed charge rate to override the normal calculations. Transmission and distribution costs are not included. Fuel costs must be input by the user. 2 - Method of solution: The code follows the guidelines of AEC Report NUS-531. A base capital-cost model and a base operating- and maintenance-cost model are selected and adjusted for desired size, location, date, etc. Costs are discounted to the year of first commercial operation and levelized to provide annual cost of electric power generation. 3 - Restrictions on the complexity of the problem: The capital cost models are of doubtful validity outside the 500 to 1500 MW(e) range

Advanced nuclear fuel cycles and radioactive waste management

International Nuclear Information System (INIS)

2006-01-01

This study analyses a range of advanced nuclear fuel cycle options from the perspective of their effect on radioactive waste management policies. It presents various fuel cycle options which illustrate differences between alternative technologies, but does not purport to cover all foreseeable future fuel cycles. The analysis extends the work carried out in previous studies, assesses the fuel cycles as a whole, including all radioactive waste generated at each step of the cycles, and covers high-level waste repository performance for the different fuel cycles considered. The estimates of quantities and types of waste arising from advanced fuel cycles are based on best available data and experts' judgement. The effects of various advanced fuel cycles on the management of radioactive waste are assessed relative to current technologies and options, using tools such as repository performance analysis and cost studies. (author)

Life cycle assessment integrated with thermodynamic analysis of bio-fuel options for solid oxide fuel cells.

Science.gov (United States)

Lin, Jiefeng; Babbitt, Callie W; Trabold, Thomas A

2013-01-01

A methodology that integrates life cycle assessment (LCA) with thermodynamic analysis is developed and applied to evaluate the environmental impacts of producing biofuels from waste biomass, including biodiesel from waste cooking oil, ethanol from corn stover, and compressed natural gas from municipal solid wastes. Solid oxide fuel cell-based auxiliary power units using bio-fuel as the hydrogen precursor enable generation of auxiliary electricity for idling heavy-duty trucks. Thermodynamic analysis is applied to evaluate the fuel conversion efficiency and determine the amount of fuel feedstock needed to generate a unit of electrical power. These inputs feed into an LCA that compares energy consumption and greenhouse gas emissions of different fuel pathways. Results show that compressed natural gas from municipal solid wastes is an optimal bio-fuel option for SOFC-APU applications in New York State. However, this methodology can be regionalized within the U.S. or internationally to account for different fuel feedstock options. Copyright © 2012 Elsevier Ltd. All rights reserved.

Choice of Hemodialysis Access in Older Adults: A Cost-Effectiveness Analysis.

Science.gov (United States)

Hall, Rasheeda K; Myers, Evan R; Rosas, Sylvia E; O'Hare, Ann M; Colón-Emeric, Cathleen S

2017-06-07

Although arteriovenous fistulas have been found to be the most cost-effective form of hemodialysis access, the relative benefits of placing an arteriovenous fistula versus an arteriovenous graft seem to be least certain for older adults and when placed preemptively. However, older adults' life expectancy is heterogeneous, and most patients do not undergo permanent access creation until after dialysis initiation. We evaluated cost-effectiveness of arteriovenous fistula placement after dialysis initiation in older adults as a function of age and life expectancy. Using a hypothetical cohort of patients on incident hemodialysis with central venous catheters, we constructed Markov models of three treatment options: ( 1 ) arteriovenous fistula placement, ( 2 ) arteriovenous graft placement, or ( 3 ) continued catheter use. Costs, utilities, and transitional probabilities were derived from existing literature. Probabilistic sensitivity analyses were performed by age group (65-69, 70-74, 75-79, 80-84, and 85-89 years old) and quartile of life expectancy. Costs, quality-adjusted life-months, and incremental cost-effectiveness ratios were evaluated for up to 5 years. The arteriovenous fistula option was cost effective compared with continued catheter use for all age and life expectancy groups, except for 85-89 year olds in the lowest life expectancy quartile. The arteriovenous fistula option was more cost effective than the arteriovenous graft option for all quartiles of life expectancy among the 65- to 69-year-old age group. For older age groups, differences in cost-effectiveness between the strategies were attenuated, and the arteriovenous fistula option tended to only be cost effective in patients with life expectancy >2 years. For groups for which the arteriovenous fistula option was not cost saving, the cost to gain one quality-adjusted life-month ranged from $2294 to $14,042. Among older adults, the cost-effectiveness of an arteriovenous fistula placed within the first

MOX fuel use as a back-end option: Trends, main issues and impacts on fuel cycle management

International Nuclear Information System (INIS)

Fukuda, K.; Choi, J.-S.; Shani, R.; Durpel, L. van den; Bertel, E.; Sartori, E.

2000-01-01

In the past decades while the FBIULWR fuel cycle concept was zealously being developed, MOX-fuel use in thermal reactors was taken as an alternative back-end policy option. However, the plutonium recycling with LWRs has evolved to industrial level, gaining high maturity through the incubative period while FBR deployment was envisaged. Today, MOX-fuel use in LWRs makes integral part of the fuel cycle for those countries relying on the recycling policy. Developments to improve the fuel cycle performance, including the minimisation of remaining wastes, and the reactor engineering aspects owing to MOX-fuel use, are continued. This paper jointly presented by IAEA and OECD/NEA brings an integrated overview on MOX use as a back-end policy, covering MOX fuel utilisation, fuel performance and technology, economics, licensing, MOX fuel trends in the coming decades. (author)

An approach for assessing development and deployment risks in the DOE fuel cycle options evaluation and screening study - 5267

International Nuclear Information System (INIS)

Gehin, J.C.; Worrall, A.; Oakley, B.; Jenni, K.; Taiwo, T.; Wigeland, R.

2015-01-01

One of the key objectives of the U.S. Department of Energy (DOE) Nuclear Energy Research/development road-map is the development of sustainable nuclear fuel cycles that can improve natural resource utilization and provide solutions to the management of nuclear wastes. Recently, an evaluation and screening (ES) of fuel cycle systems has been conducted to identify those options that provide the best opportunities for obtaining such improvements and also to identify the required research and development activities that can support the development of advanced fuel cycle options. In order to evaluate and screen fuel cycle systems in the ES study, nine criteria were used including Development and Deployment Risk (DDR). More specifically, this criterion was represented by the following metrics: Development time, development cost, deployment cost from prototypic validation to first-of-a-kind commercial, compatibility with the existing nuclear fuel cycle infrastructure, existence of regulations for the fuel cycle and familiarity with licensing, and existence of market incentives and/or barriers to commercial implementation of fuel cycle processes. Given the comprehensive nature of the study, a systematic approach was needed to determine metric data for the DDR criterion. As would be expected, the Evaluation Group representing the once-through use of uranium in thermal reactors is always the highest ranked fuel cycle Evaluation Group for this DDR criterion. Evaluation Groups that consist of once-through fuel cycles that use existing reactor types are consistently ranked very high. The highest ranked limited and continuous recycle fuel cycle Evaluation Groups are those that recycle Pu in thermal reactors. The lowest ranked fuel cycles are predominately continuous recycle single stage and multi-stage fuel cycles that involve TRU and/or U 233 recycle. (authors)

Nuclear Fuel Cycle Evaluation and Real Options

Directory of Open Access Journals (Sweden)

L. Havlíček

2008-01-01

Full Text Available The first part of this paper describes the nuclear fuel cycle. It is divided into three parts. The first part, called Front-End, covers all activities connected with fuel procurement and fabrication. The middle part of the cycle includes fuel reload design activities and the operation of the fuel in the reactor. Back-End comprises all activities ensuring safe separation of spent fuel and radioactive waste from the environment. The individual stages of the fuel cycle are strongly interrelated. Overall economic optimization is very difficult. Generally, NPV is used for an economic evaluation in the nuclear fuel cycle. However the high volatility of uranium prices in the Front-End, and the large uncertainty of both economic and technical parameters in the Back-End, make the use of NPV difficult. The real option method is able to evaluate the value added by flexibility of decision making by a company under conditions of uncertainty. The possibility of applying this method to the nuclear fuel cycle evaluation is studied. 

ATR Spent Fuel Options Study

International Nuclear Information System (INIS)

Connolly, Michael James; Bean, Thomas E.; Brower, Jeffrey O.; Luke, Dale E.; Patterson, M. W.; Robb, Alan K.; Sindelar, Robert; Smith, Rebecca E.; Tonc, Vincent F.; Tripp, Julia L.; Winston, Philip L.

2017-01-01

The Advanced Test Reactor (ATR) is a materials and fuels test nuclear reactor that performs irradiation services for the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE), Naval Reactors, the National Nuclear Security Administration (NNSA), and other research programs. ATR achieved initial criticality in 1967 and is expected to operate in support of needed missions until the year 2050 or beyond. It is anticipated that ATR will generate approximately 105 spent nuclear fuel (SNF) elements per year through the year 2050. Idaho National Laboratory (INL) currently stores 2,008 ATR SNF elements in dry storage, 976 in wet storage, and expects to have 1,000 elements in wet storage before January 2017. A capability gap exists at INL for long-term (greater than the year 2050) management, in compliance with the Idaho Settlement Agreement (ISA), of ATR SNF until a monitored retrievable geological repository is open. INL has significant wet and dry storage capabilities that are owned by the DOE Office of Environmental Management (EM) and operated and managed by Fluor Idaho, which include the Idaho Nuclear Technology and Engineering Center's (INTEC's) CPP-666, CPP-749, and CPP-603. In addition, INL has other capabilities owned by DOE-NE and operated and managed by Battelle Energy Alliance, LLC (BEA), which are located at the Materials and Fuel Complex (MFC). Additional storage capabilities are located on the INL Site at the Naval Reactors Facility (NRF). Current INL SNF management planning, as defined in the Fluor Idaho contract, shows INTEC dry fuel storage, which is currently used for ATR SNF, will be nearly full after transfer of an additional 1,000 ATR SNF from wet storage. DOE-NE tasked BEA with identifying and analyzing options that have the potential to fulfill this capability gap. BEA assembled a team comprised of SNF management experts from Fluor Idaho, Savannah River Site (SRS), INL/BEA, and the MITRE Corp with an objective of developing and analyzing

ATR Spent Fuel Options Study

Energy Technology Data Exchange (ETDEWEB)

Connolly, Michael James [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bean, Thomas E. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Brower, Jeffrey O. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Luke, Dale E. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Patterson, M. W. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Robb, Alan K. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sindelar, Robert [Idaho National Lab. (INL), Idaho Falls, ID (United States); Smith, Rebecca E. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Tonc, Vincent F. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Tripp, Julia L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Winston, Philip L. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2017-01-01

The Advanced Test Reactor (ATR) is a materials and fuels test nuclear reactor that performs irradiation services for the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE), Naval Reactors, the National Nuclear Security Administration (NNSA), and other research programs. ATR achieved initial criticality in 1967 and is expected to operate in support of needed missions until the year 2050 or beyond. It is anticipated that ATR will generate approximately 105 spent nuclear fuel (SNF) elements per year through the year 2050. Idaho National Laboratory (INL) currently stores 2,008 ATR SNF elements in dry storage, 976 in wet storage, and expects to have 1,000 elements in wet storage before January 2017. A capability gap exists at INL for long-term (greater than the year 2050) management, in compliance with the Idaho Settlement Agreement (ISA), of ATR SNF until a monitored retrievable geological repository is open. INL has significant wet and dry storage capabilities that are owned by the DOE Office of Environmental Management (EM) and operated and managed by Fluor Idaho, which include the Idaho Nuclear Technology and Engineering Center’s (INTEC’s) CPP-666, CPP-749, and CPP-603. In addition, INL has other capabilities owned by DOE-NE and operated and managed by Battelle Energy Alliance, LLC (BEA), which are located at the Materials and Fuel Complex (MFC). Additional storage capabilities are located on the INL Site at the Naval Reactors Facility (NRF). Current INL SNF management planning, as defined in the Fluor Idaho contract, shows INTEC dry fuel storage, which is currently used for ATR SNF, will be nearly full after transfer of an additional 1,000 ATR SNF from wet storage. DOE-NE tasked BEA with identifying and analyzing options that have the potential to fulfill this capability gap. BEA assembled a team comprised of SNF management experts from Fluor Idaho, Savannah River Site (SRS), INL/BEA, and the MITRE Corp with an objective of developing and analyzing

Development of a financing model for nuclear fuel cycle cost evaluation

International Nuclear Information System (INIS)

Takahashi, Makoto; Yajima, Masayuki

1984-01-01

It is necessary to evaluate the prices of nuclear fuel pre- and post-processing in order to analyse the costs of the nuclear power generation. Those prices are directly related to the costs of construction and operation of facilities in the nuclear fuel cycle. In this report, we propose a model which evaluates financing of an undertaking that constructs and operates one of the facilities such as uranium enrichment, reprocessing or interim storage of spent fuels. The model is divided into two phases, the construction phase and the operation phase. In the construction phase, it calculates expenses during the facility construction and corresponding financings for each term. In the operation phase, the model refers to the results of the construction phase and performs calculations on profits and losses, cash-flow, and disposition to profits term by according to a certain operation schedule. Using this model, feasibility of the undertaking and effects of various pricing strategies on the nuclear fuel costs can be evaluated by simulations. (author)

Future trends of light-water reactor fuel-cycle costs

International Nuclear Information System (INIS)

Tamiya, S.; Otomo, T.; Meguro, T.

1977-01-01

In past cost estimates, the main fuel-cycle components were mining and milling, uranium enrichment and fuel fabrication, and the reprocessing charge deemed to be recovered by plutonium credit. Since the oil crisis, all costs of fuel-cycle components have increased as well as construction costs of power stations. Recent analysis shows that costs in the back-end of the fuel cycle are much higher than those anticipated several years ago, although their contribution to the nuclear electricity generating cost would be small. This situation has now changed but there are still many uncertainties, i.e. regulatory requirements for reprocessing plants concerning safety, safeguards, environmental protection and high-level waste management. Thus it is more difficult to estimate overall investments and, therefore, the costs of the back-end of the fuel-cycle sector. This paper reviews the future trend of nuclear fuel-cycle costs of LWRs, based on recent analysis; and those factors which affect fuel-cycle costs are discussed. To reduce the uncertainties of the cost estimates as soon as possible, international discussion is necessary on items such as the treatment and disposal of high-level radioactive wastes, siting reprocessing plants, physical protection of plutonium, and the effects of plutonium on the environment. (author)

Cost related sensitivity analysis for optimal operation of a grid-parallel PEM fuel cell power plant

Science.gov (United States)

El-Sharkh, M. Y.; Tanrioven, M.; Rahman, A.; Alam, M. S.

Fuel cell power plants (FCPP) as a combined source of heat, power and hydrogen (CHP&H) can be considered as a potential option to supply both thermal and electrical loads. Hydrogen produced from the FCPP can be stored for future use of the FCPP or can be sold for profit. In such a system, tariff rates for purchasing or selling electricity, the fuel cost for the FCPP/thermal load, and hydrogen selling price are the main factors that affect the operational strategy. This paper presents a hybrid evolutionary programming and Hill-Climbing based approach to evaluate the impact of change of the above mentioned cost parameters on the optimal operational strategy of the FCPP. The optimal operational strategy of the FCPP for different tariffs is achieved through the estimation of the following: hourly generated power, the amount of thermal power recovered, power trade with the local grid, and the quantity of hydrogen that can be produced. Results show the importance of optimizing system cost parameters in order to minimize overall operating cost.

Global warming response options in Brazil's forest sector: comparison of project-level costs and benefits

International Nuclear Information System (INIS)

Fearnside, P.M.

1995-01-01

A project-level assessment of monetary and carbon costs and benefits for five classes of global warming response options in the forest sector is attempted for typical Brazilian conditions. Options considered are: silvicultural plantations (for pulp, charcoal and sawlogs), sustainable timber management and reduction of deforestation. Comparison of pulpwood and sawlog plantations with the vegetation characteristic of deforested areas indicates of modest carbon benefit. Plantations for charcoal can produce a substantial carbon benefit through fossil fuel substitution, but much of this calculated benefit disappears if discount rates greater than zero are applied to carbon. Sustainable timber management, when compared with existing forest, represents a net carbon loss, accumulation of carbon in wood products being insufficient to compensate for biomass reduction over a 100 year time scale. Reduction of deforestation has great potential as a global warming response option, its per-hectare carbon benefits being approximately four times that of silvicultural plantation establishment for pulp and sawlogs over a 100 year period. The costs of reducing deforestation are difficult to assess, however, due to the importance of government policy changes such as removal of land speculation and land tenure establishment as motives for clearing. Although these changes would not cost money and would have tremendous carbon and other benefits, they have not yet occurred. (Author)

FIA BioSum: a tool to evaluate financial costs, opportunities and effectiveness of fuel treatments.

Science.gov (United States)

Jeremy Fried; Glenn. Christensen

2004-01-01

FIA BioSum, a tool developed by the USDA Forest Services Forest Inventory and Analysis (FIA) Program, generates reliable cost estimates, identifies opportunities and evaluates the effectiveness of fuel treatments in forested landscapes. BioSum is an analytic framework that integrates a suite of widely used computer models with a foundation of attribute-rich,...

The importance of vehicle costs, fuel prices, and fuel efficiency to HEV market success.

Energy Technology Data Exchange (ETDEWEB)

Santini, D. J.; Patterson, P. D.; Vyas, A. D.

1999-12-08

Toyota's introduction of a hybrid electric vehicle (HEV) named ''Prius'' in Japan and Honda's proposed introduction of an HEV in the United States have generated considerable interest in the long-term viability of such fuel-efficient vehicles. A performance and cost projection model developed entirely at Argonne National Laboratory (ANL) is used here to estimate costs. ANL staff developed fuel economy estimates by extending conventional vehicle (CV) modeling done primarily under the National Cooperative Highway Research Program. Together, these estimates are employed to analyze dollar costs vs. benefits of two of many possible HEV technologies. We project incremental costs and fuel savings for a Prius-type low-performance hybrid (14.3 seconds zero to 60 mph acceleration, 260 time) and a higher-performance ''mild'' hybrid vehicle, or MHV (11 seconds 260 time). Each HEV is compared to a U.S. Toyota Corolla with automatic transmission (11 seconds 260 time). The base incremental retail price range, projected a decade hence, is $3,200-$3,750, before considering battery replacement cost. Historical data are analyzed to evaluate the effect of fuel price on consumer preferences for vehicle fuel economy, performance, and size. The relationship between fuel price, the level of change in fuel price, and consumer attitude toward higher fuel efficiency is also evaluated. A recent survey on the value of higher fuel efficiency is presented and U.S. commercial viability of the hybrids is evaluated using discount rates of 2090 and 870. Our analysis, with our current HEV cost estimates and current fuel savings estimates, implies that the U.S. market for such HEVS would be quite limited.

Parametric analyses of single-zone thorium-fueled molten salt reactor fuel cycle options

International Nuclear Information System (INIS)

Powers, J.J.; Worrall, A.; Gehin, J.C.; Harrison, T.J.; Sunny, E.E.

2013-01-01

Analyses of fuel cycle options based on thorium-fueled Molten Salt Reactors (MSRs) have been performed in support of fuel cycle screening and evaluation activities for the United States Department of Energy. The MSR options considered are based on thermal spectrum MSRs with 3 different separations levels: full recycling, limited recycling, and 'once-through' operation without active separations. A single-fluid, single-zone 2250 MWth (1000 MWe) MSR concept consisting of a fuel-bearing molten salt with graphite moderator and reflectors was used as the basis for this study. Radiation transport and isotopic depletion calculations were performed using SCALE 6.1 with ENDF/B-VII nuclear data. New methodology developed at Oak Ridge National Laboratory (ORNL) enables MSR analysis using SCALE, modeling material feed and removal by taking user-specified parameters and performing multiple SCALE/TRITON simulations to determine the resulting equilibrium operating conditions. Parametric analyses examined the sensitivity of the performance of a thorium MSR to variations in the separations efficiency for protactinium and fission products. Results indicate that self-sustained operation is possible with full or limited recycling but once-through operation would require an external neutron source. (authors)

Fuel Transfer Cask; Procedure Option and Radiation Protection during Transferring the Spent Fuel

International Nuclear Information System (INIS)

Muhammad Khairul Ariff Mustafa; Nurhayati Ramli; Ahmad Nabil Abdul Rahim; Mohd Fazli Zakaria

2011-01-01

Reactor TRIGA PUSPATI (RTP) has been operating almost 30 years. Many components are ageing. Nuclear Malaysia has taken an initiative to manage this ageing problem to prolong the life of the reactor. Hence, reactor upgrading project already commence started with the reactor console. To upgrade the core, all the fuel must be taken out from the core. A conceptual design of fuel transfer cask already done. This paper will discuss about the option of safe working procedure for transferring the fuel to the spent fuel pool for temporary. Hence, radiation protection for operator should be considered during the process. (author)

Low-cost storage options for solar hydrogen systems for remote area power supply

International Nuclear Information System (INIS)

Suhaib Muhammad Ali; John Andrews

2006-01-01

Equipment for storing hydrogen gas under pressure typically accounts for a significant proportion of the total capital cost of solar-hydrogen systems for remote area power supply (RAPS). RAPS remain a potential early market for renewable energy - hydrogen systems because of the relatively high costs of conventional energy sources in remote regions. In the present paper the storage requirements of PV-based solar-hydrogen RAPS systems employing PEM electrolysers and fuel cells to meet a range of typical remote area daily and annual demand profiles are investigated using a spread sheet-based simulation model. It is found that as the costs of storage are lowered the requirement for longer-term storage from summer to winter is increased with consequent potential gains in the overall economics of the solar-hydrogen system. In many remote applications, there is ample space for hydrogen storages with relatively large volumes. Hence it may be most cost-effective to store hydrogen at low to medium pressures achievable by using PEM electrolysers directly to generate the hydrogen at the pressures required, without a requirement for separate electrically-driven compressors. The latter add to system costs while requiring significant parasitic electricity consumption. Experimental investigations into a number of low-cost storage options including plastic tanks and low-to-medium pressure metal and composite cylinders are reported. On the basis of these findings, the economics of solar-hydrogen RAPS systems employing large-volume low-cost storage are investigated. (authors)

Nonintravenous rescue medications for pediatric status epilepticus: A cost-effectiveness analysis.

Science.gov (United States)

Sánchez Fernández, Iván; Gaínza-Lein, Marina; Loddenkemper, Tobias

2017-08-01

To quantify the cost-effectiveness of rescue medications for pediatric status epilepticus: rectal diazepam, nasal midazolam, buccal midazolam, intramuscular midazolam, and nasal lorazepam. Decision analysis model populated with effectiveness data from the literature and cost data from publicly available market prices. The primary outcome was cost per seizure stopped ($/SS). One-way sensitivity analyses and second-order Monte Carlo simulations evaluated the robustness of the results across wide variations of the input parameters. The most cost-effective rescue medication was buccal midazolam (incremental cost-effectiveness ratio ([ICER]: $13.16/SS) followed by nasal midazolam (ICER: $38.19/SS). Nasal lorazepam (ICER: -$3.8/SS), intramuscular midazolam (ICER: -$64/SS), and rectal diazepam (ICER: -$2,246.21/SS) are never more cost-effective than the other options at any willingness to pay. One-way sensitivity analysis showed the following: (1) at its current effectiveness, rectal diazepam would become the most cost-effective option only if its cost was $6 or less, and (2) at its current cost, rectal diazepam would become the most cost-effective option only if effectiveness was higher than 0.89 (and only with very high willingness to pay of $2,859/SS to $31,447/SS). Second-order Monte Carlo simulations showed the following: (1) nasal midazolam and intramuscular midazolam were the more effective options; (2) the more cost-effective option was buccal midazolam for a willingness to pay from $14/SS to $41/SS and nasal midazolam for a willingness to pay above $41/SS; (3) cost-effectiveness overlapped for buccal midazolam, nasal lorazepam, intramuscular midazolam, and nasal midazolam; and (4) rectal diazepam was not cost-effective at any willingness to pay, and this conclusion remained extremely robust to wide variations of the input parameters. For pediatric status epilepticus, buccal midazolam and nasal midazolam are the most cost-effective nonintravenous rescue

Impact of Nuclear Energy Futures on Advanced Fuel Cycle Options

International Nuclear Information System (INIS)

Brent W. Dixon; Steven J. Piet

2004-01-01

The Nuclear Waste Policy Act requires the Secretary of Energy to inform Congress before 2010 on the need for a second geologic repository for spent nuclear fuel. By that time, the spent fuel discharged from current commercial reactors will exceed the statutory limit of the first repository (63,000 MTiHM commercial, 7,000 MT non-commercial). There are several approaches to eliminate the need for another repository in this century. This paper presents a high-level analysis of these spent fuel management options in the context of a full range of possible nuclear energy futures. The analysis indicates the best option to implement varies depending on the nuclear energy future selected. The first step in understanding the need for different spent fuel management approaches is to understand the size of potential spent fuel inventories. A full range of potential futures for domestic commercial nuclear energy is considered. These energy futures are as follows: 1. Existing License Completion - Based on existing spent fuel inventories plus extrapolation of future plant-by-plant discharges until the end of each operating license, including known license extensions. 2. Extended License Completion - Based on existing spent fuel inventories plus a plant-by-plant extrapolation of future discharges assuming on all operating plants having one 20-year extension. 3. Continuing Level Energy Generation - Based on extension of the current ∼100 GWe installed commercial base and average spent fuel discharge of 2100 MT/yr through the year 2100. 4. Continuing Market Share Generation - Based on a 1.8% compounded growth of the electricity market through the year 2100, matched by growing nuclear capacity and associated spent fuel discharge. 5. Growing Market Share Generation - Extension of current nuclear capacity and associated spent fuel discharge through 2100 with 3.2% growth representing 1.5% market growth (all energy, not just electricity) and 1.7% share growth. Share growth results in

Cost-effective climate policy in a small country

International Nuclear Information System (INIS)

Hagem, C.

1994-01-01

Unilateral action to curb CO 2 emissions in a small country or a group of countries has only a limited effect on global CO 2 emissions. However, it could be a first step toward a broader climate treaty. So far, unilateral commitments have been aimed at reducing national consumption of fossil fuels. A country that produces and consumes fossil fuels can also infiuence the global CO 2 emissions by reducing its production. The estimated cost of reducing national CO 2 emissions in Norway, through a reduction infossil fuel consumption, is presented in a report from the Environmental Tax Committee (1992). In this paper, that cost is compared with an estimated cost of reducing fossil fuel production. The calculation reveals that it could be less costly to reduce the production than the consumption, given that the effect on global CO 2 emissions is identical. 23 refs., 4 tabs

Integration of the AVLIS (atomic vapor laser isotopic separation) process into the nuclear fuel cycle. [Effect of AVLIS feed requirements on overall fuel cycle

Energy Technology Data Exchange (ETDEWEB)

Hargrove, R.S.; Knighton, J.B.; Eby, R.S.; Pashley, J.H.; Norman, R.E.

1986-08-01

AVLIS RD and D efforts are currently proceeding toward full-scale integrated enrichment demonstrations in the late 1980's and potential plant deployment in the mid 1990's. Since AVLIS requires a uranium metal feed and produces an enriched uranium metal product, some change in current uranium processing practices are necessitated. AVLIS could operate with a UF/sub 6/-in UF/sub 6/-out interface with little effect to the remainder of the fuel cycle. This path, however, does not allow electric utility customers to realize the full potential of low cost AVLIS enrichment. Several alternative processing methods have been identified and evaluated which appear to provide opportunities to make substantial cost savings in the overall fuel cycle. These alternatives involve varying levels of RD and D resources, calendar time, and technical risk to implement and provide these cost reduction opportunities. Both feed conversion contracts and fuel fabricator contracts are long-term entities. Because of these factors, it is not too early to start planning and making decisions on the most advantageous options so that AVLIS can be integrated cost effectively into the fuel cycle. This should offer economic opportunity to all parties involved including DOE, utilities, feed converters, and fuel fabricators. 10 refs., 11 figs., 2 tabs.

Financing Strategies For A Nuclear Fuel Cycle Facility

International Nuclear Information System (INIS)

David Shropshire; Sharon Chandler

2006-01-01

To help meet the nation's energy needs, recycling of partially used nuclear fuel is required to close the nuclear fuel cycle, but implementing this step will require considerable investment. This report evaluates financing scenarios for integrating recycling facilities into the nuclear fuel cycle. A range of options from fully government owned to fully private owned were evaluated using DPL (Decision Programming Language 6.0), which can systematically optimize outcomes based on user-defined criteria (e.g., lowest lifecycle cost, lowest unit cost). This evaluation concludes that the lowest unit costs and lifetime costs are found for a fully government-owned financing strategy, due to government forgiveness of debt as sunk costs. However, this does not mean that the facilities should necessarily be constructed and operated by the government. The costs for hybrid combinations of public and private (commercial) financed options can compete under some circumstances with the costs of the government option. This analysis shows that commercial operations have potential to be economical, but there is presently no incentive for private industry involvement. The Nuclear Waste Policy Act (NWPA) currently establishes government ownership of partially used commercial nuclear fuel. In addition, the recently announced Global Nuclear Energy Partnership (GNEP) suggests fuels from several countries will be recycled in the United States as part of an international governmental agreement; this also assumes government ownership. Overwhelmingly, uncertainty in annual facility capacity led to the greatest variations in unit costs necessary for recovery of operating and capital expenditures; the ability to determine annual capacity will be a driving factor in setting unit costs. For private ventures, the costs of capital, especially equity interest rates, dominate the balance sheet; and the annual operating costs, forgiveness of debt, and overnight costs dominate the costs computed for the

Cost-effectiveness of public-health policy options in the presence of pretreatment NNRTI drug resistance in sub-Saharan Africa: a modelling study.

Science.gov (United States)

Phillips, Andrew N; Cambiano, Valentina; Nakagawa, Fumiyo; Revill, Paul; Jordan, Michael R; Hallett, Timothy B; Doherty, Meg; De Luca, Andrea; Lundgren, Jens D; Mhangara, Mutsa; Apollo, Tsitsi; Mellors, John; Nichols, Brooke; Parikh, Urvi; Pillay, Deenan; Rinke de Wit, Tobias; Sigaloff, Kim; Havlir, Diane; Kuritzkes, Daniel R; Pozniak, Anton; van de Vijver, David; Vitoria, Marco; Wainberg, Mark A; Raizes, Elliot; Bertagnolio, Silvia

2018-03-01

There is concern over increasing prevalence of non-nucleoside reverse-transcriptase inhibitor (NNRTI) resistance in people initiating antiretroviral therapy (ART) in low-income and middle-income countries. We assessed the effectiveness and cost-effectiveness of alternative public health responses in countries in sub-Saharan Africa where the prevalence of pretreatment drug resistance to NNRTIs is high. The HIV Synthesis Model is an individual-based simulation model of sexual HIV transmission, progression, and the effect of ART in adults, which is based on extensive published data sources and considers specific drugs and resistance mutations. We used this model to generate multiple setting scenarios mimicking those in sub-Saharan Africa and considered the prevalence of pretreatment NNRTI drug resistance in 2017. We then compared effectiveness and cost-effectiveness of alternative policy options. We took a 20 year time horizon, used a cost effectiveness threshold of US$500 per DALY averted, and discounted DALYs and costs at 3% per year. A transition to use of a dolutegravir as a first-line regimen in all new ART initiators is the option predicted to produce the most health benefits, resulting in a reduction of about 1 death per year per 100 people on ART over the next 20 years in a situation in which more than 10% of ART initiators have NNRTI resistance. The negative effect on population health of postponing the transition to dolutegravir increases substantially with higher prevalence of HIV drug resistance to NNRTI in ART initiators. Because of the reduced risk of resistance acquisition with dolutegravir-based regimens and reduced use of expensive second-line boosted protease inhibitor regimens, this policy option is also predicted to lead to a reduction of overall programme cost. A future transition from first-line regimens containing efavirenz to regimens containing dolutegravir formulations in adult ART initiators is predicted to be effective and cost-effective in

Assessment of Startup Fuel Options for the GNEP Advanced Burner Reactor (ABR)

Energy Technology Data Exchange (ETDEWEB)

Jon Carmack (062056); Kemal O. Pasamehmetoglu (103171); David Alberstein

2008-02-01

The Global Nuclear Energy Program (GNEP) includes a program element for the development and construction of an advanced sodium cooled fast reactor to demonstrate the burning (transmutation) of significant quantities of minor actinides obtained from a separations process and fabricated into a transuranic bearing fuel assembly. To demonstrate and qualify transuranic (TRU) fuel in a fast reactor, an Advanced Burner Reactor (ABR) prototype is needed. The ABR would necessarily be started up using conventional metal alloy or oxide (U or U, Pu) fuel. Startup fuel is needed for the ABR for the first 2 to 4 core loads of fuel in the ABR. Following start up, a series of advanced TRU bearing fuel assemblies will be irradiated in qualification lead test assemblies in the ABR. There are multiple options for this startup fuel. This report provides a description of the possible startup fuel options as well as possible fabrication alternatives available to the program in the current domestic and international facilities and infrastructure.

Assessment of Used Nuclear Fuel Inventory Relative to Disposition Options

International Nuclear Information System (INIS)

Wagner, John C.; Peterson, Joshua L.; Mueller, Don; Gehin, Jess C.; Worrall, Andrew; Taiwo, Temitope; Nutt, Mark; Williamson, Mark A.; Todosow, Mike; Wigeland, Roald; Halsey, William; Omberg, Ronald; Swift, Peter; Carter, Joe

2013-01-01

This paper presents a technical assessment of the current inventory [∼70,150 metric tons of heavy metal (MTHM) as of 2011] of U.S.-discharged used nuclear fuel (UNF) to support decisions regarding fuel cycle strategies and research, development and demonstration (RD and D) needs. The assessment considered discharged UNF from commercial nuclear electricity generation and defense and research programs and determined that the current UNF inventory can be divided into the following three categories: 1. Disposal - excess material that is not needed for other purposes; 2. Research - material needed for RD and D purposes to support waste management (e.g., UNF storage, transportation, and disposal) and development of alternative fuel cycles (e.g., separations and advanced fuels/reactors); and 3. Recycle/Recovery - material with inherent and/or strategic value. A set of key assumptions and attributes relative to the disposition options was used to categorize the current UNF inventory. Based on consideration of RD and D needs, time frames and material needs for deployment of alternative fuel cycles, characteristics of the current UNF inventory, and possible uses to support national security interests, it was determined that the vast majority of the category, without the need for retrieval for reuse or research purposes. Access to the material in the Research and Recycle/Recovery categories should be retained to support RD and D needs and national security interests. This assessment does not assume any decision about future fuel cycle options or preclude any potential options, including those with potential recycling of commercial UNF, since the ∼2,000 MTHM that is generated annually could provide the feedstock needed for deployment of alternative fuel cycles.

Health and safety of competing fuel options for fuel cells in the road transport sector

Energy Technology Data Exchange (ETDEWEB)

Green, E.; Short, S.; Stutt, E.; Wickramatillake, H.; Harrison, P.

2000-07-01

This report presents a critical analysis of the health and safety issues surrounding competing transport fuel options, including those for possible future fuel-cell powered vehicles. The fuels considered in this report are gasoline (unleaded and reformulated), diesel, hydrogen (H{sub 2}), methanol, natural gas and liquefied petroleum gas (LPG). The analysis presented here is based on available information in peer-reviewed, published papers and other sources such as government department or research laboratory reports and websites. An overall evaluation of the fuels in terms of their toxicity and health effects, environmental fate, and fire and explosion safety aspects is presented. The report is based on current knowledge and makes no assumptions as to how fuels may change in the future if they are to be used in fuel-cell vehicles. The report identifies the hazards of the fuels but does not estimate the risks likely to be associated with their eventual use in fuel-cell vehicles. The focus is on the fuels themselves and not their exhaust or reaction products. sNo assessment has been made of the environmental effects data for the fuels. Broad environmental considerations such as ozone forming potential and also global warming are not considered. Basic information on environmental fate is included to provide an understanding of migratory pathways, environmental compartmentalisation and potential routes of human exposure. Other factors such as economics, government incentives or disincentives and public attitudes may have a bearing on which of the fuels are considered most appropriate for future fuel-cell vehicles; these factors are not considered in any detail in this report. (Author)

Analysis of Technology Options to Reduce the Fuel Consumption of Idling Trucks; FINAL

International Nuclear Information System (INIS)

Stodolsky, F.; Gaines, L.; Vyas, A.

2000-01-01

Long-haul trucks idling overnight consume more than 838 million gallons (20 million barrels) of fuel annually. Idling also emits pollutants. Truck drivers idle their engines primarily to (1) heat or cool the cab and/or sleeper, (2) keep the fuel warm in winter, and (3) keep the engine warm in the winter so that the engine is easier to start. Alternatives to overnight idling could save much of this fuel, reduce emissions, and cut operating costs. Several fuel-efficient alternatives to idling are available to provide heating and cooling: (1) direct-fired heater for cab/sleeper heating, with or without storage cooling; (2) auxiliary power units; and (3) truck stop electrification. Many of these technologies have drawbacks that limit market acceptance. Options that supply electricity are economically viable for trucks that are idled for 1,000-3,000 or more hours a year, while heater units could be used across the board. Payback times for fleets, which would receive quantity discounts on the prices, would be somewhat shorter

Shungnak Energy Configuration Options.

Energy Technology Data Exchange (ETDEWEB)

Rosewater, David Martin [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Eddy, John P. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-10-01

Power systems in rural Alaska villages face a unique combination of challenges that can increase the cost of energy and lowers energy supply reliability. In the case of the remote village of Shungnak, diesel and heating fuel is either shipped in by barge or flown in by aircraft. This report presents a technical analysis of several energy infrastructure upgrade and modification options to reduce the amount of fuel consumed by the community of Shungnak. Reducing fuel usage saves money and makes the village more resilient to disruptions in fuel supply. The analysis considers demand side options, such as energy efficiency, alongside the installation of wind and solar power generation options. Some novel approaches are also considered including battery energy storage and the use of electrical home heating stoves powered by renewable generation that would otherwise be spilled and wasted. This report concludes with specific recommendations for Shungnak based on economic factors, and fuel price sensitivity. General conclusions are also included to support future work analyzing similar energy challenges in remote arctic regions.

Fuel options for public bus fleets in Sweden

OpenAIRE

Xylia, Maria; Silveira, Semida

2015-01-01

The Swedish public transport sector has defined two major targets, i.e., to run 90% of the total vehicle kilometers of the fleet on non-fossil fuels and double the volume of travel via public transport by 2020, increasing the share of public transport in relation to the total personal transport in the country . The f3 report Fuel options for public bus fleets in Sweden highlights the challenges and solutions encountered, particularly when it comes to the adoption of renewable fuels in the reg...

Energy balance and GHG-abatement cost of cassava utilization for fuel ethanol in Thailand

International Nuclear Information System (INIS)

Nguyen, Thu Lan Thi; Gheewala, Shabbir H.; Garivait, Savitri

2007-01-01

Since 2001, in order to enhance ethanol's cost competitiveness with gasoline, the Thai government has approved the exemption of excise tax imposed on ethanol, controlling the retail price of gasohol (a mixture of ethanol and gasoline at a ratio of 1:9) to be less than that of octane 95 gasoline, within a range not exceeding 1.5 baht a litre. The policy to promote ethanol for transport is being supported by its positive effects on energy security and climate change mitigation. An analysis of energy, greenhouse gas (GHG) balances and GHG abatement cost was done to evaluate fuel ethanol produced from cassava in Thailand. Positive energy balance of 22.4 MJ/L and net avoided GHG emission of 1.6 kg CO 2 eq./L found for cassava-based ethanol (CE) proved that it would be a good substitute for gasoline, effective in fossil energy saving and GHG reduction. With a GHG abatement cost of US$99 per tonne of CO 2 , CE is rather less cost effective than the many other climate strategies relevant to Thailand in the short term. Opportunities for improvements are discussed to make CE a reasonable option for national climate policy

Cost Effectiveness of a Weight Management Program Implemented in the Worksite: Translation of Fuel Your Life.

Science.gov (United States)

Corso, Phaedra S; Ingels, Justin B; Padilla, Heather M; Zuercher, Heather; DeJoy, David M; Vandenberg, Robert J; Wilson, Mark G

2018-04-18

Conduct a cost-effectiveness analysis of the Fuel Your Life (FYL) program dissemination. Employees were recruited from three workplaces randomly assigned to one of the conditions: telephone coaching, small group coaching, and self-study. Costs were collected prospectively during the efficacy trial. The main outcome measures of interest were weight loss and quality-adjusted life years (QALYs). The phone condition was most costly ($601-$589/employee) and the self-study condition was least costly ($145-$143/employee). For weight loss, delivering FYL through the small group condition was no more effective, yet more expensive, than the self-study delivery. For QALYs, the group delivery of FYL was in an acceptable cost-effectiveness range ($22,400/QALY) relative to self-study (95% CI: $10,600/QALY - dominated). Prevention programs require adaptation at the local level and significantly affect the cost, effectiveness, and cost effectiveness of the program.This is an open access article distributed under the terms of the Creative Commons Attribution-Non Commercial-No Derivatives License 4.0 (CCBY-NC-ND), where it is permissible to download and share the work provided it is properly cited. The work cannot be changed in any way or used commercially without permission from the journal. http://creativecommons.org/licenses/by-nc-nd/4.0.

Compatibility analysis of DUPIC fuel (part5) - DUPIC fuel cycle economics analysis

Energy Technology Data Exchange (ETDEWEB)

Ko, Won Il; Choi, Hang Bok; Yang, Myung Seung

2000-08-01

This study examines the economics of the DUPIC fuel cycle using unit costs of fuel cycle components estimated based on conceptual designs. The fuel cycle cost (FCC) was calculated by a deterministic method in which reference values of fuel cycle components are used. The FCC was then analyzed by a Monte Carlo simulation to get the uncertainty of the FCC associated with the unit costs of the fuel cycle components. From the deterministic analysis on the one-batch equilibrium fuel cycle model, the DUPIC FCC was estimated to be 6.55-6.72 mills/kWh for proposed DUPIC fuel options, which is a little smaller than that of the once-through FCC by 0.04-0.28 mills/kWh. Considering the uncertainty (0.45-0.51 mills/kWh) of the FCC estimated by the Monte Carlo simulation method, the cost difference between the DUPIC and once-through fuel cycle is negligible. On the other hand, the material balance calculation has shown that the DUPIC fuel cycle can save natural uranium resources by -20% and reduce the spent fuel arising by -65%, compared with the once-through fuel cycle. In conclusion, the DUPIC fuel cycle possesses a strong advantage over the once-through fuel cycle from the viewpoint of the environmental effect.

Compatibility analysis of DUPIC fuel (part5) - DUPIC fuel cycle economics analysis

International Nuclear Information System (INIS)

Ko, Won Il; Choi, Hang Bok; Yang, Myung Seung

2000-08-01

This study examines the economics of the DUPIC fuel cycle using unit costs of fuel cycle components estimated based on conceptual designs. The fuel cycle cost (FCC) was calculated by a deterministic method in which reference values of fuel cycle components are used. The FCC was then analyzed by a Monte Carlo simulation to get the uncertainty of the FCC associated with the unit costs of the fuel cycle components. From the deterministic analysis on the one-batch equilibrium fuel cycle model, the DUPIC FCC was estimated to be 6.55-6.72 mills/kWh for proposed DUPIC fuel options, which is a little smaller than that of the once-through FCC by 0.04-0.28 mills/kWh. Considering the uncertainty (0.45-0.51 mills/kWh) of the FCC estimated by the Monte Carlo simulation method, the cost difference between the DUPIC and once-through fuel cycle is negligible. On the other hand, the material balance calculation has shown that the DUPIC fuel cycle can save natural uranium resources by -20% and reduce the spent fuel arising by -65%, compared with the once-through fuel cycle. In conclusion, the DUPIC fuel cycle possesses a strong advantage over the once-through fuel cycle from the viewpoint of the environmental effect

Economics of spent LWR fuel storage

International Nuclear Information System (INIS)

Clark, H.J.

1980-01-01

A low cost option for spent fuel inventories would be to ship excess fuel from the overburdened reactor to another reactor in the utility's system that has available space. The only cost would be for cask leasing and shipping. Three other alternatives all require considerable capital expenditures: reracking, new at-reactor (AR) storage facilities, and away-from-reactor (AFR) storage facilities. Fuel storage requirements will be met best by transfer of fuel or by re-racking existing reactor basins whenever these options are available. These alternatives represent not only the lowest cost storage options but also the most timely. Fuel can be shipped to other storage pools for about $10/kg depending on the distance, while costs for reracking range from $18 to 25/kg depending on the approach. These alternatives are recognized to face environmental and regulatory obstacles. However, such obstacles should be less severe than similar issues that would be encountered with AR or AFR basin storage. When storage requirements cannot be met by the first two options, the next least costly alternative for most utilities will be use of a Federal AFR. Storage cost of about $137/kg at an AFR are less costly than charges of up to $350/kg that could be incurred by the use of AR basins. AR basins are practical only when a utility requires storage capacity to accommodate annual additions of 100 MT or more of spent fuel. The large reactor complexes discharging this much feul are not currently those that require relief from fuel storage problems. A recent development in Germany may offer an AR alternative of dry storage in transportation/storage casks at a cost of $200/kg; however, this method has not yet been accepted and licensed for use in the US

Options for the interim storage of spent fuel

International Nuclear Information System (INIS)

Kromar, M.; Kurincic, B.

1995-01-01

Different concepts for the interim storage of spent fuel arising from operation of a NPP are discussed. We considered at reactor as well as away from reactor storage options. Included are enhancements of existing storage capabilities and construction of a new wet or dry storage facility. (author)

Cost benefit analysis cost effectiveness analysis

International Nuclear Information System (INIS)

Lombard, J.

1986-09-01

The comparison of various protection options in order to determine which is the best compromise between cost of protection and residual risk is the purpose of the ALARA procedure. The use of decision-aiding techniques is valuable as an aid to selection procedures. The purpose of this study is to introduce two rather simple and well known decision aiding techniques: the cost-effectiveness analysis and the cost-benefit analysis. These two techniques are relevant for the great part of ALARA decisions which need the use of a quantitative technique. The study is based on an hypothetical case of 10 protection options. Four methods are applied to the data

Fuel cycle options for light water reactors in Germany

International Nuclear Information System (INIS)

Broecking, D.; Mester, W.

1999-01-01

In Germany 19 nuclear power plants with an electrical output of 22 GWe are in operation. Annually about 450 t of spent fuel are unloaded from the reactors. Currently most of the spent fuel elements are shipped to France and the United Kingdom for reprocessing according to contracts which have been signed since the late 70es. By the amendment of the Atomic Energy Act in 1994 the previous priority for reprocessing of spent nuclear fuel was substituted by a legal equivalency of the reprocessing and direct disposal option. As a consequence some utilities take into consideration the direct disposal of their spent fuel for economical reasons. The separated plutonium will be recycled as MOX fuel in light water reactors. About 30 tons of fissile plutonium will be available to German utilities for recycling by the year 2000. Twelve German reactors are already licensed for the use of MOX fuel, five others have applied for MOX use. Eight reactors are currently using MOX fuel or used it in the past. The spent fuel elements which shall be disposed of without reprocessing will be stored in two interim dry storage facilities at Gorleben and Ahaus. The storage capacities are 3800 and 4200 tHM, respectively. The Gorleben salt dome is currently investigated to prove its suitability as a repository for high level radioactive waste, either in a vitrified form or as conditioned spent fuel. The future development of the nuclear fuel cycle and radioactive waste management depends on the future role of nuclear energy in Germany. According to estimations of the German utilities no additional nuclear power plants are needed in the near future. Around the middle of the next decade it will have to be decided whether existing plants should be substituted by new ones. For the foreseeable time German utilities are interested in a highly flexible approach to the nuclear fuel cycle and waste management keeping open both spent fuel management options: the closed fuel cycle and direct disposal of

The feasibility study I on the blanket fuel options for the ATW/HYPER

Energy Technology Data Exchange (ETDEWEB)

Hwang, Woan; Lee, Byoung Oon; Lee, Bong Sang; Park, Won Seok; Meyer, M.K; Hayes, S.L

2001-01-01

The choice of a blanket fuel cycle technology and the fuel type for HYPER/ATW are important to develop an ADS with better economics, performance and safety. Even though several fuel types have been considered as an alternative of the blanket fuels for HYPER/ATW, the metal alloy and the dispersion fuels were selected as the candidate fuels for ADS, and the technical feasibilities for both fuels are evaluated in this report. General performance characteristics, fabrication abilities, technical aspects, safety aspects, economics, and non-proliferation aspects for each fuel type are reviewed and evaluated. And some technological problems are addressed in this report, focused on the development strategy, the roadmaps, and the flexibility to meet the missions and specific designs. This study has been performed at the first stage of conceptual design. Since it is under the lack of physical properties for each fuel material, no an attempt is made to select the best fuel option, but the more better fuel options are recommended.

The feasibility study I on the blanket fuel options for the ATW/HYPER

International Nuclear Information System (INIS)

Hwang, Woan; Lee, Byoung Oon; Lee, Bong Sang; Park, Won Seok; Meyer, M.K; Hayes, S.L.

2001-01-01

The choice of a blanket fuel cycle technology and the fuel type for HYPER/ATW are important to develop an ADS with better economics, performance and safety. Even though several fuel types have been considered as an alternative of the blanket fuels for HYPER/ATW, the metal alloy and the dispersion fuels were selected as the candidate fuels for ADS, and the technical feasibilities for both fuels are evaluated in this report. General performance characteristics, fabrication abilities, technical aspects, safety aspects, economics, and non-proliferation aspects for each fuel type are reviewed and evaluated. And some technological problems are addressed in this report, focused on the development strategy, the roadmaps, and the flexibility to meet the missions and specific designs. This study has been performed at the first stage of conceptual design. Since it is under the lack of physical properties for each fuel material, no an attempt is made to select the best fuel option, but the more better fuel options are recommended

A comparative study on recycling spent fuels in gas-cooled fast reactors

International Nuclear Information System (INIS)

Choi, Hangbok; Baxter, Alan

2010-01-01

This study evaluates advanced Gas-cooled Fast Reactor (GFR) fuel cycle scenarios which are based on recycling spent nuclear fuel for the sustainability of nuclear energy. A 600 MWth GFR was used for the fuel cycle analysis, and the equilibrium core was searched with different fuel-to-matrix volume ratios such as 70/30 and 60/40. Two fuel cycle scenarios, i.e., a one-tier case combining a Light Water Reactor (LWR) and a GFR, and a two-tier case using an LWR, a Very High Temperature Reactor (VHTR), and a GFR, were evaluated for mass flow and fuel cycle cost, and the results were compared to those of LWR once-through fuel cycle. The mass flow calculations showed that the natural uranium consumption can be reduced by more than 57% and 27% for the one-tier and two-tier cycles, respectively, when compared to the once-through fuel cycle. The transuranics (TRU) which pose a long-term problem in a high-level waste repository, can be significantly reduced in the multiple recycle operation of these options, resulting in more than 110 and 220 times reduction of TRU inventory to be geologically disposed for the one-tier and two-tier fuel cycles, respectively. The fuel cycle costs were estimated to be 9.4 and 8.6 USD/MWh for the one-tier fuel cycle when the GFR fuel-to-matrix volume ratio was 70/30 and 60/40, respectively. However the fuel cycle cost is reduced to 7.3 and 7.1 USD/MWh for the two-tier fuel cycle, which is even smaller than that of the once-through fuel cycle. In conclusion the GFR can provide alternative fuel cycle options to the once-through and other fast reactor fuel cycle options, by increasing the natural uranium utilization and reducing the fuel cycle cost.

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

International Nuclear Information System (INIS)

Sousselier, Y.

1964-01-01

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

Spent Nuclear Fuel Option Study on Hybrid Reactor for Waste Transmutation

International Nuclear Information System (INIS)

Hong, Seong Hee; Kim, Myung Hyun

2016-01-01

DUPIC nuclear fuel can be used in hybrid reactor by compensation of subcritical level through (U-10Zr) fuel. Energy production performance of Hyb-WT with DUPIC is grateful because it has high EM factor and performs waste transmutation at the same time. However, waste transmutation performance should be improved by different fissile fuel instead of (U-10Zr) fuel. SNF (Spent Nuclear Fuel) disposal is one of the problems in the nuclear industry. FFHR (Fusion-Fission Hybrid Reactor) is one of the most attractive option on reuse of SNF as a waste transmutation system. Because subcritical system like FFHR has some advantages compared to critical system. Subcritical systems have higher safety potential than critical system. Also, there is suppressed excess reactivity at BOC (Beginning of Cycle) in critical system, on the other hand there is no suppressed reactivity in subcritical system. Our research team could have designed FFHR for waste transmutation; Hyb-WT. Various researches have been conducted on fuel and coolant option for optimization of transmutation performance. However, Hyb-WT has technical disadvantage. It is required fusion power (Pfus) which is the key design parameter in FFHR is increased for compensation of decreasing subcritical level. As a result, structure material integrity is damaged under high irradiation condition by increasing Pfus. Also, deep burn of reprocessed SNF is limited by weakened integrity of structure material. Therefore, in this research, SNF option study will be conducted on DUPIC (Direct Use of Spent PWR Fuel in CANDU Reactor) fuel, TRU fuel and DUPIC + TRU mixed fuel for optimization of Hyb-WT performance. Goal of this research is design check for low required fusion power and high waste transmutation. In this paper, neutronic analysis is conducted on Hyb-WT with DUPIC nuclear fuel. When DUPIC nuclear fuel is loaded in fast neutron system, supplement fissile materials need to be loaded together for compensation of low criticality

Spent Nuclear Fuel Option Study on Hybrid Reactor for Waste Transmutation

Energy Technology Data Exchange (ETDEWEB)

Hong, Seong Hee; Kim, Myung Hyun [Kyung Hee University, Yongin (Korea, Republic of)

2016-05-15

DUPIC nuclear fuel can be used in hybrid reactor by compensation of subcritical level through (U-10Zr) fuel. Energy production performance of Hyb-WT with DUPIC is grateful because it has high EM factor and performs waste transmutation at the same time. However, waste transmutation performance should be improved by different fissile fuel instead of (U-10Zr) fuel. SNF (Spent Nuclear Fuel) disposal is one of the problems in the nuclear industry. FFHR (Fusion-Fission Hybrid Reactor) is one of the most attractive option on reuse of SNF as a waste transmutation system. Because subcritical system like FFHR has some advantages compared to critical system. Subcritical systems have higher safety potential than critical system. Also, there is suppressed excess reactivity at BOC (Beginning of Cycle) in critical system, on the other hand there is no suppressed reactivity in subcritical system. Our research team could have designed FFHR for waste transmutation; Hyb-WT. Various researches have been conducted on fuel and coolant option for optimization of transmutation performance. However, Hyb-WT has technical disadvantage. It is required fusion power (Pfus) which is the key design parameter in FFHR is increased for compensation of decreasing subcritical level. As a result, structure material integrity is damaged under high irradiation condition by increasing Pfus. Also, deep burn of reprocessed SNF is limited by weakened integrity of structure material. Therefore, in this research, SNF option study will be conducted on DUPIC (Direct Use of Spent PWR Fuel in CANDU Reactor) fuel, TRU fuel and DUPIC + TRU mixed fuel for optimization of Hyb-WT performance. Goal of this research is design check for low required fusion power and high waste transmutation. In this paper, neutronic analysis is conducted on Hyb-WT with DUPIC nuclear fuel. When DUPIC nuclear fuel is loaded in fast neutron system, supplement fissile materials need to be loaded together for compensation of low criticality

MHR fuel cycle options for future sustainability of nuclear power

International Nuclear Information System (INIS)

Baxter, Alan; Venneri, Francesco; Rodriguez, Carmelo; Fikani, Michael

2005-01-01

The future sustainability of the nuclear option is not significantly tied to the level of resources. For example, current high quality uranium reserves (∼3.34x10 6 tons) are enough for more than 55 years at present consumption rates (IAEA estimate). Doubling of the present uranium ore price (∼$26/kg) could create about a tenfold increase in resources, providing more than 550 years of supply at present rates (World Nuclear Association estimate). There are also thorium reserves which are estimated to be about three times those of uranium, and would allow for a significant increase in annual consumption levels. The key to a sustainable nuclear future is really tied to the political and technical problems of long term waste disposal, and the perceived risks of nuclear weapons proliferation. Thus fuel cycle options for a sustainable nuclear future must address and solve these issues. High temperature, Gas-Cooled, Graphite Moderated, reactors (MHRs) have nuclear and operational characteristics to provide multiple fuel cycle options to solve these issues. Three fuel cycles for the MHD are described in this paper, and their capabilities for meeting a sustainable nuclear future in terms of nuclear waste minimization and destruction, and reduction of proliferation risk, are discussed. (author)

Technological options for acid rain control

International Nuclear Information System (INIS)

Princiotta, F.T.; Sedman, C.B.

1993-01-01

The paper discusses technological options for acid rain control. Compliance with Title IV of the Clean Air Act Amendments of 1990 will require careful scrutiny of a number of issues before selecting control options to reduce sulfur dioxide (SO2) and nitrogen oxide (NOx) emissions. One key consideration is the effect of fuel switching or control technology upon the existing dust collector, with additional air toxics legislation looming ahead. A number of likely SO2 and NOx retrofit technologies and estimated costs are presented, along with results of retrofit case studies. New hybrid particulate controls are also being developed to meet future requirements

Analysis of the equilibrium trip cost accounting for the fuel cost in a single-lane traffic system without late arrival

Science.gov (United States)

Tang, Tie-Qiao; Wang, Tao; Chen, Liang; Huang, Hai-Jun

2018-01-01

In this paper, we introduce the fuel cost into each commuter's trip cost, define a new trip cost without late arrival and its corresponding equilibrium state, and use a car-following model to explore the impacts of the fuel cost on each commuter's departure time, departure interval, arrival time, arrival interval, traveling time, early arrival time and trip cost at the above equilibrium state. The numerical results show that considering the fuel cost in each commuter's trip cost has positive impacts on his trip cost and fuel cost, and the traffic situation in the system without late arrival, i.e., each commuter should explicitly consider the fuel cost in his trip cost.

Fuel cycle cost analysis on molten-salt reactors

International Nuclear Information System (INIS)

Shimazu, Yoichiro

1976-01-01

An evaluation is made of the fuel cycle costs for molten-salt reactors (MSR's), developed at Oak Ridge National Laboratory. Eight combinations of conditions affecting fuel cycle costs are compared, covering 233 U-Th, 235 U-Th and 239 Pu-Th fuels, with and without on-site continuous fuel reprocessing. The resulting fuel cycle costs range from 0.61 to 1.18 mill/kWh. A discussion is also given on the practicability of these fuel cycles. The calculations indicate that somewhat lower fuel cycle costs can be expected from reactor operation in converter mode on 235 U make-up with fuel reprocessed in batches every 10 years to avoid fission product precipitation, than from operation as 233 U-Th breeder with continuous reprocessing. (auth.)

Active Duty C-17 Aircraft Commander Fuel Efficiency Metrics and Goal Evaluation

Science.gov (United States)

2015-03-26

options. Finally, Nicholson’s (2009:1-61) work was primarily focused on cost-effectiveness of replacing petroleum-based fuel with biodiesel . Fuel...Gillson, A. “Flight Fuel Planning Policy Letter,” HQ AMC/A3V, 2014. Hileman, J.I., R.W. Stratton. “Alternative jet fuel feasibility,” Transport Policy

Environmental costs of fossil fuel energy production

International Nuclear Information System (INIS)

Riva, A.; Trebeschi, C.

1997-01-01

The costs of environmental impacts caused by fossil fuel energy production are external to the energy economy and normally they are not reflected in energy prices. To determine the environmental costs associated with an energy source a detailed analysis of all environmental impacts of the complete energy cycle is required. The economic evaluation of environmental damages is presented caused by atmospheric emissions produced by fossil fuel combustion for different uses. Considering the emission factors of sulphur oxides, nitrogen oxides, dust and carbon dioxide and the economic evaluation of their environmental damages reported in literature, a range of environmental costs associated with different fossil fuels and technologies is presented. A comparison of environmental costs resulting from atmospheric emissions produced by fossil-fuel combustion for energy production shows that natural gas has a significantly higher environmental value than other fossil fuels. (R.P.)

The Economic, repository and proliferation implications of advanced nuclear fuel cycles

International Nuclear Information System (INIS)

Deinert, Mark; Cady, K.B.

2011-01-01

The goal of this project was to compare the effects of recycling actinides using fast burner reactors, with recycle that would be done using inert matrix fuel burned in conventional light water reactors. In the fast reactor option, actinides from both spent light water and fast reactor fuel would be recycled. In the inert matrix fuel option, actinides from spent light water fuel would be recycled, but the spent inert matrix fuel would not be reprocessed. The comparison was done over a limited 100-year time horizon. The economic, repository and proliferation implications of these options all hinge on the composition of isotopic byproducts of power production. We took the perspective that back-end economics would be affected by the cost of spent fuel reprocessing (whether conventional uranium dioxide fuel, or fast reactor fuel), fuel manufacture, and ultimate disposal of high level waste in a Yucca Mountain like geological repository. Central to understanding these costs was determining the overall amount of reprocessing needed to implement a fast burner, or inert matrix fuel, recycle program. The total quantity of high level waste requiring geological disposal (along with its thermal output), and the cost of reprocessing were also analyzed. A major advantage of the inert matrix fuel option is that it could in principle be implemented using the existing fleet of commercial power reactors. A central finding of this project was that recycling actinides using an inert matrix fuel could achieve reductions in overall actinide production that are nearly very close to those that could be achieved by recycling the actinides using a fast burner reactor.

Feasibility, cost and safety of some rehabilitation options for the Maralinga test site

International Nuclear Information System (INIS)

Vande Putte, D.; Tufton, E.P.S.; Myall, M.

1992-01-01

The need to rehabilitate the former nuclear test site at Maralinga has required the development of safe and cost-effective clean-up measures. Options have been investigated, which include fencing-off parts of the site, removing surface soil, mixing surface soil and stabilising the contents of debris pits. The results of the study can be used in selecting the most suitable options or combination of options necessary to achieve a given radiological end-point. (author)

External costs of the nuclear fuel cycle. A scoping study to determine the external costs of the Dutch nuclear fuel cycle in accordance with the EC/US methodology

International Nuclear Information System (INIS)

Dodd, D.H.

1995-10-01

This report describes the results of a scoping study to estimate the external costs of the Dutch nuclear fuel cycle. This study was performed within the framework of the Commission of the European Community's External Costs of Fuel Cycles project. The external costs of a fuel cycle are those costs which are excluded from the standard calculation of the cost of electricity. These costs are borne by society as a whole and include, in particular, the health and environmental costs which result from the operation of the facilities involved in a given fuel cycle. At present the uranium enrichment, electricity generation and interim storage stages of the nuclear fuel cycle take place in the Netherlands. These stages of the Dutch nuclear fuel cycle have been studied in detail and the external costs associated with thse stages estimated using up-to-date site specific data. The other stages of the Dutch nuclear fuel cycle do not currently take place in the Netherlands. In general the external costs associated with these stages have been estimated using data from the literature. Relatively few transports of radioactive materials associated with the Dutch nuclear fuel cycle take place in the Netherlands and the external costs associated with all transports has been based on values in the literature. (orig.)

External costs of the nuclear fuel cycle. A scoping study to determine the external costs of the Dutch nuclear fuel cycle in accordance with the EC/US methodology

Energy Technology Data Exchange (ETDEWEB)

Dodd, D H

1995-10-01

This report describes the results of a scoping study to estimate the external costs of the Dutch nuclear fuel cycle. This study was performed within the framework of the Commission of the European Community`s External Costs of Fuel Cycles project. The external costs of a fuel cycle are those costs which are excluded from the standard calculation of the cost of electricity. These costs are borne by society as a whole and include, in particular, the health and environmental costs which result from the operation of the facilities involved in a given fuel cycle. At present the uranium enrichment, electricity generation and interim storage stages of the nuclear fuel cycle take place in the Netherlands. These stages of the Dutch nuclear fuel cycle have been studied in detail and the external costs associated with thse stages estimated using up-to-date site specific data. The other stages of the Dutch nuclear fuel cycle do not currently take place in the Netherlands. In general the external costs associated with these stages have been estimated using data from the literature. Relatively few transports of radioactive materials associated with the Dutch nuclear fuel cycle take place in the Netherlands and the external costs associated with all transports has been based on values in the literature. (orig.).

Asian Option Pricing with Monotonous Transaction Costs under Fractional Brownian Motion

Directory of Open Access Journals (Sweden)

Di Pan

2013-01-01

Full Text Available Geometric-average Asian option pricing model with monotonous transaction cost rate under fractional Brownian motion was established. The method of partial differential equations was used to solve this model and the analytical expressions of the Asian option value were obtained. The numerical experiments show that Hurst exponent of the fractional Brownian motion and transaction cost rate have a significant impact on the option value.

Cost benefit analysis of recycling nuclear fuel cycle in Korea

International Nuclear Information System (INIS)

Lee, Jewhan; Chang, Soonheung

2012-01-01

Nuclear power has become an essential part of electricity generation to meet the continuous growth of electricity demand. The importance if nuclear waste management has been the main issue since the beginning of nuclear history. The recycling nuclear fuel cycle includes the fast reactor, which can burn the nuclear wastes, and the pyro-processing technology, which can reprocess the spent nuclear fuel. In this study, a methodology using Linear Programming (LP) is employed to evaluate the cost and benefits of introducing the recycling strategy and thus, to see the competitiveness of recycling fuel cycle. The LP optimization involves tradeoffs between the fast reactor capital cost with pyro-processing cost premiums and the total system uranium price with spent nuclear fuel management cost premiums. With the help of LP and sensitivity analysis, the effect of important parameters is presented as well as the target values for each cost and price of key factors

Fuel cycle model and the cost of a recycling thorium in the CANDU reactor

International Nuclear Information System (INIS)

Choi, Hangbok; Park, Chang Je

2005-01-01

The dry process fuel technology has a high proliferation-resistance, which allows applications not only to the existing but also to the future nuclear fuel cycle systems. In this study, the homogeneous ThO 2 -UO 2 recycling fuel cycle in a Canada deuterium uranium (CANDU) reactor was assessed for a fuel cycle cost evaluation. A series of parametric calculations were performed for the uranium fraction, enrichment of the initial uranium fuel, and the fission product removal rated of the recycled fuel. The fuel cycle cost was estimated by the levelized lifetime cost model provided by the Organization for Economic Cooperation and Development/Nuclear Energy Agency. Though it is feasible to recycle the homogeneous ThO 2 -UO 2 fuel in the CANDU reactor from the viewpoint of a mass balance, the recycling fuel cycle cost is much higher than the conventional natural uranium fuel cycle cost for most cases due to the high fuel fabrication cost. (author)

A comparative and predictive study of the annual fuel cycle costs for HEU and LEU fuels in the High Flux Reactor, Petten, 1985-1993

Energy Technology Data Exchange (ETDEWEB)

Moss, R L; May, P

1985-07-01

The internationally agreed constraint on availability of supply of HEU fuels to Research and Test Reactors has necessitated that a cost analysis be carried out to determine the financial effect of converting the core of the HFR from HEU to LEU fuels. A computer program, written at Petten and based on information extracted from studies in Europe and the USA, identifies the major cost variables to be manufacturing, uranium, reprocessing and transport costs. Comparison between HEU and LEU cores have been carried out and includes the effects of inflation and exchange rate fluctuations. Conversion of the HFR core to LEU fuels is shown to be financially disadvantageous. (author)

A comparative and predictive study of the annual fuel cycle costs for HEU and LEU fuels in the High Flux Reactor, Petten, 1985-1993

International Nuclear Information System (INIS)

Moss, R.L.; May, P.

1985-01-01

The internationally agreed constraint on availability of supply of HEU fuels to Research and Test Reactors has necessitated that a cost analysis be carried out to determine the financial effect of converting the core of the HFR from HEU to LEU fuels. A computer program, written at Petten and based on information extracted from studies in Europe and the USA, identifies the major cost variables to be manufacturing, uranium, reprocessing and transport costs. Comparison between HEU and LEU cores have been carried out and includes the effects of inflation and exchange rate fluctuations. Conversion of the HFR core to LEU fuels is shown to be financially disadvantageous. (author)

Cost probability analysis of reprocessing spent nuclear fuel in the US

International Nuclear Information System (INIS)

Recktenwald, G.D.; Deinert, M.R.

2012-01-01

The methods by which nuclear power's radioactive signature could be reduced typically require the reprocessing of spent nuclear fuel. However, economic assessments of the costs that are associated with doing this are subject to a high degree of uncertainty. We present a probabilistic analysis of the costs to build, operate and decommission the facilities that would be required to reprocess all US spent nuclear fuel generated over a one hundred year time frame, starting from a 2010 power production rate. The analysis suggests a total life-cycle cost of 2.11 ± 0.26 mills/kWh, with a 90% and 99% confidence that the overall cost would remain below 2.45 and 2.75 mills/kWh respectively. The most significant effects on cost come from the efficiency of the reactor fleet and the growth rate of nuclear power. The analysis shows that discounting results in life-cycle costs decreasing as recycling is delayed. However the costs to store spent fuel closely counter the effect of discounting when an intergenerational discount rate is used.

Augmented lagrange hopfield network for economic dispatch with multiple fuel options

International Nuclear Information System (INIS)

Dieu, Vo Ngoc; Ongsakul, Weerakorn; Polprasert, Jirawadee

2011-01-01

This paper proposes an augmented Lagrange Hopfield network (ALHN) for solving economic dispatch (ED) problem with multiple fuel options. The proposed ALHN method is a continuous Hopfield neural network with its energy function based on augmented Lagrangian function. The advantages of ALHN over the conventional Hopfield neural network are easier use, more general applications, faster convergence, better optimal solution, and larger scale of problem implementation. The method solves the problem by directly searching the most suitable fuel among the available fuels of each unit and finding the optimal solution for the problem based on minimization of the energy function of the continuous Hopfield neural network. The proposed method is tested on systems up to 100 units and the obtained results are compared to those from other methods in the literature. The results have shown that the proposed method is efficient for solving the ED problem with multiple fuel options and favorable for implementation in large scale problems.

A durable and dependable solution for RTR spent fuel management

International Nuclear Information System (INIS)

Thomasson, J.

1999-01-01

RTR Operators need efficient and cost-effective services for the management of their spent fuel and this, for the full lifetime of their facility. Thanks to the integration of transport, reprocessing and conditioning services, COGEMA provides a cogent solution, with the utmost respect for safety and preservation of the environment, for the short, medium and long terms. As demonstrated in this paper, this option offers the only durable and dependable solution for the RTR spent fuel management, leading to a conditioning for the final residues directly suitable for final disposal. The main advantage of such an option is obviously the significant reduction in terms of volume and radiotoxicity of the ultimate waste when compared to direct disposal of spent fuels. The efficiency of such a solution has been proven, some RTR operators having already trusted COGEMA for the management of their aluminide fuel. With its commitment in R and D activities for the development of a high performance and reprocessable LEU fuels, COGEMA will be able to propose a solution for all types of fuels, HEU and LEU

A scheme of better utilization of PWR spent fuels

International Nuclear Information System (INIS)

Chung, Bum Jin; Kang, Chang Soon

1991-01-01

The recycle of PWR spent fuels in a CANDU reactor, so called the tandem fuel cycle is investigated in this study. This scheme of utilizing PWR spent fuels will ease the shortage of spent fuel storage capacity as well as will improve the use of uranium resources. The minimum modification the design of present CANDU reactor is seeked in the recycle. Nine different fuel types are considered in this work and are classified into two categories: refabrication and reconfiguration. For refabrication, PWR spent fuels are processed and refabricated into the present 37 rod lattice structure of fuel bundle, and for reconfiguration, meanwhile, spent fuels are simply disassembled and rods are cut to fit into the present grid configuration of fuel bundle without refabrication. For each fuel option, the neutronics calculation of lattice was conducted to evaluate the allowable burn up and distribution. The fuel cycle cost of each option was also computed to assess the economic justification. The results show that most tandem fuel cycle option considered in this study are technically feasible as well as economically viable. (Author)

Potential and cost-effectiveness of CO{sub 2}-reducing measures in the pulp and paper industry

Energy Technology Data Exchange (ETDEWEB)

Moellersten, K.; Westermark, M.; Yan, J. [Royal Institute of Technology (KTH), Stockholm (Sweden). Dept. of Chemical Engineering and Technology/Energy Processes

2001-07-01

Using the two criteria of potential CO{sub 2} reduction and cost of CO{sub 2} reduction several technical options in the pulp and paper industry are investigated. Principal CO{sub 2} reducing measures include: decreasing fuel consumption through improved heat exchanging or new processes with lower heat demand, decreasing electricity consumption, substituting fossil fuels with biofuels, exporting refined biofuels for external use, increasing CO{sub 2} neutral electricity generation, improving waste heat utilization and decreasing specific raw material consumption. The results show that electricity conservation and improvement of existing steam power cycles are the most cost-effective options that have a large potential to reduce CO{sub 2} emissions. Outsourcing of industrial energy operations to utilities may enable CO{sub 2} reducing measures that would not be carried out by industry due to differences in demands for profit on spent capita. 21 refs., 1 fig., 2 tabs.

Proceedings of fuel strategies for conventional and unconventional fuels

International Nuclear Information System (INIS)

Mahr, D.; Nechvatal, T.T.

1991-01-01

Fuel selection is a major decision for a power engineer. It is the single largest item in the power plant operating budget and has a major effect on power plant economics. Fuel determines plant design requirements and the types of systems that are provided. As a result, it affects capital budgets and financing requirements. In the last few decades, we have seen different fuels of choice at any one time. Coal has always been a staple for power generation. During the 1950s and 1960s, oil became an attractive alternative. Nuclear fuel became a popular choice due to its very low energy cost. After Three-Mile-Island, however, capital budgets went through the roof, resulting in severe financial constraints. Natural gas, which was rationed in some regions a few years ago, is now a popular choice. Some sources predict that its cost will increase faster than other fuels. To mitigate the relative variations in energy cost for different fuels, a balanced energy plan is required. A balanced power generation plan with fuel options provides the flexibility to react to unpredictable changes. The papers in this book are a continuation of the Fuel Strategies theme. Three technical topics are covered: Converting to Orimulsion, A Replacement Fuel for Heavy Oil; Innovations in Handling Conventional and Unconventional Fuels for Power Plants; and Pacific Rim Experience With Coal

Production costs of liquid fuels from biomass

International Nuclear Information System (INIS)

Bridgwater, A.V.; Double, J.M.

1994-01-01

This project was undertaken to provide a consistent and thorough review of the full range of processes for producing liquid fuels from biomass to compare both alternative technologies and processes within those technologies in order to identify the most promising opportunities that deserve closer attention. Thermochemical conversion includes both indirect liquefaction through gasification, and direct liquefaction through pyrolysis and liquefaction in pressurized solvents. Biochemical conversion is based on a different set of feedstocks. Both acid and enzyme hydrolysis are included followed by fermentation. The liquid products considered include gasoline and diesel hydrocarbons and conventional alcohol fuels of methanol and ethanol. Results are given both as absolute fuel costs and as a comparison of estimated cost to market price. In terms of absolute fuel costs, thermochemical conversion offers the lowest cost products, with the least complex processes generally having an advantage. Biochemical routes are the least attractive. The most attractive processes from comparing production costs to product values are generally the alcohol fuels which enjoy a higher market value. (author)

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

Estimation of costs for fabrication of pressurized-water reactor fuel

International Nuclear Information System (INIS)

Judkins, R.R.; Olsen, A.R.

1979-01-01

To provide a reference case on which to base cost estimates of the several fuel cycles to be considered, the facility, equipment, and operating requirements for the fabrication of fuel for current-design pressurized-water reactors were examined. From an analysis of these requirements, the capital and operating costs of a plant with a capacity of two metric tons of heavy metal per day (MTHM/day) were estimated. In a cash flow analysis, the lifetime of the plant was assumed to be 20 y, and the income from the sale of nuclear fuel assemblies over this period was equated to the total capital and operating expenses of the plant, including a specified 15% return on investment. In this way a levelized unit price for the fuel was obtained. The effects of inflation were not considered since the purpose of these estimates and the determination of unit price was to permit comparison of different types of fuels. The capital costs of the fuel fabrication plant were estimated at $32 million for the facility--land, site preparation, building--and $34 million for equipment. Annual operating costs including labor, management, materials, and utilities were estimated to be $36.5 million. From these estimates, the unit price for fabricating the fuel for the reference pressurized-water reactor was determined to be $138/kg of heavy metal or $63,600 per fuel assembly

Atmospheric Nitrogen Deposition Loadings to the Chesapeake Bay: An Initial Analysis of the Cost Effectiveness of Control Options (1996)

Science.gov (United States)

This report examines the cost effectiveness of control options which reduce nitrate deposition to the Chesapeake watershed and to the tidal Bay. The report analyzes current estimates of the reductions expected in the ozone transport region.

Nuclear fuel cycle cost and cost calculation

International Nuclear Information System (INIS)

Schmiedel, P.; Schricker, W.

1975-01-01

Four different methods of calculating the cost of the fuel cycle are explained, starting from the individual cost components with their specific input data. The results (for LWRs) are presented in tabular form and in the form of diagrams. (RB) [de

Assessment of environmental impact of nuclear and other options for electricity generation in Croatia

International Nuclear Information System (INIS)

Feretic, D.; Tomsic, Z.; Kovacevic, T.

1996-01-01

Possible scenarios of future electricity production and supply, especially their environmental impact and social acceptability, have recently been put in the focus of overall interest. This paper analyzes the air impact and costs of possible developing options, varying the fuel types for future power plants. Nuclear option has also been taken in consideration. Two categories of costs have been introduced: internal cost (investment, O and M and fuel cost) and external cost (monetary equivalent of the environmental damage caused by plant operation). (author)

REFCO83, Nuclear Fuel Cycle Cost Economics Using Discounted Cash Flow Analysis

International Nuclear Information System (INIS)

Delene, J.G.; Hermann, O.W.

2001-01-01

1 - Description of program or function: REFCO83 utilizes a discounted cash flow (DCF) analysis procedure to calculate batch, cycle, and lifetime levelized average nuclear fuel cycle costs. The DCF analysis establishes an energy 'cost' associated with the fuel by requiring that the revenues from the sale of energy be adequate to pay the required return on outstanding capital, to pay all expenses including taxes, and to retire the outstanding investment to zero by the end of the economic life of the set of fuel investments. The program uses reactor mass flow information together with individual fuel cost parameters and utility capital structure and money costs to calculate levelized costs cumulatively through any batch or cycle. 2 - Method of solution: A fuel cycle cost component is considered to be any fuel material purchase, processing cost, or discharge material credit in the complete fuel cycle. The costs for each individual component, i.e. uranium, enrichment, etc., may either be expensed or capitalized for tax purposes or, in the case of waste disposal, the cost may also be made proportional to power production. To properly account for the effect of income taxes, all calculations in REFCO83 are done using 'then' current dollars, including price escalations caused by inflation. The database used for the default values for REFCO83 was taken from the Nuclear Energy Cost Data Base. 3 - Restrictions on the complexity of the problem: The maximum number of fuel batches is 120

Fuel Cells: Power System Option for Space Research

Science.gov (United States)

Shaneeth, M.; Mohanty, Surajeet

2012-07-01

Fuel Cells are direct energy conversion devices and, thereby, they deliver electrical energy at very high efficiency levels. Hydrogen and Oxygen gases are electrochemically processed, producing clean electric power with water as the only by product. A typical, Fuel Cell based power system involve a Electrochemical power converter, gas storage and management systems, thermal management systems and relevant control units. While there exists different types of Fuel cells, Proton Exchange Membrane (PEM) Fuel Cells are considered as the most suitable one for portable applications. Generally, Fuel Cells are considered as the primary power system option in space missions requiring high power ( > 5kW) and long durations and also where water is a consumable, such as manned missions. This is primarily due to the advantage that fuel cell based power systems offer, in terms of specific energy. Fuel cells have the potential to attain specific energy > 500Wh/kg, specific power >500W/kg, energy density > 400Whr/L and also power density > 200 W/L. This apart, a fuel cell system operate totally independent of sun light, whereas as battery based system is fully dependent on the same. This uniqueness provides added flexibility and capabilities to the missions and modularity for power system. High power requiring missions involving reusable launch vehicles, manned missions etc are expected to be richly benefited from this. Another potential application of Fuel Cell would be interplanetary exploration. Unpredictable and dusty atmospheres of heavenly bodies limits sun light significantly and there fuel cells of different types, eg, Bio-Fuel Cells, PEMFC, DMFCs would be able to work effectively. Manned or unmanned lunar out post would require continuous power even during extra long lunar nights and high power levels are expected. Regenerative Fuel Cells, a combination of Fuel Cells and Electrolysers, are identified as strong candidate. While application of Fuel Cells in high power

Used fuel rail shock and vibration testing options analysis

Energy Technology Data Exchange (ETDEWEB)

Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Klymyshyn, Nicholas A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2014-09-25

The objective of the rail shock and vibration tests is to complete the framework needed to quantify loads of fuel assembly components that are necessary to guide materials research and establish a technical basis for review organizations such as the U.S. Nuclear Regulatory Commission (NRC). A significant body of experimental and numerical modeling data exists to quantify loads and failure limits applicable to normal conditions of transport (NCT) rail transport, but the data are based on assumptions that can only be verified through experimental testing. The test options presented in this report represent possible paths for acquiring the data that are needed to confirm the assumptions of previous work, validate modeling methods that will be needed for evaluating transported fuel on a case-by-case basis, and inform material test campaigns on the anticipated range of fuel loading. The ultimate goal of this testing is to close all of the existing knowledge gaps related to the loading of used fuel under NCT conditions and inform the experiments and analysis program on specific endpoints for their research. The options include tests that would use an actual railcar, surrogate assemblies, and real or simulated rail transportation casks. The railcar carrying the cradle, cask, and surrogate fuel assembly payload would be moved in a train operating over rail track modified or selected to impart shock and vibration forces that occur during normal rail transportation. Computer modeling would be used to help design surrogates that may be needed for a rail cask, a cask’s internal basket, and a transport cradle. The objective of the design of surrogate components would be to provide a test platform that effectively simulates responses to rail shock and vibration loads that would be exhibited by state-of-the-art rail cask, basket, and/or cradle structures. The computer models would also be used to help determine the placement of instrumentation (accelerometers and strain gauges

Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - I: DUPIC Fuel Fabrication Cost

International Nuclear Information System (INIS)

Choi, Hangbok; Ko, Won Il; Yang, Myung Seung

2001-01-01

A preliminary conceptual design of a Direct Use of spent Pressurized water reactor (PWR) fuel In Canada deuterium uranium (CANDU) reactors (DUPIC) fuel fabrication plant was studied, which annually converts spent PWR fuel of 400 tonnes heavy element (HE) into CANDU fuel. The capital and operating costs were estimated from the viewpoint of conceptual design. Assuming that the annual discount rate is 5% during the construction (5 yr) and operation period (40 yr) and contingency is 25% of the capital cost, the levelized unit cost (LUC) of DUPIC fuel fabrication was estimated to be 616 $/kg HE, which is mostly governed by annual operation and maintenance costs that correspond to 63% of LUC. Among the operation and maintenance cost components being considered, the waste disposal cost has the dominant effect on LUC (∼49%). From sensitivity analyses of production capacity, discount rate, and contingency, it was found that the production capacity of the plant is the major parameter that affects the LUC

A cost-effective microbial fuel cell to detect and select for photosynthetic electrogenic activity in algae and cyanobacteria

NARCIS (Netherlands)

Luimstra, V.M.; Kennedy, S.J.; Güttler, J.; Wood, S.A.; Williams, D.E.; Packer, M.A.

2014-01-01

This work describes the development of an easily constructed, cost-effective photosynthetic microbial fuel cell design with highly reproducible electrochemical characteristics that can be used to screen algae and cyanobacteria for photosynthetic electrogenic activity. It is especially suitable for

An integrated appraisal of energy recovery options in the United Kingdom using solid recovered fuel derived from municipal solid waste.

Science.gov (United States)

Garg, A; Smith, R; Hill, D; Longhurst, P J; Pollard, S J T; Simms, N J

2009-08-01

This paper reports an integrated appraisal of options for utilising solid recovered fuels (SRF) (derived from municipal solid waste, MSW) in energy intensive industries within the United Kingdom (UK). Four potential co-combustion scenarios have been identified following discussions with industry stakeholders. These scenarios have been evaluated using (a) an existing energy and mass flow framework model, (b) a semi-quantitative risk analysis, (c) an environmental assessment and (d) a financial assessment. A summary of results from these evaluations for the four different scenarios is presented. For the given ranges of assumptions; SRF co-combustion with coal in cement kilns was found to be the optimal scenario followed by co-combustion of SRF in coal-fired power plants. The biogenic fraction in SRF (ca. 70%) reduces greenhouse gas (GHG) emissions significantly ( approximately 2500 g CO(2) eqvt./kg DS SRF in co-fired cement kilns and approximately 1500 g CO(2) eqvt./kg DS SRF in co-fired power plants). Potential reductions in electricity or heat production occurred through using a lower calorific value (CV) fuel. This could be compensated for by savings in fuel costs (from SRF having a gate fee) and grants aimed at reducing GHG emission to encourage the use of fuels with high biomass fractions. Total revenues generated from coal-fired power plants appear to be the highest ( 95 pounds/t SRF) from the four scenarios. However overall, cement kilns appear to be the best option due to the low technological risks, environmental emissions and fuel cost. Additionally, cement kiln operators have good experience of handling waste derived fuels. The scenarios involving co-combustion of SRF with MSW and biomass were less favourable due to higher environmental risks and technical issues.

An integrated appraisal of energy recovery options in the United Kingdom using solid recovered fuel derived from municipal solid waste

International Nuclear Information System (INIS)

Garg, A.; Smith, R.; Hill, D.; Longhurst, P.J.; Pollard, S.J.T.; Simms, N.J.

2009-01-01

This paper reports an integrated appraisal of options for utilising solid recovered fuels (SRF) (derived from municipal solid waste, MSW) in energy intensive industries within the United Kingdom (UK). Four potential co-combustion scenarios have been identified following discussions with industry stakeholders. These scenarios have been evaluated using (a) an existing energy and mass flow framework model, (b) a semi-quantitative risk analysis, (c) an environmental assessment and (d) a financial assessment. A summary of results from these evaluations for the four different scenarios is presented. For the given ranges of assumptions; SRF co-combustion with coal in cement kilns was found to be the optimal scenario followed by co-combustion of SRF in coal-fired power plants. The biogenic fraction in SRF (ca. 70%) reduces greenhouse gas (GHG) emissions significantly (∼2500 g CO 2 eqvt./kg DS SRF in co-fired cement kilns and ∼1500 g CO 2 eqvt./kg DS SRF in co-fired power plants). Potential reductions in electricity or heat production occurred through using a lower calorific value (CV) fuel. This could be compensated for by savings in fuel costs (from SRF having a gate fee) and grants aimed at reducing GHG emission to encourage the use of fuels with high biomass fractions. Total revenues generated from coal-fired power plants appear to be the highest ( Pounds 95/t SRF) from the four scenarios. However overall, cement kilns appear to be the best option due to the low technological risks, environmental emissions and fuel cost. Additionally, cement kiln operators have good experience of handling waste derived fuels. The scenarios involving co-combustion of SRF with MSW and biomass were less favourable due to higher environmental risks and technical issues.

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....

Rough order of magnitude cost estimate for immobilization of 18.2 MT of plutonium sharing existing facilities at Hanford with MOX fuel fabrication facility: alternative 4B

International Nuclear Information System (INIS)

DiSabatino, A.

1998-01-01

The purpose of this Cost Estimate Report is to identify preliminary capital and operating costs for a facility to immobilize 18.2 metric tons (nominal) of plutonium as a ceramic in an existing facility at Hanford, the Fuels and Materials Examination Facility (FMEF). The MOX Fuel Fabrication Facility (MFFF), which is being costed in a separate report, will also be located in the FMEF in this co-location option

CANFLEX-RU fuel development programs as one option of advanced fuel cycles in Korea

International Nuclear Information System (INIS)

Suk, Ho Chun; Sim, Ki-Seob; Chung, Jang Hwan

1999-01-01

As one of the possible fuel cycles in Korea, RU (Recycled Uranium) fuel offers a very attractive alternative to the use of NU (Natural Uranium) and SEU in the CANDU reactors, because Korea is a unique country having both PWR and CANDU reactors. Korea can therefore exploit the natural synergism between the two reactor types to minimise overall waste production, and maximise energy derived from the fuel, by burning the spent fuel from its PWR reactors in CANDU reactors. Potential benefits can be derived from a number of stages in the fuel cycle: no enrichment required, no enrichment tails, direct conversion to UO 2 lower sensitivity to 234 U and 236 U absorption in the CANDU reactor, expected lower cost relative to NU and SEU. These benefits all fit well with the PWR-CANDU fuel cycle synergy. RU arising from the reprocessing of European and Japanese oxide spent fuel by 2000 is projected to be approaching 25,000 te. The use of RU fuel in a CANDU-6 reactor should result in no serious radiological difficulties and no requirements for special precautions and should not require any new technologies for the fuel fabrication and handling. A KAERI's feasibility shows that the use of the CANFLEX bundle as the carrier for RU will be compatible with the reactor design, current safety and operational requirements, and there will be no significant fuel performance difference from the CANDU 37-element NU fuel bundle. Compared with the 37-element NU bundle, the RU fuel has significantly improved fuel cycle economics derived from increased burnups, a large reduction in fuel requirements and spent fuel arisings and the potential lower cost for RU material. There is the potential for annual fuel cost savings to be in the range of one-third to two-thirds, with enhanced operating margins using RU in the CANFLEX bundle design. These benefits provide the rationale for justifying R and D effort on the use of RU fuel for advanced fuel cycles in the CANDU reactors of Korea. The RU fuel

Cost-effectiveness Analysis for Technology Acquisition.

Science.gov (United States)

Chakravarty, A; Naware, S S

2008-01-01

In a developing country with limited resources, it is important to utilize the total cost visibility approach over the entire life-cycle of the technology and then analyse alternative options for acquiring technology. The present study analysed cost-effectiveness of an "In-house" magnetic resonance imaging (MRI) scan facility of a large service hospital against outsourcing possibilities. Cost per unit scan was calculated by operating costing method and break-even volume was calculated. Then life-cycle cost analysis was performed to enable total cost visibility of the MRI scan in both "In-house" and "outsourcing of facility" configuration. Finally, cost-effectiveness analysis was performed to identify the more acceptable decision option. Total cost for performing unit MRI scan was found to be Rs 3,875 for scans without contrast and Rs 4,129 with contrast. On life-cycle cost analysis, net present value (NPV) of the "In-house" configuration was found to be Rs-(4,09,06,265) while that of "outsourcing of facility" configuration was Rs-(5,70,23,315). Subsequently, cost-effectiveness analysis across eight Figures of Merit showed the "In-house" facility to be the more acceptable option for the system. Every decision for acquiring high-end technology must be subjected to life-cycle cost analysis.

Technological substitution options for controlling greenhouse gas emissions

International Nuclear Information System (INIS)

Barbier, E.B.; Burgess, J.C.; Pearce, D.W.

1991-01-01

This chapter is concerned with technological options for greenhouse gas substitution. The authors interpret the term substitution to exclude energy conservation/efficiency measures, investments in afforestation (sinks), and greenhouse gas removal or abatement technologies. Their working definition of greenhouse gas substitution includes (1) replacement technologies, for example, substituting a greenhouse gas technology with a nongreenhouse gas technology; and (2) reduction technologies, for example, substituting a greenhouse gas technology with an alternative technology that reduces greenhouse gas emissions. Essentially, replacement technologies involve 100 percent reduction in CO 2 ; reduction technologies involve a partial reduction in CO 2 . Of the man-made sources of greenhouse gases, energy is the most important and is expected to contribute to at least half of the global warming effect in the near future. The majority of this impact is from fossil fuel combustion as a source of carbon dioxide (CO 2 ), although fossil fuels also contribute significantly to methane (CH 4 ), to nitrous oxide (N 2 O), and to low-level ozone (O 3 ) through production of various nitrogen gases (NO x ) and carbon monoxide (CO). This study analyzes the available greenhouse gas substitutions and their costs. The authors concentrate particularly on substitutions for fossil-fuel combustion and CFC production and consumption. They conclude by summarizing the potential for greenhouse gas substitution, the cost-effectiveness of the various options and the design of incentives for substitution

Results from the OECD report on international projections of electricity generating costs

International Nuclear Information System (INIS)

Paffenbarger, J.A.; Bertel, E.

1998-01-01

The International Energy Agency and Nuclear Energy Agency of the OECD have periodically undertaken a joint study on electricity generating costs in OECD Member countries and selected non-Member countries. This paper presents key results from the 1998 update of this study. Experts from 19 countries drawn from electric utility companies and government provided data on capital costs, operating and maintenance costs, and fuel costs from which levelized electricity generating costs (US cents/kWh) for baseload power plants were estimated in each country using a common set of economic assumptions. Light water nuclear power plants, pulverized coal plants, and natural gas-fired combined cycle gas turbines were the principal options evaluated. five and 10% discount rates, 40-year operating lifetime, and 75% annual load factor were the base assumptions, with sensitivity analyses on operating lifetime and load factor. Fuel costs and fuel escalation were provided individually by country, with a sensitivity case to evaluate costs assuming no real fuel price escalation over plant lifetimes. Of the three principal fuel/technology options, none is predominantly the cheapest option for all economic assumptions. However, fossil-fueled options are generally estimated to be the least expensive option. The study confirms that gas-fired combined cycles have improved their economic performance in most countries in recent years and are strong competitors to nuclear and coal-fired plants. Eleven out of the 18 countries with two or more options show gas-fired plants to be the cheapest option at 10% discount rate. Coal remains a strong competitor to gas when lower discount rates are used. Nuclear is the least expensive at both 5 and 10% discount rate in only two countries. Generally, with gas prices above 5 US$/GJ, nuclear plants constructed at overnight capital costs below 1 650 $/kWe have the potential to be competitive only at lower discount rates

Hydrogen as a fuel for fuel cell vehicles: A technical and economic comparison

Energy Technology Data Exchange (ETDEWEB)

Ogden, J.; Steinbugler, M.; Kreutz, T. [Princeton Univ., NJ (United States). Center for Energy and Environmental Studies

1997-12-31

All fuel cells currently being developed for near term use in vehicles require hydrogen as a fuel. Hydrogen can be stored directly or produced onboard the vehicle by reforming methanol, ethanol or hydrocarbon fuels derived from crude oil (e.g., Diesel, gasoline or middle distillates). The vehicle design is simpler with direct hydrogen storage, but requires developing a more complex refueling infrastructure. In this paper, the authors compare three leading options for fuel storage onboard fuel cell vehicles: compressed gas hydrogen storage; onboard steam reforming of methanol; onboard partial oxidation (POX) of hydrocarbon fuels derived from crude oil. Equilibrium, kinetic and heat integrated system (ASPEN) models have been developed to estimate the performance of onboard steam reforming and POX fuel processors. These results have been incorporated into a fuel cell vehicle model, allowing us to compare the vehicle performance, fuel economy, weight, and cost for various fuel storage choices and driving cycles. A range of technical and economic parameters were considered. The infrastructure requirements are also compared for gaseous hydrogen, methanol and hydrocarbon fuels from crude oil, including the added costs of fuel production, storage, distribution and refueling stations. Considering both vehicle and infrastructure issues, the authors compare hydrogen to other fuel cell vehicle fuels. Technical and economic goals for fuel cell vehicle and hydrogen technologies are discussed. Potential roles for hydrogen in the commercialization of fuel cell vehicles are sketched.

Mitigation Options in Forestry, Land-Use, Change and Biomass Burning in Africa

International Nuclear Information System (INIS)

Makundi, Willy R.

1998-01-01

Mitigation options to reduce greenhouse gas emissions and sequester carbon in land use sectors are describe in some detail. The paper highlights those options in the forestry sector, which are more relevant to different parts of Africa. It briefly outlines a bottom-up methodological framework for comprehensively assessing mitigation options in land use sectors. This method emphasizes the application of end-use demand projections to construct a baseline and mitigation scenarios and explicitly addresses the carbon storage potential on land and in wood products, as well as use of wood to substitute for fossil fuels. Cost-effectiveness indicators for ranking mitigation options are proposed, including those, which account for non-carbon monetary benefits such as those derived from forest products, as well as opportunity cost of pursuing specific mitigation option. The paper finally surveys the likely policies, barriers and incentives to implement such mitigation options in African countries.; copyrighted ; Y

Assessment of bio-fuel options for solid oxide fuel cell applications

Science.gov (United States)

Lin, Jiefeng

Rising concerns of inadequate petroleum supply, volatile crude oil price, and adverse environmental impacts from using fossil fuels have spurred the United States to promote bio-fuel domestic production and develop advanced energy systems such as fuel cells. The present dissertation analyzed the bio-fuel applications in a solid oxide fuel cell-based auxiliary power unit from environmental, economic, and technological perspectives. Life cycle assessment integrated with thermodynamics was applied to evaluate the environmental impacts (e.g., greenhouse gas emission, fossil energy consumption) of producing bio-fuels from waste biomass. Landfill gas from municipal solid wastes and biodiesel from waste cooking oil are both suggested as the promising bio-fuel options. A nonlinear optimization model was developed with a multi-objective optimization technique to analyze the economic aspect of biodiesel-ethanol-diesel ternary blends used in transportation sectors and capture the dynamic variables affecting bio-fuel productions and applications (e.g., market disturbances, bio-fuel tax credit, policy changes, fuel specification, and technological innovation). A single-tube catalytic reformer with rhodium/ceria-zirconia catalyst was used for autothermal reformation of various heavy hydrocarbon fuels (e.g., diesel, biodiesel, biodiesel-diesel, and biodiesel-ethanol-diesel) to produce a hydrogen-rich stream reformates suitable for use in solid oxide fuel cell systems. A customized mixing chamber was designed and integrated with the reformer to overcome the technical challenges of heavy hydrocarbon reformation. A thermodynamic analysis, based on total Gibbs free energy minimization, was implemented to optimize the operating environment for the reformations of various fuels. This was complimented by experimental investigations of fuel autothermal reformation. 25% biodiesel blended with 10% ethanol and 65% diesel was determined to be viable fuel for use on a truck travelling with

Performance and economic penalties of some LEU [low enriched uranium] conversion options for the Australian Reactor HIFAR

International Nuclear Information System (INIS)

McCulloch, D.B.; Robinson, G.S.

1987-01-01

Performance calculations for the conversion of HIFAR to low enriched uranium (LEU) fuel have been extended to a wide range of 235 U loadings per fuel element. Using a simple approximate algorithm for the likely costs of LEU compared with highly enriched uranium (HEU) fuel elements, the increases in annual fuelling costs for LEU compared with HEU fuel are examined for a range of conversion options involving different performance penalties. No significant operational/safety problems were found for any of the options canvassed. (Author)

Cost Savings of Nuclear Power with Total Fuel Reprocessing

International Nuclear Information System (INIS)

Solbrig, Charles W.; Benedict, Robert W.

2006-01-01

The cost of fast reactor (FR) generated electricity with pyro-processing is estimated in this article. It compares favorably with other forms of energy and is shown to be less than that produced by light water reactors (LWR's). FR's use all the energy in natural uranium whereas LWR's utilize only 0.7% of it. Because of high radioactivity, pyro-processing is not open to weapon material diversion. This technology is ready now. Nuclear power has the same advantage as coal power in that it is not dependent upon a scarce foreign fuel and has the significant additional advantage of not contributing to global warming or air pollution. A jump start on new nuclear plants could rapidly allow electric furnaces to replace home heating oil furnaces and utilize high capacity batteries for hybrid automobiles: both would reduce US reliance on oil. If these were fast reactors fueled by reprocessed fuel, the spent fuel storage problem could also be solved. Costs are derived from assumptions on the LWR's and FR's five cost components: 1) Capital costs: LWR plants cost $106/MWe. FR's cost 25% more. Forty year amortization is used. 2) The annual O and M costs for both plants are 9% of the Capital Costs. 3) LWR fuel costs about 0.0035 $/kWh. Producing FR fuel from spent fuel by pyro-processing must be done in highly shielded hot cells which is costly. However, the five foot thick concrete walls have the advantage of prohibiting diversion. LWR spent fuel must be used as feedstock for the FR initial core load and first two reloads so this FR fuel costs more than LWR fuel. FR fuel costs much less for subsequent core reloads ( 6 /MWe. The annual cost for a 40 year licensed plant would be 2.5 % of this or less if interest is taken into account. All plants will eventually have to replace those components which become radiation damaged. FR's should be designed to replace parts rather than decommission. The LWR costs are estimated to be 2.65 cents/kWh. FR costs are 2.99 cents/kWh for the first

Cost evaluation of a commercial-scale DUPIC fuel fabrication facility (Part I) -Summary

Energy Technology Data Exchange (ETDEWEB)

Ko, Won Il; Choi, Hang Bok; Yang, Myung Seung [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-08-01

A conceptual design of a commercial scale DUPIC fuel fabrication facility was initiated to provide some insights into the costs associated with construction, operation, and decommissioning. The primary conclusion of this report is that it is feasible to design, license, construct, test, and operate a facility that will process 400 MTHE/yr of spent PWR fuel and reconfigure the fuel into CANDU fuel bundles at a reasonable unit cost of the fuel material. Although DUPIC fuel fabrication by vibropacking method is clearly cheaper than that of the pellet method, the feasibility of vibropac technology for DUPIC fuel fabrication and use of vibroac fuel in CANDU reactors may has to be studied in depth in order to use as an alternative to the conventional pellet fuel method. Especially, there are some questions on meeting the CANDU requirements in thermal and mechanical terms as well as density of fuel. Wherever possible, this report used representative costs of currently available technologies as the bases for cost estimation. It should also be noted that the conceptual design and cost information contained in this report was extracted from the public domain and general open literature. Later studies have to focus on other important areas of concern such as safety, security, safeguards, process optimization etc. 7 figs., 6 tabs. (Author)

Annex 34 : task 1 : analysis of biodiesel options : biomass-derived diesel fuels : final report

Energy Technology Data Exchange (ETDEWEB)

McGill, R [Oak Ridge National Laboratory, TN (United States); Aakko-Saksa, P; Nylund, N O [TransEnergy Consulting Ltd., Helsinki (Finland)

2009-06-15

Biofuels are derived from woody biomass, non-woody biomass, and organic wastes. The properties of vegetable oil feedstocks can have profound effects on the properties of the finished biodiesel product. However, all biodiesel fuels have beneficial effects on engine emissions. This report discussed the use of biodiesel fuels as replacements for part of the diesel fuel consumed throughout the world. Biodiesel fuels currently being produced from fatty acid esters today were reviewed, as well as some of the more advanced diesel replacement fuels. The report was produced as part of the International Energy Agency (IEA) Advanced Motor Fuels (AMF) Implementing Agreement Annex 34, and was divided into 14 sections: (1) an introduction, (2) biodiesel and biomass, (3) an explanation of biodiesel, (4) properties of finished biodiesel fuels, (5) exhaust emissions of finished biodiesel fuels and blends, (6) life-cycle emissions and energy, (7) international biodiesel (FAME) technical standards and specifications, (8) growth in production and use of biodiesel fuels, (9) biofuel refineries, (10) process technology, (11) development and status of biorefineries, (12) comparison of options to produce biobased diesel fuels, (13) barriers and gaps in knowledge, and (14) references. 113 refs., 37 tabs., 74 figs.

Techno-economic analysis of a local district heating plant under fuel flexibility and performance

DEFF Research Database (Denmark)

Rudra, Souman; Rosendahl, Lasse

2017-01-01

are calculated using the same procedure according to the use of various local renewable fuels known as “biogas option,” “solar option,” “heat pump option,” and “imported heat option.” A comparison has been made between the reference option and other options. The greatest reduction in heat cost is obtained from......, an investigation has been made to reduce the use of fossil fuels for district heating system and make use of the local renewable resources (biogas, solar, and heat pump) for district heating purposes. In this article, the techno-economic assessment is achieved through the development of a suite of models...... the biogas option by replacing a new engine, where 66 % of the current fuel is substituted with biogas....

Fuel Cell System for Transportation -- 2005 Cost Estimate

Energy Technology Data Exchange (ETDEWEB)

Wheeler, D.

2006-10-01

Independent review report of the methodology used by TIAX to estimate the cost of producing PEM fuel cells using 2005 cell stack technology. The U.S. Department of Energy (DOE) Hydrogen, Fuel Cells and Infrastructure Technologies Program Manager asked the National Renewable Energy Laboratory (NREL) to commission an independent review of the 2005 TIAX cost analysis for fuel cell production. The NREL Systems Integrator is responsible for conducting independent reviews of progress toward meeting the DOE Hydrogen Program (the Program) technical targets. An important technical target of the Program is the proton exchange membrane (PEM) fuel cell cost in terms of dollars per kilowatt ($/kW). The Program's Multi-Year Program Research, Development, and Demonstration Plan established $125/kW as the 2005 technical target. Over the last several years, the Program has contracted with TIAX, LLC (TIAX) to produce estimates of the high volume cost of PEM fuel cell production for transportation use. Since no manufacturer is yet producing PEM fuel cells in the quantities needed for an initial hydrogen-based transportation economy, these estimates are necessary for DOE to gauge progress toward meeting its targets. For a PEM fuel cell system configuration developed by Argonne National Laboratory, TIAX estimated the total cost to be $108/kW, based on assumptions of 500,000 units per year produced with 2005 cell stack technology, vertical integration of cell stack manufacturing, and balance-of-plant (BOP) components purchased from a supplier network. Furthermore, TIAX conducted a Monte Carlo analysis by varying ten key parameters over a wide range of values and estimated with 98% certainty that the mean PEM fuel cell system cost would be below DOE's 2005 target of $125/kW. NREL commissioned DJW TECHNOLOGY, LLC to form an Independent Review Team (the Team) of industry fuel cell experts and to evaluate the cost estimation process and the results reported by TIAX. The results of

Cost-effectiveness of the management of rh-negative pregnant women.

Science.gov (United States)

Duplantie, Julie; Gonzales, Odilon Martinez; Bois, Antoine; Nshimyumukiza, Léon; Gekas, Jean; Bujold, Emmanuel; Morin, Valérie; Vallée, Maud; Giguère, Yves; Gagné, Christian; Rousseau, François; Reinharz, Daniel

2013-08-01

The purpose of this study was to determine the most cost-effective option to prevent alloimmunization against the Rh factor. A virtual population of Rh-negative pregnant women in Quebec was built to simulate the cost-effectiveness of preventing alloimmunization. The model considered four options: (1) systematic use of anti-D immunoglobulin; (2) fetal Rh(D) genotyping; (3) immunological determination of the father's Rh type; (4) mixed screening: immunological determination of the father's Rh type, followed if positive by fetal Rh(D) genotyping. Two outcomes were considered, in addition to the estimated costs: (1) the number of babies without hemolytic disease, and (2) the number of surviving infants. In a first pregnancy, two options emerged as the most cost-effective options: systematic prophylaxis and immunological Rh typing of the father, with overlapping confidence intervals between them. In a second pregnancy, the results were similar. In all cases (first or second pregnancy or a combination of the two) fetal genotyping was not found to be a cost-effective option. Routine prophylaxis and immunological Rh typing of the father are the most cost-effective options for the prevention of Rh alloimmunization. Considering that immunological typing of the father would probably not be carried out by the majority of clinicians, routine prophylaxis remains the preferred option. However, this could change if the cost of Rh(D) fetal genotyping fell below $140 per sample.

Comparative analyses of forest fuels in a life cycle perspective with a focus on transport systems

Energy Technology Data Exchange (ETDEWEB)

Eriksson, Lisa Naeslund [Ecotechnology, Department of Engineering, Physics and Mathematics, Mid Sweden University, SE-831 25 Oestersund (Sweden)

2008-08-15

Local, national and international transportation of forest fuels with regard to costs, primary energy use and CO{sub 2} emission was analysed. The main issue was the extent to which both mode and distance of transport affect the monetary cost, CO{sub 2} emission and primary energy use arising from the use of various types of forest residues for energy purpose. Local applications proved the most efficient options of those studied. Chipping of bundles at a terminal, for transport by rail and sea to national or international end-users, has low costs and produces only modest CO{sub 2} emissions. For the pellet options, the cost is about the same as for chipping, but require more primary energy and emit more CO{sub 2}. The traditional chipping system is more expensive than the other options. The costs of the international options over a transport distance of 1100 km vary between 21 and 28 EUR{sub 2007}/MWh, whereas pellet options cost between 22 and 25 EUR{sub 2007}/MWh. The primary energy required for transport of logging residues vis-a-vis pellets falls in the range 4-7% and 2-4%, respectively, of the bio-energy delivered. The primary energy needed to produce pellets gives them a lower fossil fuel substitution rate per hectare, compared with bundle systems. Similarly, for chip systems vis-a-vis bundle systems, the biomass delivered to the conversion plant is reduced by the greater physical dry-matter losses entailed by chipping systems in the forest-fuel chain. (author)

Mitigation options in forestry, land-use change and biomass burning in Africa

Energy Technology Data Exchange (ETDEWEB)

Makundi, Willy R.L. [Univ. of California, Lawrence Berkeley National Lab. (United States)

1998-10-01

Mitigation options to reduce greenhouse gas emissions and sequester carbon in land use sectors are described in some detail. The paper highlights those options in the forestry sector, which are more relevant to different parts of Africa. It briefly outlines a bottom-up methodological framework for comprehensively assessing mitigation options in land use sectors. This method emphasizes the application of end-use demand projections to construct baseline and mitigation scenarios and explicitly addresses the carbon storage potential on land an in wood products, as well as use of wood to substitute for fossil fuels. Cost-effectiveness indicators for ranking mitigation options are proposed, including those which account for non-carbon monetary benefits such as those derived from forest products, as well as opportunity cost of pursuing specific mitigation option. The paper finally surveys the likely policies, barriers and incentives to implement such mitigation options in African countries. (au) 13 refs.

Mitigation options in forestry, land-use change and biomass burning in Africa

International Nuclear Information System (INIS)

Makundi, Willy R.L.

1998-01-01

Mitigation options to reduce greenhouse gas emissions and sequester carbon in land use sectors are described in some detail. The paper highlights those options in the forestry sector, which are more relevant to different parts of Africa. It briefly outlines a bottom-up methodological framework for comprehensively assessing mitigation options in land use sectors. This method emphasizes the application of end-use demand projections to construct baseline and mitigation scenarios and explicitly addresses the carbon storage potential on land an in wood products, as well as use of wood to substitute for fossil fuels. Cost-effectiveness indicators for ranking mitigation options are proposed, including those which account for non-carbon monetary benefits such as those derived from forest products, as well as opportunity cost of pursuing specific mitigation option. The paper finally surveys the likely policies, barriers and incentives to implement such mitigation options in African countries. (au) 13 refs

Cost and cost-effectiveness of tuberculosis treatment shortening: a model-based analysis.

Science.gov (United States)

Gomez, G B; Dowdy, D W; Bastos, M L; Zwerling, A; Sweeney, S; Foster, N; Trajman, A; Islam, M A; Kapiga, S; Sinanovic, E; Knight, G M; White, R G; Wells, W A; Cobelens, F G; Vassall, A

2016-12-01

Despite improvements in treatment success rates for tuberculosis (TB), current six-month regimen duration remains a challenge for many National TB Programmes, health systems, and patients. There is increasing investment in the development of shortened regimens with a number of candidates in phase 3 trials. We developed an individual-based decision analytic model to assess the cost-effectiveness of a hypothetical four-month regimen for first-line treatment of TB, assuming non-inferiority to current regimens of six-month duration. The model was populated using extensive, empirically-collected data to estimate the economic impact on both health systems and patients of regimen shortening for first-line TB treatment in South Africa, Brazil, Bangladesh, and Tanzania. We explicitly considered 'real world' constraints such as sub-optimal guideline adherence. From a societal perspective, a shortened regimen, priced at USD1 per day, could be a cost-saving option in South Africa, Brazil, and Tanzania, but would not be cost-effective in Bangladesh when compared to one gross domestic product (GDP) per capita. Incorporating 'real world' constraints reduces cost-effectiveness. Patient-incurred costs could be reduced in all settings. From a health service perspective, increased drug costs need to be balanced against decreased delivery costs. The new regimen would remain a cost-effective option, when compared to each countries' GDP per capita, even if new drugs cost up to USD7.5 and USD53.8 per day in South Africa and Brazil; this threshold was above USD1 in Tanzania and under USD1 in Bangladesh. Reducing the duration of first-line TB treatment has the potential for substantial economic gains from a patient perspective. The potential economic gains for health services may also be important, but will be context-specific and dependent on the appropriate pricing of any new regimen.

The disposal of Canada's nuclear fuel waste: engineering for a disposal facility

International Nuclear Information System (INIS)

Simmons, G.R.; Baumgartner, P.

1994-01-01

This report presents some general considerations for engineering a nuclear fuel waste disposal facility, alternative disposal-vault concepts and arrangements, and a conceptual design of a used-fuel disposal centre that was used to assess the technical feasibility, costs and potential effects of disposal. The general considerations and alternative disposal-vault arrangements are presented to show that options are available to allow the design to be adapted to actual site conditions. The conceptual design for a used-fuel disposal centre includes descriptions of the two major components of the disposal facility, the Used-Fuel Packaging Plant and the disposal vault; the ancillary facilities and services needed to carry out the operations are also identified. The development of the disposal facility, its operation, its decommissioning, and the reclamation of the site are discussed. The costs, labour requirements and schedules used to assess socioeconomic effects and that may be used to assess the cost burden of waste disposal to the consumer of nuclear energy are estimated. The Canadian Nuclear Fuel Waste Management Program is funded jointly by AECL and Ontario Hydro under the auspices of the CANDU Owners Group. (author)

Prevention of mother-to-child transmission of HIV: cost-effectiveness of antiretroviral regimens and feeding options in Rwanda.

Directory of Open Access Journals (Sweden)

Agnes Binagwaho

Full Text Available Rwanda's National PMTCT program aims to achieve elimination of new HIV infections in children by 2015. In November 2010, Rwanda adopted the WHO 2010 ARV guidelines for PMTCT recommending Option B (HAART for all HIV-positive pregnant women extended throughout breastfeeding and discontinued (short course-HAART only for those not eligible for life treatment. The current study aims to assess the cost-effectiveness of this policy choice.Based on a cohort of HIV-infected pregnant women in Rwanda, we modelled the cost-effectiveness of six regimens: dual ARV prophylaxis with either 12 months breastfeeding or replacement feeding; short course HAART (Sc-HAART prophylaxis with either 6 months breastfeeding, 12 months breastfeeding, or 18 months breastfeeding; and Sc-HAART prophylaxis with replacement feeding. Direct costs were modelled based on all inputs in each scenario and related unit costs. Effectiveness was evaluated by measuring HIV-free survival at 18 months. Savings correspond to the lifetime costs of HIV treatment and care avoided as a result of all vertical HIV infections averted.All PMTCT scenarios considered are cost saving compared to "no intervention." Sc-HAART with 12 months breastfeeding or 6 months breastfeeding dominate all other scenarios. Sc-HAART with 12 months breastfeeding allows for more children to be alive and HIV-uninfected by 18 months than Sc-HAART with 6 months breastfeeding for an incremental cost per child alive and uninfected of 11,882 USD. This conclusion is sensitive to changes in the relative risk of mortality by 18 months for exposed HIV-uninfected children on replacement feeding from birth and those who were breastfed for only 6 months compared to those breastfeeding for 12 months or more.Our findings support the earlier decision by Rwanda to adopt WHO Option B and could inform alternatives for breastfeeding duration. Local contexts and existing care delivery models should be part of national policy decisions.

Investigation of economics of nuclear fuel cycle options in the Republic of Korea based on once-through - 5468

International Nuclear Information System (INIS)

Cho, S.K.; Yim, M.S.

2015-01-01

This study performs an economic evaluation of future nuclear fuel cycle options based on once-through strategy. Various factors of the future development in Korea are also considered including nuclear phase-out, continuous use of nuclear energy at varying growth rate, and the reunification of the Korean peninsula. A spreadsheet model is developed as part of the methodology of screening material flow and economic evaluation and results are discussed for policy planning for Korea as well as for nuclear developing countries. Results indicated that economics improves as the size of nuclear power system increases. We found some significant factors that affect LCOE (levelized cost of electricity) of the back end fuel cycle. Expanded nuclear power program with further construction of nuclear power plant (continuous use and/or the reunification) is a major political variable for LCOE. To keep the cost of nuclear power as low as possible, it is very important to have a proper strategy for the back-end fuel cycle including decommissioning. For continued use of nuclear energy, the Korea needs to develop soon a long-term policy for the back-end fuel cycle rather than taking the 'sit and watch' approach to make best out of the use of nuclear power into the future

Development of a computer program for the cost analysis of spent fuel management

International Nuclear Information System (INIS)

Choi, Heui Joo; Lee, Jong Youl; Choi, Jong Won; Cha, Jeong Hun; Whang, Joo Ho

2009-01-01

So far, a substantial amount of spent fuels have been generated from the PWR and CANDU reactors. They are being temporarily stored at the nuclear power plant sites. It is expected that the temporary storage facility will be full of spent fuels by around 2016. The government plans to solve the problem by constructing an interim storage facility soon. The radioactive management act was enacted in 2008 to manage the spent fuels safety in Korea. According to the act, the radioactive waste management fund which will be used for the transportation, interim storage, and the final disposal of spent fuels has been established. The cost for the management of spent fuels is surprisingly high and could include a lot of uncertainty. KAERI and Kyunghee University have developed cost estimation tools to evaluate the cost for a spent fuel management based on an engineering design and calculation. It is not easy to develop a tool for a cost estimation under the situation that the national policy on a spent fuel management has not yet been fixed at all. Thus, the current version of the computer program is based on the current conceptual design of each management system. The main purpose of this paper is to introduce the computer program developed for the cost analysis of a spent fuel management. In order to show the application of the program, a spent fuel management scenario is prepared, and the cost for the scenario is estimated

The incremental cost of switching from Option B to Option B+ for the prevention of mother-to-child transmission of HIV.

Science.gov (United States)

O'Brien, Lisa; Shaffer, Nathan; Sangrujee, Nalinee; Abimbola, Taiwo O

2014-03-01

To estimate the incremental cost over 5 years of a policy switch from the Option B to the Option B+ protocol for the prevention of mother-to-child transmission (PMTCT) of the human immunodeficiency virus (HIV). Data from cost studies and other published sources were used to determine the cost, per woman and per cohort (1000 breastfeeding and 1000 non-breastfeeding women), of switching from Option B (maternal triple antiretroviral [ARV] regimen during pregnancy and breastfeeding plus daily nevirapine for the infant for 6 weeks) to Option B+ (maternal triple ARV regimen initiated during pregnancy and continued for life). The variables used to model the different scenarios were maternal CD4+ T lymphocyte (CD4+ cell) count (350-500 versus > 500 cells/µl), rate of decline in CD4+ cells (average, rapid, slow), breastfeeding status (yes, no) and breastfeeding duration (12, 18 or 24 months). For women with CD4+ cell counts of 350-500 cells/µl, the incremental cost per 1000 women was 157,345 United States dollars (US$) for breastfeeding women and US$ 92,813 for non-breastfeeding women. For women with CD4+ cell counts > 500 cells/µl, the incremental cost per 1000 women ranged from US$ 363,443 to US$ 484,591 for breastfeeding women and was US$ 605,739 for non-breastfeeding women. From a cost perspective, a policy switch from Option B to Option B+ is feasible in PMTCT programme settings where resources are currently being allocated to Option B.

Optimal dual-fuel propulsion for minimum inert weight or minimum fuel cost

Science.gov (United States)

Martin, J. A.

1973-01-01

An analytical investigation of single-stage vehicles with multiple propulsion phases has been conducted with the phasing optimized to minimize a general cost function. Some results are presented for linearized sizing relationships which indicate that single-stage-to-orbit, dual-fuel rocket vehicles can have lower inert weight than similar single-fuel rocket vehicles and that the advantage of dual-fuel vehicles can be increased if a dual-fuel engine is developed. The results also indicate that the optimum split can vary considerably with the choice of cost function to be minimized.

Cheaper fuel and higher health costs among the poor in rural Nepal

Energy Technology Data Exchange (ETDEWEB)

Pant, Krishna Prasad [Ministry of Agriculture and Cooperatives, Vidhya Lane, Devnagar, Kathmandu (Nepal)], email: kppant@yahoo.com

2012-03-15

Biomass fuels are used by the majority of resource poor households in low-income countries. Though biomass fuels, such as dung-briquette and firewood are apparently cheaper than the modern fuels indoor pollution from burning biomass fuels incurs high health costs. But, the health costs of these conventional fuels, mostly being indirect, are poorly understood. To address this gap, this study develops probit regression models using survey data generated through interviews from households using either dung-briquette or biogas as the primary source of fuel for cooking. The study investigates factors affecting the use of dung-briquette, assesses its impact on human health, and estimates the associated household health costs. Analysis suggests significant effects of dung-briquette on asthma and eye diseases. Despite of the perception of it being a cheap fuel, the annual health cost per household due to burning dung-briquette (US$ 16.94) is 61.3% higher than the annual cost of biogas (US$ 10.38), an alternative cleaner fuel for rural households. For reducing the use of dung-briquette and its indirect health costs, the study recommends three interventions: (1) educate women and aboriginal people, in particular, and make them aware of the benefits of switching to biogas; (2) facilitate tree planting in communal as well as private lands; and (3) create rural employment and income generation opportunities.

The external cost of the nuclear fuel cycle

International Nuclear Information System (INIS)

Schieber, C.; Schneider, T.

2002-01-01

The external cost of the nuclear fuel cycle has been evaluated in the particular context of France as part of the European Commission's ExternE project. All the steps in the fuel cycle which involve the use of cutting edge technology were taken into consideration, from mining of uranium ores to waste disposal, via construction, dismantling of nuclear power plants and the transport of radioactive materials. The general methodology adopted in the study, known as the 'Impact Pathway Analysis', is based on a sequence of evaluations from source terms to the potential= effects on man and the environment, and then to their monetary evaluation, using a single framework devised for all the fuel cycles considered in the ExternE project. The resulting external cost is in the range of 2 to 3 mEuro/kWh when no discount rate is applied, and around 0.1 mEuro/kWh when a discount rate of 3% is considered. Further developments have been made on the external cost of a nuclear accident and on the integration of risk aversion in its evaluation. It appeared that the external cost of a nuclear accident would be about 0.04 mEuro/kWh, instead of 0.002 mEuro/kWh without taking risk aversion into account. (authors)

A comparison of hydrogen, methanol and gasoline as fuels for fuel cell vehicles: implications for vehicle design and infrastructure development

Science.gov (United States)

Ogden, Joan M.; Steinbugler, Margaret M.; Kreutz, Thomas G.

All fuel cells currently being developed for near term use in electric vehicles require hydrogen as a fuel. Hydrogen can be stored directly or produced onboard the vehicle by reforming methanol, or hydrocarbon fuels derived from crude oil (e.g., gasoline, diesel, or middle distillates). The vehicle design is simpler with direct hydrogen storage, but requires developing a more complex refueling infrastructure. In this paper, we present modeling results comparing three leading options for fuel storage onboard fuel cell vehicles: (a) compressed gas hydrogen storage, (b) onboard steam reforming of methanol, (c) onboard partial oxidation (POX) of hydrocarbon fuels derived from crude oil. We have developed a fuel cell vehicle model, including detailed models of onboard fuel processors. This allows us to compare the vehicle performance, fuel economy, weight, and cost for various vehicle parameters, fuel storage choices and driving cycles. The infrastructure requirements are also compared for gaseous hydrogen, methanol and gasoline, including the added costs of fuel production, storage, distribution and refueling stations. The delivered fuel cost, total lifecycle cost of transportation, and capital cost of infrastructure development are estimated for each alternative. Considering both vehicle and infrastructure issues, possible fuel strategies leading to the commercialization of fuel cell vehicles are discussed.

Economical Feedback of Increasing Fuel Enrichment on Electricity Cost for VVER-1000

Directory of Open Access Journals (Sweden)

Mohammed Saad Dwiddar

2015-08-01

Full Text Available A methodology of evaluating the economics of the front-end nuclear fuel cycle with a price change sensitivity analysis for a VVER-1000 reactor core as a case study is presented. The effect of increasing the fuel enrichment and its corresponding reactor cycle length on the energy cost is investigated. The enrichment component was found to represent the highly expenses dynamic component affecting the economics of the front-end fuel cycle. Nevertheless, the increase of the fuel enrichment will increase the reactor cycle length, which will have a positive feedback on the electricity generation cost (cent/KWh. A long reactor operation time with a cheaper energy cost set the nuclear energy as a competitive alternative when compared with other energy sources.

An options approach to investment in a hydrogen infrastructure

International Nuclear Information System (INIS)

Benthem, A.A. van; Kramer, G.J.; Ramer, R.

2006-01-01

This paper discusses the investments needed for the introduction of hydrogen as a transport fuel. Using option theory, we develop a model to calculate the value and optimal timing of a first commercial rollout of hydrogen vehicles in a larger area, taking Japan as a specific example. We find that the project is best viewed as an out-of-the-money call option with a small but positive option value. We estimate this value at approximately 1.5 billion euros, without tax advantages. An important finding is that the moment of investment is first and foremost determined by the maturing of the technology. By contrast, the investment timing is not as much affected by deployment strategy as is frequently thought: in particular, whether or not the hydrogen retail infrastructure is introduced smoothly does not sensitively influence the investment timing. Fairly independent of parameter assumptions, the project value at the moment of deployment is negative for the retailer and positive for the car manufacturer. This implies the need for a negotiated partnership. Finally, we assess various forms of government support, e.g. subsidies or tax cuts. Looking at the effectiveness of this support spending in relation to the advancement of hydrogen deployment, we find, again because investment timing is primarily determined by technology maturation, that tax incentives are relatively ineffective. We are lead to believe that government subsidy for technology development is a more effective means to achieve earlier investment, as faster production cost reductions for hydrogen and fuel cell vehicles lead to accelerated investment

Recycling and transmutation of spent fuel as a sustainable option for the nuclear energy development

International Nuclear Information System (INIS)

Maiorino, Jose R.; Moreira, Joao M.L.

2013-01-01

The objective of this paper is to discuss the option of recycling and transmutation of radioactive waste against Once-through Fuel Cycle (OTC) based on uranium feed under the perspective of sustainability. We use a qualitative analysis to compare OTC with closed fuel cycles based on studies already performed such as the Red Impact Project and the comparative study on accelerator driven systems and fast reactors for advanced fuel cycles performed by the Nuclear Energy Agency. The results show that recycling and transmutation fuel cycles are more attractive than the OTC from the point of view of sustainability. The main conclusion is that the decision about the construction of a deep geological repository for spent fuel disposal must be reevaluated. (author)

Cost allocation policy review: options and preferred alternatives

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-10-15

This policy review of the consultation process on the electricity cost allocation issue is presented with specific cost allocation policy issues addressed herein, such as: the new microFIT rate, accounting changes and the transition to IFRS, and review of allocating costs to load displacement generation. This report gave the current situation for all these issues, previous work, issues, viable options for dealing with these issues and the preferred alternatives.

Cost benefit analysis of two policy options for cannabis: status quo and legalisation.