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

An analysis of international nuclear fuel supply options

Science.gov (United States)

Taylor, J'tia Patrice

As the global demand for energy grows, many nations are considering developing or increasing nuclear capacity as a viable, long-term power source. To assess the possible expansion of nuclear power and the intricate relationships---which cover the range of economics, security, and material supply and demand---between established and aspirant nuclear generating entities requires models and system analysis tools that integrate all aspects of the nuclear enterprise. Computational tools and methods now exist across diverse research areas, such as operations research and nuclear engineering, to develop such a tool. This dissertation aims to develop methodologies and employ and expand on existing sources to develop a multipurpose tool to analyze international nuclear fuel supply options. The dissertation is comprised of two distinct components: the development of the Material, Economics, and Proliferation Assessment Tool (MEPAT), and analysis of fuel cycle scenarios using the tool. Development of MEPAT is aimed for unrestricted distribution and therefore uses publicly available and open-source codes in its development when possible. MEPAT is built using the Powersim Studio platform that is widely used in systems analysis. MEPAT development is divided into three modules focusing on: material movement; nonproliferation; and economics. The material movement module tracks material quantity in each process of the fuel cycle and in each nuclear program with respect to ownership, location and composition. The material movement module builds on techniques employed by fuel cycle models such as the Verifiable Fuel Cycle Simulation (VISION) code developed at the Idaho National Laboratory under the Advanced Fuel Cycle Initiative (AFCI) for the analysis of domestic fuel cycle. Material movement parameters such as lending and reactor preference, as well as fuel cycle parameters such as process times and material factors are user-specified through a Microsoft Excel(c) data spreadsheet

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

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

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

Treatment Options for Retinoblastoma

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other places in the body. Treatment Option Overview Key Points There are different types of ...

Influence of fuel costs on seawater desalination options

International Nuclear Information System (INIS)

Methnani, Mabrouk

2007-01-01

Reference estimates of seawater desalination costs for recent mega projects are all quoted in the range of US$0.50/m 3 . This however does not reflect the recent trends of escalating fossil fuel costs. In order to analyze the effect of these trends, a recently updated version of the IAEA Desalination Economic Evaluation Program, DEEP-3, has been used to compare fossil and nuclear seawater desalination options, under varied fuel cost and interest rate scenarios. Results presented for a gas combined-cycle and a modular high-temperature gas-cooled reactor design, show clear cost advantages for the latter, for both Multi-Effect Distillation (MED) and Reverse Osmosis (RO). Water production cost estimates for the Brayton cycle nuclear option are hardly affected by fuel costs, while combined cycle seawater desalination costs show an increase of more than 40% when fuel costs are doubled. For all cases run, the nuclear desalination costs are lower and if the current trend in fossil fuel prices continues as predicted by pessimist scenarios and the carbon tax carried by greenhouse emissions is enforced in the future, the cost advantage for nuclear desalination will be even more pronounced. Increasing the interest rate from 5 to 8% has a smaller effect than fuel cost variations. It translates into a water cost increase in the range of 10-20%, with the nuclear option being the more sensitive. (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

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)

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

Deployment Evaluation Methodology for the Electrometallurgical Treatment of DOE-EM Spent Nuclear Fuel

International Nuclear Information System (INIS)

Ramer, Ronald James; Adams, James Paul; Rynearson, Michael Ardel; Dahl, Christian Adam

1999-01-01

The Department of Energy - Environmental Management (DOE-EM) National Spent Nuclear Fuel Program (NSNFP) is charged with the disposition of legacy Spent Nuclear Fuel (SNF). The NSNFP, conducted by Lockheed Martin Idaho Technology Co. (LMITCO) at the Idaho National Engineering and Environmental Laboratory (INEEL), is evaluating final disposition of SNF in the DOE complex. While direct repository disposal of the SNF is the preferred disposition option, some DOE SNF may need treatment to meet acceptance criteria at various disposition sites. Evaluations of treatment needs and options have been previously prepared, and further evaluations are ongoing activities in the DOE-EM NSNFP. The treatments may range from electrometallurgical treatment (EMT) and chemical dissolution to engineering controls. As a planning basis, a need is assumed for a treatment process, either as a primary or backup technology, that is compatible with, and cost-effective for, this portion of the DOE-EM inventory. The current planning option for treating this SNF, pending completion of development work and National Environmental Policy Act (NEPA) analysis, is the EMT process under development by Argonne National Laboratory - West (ANL-W). A decision on the deployment of the EMT is pending completion of an engineering scale demonstration currently in progress at ANL-W. Treatment options and treatment locations will depend on fuel type and location of the fuel. One of the first steps associated with selecting one or more sites for treating SNF in the DOE complex is to determine the cost of each option. An economic analysis will assist in determining which fuel treatment alternative attains the optimum disposition of SNF at the lowest possible cost to the government and the public. One of the major issues associated with SNF treatment is final disposition of treatment products and associated waste streams. During conventional SNF treatment, various chemicals are added that may increase the product

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.

1996-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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 {sup 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 {sup 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.

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

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

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)

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.

Breast Cancer: Treatment Options

Science.gov (United States)

... Breast Cancer > Breast Cancer: Treatment Options Request Permissions Breast Cancer: Treatment Options Approved by the Cancer.Net Editorial ... can be addressed as quickly as possible. Recurrent breast cancer If the cancer does return after treatment for ...

Pyroprocessing of oxidized sodium-bonded fast reactor fuel - An experimental study of treatment options for degraded EBR-II fuel

Energy Technology Data Exchange (ETDEWEB)

Hermann, S.D.; Gese, N.J. [Separations Department, Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 (United States); Wurth, L.A. [Zinc Air Inc., 5314-A US Hwy 2 West, Columbia Falls, MT 59912 (United States)

2013-07-01

An experimental study was conducted to assess pyrochemical treatment options for degraded EBR-II fuel. As oxidized material, the degraded fuel would need to be converted back to metal to enable electrorefining within an existing electro-metallurgical treatment process. A lithium-based electrolytic reduction process was studied to assess the efficacy of converting oxide materials to metal with a particular focus on the impact of zirconium oxide and sodium oxide on this process. Bench-scale electrolytic reduction experiments were performed in LiCl-Li{sub 2}O at 650 C. degrees with combinations of manganese oxide (used as a surrogate for uranium oxide), zirconium oxide, and sodium oxide. In the absence of zirconium or sodium oxide, the electrolytic reduction of MnO showed nearly complete conversion to metal. The electrolytic reduction of a blend of MnO-ZrO{sub 2} in LiCl - 1 wt% Li{sub 2}O showed substantial reduction of manganese, but only 8.5% of the zirconium was found in the metal phase. The electrolytic reduction of the same blend of MnO-ZrO{sub 2} in LiCl - 1 wt% Li{sub 2}O - 6.2 wt% Na{sub 2}O showed substantial reduction of manganese, but zirconium reduction was even less at 2.4%. This study concluded that ZrO{sub 2} cannot be substantially reduced to metal in an electrolytic reduction system with LiCl - 1 wt% Li{sub 2}O at 650 C. degrees due to the perceived preferential formation of lithium zirconate. This study also identified a possible interference that sodium oxide may have on the same system by introducing a parasitic and cyclic reaction of dissolved sodium metal between oxidation at the anode and reduction at the cathode. When applied to oxidized sodium-bonded EBR-II fuel (e.g., U-10Zr), the prescribed electrolytic reduction system would not be expected to substantially reduce zirconium oxide, and the accumulation of sodium in the electrolyte could interfere with the reduction of uranium oxide, or at least render it less efficient.

Treatment Options for Wilms Tumor

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... come back) after it has been treated. Treatment Option Overview Key Points There are different types of ...

Treatment Options for Myelodysplastic Syndromes

Science.gov (United States)

... special light. Certain factors affect prognosis and treatment options. The prognosis (chance of recovery) and treatment options ... age and general health of the patient. Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Prostate Cancer)

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... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Myelodysplastic Syndromes)

Science.gov (United States)

... special light. Certain factors affect prognosis and treatment options. The prognosis (chance of recovery) and treatment options ... age and general health of the patient. Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Esophageal Cancer)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Childhood Rhabdomyosarcoma)

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... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Penile Cancer)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Vulvar Cancer)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Pancreatic Cancer)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Adrenocortical Carcinoma)

Science.gov (United States)

... affect the prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Options for Childhood Rhabdomyosarcoma

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Options for Kaposi Sarcoma

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Options for Childhood Craniopharyngioma

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... the brain where it was first found. Treatment Option Overview Key Points There are different types of ...

The EBR-II spent fuel treatment program

International Nuclear Information System (INIS)

Lineberry, M.J.; McFarlane, H.F.

1995-01-01

Argonne National Laboratory has refurbished and equipped an existing hot cell facility for demonstrating a high-temperature electrometallurgical process for treating spent nuclear fuel from the Experimental Breeder Reactor-11. Two waste forms will be produced and qualified for geologic disposal of the fission and activation products. Relatively pure uranium will be separated for storage. Following additional development, transuranium elements will be blended into one of the high-level waste streams. The spent fuel treatment program will help assess the viability of electrometallurgical technology as a spent fuel management option

Advances in HTGR spent fuel treatment technology

International Nuclear Information System (INIS)

Holder, N.D.; Lessig, W.S.

1984-08-01

GA Technologies, Inc. has been investigating the burning of spent reactor graphite under Department of Energy sponsorship since 1969. Several deep fluidized bed burners have been used at the GA pilot plant to develop graphite burning techniques for both spent fuel recovery and volume reduction for waste disposal. Since 1982 this technology has been extended to include more efficient circulating bed burners. This paper includes updates on high-temperature gas-cooled reactor fuel cycle options and current results of spent fuel treatment testing for fluidized and advanced circulating bed burners

Deployment Evaluation Methodology for the Electrometallurgical Treatment of DOE-EM Spent Nuclear Fuel

International Nuclear Information System (INIS)

Dahl, C.A.; Adams, J.P.; Rynearson, M.A.; Ramer, R.J.

1999-01-01

The Department of Energy - Environmental Management (DOE-EM) National Spent Nuclear Fuel Program (NSNFP) is charged with the disposition of legacy spent nuclear fuel (SNF). While direct repository disposal of the SNF is the preferred disposition option, some DOE SNF may need treatment to meet acceptance criteria at various disposition sites. The treatments may range from electrometallurgical treatment (EMT) and chemical dissolution to engineering controls. As a planning basis, a need is assumed for a treatment process, either as a primary or backup technology, that is compatible with, and cost-effective for, this portion of the DOE-EM inventory. The current planning option for treating this SNF, pending completion of development work and National Environmental Policy Act (NEPA) analysis, is the EMT process under development by Argonne National Laboratory - West (ANL-W). A decision on the deployment of the EMT is pending completion of an engineering scale demonstration currently in progress at ANL-W. For this study, a set of questions was developed for the EMT process for fuels at several locations. The set of questions addresses all issues associated with design, construction, and operation of a production facility. A matrix table was developed to determine questions applicable to various fuel treatment options. A work breakdown structure (WBS) was developed to identify a treatment process and costs from initial design to shipment of treatment products to final disposition. Costs were applied to determine the life-cycle cost of each option. This technique can also be applied to other treatment techniques for treating SNF

Treatment Option Overview (Myelodysplastic/Myeloproliferative Neoplasms)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ...

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

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)

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

Status of the back-end optional advanced research reactor fuel development in Korea

International Nuclear Information System (INIS)

Kim, Chang-Kyu; Lee, Yoon-Sang; Lee, Don-Bae; Oh, Seuk-Jin; Kim, Ki-Hwan; Chae, Hee-Taek; Park, Jong-Man; Sohn Dong-Seong

2003-01-01

U-Mo fuel development has been carried out for a reactor upgrade of HANARO and the back-end option in Korea. The 2nd irradiation test of the U-Mo dispersion rod fuels is underway in HANARO in order to find the optimum uranium loading density and to investigate the applicability of the monolithic U-Mo ring fuel as well as other parameters such as particle size and cladding surface-treatment. The optical observation using an immersion camera showed that the cladding surfaces of the two U 3 Si and U-Mo fuels with a high power rate changed in to the darker color, which is not as severe as those of the driving fuels in HANARO. Presumably it would be acceptable. The other fuels were observed as maintaining their initial good conditions. In connection with monolithic U-Mo fuel development, some achievements such as preliminary U-Mo tube production by a continuous casting process and a successful U-Mo foil production using a roll casting process have been obtained. In addition, some investigation on the surface-treatment of multilayer coating and Zr sputtering coating has showed the possibility of eliminating the problem of a temperature rise due to the corrosion layer formation having quite a low conductivity. The next irradiation test will aim mainly at the qualification of the U-Mo dispersion fuel for HANARO around the end of next year. In the 3rd irradiation fuel bundle, some fuels related to the basic investigation tests for the monolithic U-Mo fuel and surface-treatment for anticorrosion will be loaded. (author)

Treatment Option Overview (Chronic Lymphocytic Leukemia)

Science.gov (United States)

... examination under a microscope. Certain factors affect treatment options and prognosis (chance of recovery). Treatment options depend ... that does not get better with treatment. Treatment Option Overview Key Points There are different types of ...

Hairy Cell Leukemia Treatment Option Overview

Science.gov (United States)

... or a swollen spleen. Certain factors affect treatment options and prognosis (chance of recovery). The treatment options ... cell leukemia has not responded to treatment. Treatment Option Overview Key Points There are different types of ...

Treatment Options for Gastrointestinal Carcinoid Tumors

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... body. Has not gotten better with treatment. Treatment Option Overview Key Points There are different types of ...

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.

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

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.

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. 

Treatment Options by Stage (Pancreatic Cancer)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Options by Stage (Esophageal Cancer)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Options by Stage (Vulvar Cancer)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Options by Stage (Penile Cancer)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Options for Non-Hodgkin Lymphoma

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... lymphoma may come back as indolent lymphoma. Treatment Option Overview Key Points There are different types of ...

Treatment Options by Stage (Prostate Cancer)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Options by Stage (Adrenocortical Carcinoma)

Science.gov (United States)

... affect the prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Options for Childhood Hodgkin Lymphoma

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... the lungs , liver , bones, or bone marrow . Treatment Option Overview Key Points There are different types of ...

Treatment Options for Adult Hodgkin Lymphoma

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Small Intestine Cancer)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Adult Hodgkin Lymphoma)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Merkel Cell Carcinoma)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... common for Merkel cell carcinoma to recur. Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Childhood Hodgkin Lymphoma)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... the lungs , liver , bones, or bone marrow . Treatment Option Overview Key Points There are different types of ...

Treatment Options for AIDS-Related Lymphoma

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... nervous system is not primary CNS lymphoma. Treatment Option Overview Key Points There are different types of ...

Treatment Options for Renal Cell Cancer

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Options by Stage (Gastric Cancer)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... such as the liver or lymph nodes . Treatment Option Overview Key Points There are different types of ...

Treatment Options by Stage (Thyroid Cancer)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Options for Chronic Myelogenous Leukemia

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... of blast cells increases after a remission . Treatment Option Overview Key Points There are different types of ...

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

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...

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)

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)

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.

Treatment Options for Actinic Keratosis

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) depends mostly on ... helped by lip balm or petroleum jelly . Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Vaginal Cancer)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) depends on the ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Anal Cancer)

Science.gov (United States)

... affect the prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) depends on the ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Options by Stage (Chronic Lymphocytic Leukemia)

Science.gov (United States)

... examination under a microscope. Certain factors affect treatment options and prognosis (chance of recovery). Treatment options depend ... that does not get better with treatment. Treatment Option Overview Key Points There are different types of ...

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.

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)

Traditional preventive treatment options

DEFF Research Database (Denmark)

Longbottom, C; Ekstrand, K; Zero, D

2009-01-01

Preventive treatment options can be divided into primary, secondary and tertiary prevention techniques, which can involve patient- or professionally applied methods. These include: oral hygiene (instruction), pit and fissure sealants ('temporary' or 'permanent'), fluoride applications (patient...... options....

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

Treatment Options for Adult Soft Tissue Sarcoma

Science.gov (United States)

... reacts to the light. Certain factors affect treatment options and prognosis (chance of recovery). The treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Options by Stage (Merkel Cell Carcinoma)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... common for Merkel cell carcinoma to recur. Treatment Option Overview Key Points There are different types of ...

Treatment Options for Hodgkin Lymphoma during Pregnancy

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Adult Soft Tissue Sarcoma)

Science.gov (United States)

... reacts to the light. Certain factors affect treatment options and prognosis (chance of recovery). The treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Adult Non-Hodgkin Lymphoma)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... lymphoma may come back as indolent lymphoma. Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Small Cell Lung Cancer)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Adult Acute Lymphoblastic Leukemia)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... marrow , or other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Options for Adult Acute Lymphoblastic Leukemia

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... marrow , or other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Options for Adult Acute Myeloid Leukemia

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... back in the blood or bone marrow . Treatment Option Overview Key Points There are different types of ...

Using fine-scale fuel measurements to assess wildland fuels, potential fire behavior and hazard mitigation treatments in the southeastern USA

International Nuclear Information System (INIS)

Ottmar, Roger D.; Blake, John I.; Crolly, William T.

2012-01-01

The inherent spatial and temporal heterogeneity of fuelbeds in forests of the southeastern United States may require fine scale fuel measurements for providing reliable fire hazard and fuel treatment effectiveness estimates. In a series of five papers, an intensive, fine scale fuel inventory from the Savanna River Site in the southeastern United States is used for building fuelbeds and mapping fire behavior potential, evaluating fuel treatment options for effectiveness, and providing a comparative analysis of landscape modeled fire behavior using three different data sources including the Fuel Characteristic Classification System, LANDFIRE, and the Southern Wildfire Risk Assessment. The research demonstrates that fine scale fuel measurements associated with fuel inventories repeated over time can be used to assess broad scale wildland fire potential and hazard mitigation treatment effectiveness in the southeastern USA and similar fire prone regions. Additional investigations will be needed to modify and improve these processes and capture the true potential of these fine scale data sets for fire and fuel management planning.

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

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

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.

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)

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

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

Assessment of Options for the Treatment of Nitrate Salt Wastes at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Robinson, Bruce Alan; Funk, David John; Stevens, Patrice Ann

2016-01-01

This paper summarizes the methodology used to evaluate options for treatment of the remediated nitrate salt waste containers at Los Alamos National Laboratory. The method selected must enable treatment of the waste drums, which consist of a mixture of complex nitrate salts (oxidizer) improperly mixed with sWheat Scoop®1, an organic kitty litter and absorbent (fuel), in a manner that renders the waste safe, meets the specifications of waste acceptance criteria, and is suitable for transport and final disposal in the Waste Isolation Pilot Plant located in Carlsbad, New Mexico. A Core Remediation Team was responsible for comprehensively reviewing the options, ensuring a robust, defensible treatment recommendation. The evaluation process consisted of two steps. First, a prescreening process was conducted to cull the list on the basis for a decision of feasibility of certain potential options with respect to the criteria. Then, the remaining potential options were evaluated and ranked against each of the criteria in a consistent methodology. Numerical scores were established by consensus of the review team. Finally, recommendations were developed based on current information and understanding of the scientific, technical, and regulatory situation. A discussion of the preferred options and documentation of the process used to reach the recommended treatment options are presented.

Assessment of Options for the Treatment of Nitrate Salt Wastes at Los Alamos National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Robinson, Bruce Alan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Funk, David John [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Stevens, Patrice Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-03-17

This paper summarizes the methodology used to evaluate options for treatment of the remediated nitrate salt waste containers at Los Alamos National Laboratory. The method selected must enable treatment of the waste drums, which consist of a mixture of complex nitrate salts (oxidizer) improperly mixed with sWheat Scoop®1, an organic kitty litter and absorbent (fuel), in a manner that renders the waste safe, meets the specifications of waste acceptance criteria, and is suitable for transport and final disposal in the Waste Isolation Pilot Plant located in Carlsbad, New Mexico. A Core Remediation Team was responsible for comprehensively reviewing the options, ensuring a robust, defensible treatment recommendation. The evaluation process consisted of two steps. First, a prescreening process was conducted to cull the list on the basis for a decision of feasibility of certain potential options with respect to the criteria. Then, the remaining potential options were evaluated and ranked against each of the criteria in a consistent methodology. Numerical scores were established by consensus of the review team. Finally, recommendations were developed based on current information and understanding of the scientific, technical, and regulatory situation. A discussion of the preferred options and documentation of the process used to reach the recommended treatment options are presented.

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)

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.

Novel preventive treatment options

DEFF Research Database (Denmark)

Longbottom, C; Ekstrand, K; Zero, D

2009-01-01

A number of novel preventive treatment options which, as with traditional methods, can be differentiated into 3 categories of prevention (primary, secondary and tertiary), have been and are being currently investigated. Those reviewed are either commercially available or appear relatively close...... of these techniques show considerable promise and dentists should be aware of these developments and follow their progress, the evidence for each of these novel preventive treatment options is currently insufficient to make widespread recommendations. Changes in dental practice should be explored to see how oral...

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

Treatment Options by Stage (Vaginal Cancer)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) depends on the ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Options for Chronic Myeloproliferative Neoplasms

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options for primary myelofibrosis. Prognosis (chance of recovery ) depends ... factors affect prognosis (chance of recovery) and treatment options for essential thrombocythemia. Prognosis (chance of recovery ) and ...

Treatment Options for Nonmelanoma Skin Cancer

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) depends mostly on ... helped by lip balm or petroleum jelly . Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Chronic Myeloproliferative Neoplasms)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options for primary myelofibrosis. Prognosis (chance of recovery ) depends ... factors affect prognosis (chance of recovery) and treatment options for essential thrombocythemia. Prognosis (chance of recovery ) and ...

Deployment evaluation methodology for the electrometallurgical treatment of DOE-EM spent nuclear fuel

International Nuclear Information System (INIS)

Dahl, C.A.; Adams, J.P.; Ramer, R.J.

1998-07-01

Part of the Department of Energy (DOE) spent nuclear fuel (SNF) inventory may require some type of treatment to meet acceptance criteria at various disposition sites. The current focus for much of this spent nuclear fuel is the electrometallurgical treatment process under development at Argonne National Laboratory. Potential flowsheets for this treatment process are presented. Deployment of the process for the treatment of the spent nuclear fuel requires evaluation to determine the spent nuclear fuel program need for treatment and compatibility of the spent nuclear fuel with the process. The evaluation of need includes considerations of cost, technical feasibility, process material disposition, and schedule to treat a proposed fuel. A siting evaluation methodology has been developed to account for these variables. A work breakdown structure is proposed to gather life-cycle cost information to allow evaluation of alternative siting strategies on a similar basis. The evaluation methodology, while created specifically for the electrometallurgical evaluation, has been written such that it could be applied to any potential treatment process that is a disposition option for spent nuclear fuel. Future work to complete the evaluation of the process for electrometallurgical treatment is discussed

Treatment Option Overview (Kaposi Sarcoma)

Science.gov (United States)

... Treatment Childhood Vascular Tumors Treatment Research Kaposi Sarcoma Treatment (PDQ®)–Patient Version General Information About Kaposi Sarcoma ... Certain factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment ...

Treatment Options by Stage (Small Cell Lung Cancer)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

Treatment Option Overview (Childhood Acute Lymphoblastic Leukemia)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) depends on: How ... cancer that does not respond to treatment. Treatment Option Overview Key Points There are different types of ...

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

Treatment Option Overview (Ewing Sarcoma)

Science.gov (United States)

... Ewing Sarcoma Treatment Osteosarcoma Treatment Research Ewing Sarcoma Treatment (PDQ®)–Patient Version General Information About Ewing Sarcoma ... started or in another part of the body. Treatment Option Overview Key Points There are different types ...

Treatment Option Overview (Ovarian Germ Cell Tumors)

Science.gov (United States)

... Germ Cell Tumors Treatment (PDQ®)–Patient Version Treatment Option Overview Go to Health Professional Version Key Points ... and restore) the body’s blood cells. New treatment options Combination chemotherapy (the use of more than one ...

Graphite fuels combustion off-gas treatment options

International Nuclear Information System (INIS)

Kirkham, R.J.; Lords, R.E.

1993-03-01

Scenarios for burning bulk graphite and for burning crushed fuel particles from graphite spent nuclear fuels have been considered. Particulates can be removed with sintered metal filters. Subsequent cooling would then condense semi-volatile fission products into or onto a particulate. These particulates would be trapped by a second sintered metal filter or downstream packed bed. A packed bed scrub column can be used to eliminate most of the iodine-129 and tritium. A molecular sieve bed is proposed to collect the residual 129 I and other tramp radionuclides downstream (Ruthenium, etc.). Krypton-85 can be recovered, if need be, either by cryogenics or by the KALC process (Krypton Adsorption in Liquid Carbon dioxide). Likewise carbon-14 in the form of carbon dioxide could be collected with a caustic or lime scrub solution and incorporated into a grout. Sulfur dioxide present will be well below regulatory concern level of 4.0 tons per year and most of it would be removed by the scrubber. Carbon monoxide emissions will depend on the choice of burner and start-up conditions. Should the system exceed the regulatory concern level, a catalytic converter in the final packed bed will be provided. Radon and its daughters have sufficiently short half-lives (less than two minutes). If necessary, an additional holdup bed can be added before the final HEPA filters or additional volume can be added to the molecular sieve bed to limit radon emissions. The calculated total effective dose equivalent at the Idaho National Engineering Laboratory boundary from a single release of all the 3 , 14 C, 85 Kr, and 129 I in the total fuel mass if 0.43 mrem/year

Treatment options for Primary CNS Lymphoma.

Science.gov (United States)

Laghari, Altaf Ali; Ahmed, Syed Ijlal; Jabbar, Adnan; Shamim, Muhammad Shahzad

2018-03-01

Primary CNS lymphoma (PCNSL) is a rare and aggressive brain tumour that is uniformly fatal. The rarity of the disease and the poor response to treatment makes it difficult to reach a consensus with regards to treatment options. In this review, the authors have discussed different treatment modalities used in the management of PCNSL including chemotherapy, surgery and radiation, as well as the results of recent clinical trials on treatment options for PCNSL.

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

40 CFR 270.235 - Options for incinerators, cement kilns, lightweight aggregate kilns, solid fuel boilers, liquid...

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Options for incinerators, cement kilns... Technology (MACT) Standards § 270.235 Options for incinerators, cement kilns, lightweight aggregate kilns... incinerator, cement kiln, lightweight aggregate kiln, solid fuel boiler, liquid fuel boiler, or hydrochloric...

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

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.

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)

Nail Psoriasis: A Review of Treatment Options.

Science.gov (United States)

Pasch, Marcel C

2016-04-01

Nail involvement affects 80-90 % of patients with plaque psoriasis, and is even more prevalent in patients with psoriatic arthritis. This review is the result of a systemic approach to the literature and covers topical, intralesional, conventional systemic, and biologic systemic treatments, as well as non-pharmacological treatment options for nail psoriasis. The available evidence suggests that all anti-tumor necrosis factor-α, anti-interleukin (IL)-17, and anti-IL-12/23 antibodies which are available for plaque psoriasis and psoriatic arthritis are highly effective treatments for nail psoriasis. Conventional systemic treatments, including methotrexate, cyclosporine, acitretin, and apremilast, as well as intralesional corticosteroids, can also be effective treatments for nail psoriasis. Topical treatments, including corticosteroids, calcipotriol, tacrolimus, and tazarotene, have also been shown to have a position in the treatment of nail psoriasis, particularly in mild cases. Finally, non-pharmacological treatment options, including phototherapy, photodynamic therapy, laser therapy, and several radiotherapeutic options, are also reviewed but cannot be advised as first-line treatment options. Another conclusion of this review is that the lack of a reliable core set of outcomes measures for trials in nail psoriasis hinders the interpretation of results, and is urgently needed.

Spatial analysis of fuel treatment options for chaparral on the Angeles national forest

Science.gov (United States)

G. Jones; J. Chew; R. Silverstein; C. Stalling; J. Sullivan; J. Troutwine; D. Weise; D. Garwood

2008-01-01

Spatial fuel treatment schedules were developed for the chaparral vegetation type on the Angeles National Forest using the Multi-resource Analysis and Geographic Information System (MAGIS). Schedules varied by the priority given to various wildland urban interface areas and the general forest, as well as by the number of acres treated per decade. The effectiveness of...

Treatment Option Overview (Mycosis Fungoides and the Sezary Syndrome)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... or in other parts of the body. Treatment Option Overview Key Points There are different types of ...

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.

40 CFR 80.552 - What compliance options are available to motor vehicle diesel fuel small refiners?

Science.gov (United States)

2010-07-01

... to motor vehicle diesel fuel small refiners? 80.552 Section 80.552 Protection of Environment... Motor Vehicle Diesel Fuel; Nonroad, Locomotive, and Marine Diesel Fuel; and ECA Marine Fuel Small Refiner Hardship Provisions § 80.552 What compliance options are available to motor vehicle diesel fuel...

National Option of China's Nuclear Energy Systems for Spent Fuel Management

Energy Technology Data Exchange (ETDEWEB)

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

2015-10-15

Along with safety concerns, these long standing environmental challenges are the major factors influencing the public acceptance of nuclear power. Although nuclear power plays an important role in reducing carbon emissions from energy generation, this could not fully prove it as a sustainable energy source unless we find a consensus approach to treat the nuclear wastes. There are currently no countries that have completed a whole nuclear fuel cycle, and the relative comparison of the reprocessing spent fuel options versus direct disposal option is always a controversial issue. Without exception, nowadays, China is implementing many R and D projects on spent fuel management to find a long-term solution for nuclear fuel cycle system transition, such as deep geological repositories for High Level Waste (HLW), Pu Reduction by Solvent Extraction (PUREX) technology, and fast reactor recycling Mixed U-Pu Oxide (MOX) fuels, etc. This paper integrates the current nation's projects of back-end fuel cycle, analyzes the consequences of potential successes, failures and delays in the project development to future nuclear fuel cycle transition up to 2100. We compared the dynamic results of four scenarios and then assessed relative impact on spent fuel management. The result revealed that the fuel cycle transition of reprocessing and recycling of spent fuel would bring advantages to overall nuclear systems by reducing high level waste inventory, saving natural uranium resources, and reducing plutonium management risk.

Treatment Options By Stage (Ovarian Germ Cell Tumors)

Science.gov (United States)

... Germ Cell Tumors Treatment (PDQ®)–Patient Version Treatment Option Overview Go to Health Professional Version Key Points ... and restore) the body’s blood cells. New treatment options Combination chemotherapy (the use of more than one ...

Effects of SO2 emission regulations and fuel prices on levellized energy costs for industrial steam generation options

International Nuclear Information System (INIS)

Ozdogan, Sibel; Arikol, Mahir

1992-01-01

We discuss the impacts of SO 2 emission regulations and fuel prices on levellized energy costs of industrial steam generation options. A computer model called INDUSTEAM has been utilized. The steam-supply options comprise conventional grate-firing, bubbling and circulating fluidized beds, fuel-oil, and natural-gas-fired systems. Fuels of different SO 2 pollution potential have been evaluated assuming six environmental scenarios and varying fuel prices. A capacity range of 10-90 MW th is covered. (author)

Treatment Option Overview (Childhood Acute Myeloid Leukemia/Other Myeloid Malignancies)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... the cancer does not respond to treatment. Treatment Option Overview Key Points There are different types of ...

Integrated model of Korean spent fuel and high level waste disposal options - 16091

International Nuclear Information System (INIS)

Hwang, Yongsoo; Miller, Ian

2009-01-01

This paper describes an integrated model developed by the Korean Atomic Energy Research Institute (KAERI) to simulate options for disposal of spent nuclear fuel (SNF) and reprocessing products in South Korea. A companion paper (Hwang and Miller, 2009) describes a systems-level model of Korean options for spent nuclear fuel (SNF) management in the 21. century. The model addresses alternative design concepts for disposal of SNF of different types (Candu, PWR), high level waste, and fission products arising from a variety of alternative fuel cycle back ends. It uses the GoldSim software to simulate the engineered system, near-field and far-field geosphere, and biosphere, resulting in long-term dose predictions for a variety of receptor groups. The model's results allow direct comparison of alternative repository design concepts, and identification of key parameter uncertainties and contributors to receptor doses. (authors)

The generation of denatured reactor plutonium by different options of the fuel cycle

Energy Technology Data Exchange (ETDEWEB)

Broeders, C.H.M.; Kessler, G. [Inst. for Neutron Physics and Reactor Technology, Research Center Karlsruhe (Germany)

2006-11-15

Denatured (proliferation resistant) reactor plutonium can be generated in a number of different fuel cycle options. First denatured reactor plutonium can be obtained if, instead of low enriched U-235 PWR fuel, re-enriched U-235/U-236 from reprocessed uranium is used (fuel type A). Also the envisaged existing 2,500 t of reactor plutonium (being generated world wide up to the year 2010), mostly stored in intermediate fuel storage facilities at present, could be converted during a transition phase into denatured reactor plutonium by the options fuel type B and D. Denatured reactor plutonium could have the same safeguards standard as present low enriched (<20% U-235) LWR fuel. It could be incinerated by recycling once or twice in PWRs and subsequently by multi-recycling in FRs (CAPRA type or IFRs). Once denatured, such reactor plutonium could remain denatured during multiple recycling. In a PWR, e.g., denatured reactor plutonium could be destroyed at a rate of about 250 kg/GWey. While denatured reactor plutonium could be recycled and incinerated under relieved IAEA safeguards, neptunium would still have to be monitored by the IAEA in future for all cases in which considerable amounts of neptunium are produced. (orig.)

Treatment Option Overview (Wilms Tumor and Other Childhood Kidney Tumors)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) and treatment options ... come back) after it has been treated. Treatment Option Overview Key Points There are different types of ...

Cost-Effective Fuel Treatment Planning

Science.gov (United States)

Kreitler, J.; Thompson, M.; Vaillant, N.

2014-12-01

The cost of fighting large wildland fires in the western United States has grown dramatically over the past decade. This trend will likely continue with growth of the WUI into fire prone ecosystems, dangerous fuel conditions from decades of fire suppression, and a potentially increasing effect from prolonged drought and climate change. Fuel treatments are often considered the primary pre-fire mechanism to reduce the exposure of values at risk to wildland fire, and a growing suite of fire models and tools are employed to prioritize where treatments could mitigate wildland fire damages. Assessments using the likelihood and consequence of fire are critical because funds are insufficient to reduce risk on all lands needing treatment, therefore prioritization is required to maximize the effectiveness of fuel treatment budgets. Cost-effectiveness, doing the most good per dollar, would seem to be an important fuel treatment metric, yet studies or plans that prioritize fuel treatments using costs or cost-effectiveness measures are absent from the literature. Therefore, to explore the effect of using costs in fuel treatment planning we test four prioritization algorithms designed to reduce risk in a case study examining fuel treatments on the Sisters Ranger District of central Oregon. For benefits we model sediment retention and standing biomass, and measure the effectiveness of each algorithm by comparing the differences among treatment and no treat alternative scenarios. Our objective is to maximize the averted loss of net benefits subject to a representative fuel treatment budget. We model costs across the study landscape using the My Fuel Treatment Planner software, tree list data, local mill prices, and GIS-measured site characteristics. We use fire simulations to generate burn probabilities, and estimate fire intensity as conditional flame length at each pixel. Two prioritization algorithms target treatments based on cost-effectiveness and show improvements over those

Treatment Option Overview (Plasma Cell Neoplasms Including Multiple Myeloma)

Science.gov (United States)

... factors affect prognosis (chance of recovery) and treatment options. The prognosis (chance of recovery ) depends on the ... going up even though treatment is given. Treatment Option Overview Key Points There are different types of ...

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

Look at potential options for the fast reactor fuel cycle in the United States

International Nuclear Information System (INIS)

Burch, W.D.

1984-01-01

This paper reviews the status and plans for the fast reactor fuel cycle in the United States, presents some options that are under consideration, and describes how these options are being evaluated at the present time. The United States will undertake some far-reaching examinations of the entire breeder program strategy in the coming year, and the outcome of these reviews cannot be predicted today. In other papers at this conference you have heard various perspectives from both government and industry representatives. The proposed studies to examine the associated fuel cycle strategies as they relate to the overall emerging breeder strategy are described. The present status of and recent developments in the fuel cycle R and D programs will also be summarized and updated in order to present an overall picture of the United States situation

Options Study - Phase II

Energy Technology Data Exchange (ETDEWEB)

R. Wigeland; T. Taiwo; M. Todosow; W. Halsey; J. Gehin

2010-09-01

The Options Study has been conducted for the purpose of evaluating the potential of alternative integrated nuclear fuel cycle options to favorably address the issues associated with a continuing or expanding use of nuclear power in the United States. The study produced information that can be used to inform decisions identifying potential directions for research and development on such fuel cycle options. An integrated nuclear fuel cycle option is defined in this study as including all aspects of the entire nuclear fuel cycle, from obtaining natural resources for fuel to the ultimate disposal of used nuclear fuel (UNF) or radioactive wastes. Issues such as nuclear waste management, especially the increasing inventory of used nuclear fuel, the current uncertainty about used fuel disposal, and the risk of nuclear weapons proliferation have contributed to the reluctance to expand the use of nuclear power, even though it is recognized that nuclear power is a safe and reliable method of producing electricity. In this Options Study, current, evolutionary, and revolutionary nuclear energy options were all considered, including the use of uranium and thorium, and both once-through and recycle approaches. Available information has been collected and reviewed in order to evaluate the ability of an option to clearly address the challenges associated with the current implementation and potential expansion of commercial nuclear power in the United States. This Options Study is a comprehensive consideration and review of fuel cycle and technology options, including those for disposal, and is not constrained by any limitations that may be imposed by economics, technical maturity, past policy, or speculated future conditions. This Phase II report is intended to be used in conjunction with the Phase I report, and much information in that report is not repeated here, although some information has been updated to reflect recent developments. The focus in this Options Study was to

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)

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

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

Fibromyalgia Pathogenesis and Treatment Options Update.

Science.gov (United States)

Chinn, Steven; Caldwell, William; Gritsenko, Karina

2016-04-01

This review article presents and summarizes up-to-date literature on the clinical manifestations, diagnosis, pathophysiological mechanisms, and treatment options for fibromyalgia patients. First, the most recent diagnostic criteria for fibromyalgia, as put forth by the American College of Rheumatology will be summarized. Clinical features, including chronic widespread pain, hyperalgesia, mood disorders, anxiety, and disturbed sleep patterns will be explored in-depth. The pathogenesis and pathophysiology of fibromyalgia involves alterations in multiple ascending and descending central nervous system pathways, as well as peripheral pathways, leading to heightened pain sensitivity. Risk factors have been studied extensively, and the most recent research focuses on various genetic influences and the contributions of stress and poor sleep. Lastly, the discussion in this article focuses on treatment options for fibromyalgia; some have been mainstay options for many years. Pharmacological agents include tricyclic antidepressants, anti-epileptic drugs, selective serotonin reuptake inhibitors, norepinephrine/serotonin reuptake inhibitors, as well as some investigational agents. The evidence behind non-pharmacologic treatments, including massage therapy, exercise, and acupuncture, are discussed.

Enhanced CANDU6: Reactor and fuel cycle options - Natural uranium and beyond

International Nuclear Information System (INIS)

Ovanes, M.; Chan, P. S. W.; Mao, J.; Alderson, N.; Hopwood, J. M.

2012-01-01

The Enhanced CANDU 6 R (ECo R ) is the updated version of the well established CANDU 6 family of units incorporating improved safety characteristics designed to meet or exceed Generation III nuclear power plant expectations. The EC6 retains the excellent neutron economy and fuel cycle flexibility that are inherent in the CANDU reactor design. The reference design is based on natural uranium fuel, but the EC6 is also able to utilize additional fuel options, including the use of Recovered Uranium (RU) and Thorium based fuels, without requiring major hardware upgrades to the existing control and safety systems. This paper outlines the major changes in the EC6 core design from the existing C6 design that significantly enhance the safety characteristics and operating efficiency of the reactor. The use of RU fuel as a transparent replacement fuel for the standard 37-el NU fuel, and several RU based advanced fuel designs that give significant improvements in fuel burnup and inherent safety characteristics are also discussed in the paper. In addition, the suitability of the EC6 to use MOX and related Pu-based fuels will also be discussed. (authors)

Current options for the treatment of pathological scarring.

Science.gov (United States)

Poetschke, Julian; Gauglitz, Gerd G

2016-05-01

Scarring is the consequence of surgery, trauma or different skin diseases. Apart from fresh, immature scars,that transform into mature scars over the course of would healing and that do not require further treatment,linear hypertrophic scars, widespread hypertrophic scars, keloids and atrophic scars exist. Symptoms like pruritusand pain, stigmatization as well as functional and aesthetic impairments that are very disturbing for the affected patients can bethe basis for the desire for treatment. Today, a multitude of options for the treatment and prevention of scars exists. Topical agents based on silicone or onion extract, intralesional injections of cristalline glucocorticoids (oftentimes in combinationwith cryotherapy) or 5-Fluorouracil as well as ablative and nonablative laser treatment are used. Current guidelines summarize the multitude of available treatment options and the currently available datafor the treating physicians, allowing them to make clear therapy recommendations for every single scar type. Relieving patients of their discomfort and doing their aesthetic demands justice is thus possible. Apart from scar prevention becoming more and more important, the increased use of modernlaser treatment options constitutes a key point in clinical scar treatment. At the same time the attention is turned to evaluating current therapeutic options with the help of contemporary study designs so as to graduallyimprove the level of evidence in scar treatment. © 2016 Deutsche Dermatologische Gesellschaft (DDG). Published by John Wiley & Sons Ltd.

Potential External (non-DOE) Constraints on U.S. Fuel Cycle Options

Energy Technology Data Exchange (ETDEWEB)

Steven J. Piet

2012-07-01

The DOE Fuel Cycle Technologies (FCT) Program will be conducting a screening of fuel cycle options in FY2013 to help focus fuel cycle R&D activities. As part of this screening, performance criteria and go/no-go criteria are being identified. To help ensure that these criteria are consistent with current policy, an effort was initiated to identify the status and basis of potentially relevant regulations, laws, and policies that have been established external to DOE. As such regulations, laws, and policies may be beyond DOE’s control to change, they may constrain the screening criteria and internally-developed policy. This report contains a historical survey and analysis of publically available domestic documents that could pertain to external constraints on advanced nuclear fuel cycles. “External” is defined as public documents outside DOE. This effort did not include survey and analysis of constraints established internal to DOE.

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

Fuel management options to extend the IRIS reactor cycle

International Nuclear Information System (INIS)

Petrovic, B.; Franceschini, F.

2004-01-01

To optimize plant operation, reduce scheduled maintenance outage, and increase capacity factor, IRIS is designed to enable extended cycles of up to four years. However, due to the enrichment licensing limitation (less than 5% enriched uranium oxide) there is a tradeoff between the achievable cycle length and fuel utilization, i.e., the average fuel discharge burnup. The longest individual cycle may be achieved with the single-batch straight burn, but at the expense of a lower burnup. Considering the IRIS basic performance requirements, a cycle length in the range of three to four years is deemed desirable. This paper examines different fuel management options, i.e., the influence of the required cycle length on the corresponding reloading strategy, including a two-batch and a three-batch reloading. A reference two-batch core design has been developed for the first cycle, as well as for the transition cycles leading to equilibrium. Main core performance parameters are evaluated. This core design provides the framework for the safety analyses needed to prepare the IRIS safety evaluations. Alternate designs are also considered.(author)

Impact of minor actinide recycling on sustainable fuel cycle options

Energy Technology Data Exchange (ETDEWEB)

Heidet, F.; Kim, T. K.; Taiwo, T. A.

2017-11-01

The recent Evaluation and Screening study chartered by the U.S. Department of Energy, Office of Nuclear Energy, has identified four fuel cycle options as being the most promising. Among these four options, the two single-stage fuel cycles rely on a fast reactor and are differing in the fact that in one case only uranium and plutonium are recycled while in the other case minor actinides are also recycled. The two other fuel cycles are two-stage and rely on both fast and thermal reactors. They also differ in the fact that in one case only uranium and plutonium are recycled while in the other case minor actinides are also recycled. The current study assesses the impact of recycling minor actinides on the reactor core design, its performance characteristics, and the characteristics of the recycled material and waste material. The recycling of minor actinides is found not to affect the reactor core performance, as long as the same cycle length, core layout and specific power are being used. One notable difference is that the required transuranics (TRU) content is slightly increased when minor actinides are recycled. The mass flows are mostly unchanged given a same specific power and cycle length. Although the material mass flows and reactor performance characteristics are hardly affected by recycling minor actinides, some differences are observed in the waste characteristics between the two fuel cycles considered. The absence of minor actinides in the waste results in a different buildup of decay products, and in somewhat different behaviors depending on the characteristic and time frame considered. Recycling of minor actinides is found to result in a reduction of the waste characteristics ranging from 10% to 90%. These results are consistent with previous studies in this domain and depending on the time frame considered, packaging conditions, repository site, repository strategy, the differences observed in the waste characteristics could be beneficial and help improve

Microwave treatment of BPH: still an option?

NARCIS (Netherlands)

de la Rosette, J. J.

1994-01-01

Surgery, the gold standard in the treatment of benign prostatic hyperplasia (BPH), is presently performed in the majority of patients who receive treatment. An increasing number of alternative options recently became available for treatment of BPH and especially minimal invasive treatment

Fuels planning: science synthesis and integration; environmental consequences fact sheet 06: wildland fire use: the "other" treatment option

Science.gov (United States)

Anne Black

2004-01-01

Fire suppression has reduced acres burned to an average of 2 million acres a year. An unfortunate result of this has been the accumulation of even more above-normal fuel loads in many areas. This paper discusses (1) the important ecological role of fire, (2) using fire as a fuels treatment, and (2) the benefits and risks of fire.

Alternative Cancer Treatments: 10 Options to Consider

Science.gov (United States)

Alternative cancer treatments: 10 options to consider Alternative cancer treatments can't cure your cancer, but they may provide some ... that may help them, including complementary and alternative cancer treatments. If cancer makes you feel as if you ...

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

Alternative fuel cycle options: performance characteristics and impact on nuclear power growth potential

International Nuclear Information System (INIS)

Chang, Y.I.; Till, C.E.; Rudolph, R.R.; Deen, J.R.; King, M.J.

1977-09-01

The fuel utilization characteristics for LWR, SSCR, CANDU and LMFBR reactor concepts are quantified for various fuel cycle options, including once-through cycles, thorium cycles, and denatured cycles. The implications of various alternative reactor deployment strategies on the long-term nuclear power growth potential are then quantified in terms of the maximum nuclear capacity that can be achieved and the growth pattern over time, subject to the constraint of a fixed uranium-resource base. The overall objective of this study is to shed light on any large differences in the long-term potential that exist between various alternative reactor/fuel cycle deployment strategies

Review of Saccharomyces boulardii as a treatment option in IBD

DEFF Research Database (Denmark)

Sivananthan, Kavitha; Petersen, Andreas Munk

2018-01-01

CONTEXT: Review of the yeast Saccharomyces boulardii as a treatment option for the inflammatory bowel diseases (IBD) ulcerative colitis and Crohn's disease. OBJECTIVE: IBD is caused by an inappropriate immune response to gut microbiota. Treatment options could therefore be prebiotics, probiotics......, antibiotics and/or fecal transplant. In this review, we have looked at the evidence for the yeast S. boulardii as a treatment option. MATERIAL AND METHODS: Searches in PubMed and the Cochrane Library with the MeSH words 'Saccharomyces boulardii AND IBD', 'Saccharomyces boulardii AND Inflammatory Bowel Disease....... Saccharomyces boulardii is, however, a plausible treatment option in the future, but more placebo-controlled clinical studies on both patients with ulcerative colitis and Crohn's disease are needed....

Treatment of spent fuels from research reactors and reactor development programs in Germany

International Nuclear Information System (INIS)

Closs, K.D.

1999-01-01

Quite a great number of different types of spent fuel from research reactors and development programs exists in Germany. The general policy is to send back to the USA as long as possible fuel from MTRs and TRIGAs of USA origin. An option is reprocessing in Great Britain or France. This option is pursued as long as reprocessing and reuse of the recovered material is economically justifiable. For those fuels which cannot be returned to the USA or which will not be reprocessed, a domestic back-up solution of spent fuel management has been developed in Germany, compatible with the management of spent fuel from power reactors. It consists in dry storage in special casks and, later on, direct disposal. Preliminary results from experimental R and D investigations with research reactor fuel and experience from LWR fuel lead to the conclusion that the direct disposal option even for research reactor fuel or exotic fuel does not impose major technical difficulties for the German waste management and disposal concept. (author)

Achalasia: Treatment Options Revisited

Directory of Open Access Journals (Sweden)

Willemijntje A Hoogerwerf

2000-01-01

Full Text Available The aim of all current forms of treatment of achalasia is to enable the patient to eat without disabling symptoms such as dysphagia, regurgitation, coughing or choking. Historically, this has been accomplished by mechanical disruption of the lower esophageal sphincter fibres, either by means of pneumatic dilation (PD or by open surgical myotomy. The addition of laparoscopic myotomy and botulinum toxin (BTX injection to the therapeutic armamentarium has triggered a recent series of reviews to determine the optimal therapeutic approach. Both PD and BTX have excellent short term (less than three months efficacy in the majority of patients. New data have been published that suggest that PD and BTX (with repeat injections can potentially obtain long term efficacy. PD is still considered the first-line treatment by most physicians; its main disadvantage is risk of perforation. BTX injection is evolving as an excellent, safe option for patients who are considered high risk for more invasive procedures. Laparoscopic myotomy with combined antireflux surgery is an increasingly attractive option in younger patients with achalasia, but long term follow-up studies are required to establish its efficacy and the potential for reflux-related sequelae.

Spent fuel from RA reactor inspection of state and options for management

International Nuclear Information System (INIS)

Aden, V.G.; Bulkin, S. Yu.; Sokolov, A. V.; Matausek, M.V.; Vukadin, Z.

2001-01-01

About five thousand spent fuel elements from RA reactor have been stored for over 30 years in sealed aluminum barrels in the spent fuel storage pool. This way of storage does not provide complete information about the state of spent fuel elements or the medium inside the barrels, like pressure or radioactivity. The technology has been developed and the equipment has been manufactured to inspect the state of the spent fuel and to reduce eventual internal pressure inside the aluminum barrels. The realization of this technology was started in 1999 but due to political and financial difficulties was not completed. In September the year 2000 the work was restarted. Two different ways of RA reactor spent fuel elements preparation for transportation or long-term storage are considered: 'all fuel elements canning without leak-tightness testing' and 'all fuel elements leak-tightness testing'. It is believed that the first option offers several distinct advantages, which can be summarized as: greater reliability in the course of transportation or dry storage. Higher safety for workers. Lower expenditures for non-standard equipment manufacturing. Shorter duration of work. (author)

Analysis of radwaste material management options for experimental DUPIC fuel fabrication process

Energy Technology Data Exchange (ETDEWEB)

Lee, H. H.; Park, J. J.; Yang, M. S.; Kim, K. H.; Shin, J. M.; Lee, H. S.; Ko, W. I.; Lee, J. W.; Yim, S. P.; Hong, D. H.; Lee, J. Y.; Baik, S. Y.; Song, W. S.; Yoo, B. O.; Lee, E. P.; Kang, I. S. [Korea Atomic Energy Research Institute, Taejeon (Korea)

2000-03-01

This report is desirable to review management options in advance for radioactive waste generated from manufacturing experiment of DUPIC nuclear fuel as well as residual nuclear material and dismantled equipment. This report was written for helping researchers working in related facilities to DUPIC project understanding management of DUPIC radioactive waste as well as fellows in DUPIC project. Also, it will be used as basic material to prove transparency and safeguardability of DUPIC fuel cycle. In order to meet these purposes, this report includes basic experiment plan for manufacturing DUPIC nuclear fuel, outlines for DUPIC manufacturing facility and equipment, arising source and estimated amount of radioactive waste, waste classification and packing, transport cask, transport procedures. 15 refs., 31 figs., 11 tabs. (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)

Specialists' meeting on gas-cooled reactor fuel development and spent fuel treatment

Energy Technology Data Exchange (ETDEWEB)

NONE

1985-07-01

Topics covered during the 'Specialists' meeting on gas-cooled reactor fuel development and spent fuel treatment' were as follows: Selection of constructions and materials, fuel element development concepts; Fabrication of spherical coated fuel particles and fuel element on their base; investigation of fuel properties; Spent fuel treatment and storage; Head-end processing of HTGR fuel elements; investigation of HTGR fuel regeneration process; applicability of gas-fluorine technology of regeneration of spent HTGR fuel elements.

Specialists' meeting on gas-cooled reactor fuel development and spent fuel treatment

International Nuclear Information System (INIS)

1985-01-01

Topics covered during the 'Specialists' meeting on gas-cooled reactor fuel development and spent fuel treatment' were as follows: Selection of constructions and materials, fuel element development concepts; Fabrication of spherical coated fuel particles and fuel element on their base; investigation of fuel properties; Spent fuel treatment and storage; Head-end processing of HTGR fuel elements; investigation of HTGR fuel regeneration process; applicability of gas-fluorine technology of regeneration of spent HTGR fuel elements

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

Treatment options for hepatocellular carcinoma.

Science.gov (United States)

Sandhu, Dalbir S; Tharayil, Vivek S; Lai, Jin-Ping; Roberts, Lewis R

2008-02-01

Hepatocellular carcinoma (HCC) is frequently diagnosed at advanced stages and has a high mortality rate. With improved survival of patients with cirrhotic liver disease and increased prevalence of chronic hepatitis C viral infections, a rise in the number of HCC cases is being reported worldwide. Early diagnosis and treatment can significantly improve the prognosis of patients with HCC. Although surgical resection is an important potentially curative therapy for liver tumors, in appropriately selected patients, liver transplantation has been shown to achieve excellent survival rates for a solid tumor. Locally ablative and locoregional therapies in the form of percutaneous ethanol injection, radiofrequency ablation, transcatheter arterial chemoembolization and transcatheter arterial radioembolization (TheraSphere) are viable options in patients with unresectable HCC. Unfortunately, the role of systemic therapy has been very limited in the treatment of these patients. Novel treatment options based on an improved understanding of the molecular pathogenesis of HCC are being explored. These targeted molecular therapies are aimed at growth factors and their receptors, intracellular signal transduction and cell cycle control. A substantial improvement in outcomes of intermediate and advanced stage HCC is expected with the advent of these targeted therapies, used in combination with surgical or locoregional therapies. Recent positive results from a large Phase III study of the receptor tyrosine kinase inhibitor, sorafenib, hold great promise in the treatment of HCC.

Patient knowledge on stroke risk factors, symptoms and treatment options.

Science.gov (United States)

Faiz, Kashif Waqar; Sundseth, Antje; Thommessen, Bente; Rønning, Ole Morten

2018-01-01

Public campaigns focus primarily on stroke symptom and risk factor knowledge, but patients who correctly recognize stroke symptoms do not necessarily know the reason for urgent hospitalization. The aim of this study was to explore knowledge on stroke risk factors, symptoms and treatment options among acute stroke and transient ischemic attack patients. This prospective study included patients admitted to the stroke unit at the Department of Neurology, Akershus University Hospital, Norway. Patients with previous cerebrovascular disease, patients receiving thrombolytic treatment and patients who were not able to answer the questions in the questionnaire were excluded. Patients were asked two closed-ended questions: "Do you believe that stroke is a serious disorder?" and "Do you believe that time is of importance for stroke treatment?". In addition, patients were asked three open-ended questions where they were asked to list as many stroke risk factors, stroke symptoms and stroke treatment options as they could. A total of 173 patients were included, of whom 158 (91.3%) confirmed that they regarded stroke as a serious disorder and 148 patients (85.5%) considered time being of importance. In all, 102 patients (59.0%) could not name any treatment option. Forty-one patients (23.7%) named one or more adequate treatment options, and they were younger ( p options, which may contribute to reduce prehospital delay and onset-to-treatment-time.

Treatment Option Overview (AIDS Related-Lymphoma)

Science.gov (United States)

... and treatment options. AIDS-related lymphoma is a disease in which malignant (cancer) cells form in the ... cord. The sample may also be checked for Epstein-Barr virus . This procedure is also called an LP ...

Novel treatment options in depression and psychosis

Directory of Open Access Journals (Sweden)

Ceskova E

2018-03-01

Full Text Available Eva Ceskova, Petr Silhan Department of Psychiatry, University Hospital Ostrava, Ostrava, Czech Republic Abstract: In spite of tremendous development in central nervous system research, current treatment is suboptimal, especially in severe mental disorders. In medicine, there are two main methods of improving the health care provided: seeking new treatment procedures and perfecting (optimizing the existing ones. Optimization of treatment includes not only practical tools such as therapeutic drug monitoring but also implementation of general trends in the clinical practice. New pharmacological options include new more sophisticated forms of monoaminergic drugs, old drugs rediscovered on the base of a better understanding of pathophysiology of mental illnesses, and drugs aimed at new treatment targets. In depression, treatment resistance to antidepressive pharmacotherapy represents one of the most important clinical challenges. Switching to monotherapy with new multimodal/multifunctional antidepressants and augmentation with new atypical antipsychotics (aripiprazole and brexpiprazole may be promising options. Further, current evidence supports utility and safety of adjunctive treatment of nutraceuticals. Novel approaches being studied include ketamine and opioids. Recent advances in technology and emerging knowledge about dysfunctional brain circuits and neuroplasticity have led to the development of different new neuromodulation techniques usually used as add-on therapy. Antipsychotics are still the cornerstone of the current treatment of schizophrenia. Two new partial dopamine agonists, brexpiprazole and cariprazine, are now available in addition to aripiprazole. Although the mechanisms of action are similar, the two agents differ in terms of their pharmacodynamic profiles. Further, two new formulations of long-acting injections of second-generation antipsychotics (aripiprazole lauroxil and 3-month paliperidone palmitate were introduced into

Cyanobacterial Treatment Options: Permanganate and ...

Science.gov (United States)

This presentation will begin with a brief overview of drinking water treatment options for cyanobacteria and their toxins. The treatment discussion will focus on the impacts of permanganate addition to suspensions of toxin-producing Microcystis aeruginosa, followed by powdered activated carbon (PAC) addition. Results will be presented that show changes in toxin concentrations, chlorophyll-a concentrations and cell membrane integrity. The EPA Small Systems Webinar Presentations allow the dissemination of the latest Agency guidance and research to a large geographically dispersed audience while minimizing taxpayer expense

Treatment options for carcinoma in situ testis

DEFF Research Database (Denmark)

Mortensen, M S; Gundgaard, M.G.; Daugaard, G

2011-01-01

countries only offer this to high-risk patients. The treatment options range from orchidectomy and chemotherapy to radiotherapy and in rare cases surveillance. Results of the different treatment strategies are presented in this review. The optimal radiation dose is still not clarified. Most patients have...

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)

[Necessary and unnecessary treatment options for hemorrhoids].

Science.gov (United States)

Zindel, Joel; Inglin, Roman; Brügger, Lukas

2014-12-01

Up to one third of the general population suffers from symptoms caused by hemorrhoids. Conservative treatment comes first unless the patient presents with an acute hemorrhoidal prolapse or a thrombosis. A fiber enriched diet is the primary treatment option, recommended in the perioperative period as well as a long-term prophylaxis. A timely limited application of topical ointments or suppositories and/or flavonoids are further treatment options. When symptoms persist interventional procedures for grade I-II hemorrhoids, and surgery for grade III-IV hemorrhoids should be considered. Rubber band ligation is the interventional treatment of choice. A comparable efficacy using sclerosing or infrared therapy has not yet been demonstrated. We therefore do not recommend these treatment options for the cure of hemorrhoids. Self-treatment by anal insertion of bougies is of lowrisk and may be successful, particularly in the setting of an elevated sphincter pressure. Anal dilation, sphincterotomy, cryosurgery, bipolar diathermy, galvanic electrotherapy, and heat therapy should be regarded as obsolete given the poor or missing data reported for these methods. For a long time, the classic excisional hemorrhoidectomy was considered to be the gold standard as far as surgical procedures are concerned. Primary closure (Ferguson) seems to be superior compared to the "open" version (Milligan Morgan) with respect to postoperative pain and wound healing. The more recently proposed stapled hemorrhoidopexy (Longo) is particularly advisable for circular hemorrhoids. Compared to excisional hemorrhoidectomy the Longo-operation is associated with reduced postoperative pain, shorter operation time and hospital stay as well as a faster recovery, with the disadvantage though of a higher recurrence rate. Data from Hemorrhoidal Artery Ligation (HAL)-, if appropriate in combination with a Recto-Anal Repair (HAL/RAR)-, demonstrates a similar trend towards a better tolerance of the procedure at the

Treatment options in otitis media with effusion.

Science.gov (United States)

Upadhya, Ila; Datar, J

2014-01-01

Secretary Otitis media with effusion (OME) is the accumulation of mucus in the middle ear and sometimes in the mastoid air cell system. The main etiological factor is alteration in mucociliary system of middle ear secondary to ET malfunction which may be primary or secondary. OME is the cause of concern due to its occurance in paediatric age group, highest at 2 years of age, presenting as impairment of hearing leading to delayed speech and language development, poor academic performance and behavioral problems. In spite of this there are no confirmed guidelines of treatment to overcome. Many treatment options are available medical as well as surgical. Prospective study conducted to evaluate various treatment options revealed that auto inflation of ET is the main stay of treatment. If the ET malfunction is due to any reasons like adenoids, deviated nasal septum, hypertrophied turbinates or any other cause surgical intervention of the same gives 100% results. Medical management gives good results but recurrence is equally common.

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)

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.

[Treatment options for patellar tendinopathy].

Science.gov (United States)

Duthon, V B; Borloz, S; Ziltener, J-L

2012-07-25

Patellar tendinopathy is also called jumper's knee because of its high incidence in athletes with jumping or cutting activities as soccer, basketball, volleyball. Many different treatment methods have been described. However, no consensus exists regarding the optimal treatment for this condition. According to the literature, eccentric exercise-based physical therapy should be proposed first because of its strong scientific evidence. Shockwave therapy and injections may be useful but their real efficacy still has to be proven by randomized controlled study. For patients recalcitrant to more conservative options, operative management may be indicated.

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

Assessment of alternative fuel and powertrain transit bus options using real-world operations data: Life-cycle fuel and emissions modeling

International Nuclear Information System (INIS)

Xu, Yanzhi; Gbologah, Franklin E.; Lee, Dong-Yeon; Liu, Haobing; Rodgers, Michael O.; Guensler, Randall L.

2015-01-01

Highlights: • We present a practical fuel and emissions modeling tool for alternative fuel buses. • The model assesses well-to-wheels emissions impacts of bus fleet decisions. • Mode-based approach is used to account for duty cycles and local conditions. • A case study using real-world operations data from Atlanta, GA is presented. • Impacts of alternative bus options depend on operating and geographic features. - Abstract: Hybrid and electric powertrains and alternative fuels (e.g., compressed natural gas (CNG), biodiesel, or hydrogen) can often reduce energy consumption and emissions from transit bus operations relative to conventional diesel. However, the magnitude of these energy and emissions savings can vary significantly, due to local conditions and transit operating characteristics. This paper introduces the transit Fuel and Emissions Calculator (FEC), a mode-based life-cycle emissions modeling tool for transit bus and rail technologies that compares the performance of multiple alternative fuels and powertrains across a range of operational characteristics and conditions. The purpose of the FEC is to provide a practical, yet technically sophisticated tool for regulatory agencies and policy analysts in assessing transit fleet options. The FEC’s modal modeling approach estimates emissions as a function of engine load, which in turn is a function of transit service parameters, including duty cycle (idling and speed-acceleration profile), road grade, and passenger loading. This approach allows for customized assessments that account for local conditions. Direct emissions estimates are derived from the scaled tractive power (STP) operating mode bins and emissions factors employed in the U.S. EPA’s MOVES (MOtor Vehicle Emissions Simulator) model. Life-cycle emissions estimates are calculated using emissions factors from the GREET (Greenhouse Gases, Regulated Emissions, and Energy Use in Transportation) model. The case study presented in this paper

Fusion option to dispose of spent nuclear fuel and transuranic elements

International Nuclear Information System (INIS)

Gohar, Y.

2000-01-01

The fusion option is examined to solve the disposition problems of the spent nuclear fuel and the transuranic elements. The analysis of this report shows that the top rated solution, the elimination of the transuranic elements and the long-lived fission products, can be achieved in a fusion reactor. A 167 MW of fusion power from a D-T plasma for sixty years with an availability factor of 0.75 can transmute all the transuranic elements and the long-lived fission products of the 70,000 tons of the US inventory of spent nuclear fuel generated up to the year 2015. The operating time can be reduced to thirty years with use of 334 MW of fusion power, a system study is needed to define the optimum time. In addition, the fusion solution eliminates the need for a geological repository site, which is a major advantage. Meanwhile, such utilization of the fusion power will provide an excellent opportunity to develop fusion energy for the future. Fusion blankets with a liquid carrier for the transuranic elements can achieve a transmutation rate for the transuranic elements up to 80 kg/MW.y of fusion power with k eff of 0.98. In addition, the liquid blankets have several advantages relative to the other blanket options. The energy from this transmutation is utilized to produce revenue for the system. Molten salt (Flibe) and lithium-lead eutectic are identified as the most promising liquids for this application, both materials are under development for future fusion blanket concepts. The Flibe molten salt with transuranic elements was developed and used successfully as nuclear fuel for the molten salt breeder reactor in the 1960's

Greenhouse gas emissions reduction from fossil fuels: options and prospects

International Nuclear Information System (INIS)

McDonald, M.M.

1999-01-01

If levels of carbon dioxide in the atmosphere are to be stabilized over the next 50 years, net emissions from the use of fossil fuels have to be reduced. One concept worth exploring is the removal of carbon dioxide from plant flue gases and disposing of it in a manner that sequesters it from the atmosphere. A number of technologies, which are either commercially available or under development, promise to make this concept viable. The question of where to dispose of the carbon dioxide removed is not the limiting factor, given the potential for use in enhanced hydrocarbon production as well as other geological disposal options. In the longer term, fossil fuel use will significantly decline, but these extraction and sequestration technologies can provide the time for the transition to take place in a manner which causes least impact to the economies of the world. (author)

Thorium Fuel Options for Sustained Transuranic Burning in Pressurized Water Reactors - 12381

Energy Technology Data Exchange (ETDEWEB)

Rahman, Fariz Abdul; Lee, John C. [University of Michigan, Ann Arbor, MI (United States); Franceschini, Fausto; Wenner, Michael [Westinghouse Electric Company LLC, Cranberry Township, PA (United States)

2012-07-01

As described in companion papers, Westinghouse is proposing the adoption of a thorium-based fuel cycle to burn the transuranics (TRU) contained in the current Used Nuclear Fuel (UNF) and transition towards a less radio-toxic high level waste. A combination of both light water reactors (LWR) and fast reactors (FR) is envisaged for the task, with the emphasis initially posed on their TRU burning capability and eventually to their self-sufficiency. Given the many technical challenges and development times related to the deployment of TRU burners fast reactors, an interim solution making best use of the current resources to initiate burning the legacy TRU inventory while developing and testing some technologies of later use is desirable. In this perspective, a portion of the LWR fleet can be used to start burning the legacy TRUs using Th-based fuels compatible with the current plants and operational features. This analysis focuses on a typical 4-loop PWR, with 17x17 fuel assembly design and TRUs (or Pu) admixed with Th (similar to U-MOX fuel, but with Th instead of U). Global calculations of the core were represented with unit assembly simulations using the Linear Reactivity Model (LRM). Several assembly configurations have been developed to offer two options that can be attractive during the TRU transmutation campaign: maximization of the TRU transmutation rate and capability for TRU multi-recycling, to extend the option of TRU recycling in LWR until the FR is available. Homogeneous as well as heterogeneous assembly configurations have been developed with various recycling schemes (Pu recycle, TRU recycle, TRU and in-bred U recycle etc.). Oxide as well as nitride fuels have been examined. This enabled an assessment of the potential for burning and multi-recycling TRU in a Th-based fuel PWR to compare against other more typical alternatives (U-MOX and variations thereof). Results will be shown indicating that Th-based PWR fuel is a promising option to multi-recycle and

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.

Electrometallurgical treatment of aluminum-matrix fuels

International Nuclear Information System (INIS)

Willit, J.L.; Gay, E.C.; Miller, W.E.; McPheeters, C.C.; Laidler, J.J.

1996-01-01

The electrometallurgical treatment process described in this paper builds on our experience in treating spent fuel from the Experimental Breeder Reactor (EBR-II). The work is also to some degree, a spin-off from applying electrometallurgical treatment to spent fuel from the Hanford single pass reactors (SPRs) and fuel and flush salt from the Molten Salt Reactor Experiment (MSRE) in treating EBR-II fuel, we recover the actinides from a uranium-zirconium fuel by electrorefining the uranium out of the chopped fuel. With SPR fuel, uranium is electrorefined out of the aluminum cladding. Both of these processes are conducted in a LiCl-KCl molten-salt electrolyte. In the case of the MSRE, which used a fluoride salt-based fuel, uranium in this salt is recovered through a series of electrochemical reductions. Recovering high-purity uranium from an aluminum-matrix fuel is more challenging than treating SPR or EBR-II fuel because the aluminum- matrix fuel is typically -90% (volume basis) aluminum

An update on adjunctive treatment options for bipolar disorder.

Science.gov (United States)

Dean, Olivia M; Gliddon, Emma; Van Rheenen, Tamsyn E; Giorlando, Francesco; Davidson, Sandra K; Kaur, Manreena; Ngo, Trung T; Williams, Lana J

2018-03-01

Bipolar disorder is a complex illness often requiring combinations of therapies to successfully treat symptoms. In recent years, there have been significant advancements in a number of therapies for bipolar disorder. It is therefore timely to provide an overview of current adjunctive therapeutic options to help treating clinicians to inform their patients and work towards optimal outcomes. Publications were identified from PubMed searches on bipolar disorder and pharmacotherapy, nutraceuticals, hormone therapy, psychoeducation, interpersonal and social rhythm therapy, cognitive remediation, mindfulness, e-Health and brain stimulation techniques. Relevant articles in these areas were selected for further review. This paper provides a narrative review of adjunctive treatment options and is not a systematic review of the literature. A number of pharmacotherapeutic, psychological and neuromodulation treatment options are available. These have varying efficacy but all have shown benefit to people with bipolar disorder. Due to the complex nature of treating the disorder, combination treatments are often required. Adjunctive treatments to traditional pharmacological and psychological therapies are proving useful in closing the gap between initial symptom remission and full functional recovery. Given that response to monotherapy is often inadequate, combination regimens for bipolar disorder are typical. Correspondingly, psychiatric research is working towards a better understanding of the disorder's underlying biology. Therefore, treatment options are changing and adjunctive therapies are being increasingly recognized as providing significant tools to improve patient outcomes. Towards this end, this paper provides an overview of novel treatments that may improve clinical outcomes for people with bipolar disorder. © 2018 John Wiley & Sons A/S. Published by John Wiley & Sons Ltd.

Reactor-based management of used nuclear fuel: assessment of major options.

Science.gov (United States)

Finck, Phillip J; Wigeland, Roald A; Hill, Robert N

2011-01-01

This paper discusses the current status of the ongoing Advanced Fuel Cycle Initiative (AFCI) program in the U.S. Department of Energy that is investigating the potential for using the processing and recycling of used nuclear fuel to improve radioactive waste management, including used fuel. A key element of the strategies is to use nuclear reactors for further irradiation of recovered chemical elements to transmute certain long-lived highly-radioactive isotopes into less hazardous isotopes. Both thermal and fast neutron spectrum reactors are being studied as part of integrated nuclear energy systems where separations, transmutation, and disposal are considered. Radiotoxicity is being used as one of the metrics for estimating the hazard of used fuel and the processing of wastes resulting from separations and recycle-fuel fabrication. Decay heat from the used fuel and/or wastes destined for disposal is used as a metric for use of a geologic repository. Results to date indicate that the most promising options appear to be those using fast reactors in a repeated recycle mode to limit buildup of higher actinides, since the transuranic elements are a key contributor to the radiotoxicity and decay heat. Using such an approach, there could be much lower environmental impact from the high-level waste as compared to direct disposal of the used fuel, but there would likely be greater generation of low-level wastes that will also require disposal. An additional potential waste management benefit is having the ability to tailor waste forms and contents to one or more targeted disposal environments (i.e., to be able to put waste in environments best-suited for the waste contents and forms). Copyright © 2010 Health Physics Society

My fuel treatment planner: a user guide.

Science.gov (United States)

Robin L. Biesecker; Roger D. Fight

2006-01-01

My Fuel Treatment Planner (MyFTP) is a tool for calculating and displaying the financial costs and potential revenues associated with forest fuel reduction treatments. It was designed for fuel treatment planners including those with little or no background in economics, forest management, or timber sales. This guide provides the information needed to acquire, load, and...

Back-end of the nuclear fuel cycle. A comparison of the direct disposal and reprocessing options

International Nuclear Information System (INIS)

Allan, C.J.; Baumgartner, P.

1997-01-01

Based on the need to address public concerns, the need to ensure long-term safety and an ethical concern for future generations, many countries are developing technology to dispose of nuclear fuel waste. The waste substances in used fuel can be disposed of either by directly disposing of the used fuel assemblies themselves, or by disposing of the long-lived waste from fuel reprocessing. The basic thesis of this paper is that the direct disposal of either used fuel or of the long-lived heat-generating and non-heat generating waste that arise from reprocessing is technically and economically feasible and that both options will meet the fundamental objectives of protecting human health and the environment. Decisions about whether, or when, to reprocess used fuel, or about whether to dispose of used fuel directly, are not fundamentally waste management issues. (author)

Spent fuel treatment at ANL-West

International Nuclear Information System (INIS)

Goff, K.M.; Benedict, R.W.; Levinskas, D.

1994-01-01

At Argonne National Laboratory-West (ANL-West) there are several thousand kilograms of metallic spent nuclear fuel containing bond sodium. This fuel will be treated in the Fuel Cycle Facility at ANL-West to produce stable waste forms for storage and disposal. The treatment operations will employ a pyrochemical process that also has applications for treating most of the fuel types within the Department of Energy complex. The treatment equipment is in its last stage of readiness, and operations will begin in the Fall of 1994

Emerging treatment options for meibomian gland dysfunction

Directory of Open Access Journals (Sweden)

Qiao J

2013-09-01

Full Text Available Jing Qiao, Xiaoming YanDepartment of Ophthalmology, Peking University First Hospital, Key Laboratory of Vision Loss and Restoration, Ministry of Education, Beijing, People's Republic of ChinaAbstract: Meibomian gland dysfunction (MGD is one of the most common diseases observed in clinics; it influences a great number of people, and is the leading cause of evaporative dry eye. Given the increased recognition of the importance of MGD, a great amount of attention has been paid to therapies targeting this condition. The traditional treatments of MGD consist of warm compresses and lid hygiene for removing an obstructed meibum, as well as antibiotics and anti-inflammatory agents to improve the quality of the meibum. However, each of these treatments has a different shortcoming and the treatment of MGD remains challenging. Despite the numerous possible treatment options for MGD, it is still difficult to obtain complete relief of signs and symptoms. This review focuses on current emerging treatment options for MGD including intraductal meibomian gland probing, emulsion eye drops containing lipids, the LipiFlow® thermal pulsation system, N-acetyl-cysteine, azithromycin, oral supplementation with omega-3 essential fatty acids, and cyclosporine A.Keywords: meibomian gland dysfunction, dry eye, emerging treatment

Cyanobacterial Treatment Options: Permanganate and Powdered Activated Carbon

Science.gov (United States)

This presentation will begin with a brief overview of drinking water treatment options for cyanobacteria and their toxins. The treatment discussion will focus on the impacts of permanganate addition to suspensions of toxin-producing Microcystis aeruginosa, followed by powdered ac...

The option value of innovative treatments in the context of chronic myeloid leukemia.

Science.gov (United States)

Sanchez, Yuri; Penrod, John R; Qiu, Xiaoli Lily; Romley, John; Thornton Snider, Julia; Philipson, Tomas

2012-11-01

To quantify in the context of chronic myeloid leukemia (CML) the additional value patients receive when innovative treatments enable them to survive until the advent of even more effective future treatments (ie, the "option value"). Observational study using data from the Surveillance, Epidemiology and End Results (SEER) cancer registry comprising all US patients with CML diagnosed between 2000 and 2008 (N = 9,760). We quantified the option value of recent breakthroughs in CML treatment by first conducting retrospective survival analyses on SEER data to assess the effectiveness of TKI treatments, and then forecasting survival from CML and other causes to measure expected future medical progress. We then developed an analytical framework to calculate option value of innovative CML therapies, and used an economic model to value these gains. We calculated the option value created both by future innovations in CML treatment and by medical progress in reducing background mortality. For a recently diagnosed CML patient, the option value of innovative therapies from future medical innovation amounts to 0.76 life-years. This option value is worth $63,000, equivalent to 9% of the average survival gains from existing treatments. Future innovations in CML treatment jointly account for 96% of this benefit. The option value of innovative treatments has significance in the context of CML and, more broadly, in disease areas with rapid innovation. Incorporating option value into traditional valuations of medical innovations is both a feasible and a necessary practice in health technology assessment.

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)

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

Tooth wear : a systematic review of treatment options

NARCIS (Netherlands)

Muts, Erik-Jan; van Pelt, Hans; Edelhoff, Daniel; Krejci, Ivo; Cune, Marco

2014-01-01

STATEMENT OF PROBLEM: Treatment of tooth wear is increasing. Because no evidence-based guidelines are available, the clinician may have difficulties deciding which treatment option to choose to resolve complex situations. PURPOSE: The purpose of this systematic review was to identify similarities

Stereotactic Neurosurgical Treatment Options for Childhood Craniopharyngioma

Directory of Open Access Journals (Sweden)

Michael eTrippel

2012-05-01

Full Text Available Craniopharyngioma are the most common non glial tumors in childhood. The results of different studies indicate that radical excision surgery is not an appropriate treatment strategy for childhood craniopharyngioma with hypothalamic involvement. Stereotactic neurosurgery provides save, minimal invasive and cost efficient options in the treatment of childhood craniopharyngioma. In this review a summary of the contribution of the stereotactic neurosurgery in the interdisciplinary treatment regime of childhood craniopharyngioma will be given and discussed in detail.

Fuel cycle options for light water reactors and heavy water reactors. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

1999-11-01

In the second half of the 20th century nuclear power has evolved from the research and development environment to an industry that supplies 16% of the world's electricity. By the end of 1997, over 8500 reactor-years of operating experience had been accumulated. Global environmental change, and the continuing increase in global energy supply required to provide increasing populations with an improving standard of living, make the contribution from nuclear energy even more important for the next century. For nuclear power to achieve its full potential and make its needed contribution, it must be safe, economical, reliable and sustainable. All of these factors can be enhanced by judicious choice and development of advanced fuel cycle options. The Technical Committee Meeting (TCM) on Fuel Cycle Options for Light Water Reactors and Heavy Water Reactors was hosted by Atomic Energy of Canada Limited (AECL) on behalf of the Canadian Government and was jointly conducted within the frame of activities of the IAEA International Working Group on Advanced Technologies for Light Water Reactors (IWG-LWR) and the IAEA International Working Group on Advanced Technologies for Heavy Water Reactors (IWG-HWR). The TCM provided the opportunity to have in-depth discussions on important technical topics which were highlighted in the International Symposium on Nuclear Fuel Cycle and Reactor Strategies: Adjusting to New Realities, held in Vienna, 3-6 June 1997. The main results and conclusions of the TCM were presented as input for discussion at the first meeting of the IAEA newly formed International Working Group on Fuel Cycle Options

Spent Fuel in Chile

International Nuclear Information System (INIS)

López Lizana, F.

2015-01-01

The government has made a complete and serious study of many different aspects and possible road maps for nuclear electric power with strong emphasis on safety and energy independence. In the study, the chapter of SFM has not been a relevant issue at this early stage due to the fact that it has been left for later implementation stage. This paper deals with the options Chile might consider in managing its Spent Fuel taking into account foreign experience and factors related to safety, economics, public acceptance and possible novel approaches in spent fuel treatment. The country’s distinctiveness and past experience in this area taking into account that Chile has two research reactors which will have an influence in the design of the Spent Fuel option. (author)

Electrometallurgical treatment of oxide spent fuels

International Nuclear Information System (INIS)

Karell, E. J.

1999-01-01

The Department of Energy (DOE) inventory of spent nuclear fuel contains a wide variety of oxide fuel types that may be unsuitable for direct repository disposal in their current form. The molten-salt electrometallurgical treatment technique developed by Argonne National Laboratory (ANL) has the potential to simplify preparing and qualifying these fuels for disposal by converting them into three uniform product streams: uranium metal, a metal waste form, and a ceramic waste form. This paper describes the major steps in the electrometallurgical treatment process for oxide fuels and provides the results of recent experiments performed to develop and scale up the process

Lack of tolerable treatment options for patients with schizophrenia

Directory of Open Access Journals (Sweden)

Citrome L

2015-12-01

Full Text Available Leslie Citrome,1 Anna Eramo,2 Clement Francois,2 Ruth Duffy,3 Susan N Legacy,3 Steve J Offord,3 Holly B Krasa,3 Stephen S Johnston,4 Alice Guiraud-Diawara,5 Siddhesh A Kamat,3 Patricia Rohman3 1Department of Psychiatry and Behavioral Sciences, New York Medical College, Valhalla, NY, 2Lundbeck, Deerfield, IL, 3Otsuka America Pharmaceuticals, Princeton, NJ, 4Truven Health Analytics, Bethesda, MD, USA; 5Lundbeck SAS, Issy-les-Moulineaux, France Purpose: Atypical antipsychotics (AAs, an effective treatment for schizophrenia, have a range of pharmacologic properties leading to differences in tolerability as well as heterogeneity in treatment response. Individual patient characteristics must be considered when making treatment choices, especially from an adverse event (AE or tolerability perspective. Despite the availability of numerous AAs, after appraising patient characteristics at the time of treatment selection, physicians may quickly run out of tolerable treatment options. Patients and methods: AE risk factors, defined as having either a prior history of an AE or a risk factor for that AE, were determined for Medicaid-insured and Commercially insured patients using database analysis. Patients receiving AA treatment between January 1, 2010 and December 31, 2012 defined the index date of first observed AA prescription during this period. Nine AAs were evaluated for association with AE risk factors as informed by drug prescribing information from the different manufacturers and published meta-analyses. The proportion of patients with pre-index AE risk factors prescribed an AA associated with that risk factor was then determined. Results: A high proportion of patients (>80% were prescribed an AA associated with extrapyramidal symptoms or akathisia despite experiencing extrapyramidal symptoms or akathisia prior to AA treatment initiation. Similar trends were observed among patients with diabetes (>60% and obesity (>40%. From the nine treatment

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

Nuclear fuel cycle. Which way forward for multilateral approaches? An international expert group examines options

International Nuclear Information System (INIS)

Pellaud, Bruno

2005-01-01

For several years now, the debate on the proliferation of nuclear weapons has been dominated by individuals and countries that violate rules of good behaviour - as sellers or acquirers of clandestine nuclear technology. As a result, the 1968 Treaty on the Non-Proliferation of Nuclear Weapons (NPT) has been declared to be 'inadequate' by some, 'full of loopholes' by others. Two basic approaches have been put forward to tighten up the NPT; both seek to ensure that the nuclear non-proliferation regime maintains its authority and credibility in the face of these very real challenges. One calls for non-nuclear weapon States to accept a partial denial of technology through a reinterpretation of the NPT's provisions governing the rights of access to nuclear technologies. The unwillingness of most non-nuclear-weapon States to accept additional restrictions under the NPT makes this approach difficult. The other approach would apply multinational alternatives to the national operation of uranium-enrichment and plutonium-separation technologies, and to the disposal of spent nuclear fuel. In this perspective, IAEA Director General Mohamed ElBaradei proposed in 2003 to revisit the concept of multilateral nuclear approaches (MNA) that was intensively discussed several decades ago. Several such approaches were adopted at that time in Europe, which became the true homeland of MNAs. Nonetheless, MNAs have failed so far to materialise outside Europe due to different political and economic perceptions. In June 2004, the Director General appointed an international group of experts to consider possible multilateral approaches to the nuclear fuel cycle. The overall purpose was to assess MNAs in the framework of a double objective: strengthening the international nuclear non-proliferation regime and making the peaceful uses of nuclear energy more economical and attractive. In the report submitted to the Director General in February 2005, the Group identified a number of options - options

Treatment options for patellofemoral instability in sports traumatology

Directory of Open Access Journals (Sweden)

Philippe M. Tscholl

2013-09-01

Full Text Available Patellofemoral instability not only involves lateral patellar dislocation, patellar mal-tracking or subluxation but can also cause a limiting disability for sports activities. Its underlying causes are known as morphological anomalies of the patellofemoral joint or the mechanical axis, femorotibial malrotation, variants of the knee extensor apparatus, and ligamentous insufficiencies often accompanied by poor proprioception. Athletes with such predisposing factors are either suffering from unspecific anterior knee pain or from slightly traumatic or recurrent lateral patellar dislocation Treatment options of patellar instability are vast, and need to be tailored individually depending on the athlete’s history, age, complaints and physical demands. Different conservative and surgical treatment options are reviewed and discussed, especially limited expectations after surgery.

Mobile Melt-Dilute Treatment for Russian Spent Nuclear Fuel

International Nuclear Information System (INIS)

Peacock, H.

2002-01-01

Treatment of spent Russian fuel using a Melt-Dilute (MD) process is proposed to consolidate fuel assemblies into a form that is proliferation resistant and provides critically safety under storage and disposal configurations. Russian fuel elements contain a variety of fuel meat and cladding materials. The Melt-Dilute treatment process was initially developed for aluminum-based fuels so additional development is needed for several cladding and fuel meat combinations in the Russian fuel inventory (e.g. zirconium-clad, uranium-zirconium alloy fuel). A Mobile Melt-Dilute facility (MMD) is being proposed for treatment of spent fuels at reactor site storage locations in Russia; thereby, avoiding the costs of building separate treatment facilities at each site and avoiding shipment of enriched fuel assemblies over the road. The MMD facility concept is based on laboratory tests conducted at the Savannah River Technology Center (SRTC), and modular pilot-scale facilities constructed at the Savannah River Site for treatment of US spent fuel. SRTC laboratory tests have shown the feasibility of operating a Melt-Dilute treatment process with either a closed system or a filtered off-gas system. The proposed Mobile Melt-Dilute process is presented in this paper

Part 5. Fuel cycle options

International Nuclear Information System (INIS)

Lineberry, M.J.; McFarlane, H.F.; Amundson, P.I.; Goin, R.W.; Webster, D.S.

1980-01-01

The results of the FBR fuel cycle study that supported US contributions to the INFCE are presented. Fuel cycle technology is reviewed from both generic and historical standpoints. Technology requirements are developed within the framework of three deployment scenarios: the reference international, the secured area, and the integral cycle. Reprocessing, fabrication, waste handling, transportation, and safeguards are discussed for each deployment scenario. Fuel cycle modifications designed to increase proliferation defenses are described and assessed for effectiveness and technology feasibility. The present status of fuel cycle technology is reviewed and key issues that require resolution are identified

Core design options for high conversion BWRs operating in Th–233U fuel cycle

International Nuclear Information System (INIS)

Shaposhnik, Y.; Shwageraus, E.; Elias, E.

2013-01-01

Highlights: • BWR core operating in a closed self-sustainable Th– 233 U fuel cycle. • Seed blanket optimization that includes assembly size array and axial dimensions. • Fully coupled MC with fuel depletion and thermo-hydraulic feedback modules. • Thermal-hydraulic analysis includes MCPR observation. -- Abstract: Several options of fuel assembly design are investigated for a BWR core operating in a closed self-sustainable Th– 233 U fuel cycle. The designs rely on an axially heterogeneous fuel assembly structure consisting of a single axial fissile zone “sandwiched” between two fertile blanket zones, in order to improve fertile to fissile conversion ratio. The main objective of the study was to identify the most promising assembly design parameters, dimensions of fissile and fertile zones, for achieving net breeding of 233 U. The design challenge, in this respect, is that the fuel breeding potential is at odds with axial power peaking and the core minimum critical power ratio (CPR), hence limiting the maximum achievable core power rating. Calculations were performed with the BGCore system, which consists of the MCNP code coupled with fuel depletion and thermo-hydraulic feedback modules. A single 3-dimensional fuel assembly having reflective radial boundaries was modeled applying simplified restrictions on the maximum centerline fuel temperature and the CPR. It was found that axially heterogeneous fuel assembly design with a single fissile zone can potentially achieve net breeding, while matching conventional BWR core power rating under certain restrictions to the core loading pattern design

Nonsurgical Treatment Options for Basal Cell Carcinoma

International Nuclear Information System (INIS)

Lien, M. H.; Sondak, V. K.; Sondak, V. K.

2011-01-01

Basal cell carcinoma (BCC) remains the most common form of non melanoma skin cancer (NMSC) in Caucasians, with perhaps as many as 2 million new cases expected to occur in the United States in 2010. Many treatment options, including surgical interventions and nonsurgical alternatives, have been utilized to treat BCC. In this paper, two non-surgical options, imiquimod therapy and photodynamic therapy (PDT), will be discussed. Both modalities have demonstrated acceptable disease control rates, cosmetically superior outcomes, and short-term cost-effectiveness. Further studies evaluating long-term cure rates and long-term cost effectiveness of imiquimod therapy and PDT are needed.

Management of super-grade plutonium in spent nuclear fuel

International Nuclear Information System (INIS)

McFarlane, H. F.; Benedict, R. W.

2000-01-01

This paper examines the security and safeguards implications of potential management options for DOE's sodium-bonded blanket fuel from the EBR-II and the Fermi-1 fast reactors. The EBR-II fuel appears to be unsuitable for the packaging alternative because of DOE's current safeguards requirements for plutonium. Emerging DOE requirements, National Academy of Sciences recommendations, draft waste acceptance requirements for Yucca Mountain and IAEA requirements for similar fuel also emphasize the importance of safeguards in spent fuel management. Electrometallurgical treatment would be acceptable for both fuel types. Meeting the known requirements for safeguards and security could potentially add more than $200M in cost to the packaging option for the EBR-II fuel

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.

Social Cost Assessment for Nuclear Fuel Cycle Options in the Republic of Korea

Energy Technology Data Exchange (ETDEWEB)

Joo, Ji-eun; Yim, Man-Sung [KAIST, Daejeon (Korea, Republic of)

2016-10-15

This paper will investigate the vast array of economic factors to estimate the true cost of the nuclear power. There are many studies addressing the external costs of energy production. However, it is only since the 1990s that the external costs of nuclear powered electricity production has been studied in detail. Each investigation has identified their own set of external costs and developed formulas and models using a variety of statistical techniques. The objective of this research is to broaden the scope of the parameters currently consider by adding new areas and expanding on the types of situations considered. Previously the approach to evaluating the external cost of nuclear power did not include various fuel cycle options and influencing parameters. Cost has always been a very important factor in decision-making, in particular for policy choices evaluating the alternative energy sources and electricity generation technologies. Assessment of external costs in support of decision-making should reflect timely consideration of important country specific policy objective. PWR-MOX and FR-Pyro are the best fuel cycle in parameter of environment impacts, but OT or OT-ER is proper than FR-Pyro in human beings. Using the OT fuel cycle is better than FR-Pyro to reduce the conflict cost. When energy supply is deficient, FR-Pyro fuel cycle stands longer than other fuel cycles. Proliferation resistance is shown as 'high' in all fuel cycles, so there are no difference between fuel cycles. When the severe accident occurs, FR-Pyro cycle is economical than other OT based fuel cycles.

Fuel accumulation and forest structure change following hazardous fuel reduction treatments throughout California

Science.gov (United States)

Nicole M. Vaillant; Erin K. Noonan-Wright; Alicia L. Reiner; Carol M. Ewell; Benjamin M. Rau; Josephine A. Fites-Kaufman; Scott N. Dailey

2015-01-01

Altered fuel conditions coupled with changing climate have disrupted fire regimes of forests historically characterised by high-frequency and low-to-moderate-severity fire. Managers use fuel treatments to abate undesirable fire behaviour and effects. Short-term effectiveness of fuel treatments to alter fire behaviour and effects is well documented; however, long-term...

Biofuels Fuels Technology Pathway Options for Advanced Drop-in Biofuels Production

Energy Technology Data Exchange (ETDEWEB)

Kevin L Kenney

2011-09-01

Advanced drop-in hydrocarbon biofuels require biofuel alternatives for refinery products other than gasoline. Candidate biofuels must have performance characteristics equivalent to conventional petroleum-based fuels. The technology pathways for biofuel alternatives also must be plausible, sustainable (e.g., positive energy balance, environmentally benign, etc.), and demonstrate a reasonable pathway to economic viability and end-user affordability. Viable biofuels technology pathways must address feedstock production and environmental issues through to the fuel or chemical end products. Potential end products include compatible replacement fuel products (e.g., gasoline, diesel, and JP8 and JP5 jet fuel) and other petroleum products or chemicals typically produced from a barrel of crude. Considering the complexity and technology diversity of a complete biofuels supply chain, no single entity or technology provider is capable of addressing in depth all aspects of any given pathway; however, all the necessary expert entities exist. As such, we propose the assembly of a team capable of conducting an in-depth technology pathway options analysis (including sustainability indicators and complete LCA) to identify and define the domestic biofuel pathways for a Green Fleet. This team is not only capable of conducting in-depth analyses on technology pathways, but collectively they are able to trouble shoot and/or engineer solutions that would give industrial technology providers the highest potential for success. Such a team would provide the greatest possible down-side protection for high-risk advanced drop-in biofuels procurement(s).

Assessing environmental and health impact of the nuclear fuel cycle. Methodology and application to prospective actinides recycling options

International Nuclear Information System (INIS)

Garzenne, Claude; Grouiller, Jean-Paul; Le Boulch, Denis

2005-01-01

French Industrial Companies: EDF, AREVA (COGEMA and FRAMATOME-ANP), associated with ANDRA, the organization in charge of the waste management in France, and Public Research Institute CEA and IRSN, involved in the nuclear waste management, have developed in collaboration a methodology intended to assess the environmental and health impact of the nuclear fuel cycle. This methodology, based on fuel cycle simulation, Life Cycle Analysis, and Impact Studies of each fuel cycle facilities, has been applied to a set of nuclear scenarios covering a very contrasted range of waste management options, in order to characterize the effect of High Level Waste transmutation, and to estimate to what extent it could contribute to reduce their overall impact on health and environment. The main conclusion we could draw from this study is that it is not possible to discriminate, as far as health and environmental impacts are concerned, nuclear scenarios implementing very different levels of HLW transmutation, representative of the whole range of available options. The main limitation of this work is due to the hypothesis of normal behavior of all fuel cycle facilities: main future improvement of the methodology would be to take the accidental risk into account. (author)

Radioactive waste management and spent nuclear fuel storing. Options and priorities

International Nuclear Information System (INIS)

Popescu, Ion

2001-01-01

As a member of the states' club using nuclear energy for peaceful applications, Romania approaches all the activities implied by natural uranium nuclear fuel cycle, beginning with uranium mining and ending with electric energy generation. Since, in all steps of the nuclear fuel cycle radioactive wastes are resulting, in order to protect the environment and the life, the correct and competent radioactive waste management is compulsory. Such a management implies: a. Separating the radioisotopes in all the effluences released into environment; b. Treating separately the radioisotopes to be each properly stored; c. Conditioning waste within resistant matrices ensuring long term isolation of the radioactive waste destined to final disposal; d. Building radioactive waste repositories with characteristics of isolation guaranteed for long periods of time. To comply with the provisions of the International Convention concerning the safety of the spent nuclear fuel and radioactive waste management, signed on 5 September 1997, Romania launched its program 'Management of Radioactive Wastes and Dry Storing of Spent Nuclear Fuel' having the following objectives: 1. Establishing the technology package for treating and conditioning the low and medium active waste from Cernavoda NPP to prepare them for final disposal; 2. Geophysical and geochemical investigations of the site chosen for the low and medium active final disposal (DFDSMA); 3. Evaluating the impact on environment and population of the DFDSMA; 4. Providing data necessary in the dry intermediate storing of spent nuclear fuel and the continuous and automated surveillance; 5. Establishing multiple barriers for spent nuclear fuel final disposal in order to establish the repository in granitic rocks and salt massives; 6. Designing and testing containers for final disposal of spent nuclear fuel guaranteeing the isolation over at least 500 years; 7. Computational programs for evaluation of radionuclide leakage in environment in

R and D for back-end options for irradiated research reactor fuel in Germany

International Nuclear Information System (INIS)

Bruecher, H.; Curtius, H.; Fachinger, J.

2001-01-01

Out of 11.5 t of irradiated fuel arising from German research reactors until the end of this decade, 3.9 t are intended to be returned to the USA, and 2.3 t are expected to be recycled for reuse of uranium. The remaining 5.3 t, as well as the fuel irradiated after the year 2010, will have to follow the domestic back-end option of extended dry interim storage in Castor-type casks, followed by disposal in a deep geological repository. R and D is going on in the Research Centre Juelich to investigate the long-term behaviour of U-Al based fuel in a salt repository. First results from leaching experiments show I) a fast dissolution of the fuel with mobilization of its radionuclide inventory, and 2) the following formation of amorphous Al-Mg-hydroxide phases. Long-lived actinides from the fuel were shown to be fixed in these phases and hence immobilized. Future R and D will be to investigate the nature and stability of these phases for long-term safety assessments. Investigations will have to be extended to cover alternative disposal sites (granite clay) as well as different (e.g. silicon based) fuels. (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)

Fuel particles in the Chernobyl cooling pond: current state and prediction for remediation options

International Nuclear Information System (INIS)

Bulgakov, A.; Konoplev, A.; Smith, J.; Laptev, G.; Voitsekhovich, O.

2009-01-01

During the coming years, a management and remediation strategy for the Chernobyl cooling pond (CP) will be implemented. Remediation options include a controlled reduction in surface water level of the cooling pond and stabilisation of exposed sediments. In terrestrial soils, fuel particles deposited during the Chernobyl accident have now almost completely disintegrated. However, in the CP sediments the majority of 90 Sr activity is still in the form of fuel particles. Due to the low dissolved oxygen concentration and high pH, dissolution of fuel particles in the CP sediments is significantly slower than in soils. After the planned cessation of water pumping from the Pripyat River to the Pond, significant areas of sediments will be drained and exposed to the air. This will significantly enhance the dissolution rate and, correspondingly, the mobility and bioavailability of radionuclides will increase with time. The rate of acidification of exposed bottom sediments was predicted on the basis of acidification of similar soils after liming. Using empirical equations relating the fuel particle dissolution rate to soil and sediment pH allowed prediction of fuel particle dissolution and 90 Sr mobilisation for different remediation scenarios. It is shown that in exposed sediments, fuel particles will be almost completely dissolved in 15-25 years, while in parts of the cooling pond which remain flooded, fuel particle dissolution will take about a century

Review of Saccharomyces boulardii as a treatment option in IBD.

Science.gov (United States)

Sivananthan, Kavitha; Petersen, Andreas Munk

2018-05-17

Review of the yeast Saccharomyces boulardii as a treatment option for the inflammatory bowel diseases (IBD) ulcerative colitis and Crohn's disease. IBD is caused by an inappropriate immune response to gut microbiota. Treatment options could therefore be prebiotics, probiotics, antibiotics and/or fecal transplant. In this review, we have looked at the evidence for the yeast S. boulardii as a treatment option. Searches in PubMed and the Cochrane Library with the MeSH words 'Saccharomyces boulardii AND IBD', 'Saccharomyces boulardii AND Inflammatory Bowel Disease', 'Saccharomyces boulardii AND ulcerative colitis' and 'Saccharomyces boulardii AND Crohn's disease' gave total a total of 80 articles. After exclusions because of irrelevance, articles in other languages and some articles that were not available, 16 articles were included in this review. Three of the clinical trials showed a positive effect of S. boulardii in IBD patients (two Crohn's disease, one ulcerative colitis), while there was one trial that didn't prove any effect (Crohn's disease). Included Animal trials and cell assays describes different anti-inflammatory mechanisms of S. boulardii supporting a possible effect when treating IBD patients. The number of studies of S. boulardii as treatment for IBD is limited. Furthermore, the existing trials have small populations and short duration. We do not have enough evidence to prove the effect of S. boulardii in IBD. Saccharomyces boulardii is, however, a plausible treatment option in the future, but more placebo-controlled clinical studies on both patients with ulcerative colitis and Crohn's disease are needed.

Fuel price and technological uncertainty in a real options model for electricity planning

International Nuclear Information System (INIS)

Fuss, Sabine; Szolgayova, Jana

2010-01-01

Electricity generation is an important source of total CO 2 emissions, which in turn have been found to relate to an acceleration of global warming. Given that many OECD countries have to replace substantial portions of their electricity-generating capacity over the next 10-20 years, investment decisions today will determine the CO 2 -intensity of the future energy mix. But by what type of power plants will old (mostly fossil-fuel-fired) capacity be replaced? Given that modern, less carbon-intensive technologies are still expensive but can be expected to undergo improvements due to technical change in the near future, they may become more attractive, especially if fossil fuel price volatility makes traditional technologies more risky. At the same time, technological progress is an inherently uncertain process itself. In this paper, we use a real options model with stochastic technical change and stochastic fossil fuel prices in order to investigate their impact on replacement investment decisions in the electricity sector. We find that the uncertainty associated with the technological progress of renewable energy technologies leads to a postponement of investment. Even the simultaneous inclusion of stochastic fossil fuel prices in the same model does not make renewable energy competitive compared to fossil-fuel-fired technology in the short run based on the data used. This implies that policymakers have to intervene if renewable energy is supposed to get diffused more quickly. Otherwise, old fossil-fuel-fired equipment will be refurbished or replaced by fossil-fuel-fired capacity again, which enforces the lock-in of the current system into unsustainable electricity generation. (author)

Acute intermittent porphyria: Diagnostic dilemma and treatment options

Directory of Open Access Journals (Sweden)

Mohan Deep Kaur

2015-01-01

Full Text Available Acute intermittent porphyria (AIP presents with diverse group of symptoms making its early diagnosis difficult. Delaying diagnosis and treatment of AIP can be fatal or can cause long term or permanent neurological damage. We present here a case report of AIP where the diagnosis was missed. The diversity of symptoms and details concerning the treatment options for AIP are discussed.

Acute intermittent porphyria: Diagnostic dilemma and treatment options

Science.gov (United States)

Kaur, Mohan Deep; Hazarika, Nita; Saraswat, Namita; Sood, Rajesh

2015-01-01

Acute intermittent porphyria (AIP) presents with diverse group of symptoms making its early diagnosis difficult. Delaying diagnosis and treatment of AIP can be fatal or can cause long term or permanent neurological damage. We present here a case report of AIP where the diagnosis was missed. The diversity of symptoms and details concerning the treatment options for AIP are discussed. PMID:26330726

Spent fuel management options for research reactors in Latin America

International Nuclear Information System (INIS)

2006-06-01

Research reactors (RRs) have been operated in Latin America since the late 1950s, and a total of 23 RRs have been built in the region. At the time of writing (November 2005), 18 RRs are in operation, 4 have been shut down and 1 has been decommissioned. The number of operating RRs in Latin America represents around 6% of the existing operational RRs worldwide and around 21% of the RRs operating in developing countries. Common to all RRs in the region is a consistent record of safe and successful operation. With the purpose of carrying out a collaborative study of different aspects of the management of spent fuel from RRs, some countries from the region proposed to the IAEA in 2000 the organization of a Regional Project. The project (IAEA TC Regional Project RLA/4/018) that was approved for the biennium 2001-2002 and extended for 2003-2004 included the participation of Argentina, Brazil, Chile, Mexico and Peru. The main objectives of this project were: (a) to define the basic conditions for a regional strategy for managing spent fuel that will provide solutions compatible with the economic and technological realities of the countries involved; and (b) to determine what is needed for the temporary wet and dry storage of spent fuel from the research reactors in the countries of the Latin American region that participated in the project. This TECDOC is based on the results of TC Regional Project RLA/4/018. This project was successful in identifying and assessing a number of viable alternatives for RRSF management in the Latin American region. Options for operational and interim storage, spent fuel conditioning and final disposal have been carefully considered. This report presents the views of Latin American experts on RR spent fuel management and will be useful as reference material for the Latin American RR community, decision making authorities in the region and the public in general

Delayed conifer mortality after fuel reduction treatments: Interactive effects of fuel, fire intensity, and bark beetles

Science.gov (United States)

Youngblood, A.; Grace, J.B.; Mciver, J.D.

2009-01-01

Many low-elevation dry forests of the western United States contain more small trees and fewer large trees, more down woody debris, and less diverse and vigorous understory plant communities compared to conditions under historical fire regimes. These altered structural conditions may contribute to increased probability of unnaturally severe wildfires, susceptibility to uncharacteristic insect outbreaks, and drought-related mortality. Broad-scale fuel reduction and restoration treatments are proposed to promote stand development on trajectories toward more sustainable structures. Little research to date, however, has quantified the effects of these treatments on the ecosystem, especially delayed and latent tree mortality resulting directly or indirectly from treatments. In this paper, we explore complex hypotheses relating to the cascade of effects that influence ponderosa pine (Pinus ponderosa) and Douglas-fir (Pseudotsuga menziesii) mortality using structural equation modeling (SEM). We used annual census and plot data through six growing seasons after thinning and four growing seasons after burning from a replicated, operational-scale, completely randomized experiment conducted in northeastern Oregon, USA, as part of the national Fire and Fire Surrogate study. Treatments included thin, burn, thin followed by burn (thin+burn), and control. Burn and thin+burn treatments increased the proportion of dead trees while the proportion of dead trees declined or remained constant in thin and control units, although the density of dead trees was essentially unchanged with treatment. Most of the new mortality (96%) occurred within two years of treatment and was attributed to bark beetles. Bark beetle-caused tree mortality, while low overall, was greatest in thin + burn treatments. SEM results indicate that the probability of mortality of large-diameter ponderosa pine from bark beetles and wood borers was directly related to surface fire severity and bole charring, which in

A comparative review of the options for treatment of erectile dysfunction: which treatment for which patient?

Science.gov (United States)

Hatzimouratidis, Konstantinos; Hatzichristou, Dimitrios G

2005-01-01

The field of erectile dysfunction (ED) has been revolutionised over the last two decades. Several treatment options are available today, most of which are associated with high efficacy rates and favourable safety profiles. A MEDLINE search was undertaken in order to evaluate all currently available data on treatment modalities for ED. Phosphodiesterase type 5 (PDE5) inhibitors (sildenafil, tadalafil, vardenafil) are currently the first-choice of most physicians and patients for the treatment of ED. PDE5 inhibitors have differences in their pharmacological profiles, the most obvious being the long duration of action of tadalafil, but there are no data supporting superiority for any one of them in terms of efficacy or safety. Sublingual apomorphine has limited efficacy compared with the PDE5 inhibitors, and its use is limited to patients with mild ED. Treatment failures with oral drugs may be due to medication, clinician and patient issues. The physician needs to address all of these issues in order to identify true treatment failures. Patients who are truly unresponsive to oral drugs may be offered other treatment options.Intracavernous injections of alprostadil alone, or in combination with other vasoactive agents (papaverine and phentolamine), remain an excellent treatment option, with proven efficacy and safety over time. Topical pharmacotherapy is appealing in nature, but currently available formulations have limited efficacy. Vacuum constriction devices may be offered mainly to elderly patients with occasional intercourse attempts, as younger patients show limited preference because of the unnatural erection that is associated with this treatment modality. Penile prostheses are generally the last treatment option offered, because of invasiveness, cost and non-reversibility; however, they are associated with high satisfaction rates in properly selected patients. All treatment options are associated with particular strengths and weaknesses. A patient

Reprocessing of research reactor fuel the Dounreay option

Energy Technology Data Exchange (ETDEWEB)

Cartwright, P.

1997-08-01

Reprocessing is a proven process for the treatment of spent U/Al Research Reactor fuel. At Dounreay 12679 elements have been reprocessed during the past 30 years. For reactors converting to LEU fuel the uranium recovered in reprocessing can be blended down to less than 20% U{sub 235}, enrichment and be fabricated into new elements. For reactors already converted to LEU it is technically possible to reprocess spent silicide fuel to reduce the U{sub 235} burden and present to a repository only stable conditioned waste. The main waste stream from reprocessing which contains the Fission products is collected in underground storage tanks where it is kept for a period of at least five years before being converted to a stable solid form for return to the country of origin for subsequent storage/disposal. Discharges to the environment from reprocessing are low and are limited to the radioactive gases contained in the spent fuel and a low level liquid waste steam. Both of these discharges are independently monitored, and controlled within strict discharge limits set by the UK Government`s Scottish Office. Transportation of spent fuel to Dounreay has been undertaken using many routes from mainland Europe and has utilised over the past few years both chartered and scheduled vessel services. Several different transport containers have been handled and are currently licensed in the UK. This paper provides a short history of MTR reprocessing at Dounreay, and provides information to show reprocessing can satisfy the needs of MTR operators, showing that reprocessing is a valuable asset in non-proliferation terms, offers a complete solution and is environmentally acceptable.

Polyvalent fuel treatment facility (TCP): shearing and dissolution of used fuel at La Hague facility

Energy Technology Data Exchange (ETDEWEB)

Brueziere, J.; Tribout-Maurizi, A.; Durand, L.; Bertrand, N. [Recycling Business Unit, AREVA, 1 place de la coupole, 92084 Paris La defense Cedex (France)

2013-07-01

Although many used nuclear fuel types have already been recycled, recycling plants are generally optimized for Light Water Reactor (LWR) UO{sub x} fuel. Benefits of used fuel recycling are consequently restricted to those fuels, with only limited capacity for the others like LWR MOX, Fast Reactor (FR) MOX or Research and Test Reactor (RTR) fuel. In order to recycle diverse fuel types, an innovative and polyvalent shearing and dissolving cell is planned to be put in operation in about 10 years at AREVA's La Hague recycling plant. This installation, called TCP (French acronym for polyvalent fuel treatment) will benefit from AREVA's industrial feedback, while taking part in the next steps towards a fast reactor fuel cycle development using innovative treatment solutions. Feasibility studies and R/Development trials on dissolution and shearing are currently ongoing. This new installation will allow AREVA to propose new services to its customers, in particular in term of MOX fuel, Research Test Reactors fuel and Fast Reactor fuel treatment. (authors)

Analysis of fuel options for the breakeven core configuration of the Advanced Recycling Reactor

Energy Technology Data Exchange (ETDEWEB)

Stauff, N.E.; Klim, T.K.; Taiwo, T.A. [Argonne National Laboratory, Argonne, IL (United States); Fiorina, C. [Politecnico di Milano, Milan (Italy); Franceschini, F. [Westinghouse Electric Company LLC., Cranberry Township, Pennsylvania (United States)

2013-07-01

A trade-off study is performed to determine the impacts of various fuel forms on the core design and core physics characteristics of the sodium-cooled Toshiba- Westinghouse Advanced Recycling Reactor (ARR). The fuel forms include oxide, nitride, and metallic forms of U and Th. The ARR core configuration is redesigned with driver and blanket regions in order to achieve breakeven fissile breeding performance with the various fuel types. State-of-the-art core physics tools are used for the analyses. In addition, a quasi-static reactivity balance approach is used for a preliminary comparison of the inherent safety performances of the various fuel options. Thorium-fueled cores exhibit lower breeding ratios and require larger blankets compared to the U-fueled cores, which is detrimental to core compactness and increases reprocessing and manufacturing requirements. The Th cores also exhibit higher reactivity swings through each cycle, which penalizes reactivity control and increases the number of control rods required. On the other hand, using Th leads to drastic reductions in void and coolant expansion coefficients of reactivity, with the potential for enhancing inherent core safety. Among the U-fueled ARR cores, metallic and nitride fuels result in higher breeding ratios due to their higher heavy metal densities. On the other hand, oxide fuels provide a softer spectrum, which increases the Doppler effect and reduces the positive sodium void worth. A lower fuel temperature is obtained with the metallic and nitride fuels due to their higher thermal conductivities and compatibility with sodium bonds. This is especially beneficial from an inherent safety point of view since it facilitates the reactor cool-down during loss of power removal transients. The advantages in terms of inherent safety of nitride and metallic fuels are maintained when using Th fuel. However, there is a lower relative increase in heavy metal density and in breeding ratio going from oxide to metallic

Treatment Options for Narcolepsy.

Science.gov (United States)

Barateau, Lucie; Lopez, Régis; Dauvilliers, Yves

2016-05-01

Narcolepsy type 1 and narcolepsy type 2 are central disorders of hypersomnolence. Narcolepsy type 1 is characterized by excessive daytime sleepiness and cataplexy and is associated with hypocretin-1 deficiency. On the other hand, in narcolepsy type 2, cerebrospinal fluid hypocretin-1 levels are normal and cataplexy absent. Despite major advances in our understanding of narcolepsy mechanisms, its current management is only symptomatic. Treatment options may vary from a single drug that targets several symptoms, or multiple medications that each treats a specific symptom. In recent years, narcolepsy treatment has changed with the widespread use of modafinil/armodafinil for daytime sleepiness, antidepressants (selective serotonin and dual serotonin and noradrenalin reuptake inhibitors) for cataplexy, and sodium oxybate for both symptoms. Other psychostimulants can also be used, such as methylphenidate, pitolisant and rarely amphetamines, as third-line therapy. Importantly, clinically relevant subjective and objective measures of daytime sleepiness are required to monitor the treatment efficacy and to provide guidance on whether the treatment goals are met. Associated symptoms and comorbid conditions, such as hypnagogic/hypnopompic hallucinations, sleep paralysis, disturbed nighttime sleep, unpleasant dreams, REM- and non REM-related parasomnias, depressive symptoms, overweight/obesity, and obstructive sleep apnea, should also be taken into account and managed, if required. In the near future, the efficacy of new wake-promoting drugs, anticataplectic agents, hypocretin replacement therapy and immunotherapy at the early stages of the disease should also be evaluated.

Nuclear fuel cycle in France: today's situation and long term options

International Nuclear Information System (INIS)

Boullis, B.; Drevon, C.; Pays, M.

2015-01-01

In France plutonium and uranium are recycled as MOX fuel (used in 22 reactors) and URE (enriched uranium from spent fuel). Fission products and minor actinides, that composed ultimate wastes, are vitrified and cast in stainless steel containers. Fuel recycling has reached industrial maturity and about 30.000 tonnes of spent fuels have been processed. This strategy has allowed France to save about 17% of its annual consumption of uranium and to get a least volume of high-level radioactive wastes. This strategy can be pushed forwards by introducing a multi-recycling option in which plutonium and uranium from spent MOX fuels are recycled. Multi-recycling produces a nuclear fuel that is polluted with remainders of actinides and fission products and to compensate this deterioration of its neutronic properties a higher concentration of fissile materials is required. For safety reasons the concentration of plutonium in MOX fuels is limited to 12% so multi-recycling is not a strategy for a fleet of PWRs only. Fast neutron reactors use uranium and plutonium in a more efficiently way and can be a solution for multi-recycling. The study shows that for a constant output of 420 TWh a year a fleet of PWRs need 7600 tonnes of natural uranium. If mono-recycling is allowed this consumption decreases to 6300 tonnes a year and if multi-recycling is allowed by integrating fast reactors in the proportion of 40% of the fleet, this consumption drops to 2700 tonnes a year. The study also shows the changes in the production of wastes in relation with multi-recycling. (A.C.)

The option study of air shipment of DUPIC fuel elements to Canada

International Nuclear Information System (INIS)

Lee, H. H.; Park, J. J.; Shin, J. M.; Kim, J. H.; Yang, M. S.; Koo, J. H.

2003-01-01

KAERI developed a DUPIC nuclear fuel with the refabrication of spent PWR fuel discharged from domestic nuclear power plant by a dry process at M6 hot-cell in IMEF. To verify the performance of DUPIC nuclear fuel, irradiation test at operating conditions of commercially operating power plant is essential. Since the HANARO research reactor of KAERI does not have Fuel Test Loop(FTL) for irradiating nuclear fuel under high temperature and high pressure conditions, DUPIC fuel cannot be irradiated in the FTL of HANARO until about 2008. In the 13-th PRM among Korea, Canada, USA and IAEA, AECL proposed that KAERI fabricated DUPIC fuel can be irradiated in the FTL of the NRU research reactor without charge of neutrons. The transportation quantity of DUPIC fuel to Canada is 10 elements(about 6 kg). This transportation package is classified as the 7-th class according to 'recommendation on the transport of dangerous goods' made by the United Nations. Air shipment was investigated as a promising option because it is generally understood that air shipment is more appropriate than ship shipment for transportation of small quantity of nuclear materials from the perspectives of cost and transportation period. In case of air shipment, the IATA regulations have been more intensified since the July of 2001. To make matters worse, it becomes more difficult to get the ratification of corresponding authorities due to 9.11 terror. It was found that at present there is no proper air transportation cask for DUPIC fuel. So, air transportation is considered to be impossible. An alternative of using the exemption limit of fissile material was reviewed. Its results showed that in case of going via USA territory, approvals from US DOT should be needed. The approvals include shipping and cask approvals on technical cask testing. Furthermore, since passes through territories of Japan and Russia have to be done in case of using a regular air cargo from Korea to Canada, approvals from Russia and

Beyond Fuel Treatment Effectiveness: Characterizing Interactions between Fire and Treatments in the US

Directory of Open Access Journals (Sweden)

Kevin Barnett

2016-10-01

Full Text Available In the United States, fuel reduction treatments are a standard land management tool to restore the structure and composition of forests that have been degraded by past management. Although treatments can have multiple purposes, their principal objective is to create landscape conditions where wildland fire can be safely managed to help achieve long-term land management goals. One critique is that fuel treatment benefits are unlikely to transpire due to the low probability that treated areas will be burned by a subsequent fire within a treatment’s lifespan, but little quantitative information exists to corroborate this argument. We summarized the frequency, extent, and geographic variation of fire and fuel treatment interactions on federal lands within the conterminous United States (CONUS. We also assessed how the encounters between fuel treatments and fires varied with treatment size, treatment age, and number of times treated. Overall, 6.8% of treatment units evaluated were encountered by a subsequent fire during the study period, though this rate varied among ecoregions across the CONUS. Larger treatment units were more likely to be encountered by a fire, and treatment units were most frequently burned within one year of the most recent treatment, the latter of which is likely because of ongoing maintenance of existing treatments. Our results highlight the need to identify and prioritize additional opportunities to reduce fuel loading and fire risk on the millions of hectares of federal lands in the CONUS that are in need of restoration.

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

Desmoid tumors: clinical features and treatment options: a case ...

African Journals Online (AJOL)

Desmoid tumors: clinical features and treatment options: a case report and a review of literature. Amel Achour Jenayah, Hajer Bettaieb, Sarra Saoudi, Anissa Gharsa, Ezzeddine Sfar, Fethia Boudaya, Dalenda Chelli ...

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

Energy Technology Data Exchange (ETDEWEB)

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

1998-03-15

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

Engineered Option Treatment of Remediated Nitrate Salts: Surrogate Batch-Blending Testing

Energy Technology Data Exchange (ETDEWEB)

Anast, Kurt Roy [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-03-11

This report provides results from batch-blending test work for remediated nitrate salt (RNS) treatment. Batch blending was identified as a preferred option for blending RNS and unremediated nitrate salt (UNS) material with zeolite to effectively safe the salt/Swheat material identified as ignitable (U.S. Environmental Protection Agency code D001). Blending with zeolite was the preferred remediation option identified in the Options Assessment Report and was originally proposed as the best option for remediation by Clark and Funk in their report, Chemical Reactivity and Recommended Remediation Strategy for Los Alamos Remediated Nitrate Salt (RNS) Wastes, and also found to be a preferred option in the Engineering Options Assessment Report: Nitrate Salt Waste Stream Processing. This test work evaluated equipment and recipe alternatives to achieve effective blending of surrogate waste with zeolite.

Current status in the treatment options for esophageal achalasia.

Science.gov (United States)

Chuah, Seng-Kee; Chiu, Chien-Hua; Tai, Wei-Chen; Lee, Jyong-Hong; Lu, Hung-I; Changchien, Chi-Sin; Tseng, Ping-Huei; Wu, Keng-Liang

2013-09-07

Recent advances in the treatment of achalasia include the use of high-resolution manometry to predict the outcome of patients and the introduction of peroral endoscopic myotomy (POEM). The first multicenter randomized, controlled, 2-year follow-up study conducted by the European Achalasia Trial group indicated that laparoscopic Heller myotomy (LHM) was not superior to pneumatic dilations (PD). Publications on the long-term success of laparoscopic surgery continue to emerge. In addition, laparoscopic single-site surgery is applicable to advanced laparoscopic operations such as LHM and anterior fundoplication. The optimal treatment option is an ongoing matter of debate. In this review, we provide an update of the current progress in the treatment of esophageal achalasia. Unless new conclusive data prove otherwise, LHM is considered the most durable treatment for achalasia at the expense of increased reflux-associated complications. However, PD is the first choice for non-surgical treatment and is more cost-effective. Repeated PD according to an "on-demand" strategy based on symptom recurrence can achieve long-term remission. Decision making should be based on clinical evidence that identifies a subcategory of patients who would benefit from specific treatment options. POEM has shown promise but its long-term efficacy and safety need to be assessed further.

Angina pectoris: current therapy and future treatment options.

Science.gov (United States)

Parikh, Raj; Kadowitz, Philip J

2014-02-01

Angina pectoris is the consequence of an inequality between the demand and supply of blood to the heart. Angina manifests itself as chest pain or discomfort and is a common complaint of patients in the hospital and in the clinic. There are, in fact, roughly half a million new cases of angina per year. Chest pain, while having many etiologies, is generally considered to be most lethal when related to a cardiac cause. In this review, the authors outline the current medical and surgical therapies that are used in the management of angina. Highlights of the various clinical trials that have assisted in the investigation of these therapies are summarized also. Then, the authors provide a focused review of the novel therapy options for angina that are currently being explored. From new medical treatments to revised surgical techniques to the discovery of stem cell therapy, many innovative options are being investigated for the treatment of angina.

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)

Current treatment options for vulvovaginal candidiasis caused by azole-resistant Candida species.

Science.gov (United States)

Sobel, J D; Sobel, R

2018-06-22

Clinicians are increasingly challenged by patients with refractory vulvovaginal candidiasis (VVC) caused by azole-resistant Candida species. Fluconazole resistant C.albicans is a growing and perplexing problem following years of indiscriminate drug prescription and unnecessary drug exposure and for which there are few therapeutic alternatives. Regrettably, although the azole class of drugs has expanded, new classes of antifungal drugs have not been forthcoming, limiting effective treatment options in patients with azole resistant Candida vaginitis. Areas covered: This review covers published data on epidemiology, pathophysiology and treatment options for women with azole-resistant refractory VVC. Expert opinion: Fluconazole resistant C.albicans adds to the challenge of azole resistant non-albicans Candida spp. Both issues follow years of indiscriminate drug prescription and unnecessary fluconazole exposure. Although an understanding of azole resistance in yeast has been established, this knowledge has not translated into useful therapeutic advantage. Treatment options for such women with refractory symptoms are extremely limited. New therapeutic options and strategies are urgently needed to meet this challenge of azole drug resistance.

New Fathers' Perinatal Depression and Anxiety-Treatment Options: An Integrative Review.

Science.gov (United States)

O'Brien, Anthony P; McNeil, Karen A; Fletcher, Richard; Conrad, Agatha; Wilson, Amanda J; Jones, Donovan; Chan, Sally W

2017-07-01

More than 10% of fathers experience depression and anxiety during the perinatal period, but paternal perinatal depression (PPND) and anxiety have received less attention than maternal perinatal mental health problems. Few mainstream treatment options are available for men with PPND and anxiety. The aim of this literature review was to summarize the current understanding of PPND and the treatment programs specifically designed for fathers with perinatal depression. Eight electronic databases were searched using a predefined strategy, and reference lists were also hand searched. PPND and anxiety were identified to have a negative impact on family relationships, as well as the health of mothers and children. Evidence suggests a lack of support and tailored treatment options for men having trouble adjusting to the transition to fatherhood. Of the limited options available, cognitive behavioral therapy, group work, and blended delivery programs, including e-support approaches appear to be most effective in helping fathers with perinatal depression and anxiety. The review findings have important implications for the understanding of PPND and anxiety. Future research is needed to address the adoption of father-inclusive and father-specific models of care to encourage fathers' help-seeking behavior. Inclusion of male-specific requirements into support and treatment options can improve the ability of services to engage new fathers. Psychotherapeutic intervention could assist to address the cognitive differences and dissonance for men adjusting to the role of father, including male identity and role expectations.

Current treatment options for meningioma.

Science.gov (United States)

Apra, Caroline; Peyre, Matthieu; Kalamarides, Michel

2018-03-01

With an annual incidence of 5/100,000, meningioma is the most frequent primary tumor of the central nervous system. Risk factors are radiotherapy and hormone intake. Most meningiomas are grade I benign tumors, but up to 15% are atypical and 2% anaplastic according to the WHO 2016 histological criteria. Areas covered: This review details the current standard therapy based on international guidelines and recent literature, and describes new approaches developed to treat refractory cases. First-line treatments are observation and surgery, but adjuvant radiotherapy/radiosurgery is discussed for atypical and indicated for anaplastic meningiomas. The most problematic cases include skull base meningiomas that enclose vasculo-nervous structures and surgery- and radiation-refractory tumors that present with significant morbidity and mortality. The treatment of recurrent tumors is based on radiotherapy and repeated surgery. Systematic therapies are not effective in general but several clinical trials are ongoing. Expert commentary: Molecular characterization of the tumors, based on genetic mutations such as NF2, SMO, TERT, TRAF7, and on the methylation profile are developing, completing the histological classification and giving new insights into prognosis and treatment options.

Thermal treatment of sewage sludge from waste water. Tratamiento termico de lodos procedentes de aguas residuales

Energy Technology Data Exchange (ETDEWEB)

Andreottola, G. (Universidad de Trento (Italy)); Canziani, R.; Ragazzi, M. (Politicnico de Milan (Italy))

1994-01-01

Thermal Treatment of sewage sludge can be beneficial as a pre-treatment step of many treatment/disposal options, but above all, it allows the recovery of the energetic content sludge. Energy recovery from sewage sludge can be performed in many ways; direct incineration thermal drying followed by incineration and co-combustion with municipal solid wastes or other non conventional fuels. Another option is the recovery of waste energy (e.g. from an endo thermal engine using biogas as fuel) to dry sludge wich, in turn can be used as a fuel. The paper will evaluate several options of thermal treatment of sewage sludge, with particular emphasis on the energetic yield from different processes. (Author)

Analysis of environmental friendliness of DUPIC fuel cycle

International Nuclear Information System (INIS)

Ko, Won Il; Kim, Ho Dong

2001-07-01

Some properties of irradiated DUPIC fuels are compared with those of other fuel cycles. It was indicated that the toxicity of the DUPIC option based on 1 GWe-yr is much smaller than those of other fuel cycle options, and is just about half the order of magnitude of other fuel cycles. From the activity analysis of 99 Tc and 237 Np, which are important to the long-term transport of fission products stored in geologic media, the DUPIC option, was being contained only about half of those other options. It was found from the actinide content estimation that the MOX option has the lowest plutonium arising based on 1 GWe-year and followed by the DUPIC option. However, fissile Pu content generated in the DUPIC fuel was the lowest among the fuel cycle options. From the analysis of radiation barrier in proliferation resistance aspect, the fresh DUPIC fuel can play a radiation barrier part, better than CANDU spent fuels as well as fresh MOX fuel. It is indicated that the DUPIC fuel cycle has the excellent resistance to proliferation, compared with an existing reprocessing option and CANDU once-through option. In conclusions, DUPIC fuel cycle would have good properties on environmental effect and proliferation resistance, compared to other fuel cycle cases

Fuels planning: science synthesis and integration; economic uses fact sheet 03: economic impacts of fuel treatments

Science.gov (United States)

Rocky Mountain Research Station USDA Forest Service

2004-01-01

With increased interest in reducing hazardous fuels in dry inland forests of the American West, agencies and the public will want to know the economic impacts of fuel reduction treatments. This fact sheet discusses the economic impact tool, a component of My Fuel Treatment Planner, for evaluating economic impacts.

Effect of mastication and other mechanical treatments on fuel structure in chaparral

Science.gov (United States)

Brennan, Teresa J.; Keeley, Jon E.

2015-01-01

Mechanical fuel treatments are a common pre-fire strategy for reducing wildfire hazard that alters fuel structure by converting live canopy fuels to a compacted layer of dead surface fuels. Current knowledge concerning their effectiveness, however, comes primarily from forest-dominated ecosystems. Our objectives were to quantify and compare changes in shrub-dominated chaparral following crushing, mastication, re-mastication and mastication-plus-burning treatments, and to assess treatment longevity. Results from analysis of variance (ANOVA) identified significant differences in all fuel components by treatment type, vegetation type and time since treatment. Live woody fuel components of height, cover and mass were positively correlated with time since treatment, whereas downed woody fuel components were negatively correlated. Herbaceous fuels, conversely, were not correlated, and exhibited a 5-fold increase in cover across treatment types in comparison to controls. Average live woody fuel recovery was 50% across all treatment and vegetation types. Differences in recovery between time-since-treatment years 1–8 ranged from 32–65% and exhibited significant positive correlations with time since treatment. These results suggest that treatment effectiveness is short term due to the rapid regrowth of shrubs in these systems and is compromised by the substantial increase in herbaceous fuels. Consequences of not having a full understanding of these treatments are serious and leave concern for their widespread use on chaparral-dominated landscapes.

Development of MOX facilities and the impact on the nuclear fuel markets

International Nuclear Information System (INIS)

Patterson, J.

1990-01-01

Mixed-oxide (MOX) fuel is nearing maturity as a fuel supply option. This paper briefly reviews the history and current status of the MOX fuel market, including the projected increase in demand for MOX fuel as more plutonium becomes available from the operation of commercial irradiated fuel reprocessing plants in Europe. The uncertainties of such projected demand are discussed, together with the anticipated requirements from the next generation of MOX fabrication plants. The impact of the growing demand for MOX fuel is assessed in the traditional sectors of the uranium fuel cycle. Finally, the author turns to a generalized treatment of the economic aspects of MOX fuel utilization, showing the financially attractive regimes of MOX use which will benefit nuclear power utilities and continue to ensure that MOX fuel can consolidate its position as a mature fuel supply option in those countries that have opted to recycle their spent fuel

Neonatal hepatic haemangioendothelioma: treatment options and dilemmas

International Nuclear Information System (INIS)

Meijs, Bram B. van der; Merks, Johannes H.M.; Haan, Timo R. de; Tabbers, Merit M.; Rijn, Rick R. van

2009-01-01

We describe a case of rapidly progressive neonatal diffuse hepatic haemangioendotheliomas. The clinical picture was characterized by respiratory insufficiency due to gross abdominal enlargement, coagulopathy, and the development of cardiovascular insufficiency during the course of disease. Pharmacological, radiotherapeutic and endovascular treatment options all proved ineffective. We describe our own experience and the steps taken to treat this child. Unfortunately, the child died as a consequence of the disease. As cases like this are rare and are associated with severe morbidity and high mortality, more knowledge needs to be gained on infantile hepatic haemangioendotheliomas and their optimal treatment. The use of a web-based data registry could be beneficial. (orig.)

Hyaluronic acid and other conservative treatment options for osteoarthritis of the ankle

NARCIS (Netherlands)

Witteveen, Angelique G. H.; Hofstad, Cheriel J.; Kerkhoffs, Gino M. M. J.

2015-01-01

Background The cause of ankle osteoarthritis (OA) is usually trauma. Patients are relatively young, since ankle trauma occurs at a relatively young age. Several conservative treatment options are available, evidence of the benefits and harms of these options are lacking. Objectives To assess the

Progressive Supranuclear Palsy and Corticobasal Degeneration: Pathophysiology and Treatment Options

OpenAIRE

Lamb, Ruth; Rohrer, Jonathan D.; Lees, Andrew J.; Morris, Huw R.

2016-01-01

Opinion statement There are currently no disease-modifying treatments for progressive supranuclear palsy (PSP) or corticobasal degeneration (CBD), and no approved pharmacological or therapeutic treatments that are effective in controlling their symptoms. The use of most pharmacological treatment options are based on experience in other disorders or from non-randomized historical controls, case series, or expert opinion. Levodopa may provide some improvement in symptoms of Parkinsonism (specif...

Progressive Supranuclear Palsy and Corticobasal Degeneration: Pathophysiology and Treatment Options

OpenAIRE

Lamb, R.; Rohrer, J. D.; Lees, A. J.; Morris, H. R.

2016-01-01

There are currently no disease-modifying treatments for progressive supranuclear palsy (PSP) or corticobasal degeneration (CBD), and no approved pharmacological or therapeutic treatments that are effective in controlling their symptoms. The use of most pharmacological treatment options are based on experience in other disorders or from non-randomized historical controls, case series, or expert opinion. Levodopa may provide some improvement in symptoms of Parkinsonism (specifically bradykinesi...

24-h Efficacy of Glaucoma Treatment Options.

Science.gov (United States)

Konstas, Anastasios G P; Quaranta, Luciano; Bozkurt, Banu; Katsanos, Andreas; Garcia-Feijoo, Julian; Rossetti, Luca; Shaarawy, Tarek; Pfeiffer, Norbert; Miglior, Stefano

2016-04-01

Current management of glaucoma entails the medical, laser, or surgical reduction of intraocular pressure (IOP) to a predetermined level of target IOP, which is commensurate with either stability or delayed progression of visual loss. In the published literature, the hypothesis is often made that IOP control implies a single IOP measurement over time. Although the follow-up of glaucoma patients with single IOP measurements is quick and convenient, such measurements often do not adequately reflect the untreated IOP characteristics, or indeed the quality of treated IOP control during the 24-h cycle. Since glaucoma is a 24-h disease and the damaging effect of elevated IOP is continuous, it is logical that we should aim to understand the efficacy of all treatment options throughout the 24-h period. This article first reviews the concept and value of diurnal and 24-h IOP monitoring. It then critically evaluates selected available evidence on the 24-h efficacy of medical, laser and surgical therapy options. During the past decade several controlled trials have significantly enhanced our understanding on the 24-h efficacy of all glaucoma therapy options. Nevertheless, more long-term evidence is needed to better evaluate the 24-h efficacy of glaucoma therapy and the precise impact of IOP characteristics on glaucomatous progression and visual prognosis.

Studies relating to construction materials to be used in different options for head end treatment in reprocessing of mixed carbide fuel of plutonium and uranium

International Nuclear Information System (INIS)

Rajan, S.K.; Palamalai, A.; Ravi, T.N.; Sampath, M.; Raman, V.R.; Balasubramanian, G.R.

1993-01-01

Mixed carbide of uranium and plutonium has been chosen as the fuel for the first core of Fast Breeder Test Reactor, installed in the Indira Gandhi Centre for Atomic Research. Reprocessing of this fuel is one of the vital steps to prove the viability of the fuel cycle. The head end treatment process introduces constraints in the reprocessing of carbide fuel when compared to the commonly used mixed oxide fuel. Three head end processes, namely direct oxidation, pyrohydrolysis and direct dissolution in nitric acid with oxidation of organic acids were considered for study for exercising the choice. The paper briefly describes the three processes. In each process probable material of construction and related problems are discussed. (author). 3 refs, 5 figs, 7 tabs

Current options for the treatment of facial angiofibromas.

Science.gov (United States)

Salido-Vallejo, R; Garnacho-Saucedo, G; Moreno-Giménez, J C

2014-01-01

Facial angiofibromas are hamartomatous growths that are closely associated with tuberous sclerosis complex and, in fact, they constitute one of the main diagnostic criteria for that disease. These lesions composed of blood vessels and fibrous tissue appear on the face at an early age. Since they have important physical and psychological repercussions for patients, several treatment options have been used to remove them or improve their appearance. However, the lack of treatment guidelines prevents us from developing a common protocol for patients with this condition. The present article aims to review the treatments for facial angiofibromas used to date and to propose a new evidence-based treatment protocol. Copyright © 2012 Elsevier España, S.L. and AEDV. All rights reserved.

The application of systems engineering principles to the prioritization of sustainable nuclear fuel cycle options

International Nuclear Information System (INIS)

Price, Robert R.; Singh, Bhupinder P.; MacKinnon, Robert J.; David Sevougian, S.

2013-01-01

We investigate the implementation of the principles of systems engineering in the U.S. Department of Energy’s Fuel Cycle Technologies (FCT) Program to provide a framework for achieving its long-term mission of demonstrating and deploying sustainable nuclear fuel cycle options. A fuel cycle “screening” methodology is introduced that provides a systematic, objective, and traceable method for evaluating and categorizing nuclear fuel cycles according to their performance in meeting sustainability objectives. The goal of the systems engineering approach is to transparently define and justify the research and development (R and D) necessary to deploy sustainable fuel cycle technologies for a given set of national policy objectives. The approach provides a path for more efficient use of limited R and D resources and facilitates dialog among a variety of stakeholder groups interested in U.S. energy policy. Furthermore, the use of systems engineering principles will allow the FCT Program to more rapidly adapt to future policy changes, including any decisions based on recommendations of the Blue Ribbon Commission on America’s Nuclear Future. Specifically, if the relative importance of policy objectives changes, the FCT Program will have a structured process to rapidly determine how this impacts potential fuel cycle performance and the prioritization of needed R and D for associated technologies. - Highlights: ► Systems engineering principles applied in U.S. DOE-NE Fuel Cycle Technology Program. ► Use of decision analysis methods for determining promising nuclear fuel cycles. ► A new screening methodology to help communicate and prioritize U.S. DOE R and D needs. ► Fuel cycles categorized by performance/risk in meeting FCT Program objectives. ► Systems engineering allows DOE-NE to more rapidly adapt to future policy changes

Alternative pharmacological treatment options for agitation in Alzheimer’s disease

Directory of Open Access Journals (Sweden)

Francesco Panza

2015-11-01

Full Text Available In patients with dementia and Alzheimer’s disease (AD, treatment of neuropsychiatric symptoms (NPS is a major concern in the management of these devastating diseases. Among NPS in AD, agitation and aggression are common with earlier institutionalization, increased morbidity and mortality, and greater caregiver burden. Pharmacological treatments for AD-related agitation, specifically off-label use of atypical antipsychotics, showed only modest improvements, with increased side-effect burden and risk of mortality. Non-pharmacological treatment approaches have become the preferred firstline option. However, when such treatments fail, pharmacological options are often used. Therefore, there is an urgent need to identify effective and safe pharmacological treatments for agitation/aggression in AD and dementia. Unfortunately, progresses have been slow, with a small number of methodologically heterogeneous randomized controlled trials (RCTs, with disappointing results. However, evidence coming from recently completed RCTs on novel or repositioned drugs (mibampator, dextromethorphan/ quinidine, cannabinoids, and citalopram showed some promise in treating agitation in AD, but still with safety concerns. Further evidence will come from ongoing Phase II and III trials on promising novel drugs for treating these distressing symptoms in patients with AD and dementia.

Current Treatment Options for Auricular Hematomas.

Science.gov (United States)

MacPhail, Catriona

2016-07-01

Ear disease, such as otitis externa, resulting in aggressive head shaking or ear scratching, is the most common cause of the development of aural hematomas in dogs and cats. An underlying immunologic cause has also been proposed to explain cartilage and blood vessel fragility. Numerous options exist for management of aural hematomas, from medical management alone with corticosteroids, to simple hematoma centesis, to surgical intervention. Because this condition is usually secondary to another disease process, regardless of mode of treatment, likelihood of recurrence is low if the underlying condition is managed properly. Copyright © 2016 Elsevier Inc. All rights reserved.

Weapons-grade plutonium dispositioning. Volume 2: Comparison of plutonium disposition options

International Nuclear Information System (INIS)

Brownson, D.A.; Hanson, D.J.; Blackman, H.S.

1993-06-01

The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate disposition options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) offered to assist the NAS in this evaluation by investigating the technical aspects of the disposition options and their capability for achieving plutonium annihilation levels greater than 90%. This report was prepared for the NAS to document the gathered information and results from the requested option evaluations. Evaluations were performed for 12 plutonium disposition options involving five reactor and one accelerator-based systems. Each option was evaluated in four technical areas: (1) fuel status, (2) reactor or accelerator-based system status, (3) waste-processing status, and (4) waste disposal status. Based on these evaluations, each concept was rated on its operational capability and time to deployment. A third rating category of option costs could not be performed because of the unavailability of adequate information from the concept sponsors. The four options achieving the highest rating, in alphabetical order, are the Advanced Light Water Reactor with plutonium-based ternary fuel, the Advanced Liquid Metal Reactor with plutonium-based fuel, the Advanced Liquid Metal Reactor with uranium-plutonium-based fuel, and the Modular High Temperature Gas-Cooled Reactor with plutonium-based fuel. Of these four options, the Advanced Light Water Reactor and the Modular High Temperature Gas-Cooled Reactor do not propose reprocessing of their irradiated fuel. Time constraints and lack of detailed information did not allow for any further ratings among these four options. The INEL recommends these four options be investigated further to determine the optimum reactor design for plutonium disposition

Weapons-grade plutonium dispositioning. Volume 2: Comparison of plutonium disposition options

Energy Technology Data Exchange (ETDEWEB)

Brownson, D.A.; Hanson, D.J.; Blackman, H.S. [and others

1993-06-01

The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate disposition options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) offered to assist the NAS in this evaluation by investigating the technical aspects of the disposition options and their capability for achieving plutonium annihilation levels greater than 90%. This report was prepared for the NAS to document the gathered information and results from the requested option evaluations. Evaluations were performed for 12 plutonium disposition options involving five reactor and one accelerator-based systems. Each option was evaluated in four technical areas: (1) fuel status, (2) reactor or accelerator-based system status, (3) waste-processing status, and (4) waste disposal status. Based on these evaluations, each concept was rated on its operational capability and time to deployment. A third rating category of option costs could not be performed because of the unavailability of adequate information from the concept sponsors. The four options achieving the highest rating, in alphabetical order, are the Advanced Light Water Reactor with plutonium-based ternary fuel, the Advanced Liquid Metal Reactor with plutonium-based fuel, the Advanced Liquid Metal Reactor with uranium-plutonium-based fuel, and the Modular High Temperature Gas-Cooled Reactor with plutonium-based fuel. Of these four options, the Advanced Light Water Reactor and the Modular High Temperature Gas-Cooled Reactor do not propose reprocessing of their irradiated fuel. Time constraints and lack of detailed information did not allow for any further ratings among these four options. The INEL recommends these four options be investigated further to determine the optimum reactor design for plutonium disposition.

Development of Vegetation and Surface Fuels Following Fire Hazard Reduction Treatment

Directory of Open Access Journals (Sweden)

Scott L. Stephens

2012-08-01

Full Text Available In dry western Unites States forests where past resource management has altered the ecological role of fire and stand characteristics alike, mechanical thinning and prescribed burning are commonly applied in wildfire hazard abatement. The reduced surface fuel loads and stand structures resulting from fuels modifications are temporary, yet few studies have assessed the lifespan of treatment effects. We sampled forest fuels and vegetation following fuels reduction in a chronosequence of time since treatment in the northern Sierra Nevada and southern Cascade regions of California. Treatments altered overstory characteristics including stand density, basal area, and species composition. These effects were still present on the oldest treatment sites (8–15 years post-treatment. Other stand characteristics, particularly timelag fuel loads, seedling density, and shrub cover, exhibited substantial variability, and differences between treatment age classes and between treatment and control groups were not statistically significant.

For Some Breast Cancers, New Drug May Be Treatment Option

Science.gov (United States)

Results from an international clinical trial suggest that women with metastatic, HER2-positive breast cancer that is no longer responding to the targeted therapy trastuzumab (Herceptin) may soon have a new treatment option.

Spent fuel verification options for final repository safeguards in Finland. A study on verification methods, their feasibility and safety aspects

International Nuclear Information System (INIS)

Hautamaeki, J.; Tiitta, A.

2000-12-01

The verification possibilities of the spent fuel assemblies from the Olkiluoto and Loviisa NPPs and the fuel rods from the research reactor of VTT are contemplated in this report. The spent fuel assemblies have to be verified at the partial defect level before the final disposal into the geologic repository. The rods from the research reactor may be verified at the gross defect level. Developing a measurement system for partial defect verification is a complicated and time-consuming task. The Passive High Energy Gamma Emission Tomography and the Fork Detector combined with Gamma Spectrometry are the most potential measurement principles to be developed for this purpose. The whole verification process has to be planned to be as slick as possible. An early start in the planning of the verification and developing the measurement devices is important in order to enable a smooth integration of the verification measurements into the conditioning and disposal process. The IAEA and Euratom have not yet concluded the safeguards criteria for the final disposal. E.g. criteria connected to the selection of the best place to perform the verification. Measurements have not yet been concluded. Options for the verification places have been considered in this report. One option for a verification measurement place is the intermediate storage. The other option is the encapsulation plant. Crucial viewpoints are such as which one offers the best practical possibilities to perform the measurements effectively and which would be the better place in the safeguards point of view. Verification measurements may be needed both in the intermediate storages and in the encapsulation plant. In this report also the integrity of the fuel assemblies after wet intermediate storage period is assessed, because the assemblies have to stand the handling operations of the verification measurements. (orig.)

Social science to improve fuels management: a synthesis of research on assessing social acceptability of fuels treatments

Science.gov (United States)

Terry C. Daniel; Michael Valdiserri; Carrie R. Daniel; Pamela Jakes; Pamela Jakes; Susan Barro

2005-01-01

A series of syntheses were commissioned by the USDA Forest Service to aid in fuels mitigation project planning. This synthesis focuses on research for assessing the social acceptability of fuels treatments. The synthesis is structured around six important considerations for any social acceptability assessment: defining the fuels treatments being assessed; representing...

Fuel cells - An option for the future

International Nuclear Information System (INIS)

Vielstich, W.

1984-01-01

The direct conversion of the energy of a fuel into electrical energy in fuel cells avoids the losses inseparable from the indirect conversion via heat and mechanical energy. The idea to use this concept of energy conversion for the application in power stations would offer the following advantages: a slightly better total energy efficiency; no environmental problems; and flexibility in size according to the construction in the battery stacks. The use of acid and alkaline H 2 /O 2 fuel cells in the U.S. space program has demonstrated the high energy per weight data possible with a fuel cell device including tankage. Therefore, the application of fuel cells in electric vehicles seems to be suitable at least from the technical point of view. Kordesch has converted an Austin A-40 to electric propulsion by replacing the gasoline engine by an 8-kW truck motor powered by a 6-kW alkaline hydrogen-air fuel cell/4-kW lead-acid hybrid system. Two severe handicaps that occurred were the use of gas cylinders for the storage of the hydrogen and the voluminous CO 2 scrubber to prevent carbonization of the alkaline electrolyte. The direct conversion of a liquid fuel like methanol would be advantageous

Advanced Reactor Technology Options for Utilization and Transmutation of Actinides in Spent Nuclear Fuel

International Nuclear Information System (INIS)

2009-09-01

Renewed interest in the potential of nuclear energy to contribute to a sustainable worldwide energy mix is strengthening the IAEA's statutory role in fostering the peaceful uses of nuclear energy, in particular the need for effective exchanges of information and collaborative research and technology development among Member States on advanced nuclear power technologies (Articles III-A.1 and III-A.3). The major challenges facing the long term development of nuclear energy as a part of the world's energy mix are improvement of the economic competitiveness, meeting increasingly stringent safety requirements, adhering to the criteria of sustainable development, and public acceptability. The concern linked to the long life of many of the radioisotopes generated from fission has led to increased R and D efforts to develop a technology aimed at reducing the amount of long lived radioactive waste through transmutation in fission reactors or accelerator driven hybrids. In recent years, in various countries and at an international level, more and more studies have been carried out on advanced and innovative waste management strategies (i.e. actinide separation and elimination). Within the framework of the Project on Technology Advances in Fast Reactors and Accelerator Driven Systems (http://www.iaea.org/inisnkm/nkm/aws/fnss/index.html), the IAEA initiated a number of activities on utilization of plutonium and transmutation of long lived radioactive waste, accelerator driven systems, thorium fuel options, innovative nuclear reactors and fuel cycles, non-conventional nuclear energy systems, and fusion/fission hybrids. These activities are implemented under the guidance and with the support of the IAEA Nuclear Energy Department's Technical Working Group on Fast Reactors (TWG-FR). This publication compiles the analyses and findings of the Coordinated Research Project (CRP) on Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste (2002

Application of spent fuel treatment technology to plutonium immobilization

International Nuclear Information System (INIS)

McPheeters, C.C.; Ackerman, J.P.; Gay, E.C., Johnson, G.K.

1996-01-01

The purpose of the electrometallurgical treatment technology being developed at Argonne National Laboratory (ANL) is to convert certain spent nuclear fuels into waste forms that are suitable for disposal in a geological repository for nuclear waste. The spent fuels of interest are those that cannot be safely stored for a long time in their current condition, and those that cannot be qualified for repository disposal. This paper explores the possibility of applying this electrometallurgical treatment technology to immobilization of surplus fissile materials, primarily plutonium. Immobilization of surplus fissile materials by electrometallurgical treatment could be done in the same facilities, at the same time. and in the same equipment as the proposed treatment of the present inventory of spent nuclear fuel. The cost and schedule savings of this simultaneous treatment scheme would be significant

Alternative Fuels Data Center: Ethanol Fueling Stations

Science.gov (United States)

... More in this section... Ethanol Basics Benefits & Considerations Stations Locations Infrastructure fueling stations by location or along a route. Infrastructure Development Learn about ethanol fueling infrastructure; codes, standards, and safety; and ethanol equipment options. Maps & Data E85 Fueling Station

Municipal solid waste options : integrating organics management and residual disposal treatment : executive summary

Energy Technology Data Exchange (ETDEWEB)

Cant, M. (comp.) [Totten Sims Hubicki Associates Ltd., Calgary, AB (Canada); Van der Werf, P. [2cg Inc., Edmonton, AB (Canada); Kelleher, M. [Kelleher Environmental, Toronto, ON (Canada); Merriman, D. [MacViro Consultants, Markham, ON (Canada); Fitcher, K. [Gartner Lee Ltd., Toronto, ON (Canada); MacDonald, N. [CH2M Hill Engineering Ltd., Calgary, AB (Canada)

2006-04-15

The Municipal Solid Waste (MSW) Options Report explored different MSW management options for 3 community sizes: 20,000, 80,000 and 200,0000 people. It was released at a time when many communities were developing waste management plans to cost-effectively reduce environmental impacts and conserve landfill capacity. The purpose of this report was to provide a greater understanding on the environmental, social, economic, energy recovery/utilization and greenhouse gas (GHG) considerations of MSW management. The report also demonstrated the interrelationships between the management of organics and residuals. It was based on information from existing waste diversion and organics management options and emerging residual treatment technology options. The following organics management and residual treatment disposal options were evaluated: composting; anaerobic digestion; sanitary landfills; bioreactor landfills; and thermal treatment. Composting was examined with reference to both source separated organics (SSO) and mixed waste composting. SSO refers to the separation of materials suitable for composting solid waste from households, while mixed waste composting refers to the manual or mechanical removal of recyclable material from the waste, including compost. The composting process was reviewed along with available technologies such as non-reactor windrow; aerated static pile; reactor enclosed channel; and, container tunnel. An evaluation of SSO and mixed waste composting was then presented in terms of environmental, social, financial and GHG impacts. refs., tabs., figs.

Current options for the treatment of optic neuritis

Directory of Open Access Journals (Sweden)

Pula JH

2012-07-01

Full Text Available John H Pula,1 Christopher J MacDonald21Division of Neuro-ophthalmology, University of Illinois College of Medicine at Peoria, Peoria; 2University of Illinois College of Medicine at Urbana-Champaign, Champaign, IL, USAAbstract: Optic neuritis can be defined as typical (associated with multiple sclerosis, improving independent of steroid treatment, or atypical (not associated with multiple sclerosis, steroid-dependent improvement. Causes of atypical optic neuritis include connective tissue diseases (eg, lupus, vasculitis, sarcoidosis, or neuromyelitis optica. In this manuscript, updated treatment options for both typical and atypical optic neuritis are reviewed. Conventional treatments, such as corticosteroids, therapeutic plasma exchange, and intravenous immunoglobulin therapy are all discussed with commentary regarding evidence-based outcomes. Less commonly used treatments and novel purported therapies for optic neuritis are also reviewed. Special scenarios in the treatment of optic neuritis – pediatric optic neuritis, acute demyelinating encephalomyelitis, and optic neuritis occurring during pregnancy – are specifically examined.Keywords: optic neuritis, optic neuropathy, treatment, neuroophthalmology

Pilot-scale equipment development for pyrochemical treatment of spent oxide fuel

International Nuclear Information System (INIS)

Herrmann, S. D.

1999-01-01

Fundamental objectives regarding spent nuclear fuel treatment technologies include, first, the effective distribution of spent fuel constituents among product and stable waste forms and, second, the minimization and standardization of waste form types and volumes. Argonne National Laboratory (ANL) has developed and is presently demonstrating the electrometallurgical treatment of sodium-bonded metal fuel from Experimental Breeder Reactor II, resulting in an uranium product and two stable waste forms, i.e. ceramic and metallic. Engineering efforts are underway at ANL to develop pilot-scale equipment which would precondition irradiated oxide fuel via pyrochemical processing and subsequently allow for electrometallurgical treatment of such non-metallic fuels into standard product and waste forms. This paper highlights the integration of proposed spent oxide fuel treatment with existing electrometallurgical processes. System designs and technical bases for development of pilot-scale oxide reduction equipment are also described

Current and emerging treatment options for nasopharyngeal carcinoma

Directory of Open Access Journals (Sweden)

Spratt DE

2012-10-01

Full Text Available Daniel E Spratt, Nancy LeeDepartment of Radiation Oncology, Memorial Sloan-Kettering Cancer Center, New York, NY, USAAbstract: In this article, we focus on the current and emerging treatments in nasopharyngeal cancer (NPC. A detailed evolution of the current standard of care, and new techniques and treatment options will be reviewed. Intergroup 0099 established the role for chemoradiotherapy (chemo-RT in the treatment of nasopharyngeal carcinoma. Multiple randomized Phase III trials have shown the benefit of chemo-RT; however, none of these studies utilized modern radiotherapy (RT techniques of intensity-modulated radiation therapy (IMRT. IMRT has the ability to deliver high doses of radiation to the target structures while sparing adjacent bystander healthy tissues, and has now become the preferred RT treatment modality. Chemotherapy also has had a shifting paradigm of induction and/or adjuvant chemotherapy combined with RT alone, to the investigation with concurrent chemo-RT. New treatment options including targeted monoclonal antibodies and small molecule tyrosine kinase inhibitors are being studied in NPC. These new biologic therapies have promising in vitro activity for NPC, and emerging clinical studies are beginning to define their role. RT continues to expand its capabilities, and since IMRT and particle therapy, specifically intensity-modulated proton therapy (IMPT, has reports of impressive dosimetric efficacy in-silica. Adaptive RT is attempting to reduce toxicity while maintaining treatment efficacy, and the clinical results are still in their youth. Lastly, Epstein–Barr virus (EBV DNA has recently been studied for prediction of tumor response and its use as a biomarker is increasingly promising to aid in early detection as well as supplementing the current staging system. RT with or without chemotherapy remains the standard of care for nasopharyngeal carcinoma. Advances in RT technique, timing of chemotherapy, biologically

Hazardous fuel treatments, suppression cost impacts, and risk mitigation

Science.gov (United States)

Matthew P. Thompson; Michael S. Hand; Julie W. Gilbertson-Day; Nicole M. Vaillant; Darek J. Nalle

2013-01-01

Land management agencies face uncertain tradeoffs regarding investments in preparedness and fuels management versus future suppression costs and impacts to valued resources and assets. Prospective evaluation of fuel treatments allows for comparison of alternative treatment strategies in terms of socioeconomic and ecological impacts, and can facilitate tradeoff analysis...

Introduction to the study of the treatment of spent nuclear fuel

International Nuclear Information System (INIS)

Floh, B.; Araujo, J.A. de; Matsuda, H.T.

1975-01-01

An introduction is made to the study of the treatment of spent nuclear fuels. Main topics discussed are: basic information, volatilization processes, treatment of thorium based fuels (Thorex process), analytical chemistry of spent nuclear fuel and design of industrial facilities

Treatment strategies for transuranic wastes

International Nuclear Information System (INIS)

Schneider, K.J.; Swanson, J.L.; Ross, W.A.; Allen, R.P.; Yasutake, K.M.

1986-01-01

This paper presents an analysis of treatment options or strategies for transuranic wastes expected to be generated at a commercial nuclear fuel reprocessing plant. Six potential options were analyzed, ranging from no treatment to maximum volume reduction and high quality waste forms. Economics for the total management of these (treatment, transportation, disposal) indicate life-cycle savings for extensive treatment are as high as $1.7 billion for 70,000 MTU. Evaluations of the waste processing and waste forms support the selection of a number of the extensive waste treatments. It is concluded that there are significant incentives for extensive treatment of transuranic wastes

Treatment Options for Primary Nocturnal Enuresis by Parents in a ...

African Journals Online (AJOL)

femi oloka

common treatment option was waking up child at intervals during the night to void by 103 (45.2 ... patient/family education, simple behavioral ... nocturnal enuresis were employing in managing ..... Dental and Medical Sciences 2014;13:41 – 4.

Outline of a fuel treatment facility in NUCEF

International Nuclear Information System (INIS)

Sugikawa, Susumu; Umeda, Miki; Kokusen, Junya

1997-03-01

This report presents outline of the nuclear fuel treatment facility for the purpose of preparing solution fuel used in Static Experiment Critical Facility (STACY) and Transient Experiment Critical Facility (TRACY) in Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF), including descriptions of process conditions and dimensions of major process equipments on dissolution system of oxide fuel, chemical adjustment system, purification system, acid recovery system, solution fuel storage system, and descriptions of safety design philosophy such as safety considerations of criticality, solvent fire, explosion of hydrogen and red-oil and so on. (author)

ArcFuels: an ArcMap toolbar for fuel treatment planning and wildfire risk assessment

Science.gov (United States)

Nicole M. Vaillant; Alan A. Ager

2014-01-01

Fire behavior modeling and geospatial analysis can provide tremendous insight to land managers in defining both the benefits and potential impacts of fuel treatments in the context of land management goals and public expectations. ArcFuels is a streamlined fuel management planning and wildfire risk assessment system that creates a trans-scale (stand to large landscape...

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

The Northeast heating fuel market: Assessment and options

Energy Technology Data Exchange (ETDEWEB)

None

2000-07-01

In response to a Presidential request, this study examines how the distillate fuel oil market (and related energy markets) in the Northeast behaved in the winter of 1999-2000, explains the role played by residential, commercial, industrial, and electricity generation sector consumers in distillate fuel oil markets and describes how that role is influenced by the structure of tie energy markets in the Northeast. In addition, this report explores the potential for nonresidential users to move away from distillate fuel oil and how this might impact future prices, and discusses conversion of distillate fuel oil users to other fuels over the next 5 years. Because the President's and Secretary's request focused on converting factories and other large-volume users of mostly high-sulfur distillate fuel oil to other fuels, transportation sector use of low-sulfur distillate fuel oil is not examined here.

Current and emerging treatment options for myopic choroidal neovascularization

Directory of Open Access Journals (Sweden)

El Matri L

2015-04-01

Full Text Available Leila El Matri, Ahmed Chebil, Fedra Kort Department B of Ophthalmology, Hedi Rais Institute of Ophthalmology, Faculty of Medicine of Tunis, University of El Manar, Tunis, Tunisia Abstract: Choroidal neovascularization (CNV is the main cause of visual impairment in highly myopic patients younger than 50 years of age. There are different treatments for myopic CNV (mCNV, with 5- to 10-year outcomes currently. Chorioretinal atrophy is still the most important determinant factor for visual outcome. The purpose of this study is to provide an overview of the current treatments for mCNV, including laser, surgical management, verteporfin photodynamic therapy, and mainly anti-vascular endothelial growth factor therapy. Emerging treatment options are also discussed. Keywords: myopia, choroidal neovascularization, current treatment, emerging treatment

Current and future treatment options in osteoporosis.

LENUS (Irish Health Repository)

Brewer, Linda

2012-02-01

PURPOSE: The incidence of osteoporosis-related fractures will increase substantially over the coming decades as the population ages globally. This has important economic and public health implications, contributing substantially to morbidity and excess mortality in this population. METHODS: When prescribing for older patients the effectiveness profile of drugs needs to be balanced against their tolerability in individual patients. RESULTS: Currently we have good anti-fracture data to support the use of many available anti-resorptive and anabolic drugs including bisphosphonates, strontium ranelate and recombinant human parathyroid hormone. We also have evidence to demonstrate the importance of calcium and vitamin D repletion in these patients. However, in recent years our understanding of normal bone physiology and the mechanisms underlying the development of osteoporosis has significantly advanced and this has led to the development of new therapies. Novel agents, particularly denosumab, but also inhibitors of cathepsin K and anabolic agents that act on Wnt signalling, will increase the therapeutic options for clinicians in the coming years. CONCLUSION: This review discusses the evidence supporting the use of currently available treatment options for osteoporosis and potential future advances in drug therapy. Particular consideration should be given when prescribing for certain older patients who have issues with compliance or tolerance and also in those with co-morbidities or levels of frailty that may restrict the choice of therapy. Understanding the evidence for the benefit and possible harm of osteoporosis treatments is critical to appropriate management of this patient population.

Options Assessment Report: Treatment of Nitrate Salt Waste at Los Alamos National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Robinson, Bruce Alan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Stevens, Patrice Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-12-17

This report documents the methodology used to select a method of treatment for the remediated nitrate salt (RNS) and unremediated nitrate salt (UNS) waste containers at Los Alamos National Laboratory (LANL). The method selected should treat the containerized waste in a manner that renders the waste safe and suitable for transport and final disposal in the Waste Isolation Pilot Plant (WIPP) repository, under specifications listed in the WIPP Waste Acceptance Criteria (DOE/CBFO, 2013). LANL recognizes that the results must be thoroughly vetted with the New Mexico Environment Department (NMED) and that a modification to the LANL Hazardous Waste Facility Permit is a necessary step before implementation of this or any treatment option. Likewise, facility readiness and safety basis approvals must be received from the Department of Energy (DOE). This report presents LANL’s preferred option, and the documentation of the process for reaching the recommended treatment option for RNS and UNS waste, and is presented for consideration by NMED and DOE.

Options assessment report: Treatment of nitrate salt waste at Los Alamos National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Robinson, Bruce Alan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Stevens, Patrice Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-09-16

This report documents the methodology used to select a method of treatment for the remediated nitrate salt (RNS) and unremediated nitrate salt (UNS) waste containers at Los Alamos National Laboratory (LANL). The method selected should treat the containerized waste in a manner that renders the waste safe and suitable for transport and final disposal in the Waste Isolation Pilot Plant (WIPP) repository, under specifications listed in the WIPP Waste Acceptance Criteria (DOE/CBFO, 2013). LANL recognized that the results must be thoroughly vetted with the New Mexico Environment Department (NMED) and the a modification to the LANL Hazardous Waste Facility Permit is a necessary step before implementation of this or any treatment option. Likewise, facility readiness and safety basis approvals must be received from the Department of Energy (DOE). This report presents LANL's preferred option, and the documentation of the process for reaching the recommended treatment option for RNS and UNS waste, and is presented for consideration by NMED and DOE.

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.

Gastroparesis: a review of current and emerging treatment options

Directory of Open Access Journals (Sweden)

Enweluzo C

2013-09-01

Full Text Available Chijioke Enweluzo, Fahad AzizHospital Medicine, Department of Internal Medicine, Wake Forest School of Medicine, Winston Salem, NC, USAAbstract: Gastroparesis is a motility disorder of the stomach causing delay in food emptying from the stomach without any evidence of mechanical obstruction. The majority of cases are idiopathic. Patients need to be diagnosed properly by formal testing, and the evaluation of the severity of the gastroparesis may assist in guiding therapy. Initially, dietary modifications are encouraged, which include frequent and small semisolid-based meals. Promotility medications, like erythromycin, and antiemetics, like prochlorperazine, are offered for symptom relief. In patients who are refractory to pharmacologic treatment, more invasive options, such as intrapyloric botulinum toxin injections, placement of a jejunostomy tube, or implantation of a gastric stimulator, can be considered. Hemin therapy and gastric electric stimulation are emerging treatment options that are still at different stages of research. Regenerative medicine and stem cell-based therapies also hold promise for gastroparesis in the near future.Keywords: Gastroparesis, gastric emptying, gastric electrical stimulation, hemin

Basic principles of forest fuel reduction treatments

Science.gov (United States)

James K. Agee; Carl N. Skinner

2005-01-01

Successful fire exclusion in the 20th century has created severe fire problems across the West. Not every forest is at risk of uncharacteristically severe wildfire, but drier forests are in need of active management to mitigate fire hazard. We summarize a set of simple principles important to address in fuel reduction treatments: reduction of surface fuels, increasing...

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.

SURGICAL TREATMENT OF HEMORRHOIDS: A CRITICAL APPRAISAL OF THE CURRENT OPTIONS

Science.gov (United States)

CERATO, Marlise Mello; CERATO, Nilo Luiz; PASSOS, Patrícia; TREIGUE, Alberto; DAMIN, Daniel C.

2014-01-01

Introduction Surgical treatment of hemorrhoids is still a dilemma. New techniques have been developed leading to a lower rate of postoperative pain; however, they are associated with a greater likelihood of recurrence. Aim To review current indications as well as the results and complications of the main techniques currently used in the surgical treatment of hemorrhoidal disease. Methods A systematic search of the published data on the options for treatment of hemorrhoids up to December 2012 was conducted using Medline/PubMed, Cochrane, and UpToDate. Results Currently available surgical treatment options include procedure for prolapse and hemorrhoids (PPH), transanal hemorrhoidal dearterialization (THD), and conventional hemorrhoidectomy techniques. Excisional techniques showed similar results regarding pain, time to return to normal activities, and complication rates. PPH and THD were associated with less postoperative pain and lower complication rates; however, both had higher postoperative recurrence rates. Conclusion Conventional surgical techniques yield better long-term results. Despite good results in the immediate postoperative period, PPH and THD have not shown consistent long-term favorable results. PMID:24676303

Current options for palliative treatment in patients with pancreatic cancer.

Science.gov (United States)

Ridwelski, K; Meyer, F

2001-01-01

Palliative treatment is often the only remaining option in the management of pancreatic carcinoma, but its efficacy is poor due to low tumor sensitivity and inadequate treatment protocols. There are several options of palliative treatment with antitumor or supportive intention. Classical end points of palliative treatment are survival, tumor response, and quality of life. A decade ago, palliative chemotherapy consisted mainly of 5-fluorouracil as the standard agent in combination with either other agents and/or radiotherapy. Only the new antineoplastic drug gemcitabine, which was introduced simultaneously with the definition of novel end points of chemotherapy such as clinical benefit, allowed to achieve some progress. However, while gemcitabine monotherapy appeared to be superior to 5-fluorouracil and improved important parameters of quality of life, it could not provide a significant improvement of survival. A novel concept, therefore, is to improve this beneficial cytostatic response in pancreatic carcinoma using a gemcitabine-based protocol by combining it with antineoplastic drugs such as taxanes or platin analogs. This strategy may have the potential to improve the outcome in palliative chemotherapy of pancreatic carcinoma patients with advanced tumor growth or metastases. Best supportive care in pancreatic cancer consists of the treatment of symptoms, such as pain, jaundice, duodenal obstruction, weight loss, exocrine pancreatic insufficiency, and tumor-associated depression. Copyright 2001 S. Karger AG, Basel

An Integrated Fuel Depletion Calculator for Fuel Cycle Options Analysis

Energy Technology Data Exchange (ETDEWEB)

Schneider, Erich [Univ. of Texas, Austin, TX (United States); Scopatz, Anthony [Univ. of Wisconsin, Madison, WI (United States)

2016-04-25

Bright-lite is a reactor modeling software developed at the University of Texas Austin to expand upon the work done with the Bright [1] reactor modeling software. Originally, bright-lite was designed to function as a standalone reactor modeling software. However, this aim was refocused t couple bright-lite with the Cyclus fuel cycle simulator [2] to make it a module for the fuel cycle simulator.

Managing AVN following internal fixation: treatment options and clinical results.

Science.gov (United States)

Hoskinson, Simon; Morison, Zachary; Shahrokhi, Shahram; Schemitsch, Emil H

2015-03-01

Avascular necrosis (AVN) after internal fixation of intracapsular hip fractures is a progressive multifactorial disease that ultimately results in local ischemia with ensuing osteocyte necrosis and structural compromise. This disease can cause significant clinical morbidity and affects patients of any age, including young and active patients. Effective treatment of this condition among young adults is challenging due to their high functional demands. The aim of managing AVN is to relieve pain, preserve range of movement and improve function. Treatment methods vary depending on the stage of the disease and can be broadly categorised into two options, hip preserving surgery and hip arthroplasty. Although, hip preserving techniques are attractive in the young adult, they may alter the morphology of the proximal femur and make subsequent arthroplasty more challenging. Conversely, arthroplasty in the young adult may require repeat revision procedures throughout the patient's life. Current evidence suggests that modifications of prevailing treatments, in addition to new technologies, have led to the development of management strategies that may be able to alter the course of femoral head osteonecrosis. This review aims to summarise the options available for treatment of AVN in the young adult and review the clinical results. Copyright © 2014 Elsevier Ltd. All rights reserved.

Grey water characteristics and treatment options for rural areas in Jordan.

Science.gov (United States)

Halalsheh, M; Dalahmeh, S; Sayed, M; Suleiman, W; Shareef, M; Mansour, M; Safi, M

2008-09-01

Low water consumption in rural areas in Jordan had resulted in the production of concentrated grey water. Average COD, BOD and TSS values were 2568mg/l, 1056mg/l and 845mg/l, respectively. The average grey water generation was measured to be 14L/c.d. Three different treatment options were selected based on certain criterions, and discussed in this article. The examined treatment systems are septic tank followed by intermittent sand filter; septic tank followed by wetlands; and UASB-hybrid reactor. Advantages and disadvantages of each system are presented. It was concluded that UASB-hybrid reactor would be the most suitable treatment option in terms of compactness and simplicity in operation. The volume of UASB-hybrid reactor was calculated to be 0.268m(3) with a surface area of 0.138m(2) for each house having 10 inhabitants on average. Produced effluent is expected to meet Jordanian standards set for reclaimed water reuse in irrigating fruit trees.

Mechanical mastication as a fuels treatment in southeastern forests

Science.gov (United States)

Jesse K. Kreye; J. Morgan Varner; Leda N. Kobziar

2016-01-01

Mastication is an increasingly common fuels treatment that redistributes ‘‘ladder’’ fuels to the forest floor to reduce vertical fuel continuity, crown fire potential, and fireline intensity. Despite its widespread adoption, it remains unclear how mastication impacts fuels, fire behavior, or plant communities  across Southeastern forest ecosystems. We evaluated these...

Accounting treatment of currency options

Directory of Open Access Journals (Sweden)

Prošić Danica

2016-01-01

Full Text Available Currency options are often used to mitigate currency risk resulting from corporate activities. Their implementation can be complex, and there could be problems if the essential elements and principles are not fully understood. Although they are not the simplest financial products, currency options are interesting and useful to those who are trying to make a step forward in the area of currency risk management. This paper aims to present the general principles and specifics of accounting records and valuation of currency options used for hedging against risk. It is a complex process which, in addition to numerous conditions, also involves the implementation of accounting rules that deviate from the generally accepted accounting principles.

Current Treatment Options in Challenging Oral Diseases: Burning Mouth Syndrome

OpenAIRE

Bilgen Erdoğan; Murat Yılmaz

2012-01-01

Burning mouth syndrome is a chronic condition characterized by burning pain without any signs of an oral mucosal pathology, that usually affects postmenopausal women. Burning sensation is often accompanied by dysgeusia and xerostomia. The pathogenesis of the disease is unknown and an effective treatment option for most of the patients has not been defined yet. The aim of this review is to present current pharmacological and physicological treatments of burning mouth syndrome.

Current Treatment Options in Challenging Oral Diseases: Burning Mouth Syndrome

Directory of Open Access Journals (Sweden)

Bilgen Erdoğan

2012-12-01

Full Text Available Burning mouth syndrome is a chronic condition characterized by burning pain without any signs of an oral mucosal pathology, that usually affects postmenopausal women. Burning sensation is often accompanied by dysgeusia and xerostomia. The pathogenesis of the disease is unknown and an effective treatment option for most of the patients has not been defined yet. The aim of this review is to present current pharmacological and physicological treatments of burning mouth syndrome.

Treatment strategies for transuranic wastes

International Nuclear Information System (INIS)

Schneider, K.J.; Ross, W.A.; Swanson, J.L.; Allen, R.P.; Yasutake, K.M.

1986-01-01

This paper presents an analysis of treatment options or strategies for transuranic wastes expected to be generated at a commercial nuclear fuel reprocessing plant. Six potential options were analyzed, ranging from no treatment to maximum volume reduction and high quality waste forms. Economics for the total management of these wastes (treatment, transportation, disposal) indicate life-cycle savings for extensive treatment are as high as $1.7 billion for 70,000 MTU. Evaluations of the waste processing and waste forms support the selection of a number of the extensive waste treatments. It is concluded that there are significant incentives for extensive treatment of transuranic wastes

Endometriosis-associated infertility: aspects of pathophysiological mechanisms and treatment options.

Science.gov (United States)

Tanbo, Tom; Fedorcsak, Peter

2017-06-01

Endometriosis is a common condition in women of reproductive age. In addition to pain, endometriosis may also reduce fertility. The causes of infertility in women with endometriosis may range from anatomical distortions due to adhesions and fibrosis to endocrine abnormalities and immunological disturbances. In some cases, the various pathophysiological disturbances seem to interact through mechanisms so far not fully understood. Whether surgery should be offered as a treatment option in endometriosis-associated infertility has become controversial, partly due to its modest or undocumented effect. Medical or hormonal treatment alone has little or no effect and should only be used in conjunction with assisted reproductive technology (ART). Of the various methods of ART, intrauterine insemination, due to its simplicity, can be recommended in women with minimal or mild peritoneal endometriosis, even though insemination may yield a lower success rate than in women without endometriosis. In vitro fertilization (IVF) is an effective treatment option in less-advanced disease stages, and the success rates are similar to the results in other causes of infertility. However, women with more advanced stages of endometriosis have lower success rates with IVF. © 2016 Nordic Federation of Societies of Obstetrics and Gynecology.

Treatment options for permanent teeth with deep caries

OpenAIRE

Marending, Monika; Attin, Thomas; Zehnder, Matthias

2016-01-01

The goal of this narrative review was to summarize and compare treatment options for permanent teeth carious lesions that are radiographically close to the pulp chamber. Thanks to adhesive restorative materials, minimally invasive approaches are possible. In this context, the old question arises as to whether caries must be excavated completely, i.e., down to hard dentin, or whether it could be advantageous to leave some soft dentin, or even merely seal the whole lesion. To answer this questi...

Residue Derived Fuels as an Alternative Fuel for the Hellenic Power Generation Sector and their Potential for Emissions ReductionConstantinos S. Psomopoulos

Directory of Open Access Journals (Sweden)

Constantinos S. Psomopoulos

2014-09-01

Full Text Available The European Union Landfill Directive (1999/31 EC promotes more environmental friendly waste management options, by reducing the amount of wastes and more specific of biodegradable wastes, disposed of in landfills. The EU member states are adopting the mechanical-biological treatment process for municipal solid waste and non-hazardous industrial wastes to comply with the abovementioned Directive's targets on landfill diversion, and produce waste derived fuels such as refuse derived fuel and solid recovered fuel. Waste derived fuels present high calorific values depending on their synthesis and are being used both in dedicated waste-to-energy plants and as fuel substitutes in industrial processes. In this paper the refuse derived fuel and solid recovered fuel production and utilisation options in European Union are presented, and the possibilities in Greece based on the waste production and National Plan for Waste Management of the Ministry of Environment is attempted. The existing and ongoing studies on co-combustion and co-gasification with brown coal support the use of refuse derived fuel and solid recovered fuel as fuel on Hellenic Power Sector, adopting in the existing lignite power plants adequate Air Pollution Control systems. If the co-combustion or co-gasification of these alternative fuels is adopted from the Hellenic Power Sector a reduction on emissions is expected that cannot be neglected.

Failed fuel rod detector

Energy Technology Data Exchange (ETDEWEB)

Uchida, Katsuya; Matsuda, Yasuhiko

1984-05-02

The purpose of the project is to enable failed fuel rod detection simply with no requirement for dismantling the fuel assembly. A gamma-ray detection section is arranged so as to attend on the optional fuel rods in the fuel assembly. The fuel assembly is adapted such that a gamma-ray shielding plate is detachably inserted into optional gaps of the fuel rods or, alternatively, the fuel assembly can detachably be inserted to the gamma-ray shielding plate. In this way, amount of gaseous fission products accumulated in all of the plenum portions in the fuel rods as the object of the measurement can be determined without dismantling the fuel assembly. Accordingly, by comparing the amounts of the gaseous fission products, the failed fuel rod can be detected.

Spent fuel treatment to allow storage in air

International Nuclear Information System (INIS)

Williams, K.L.

1988-01-01

During Fiscal Year 1987 (FY-87), research began at the Idaho National Engineering Laboratory (INEL) to develop a treatment material and process to coat fuel rods in commercial spent fuel assemblies to allow the assemblies to be stored in hot (up to 380 0 C) air without oxidation of the fuel. This research was conducted under a research and development fund provided by the U.S. Department of Energy (DOE) and independently administered by EG and G Idaho, Inc., DOE's prime contractor at the INEL. The objectives of the research were to identify and evaluate possible treatment processes and materials, identify areas of uncertainty, and to recommend the most likely candidate to allow spent fuel dry storage in hot air. The results of the research are described: results were promising and several good candidates were identified, but further research is needed to examine the candidates to the point where comparison is possible

Effluent treatment options for nuclear thermal propulsion system ground tests

International Nuclear Information System (INIS)

Shipers, L.R.; Brockmann, J.E.

1992-01-01

A variety of approaches for handling effluent from nuclear thermal propulsion system ground tests in an environmentally acceptable manner are discussed. The functional requirements of effluent treatment are defined and concept options are presented within the framework of these requirements. System concepts differ primarily in the choice of fission-product retention and waste handling concepts. The concept options considered range from closed cycle (venting the exhaust to a closed volume or recirculating the hydrogen in a closed loop) to open cycle (real time processing and venting of the effluent). This paper reviews the strengths and weaknesses of different methods to handle effluent from nuclear thermal propulsion system ground tests

Bronchiolitis obliterans after allo-SCT: clinical criteria and treatment options

DEFF Research Database (Denmark)

Uhlving, H H; Buchvald, F; Heilmann, C J

2012-01-01

Bronchiolitis obliterans (BO) following allogeneic haematopoietic SCT (HSCT) is a serious complication affecting 1.7-26% of the patients, with a reported mortality rate of 21-100%. It is considered a manifestation of chronic graft-versus-host disease, but our knowledge of aetiology and pathogenes...... treatment options for BO and presents the treatment results with HDPM in a paediatric national HSCT-cohort.Bone Marrow Transplantation advance online publication, 29 August 2011; doi:10.1038/bmt.2011.161....

[Female sexual dysfunction: Drug treatment options].

Science.gov (United States)

Alcántara Montero, A; Sánchez Carnerero, C I

2016-01-01

Many women will likely experience a sexual problem in their lifetime. Female sexual dysfunction is a broad term used to describe 3 categories of disorders of a multifactorial nature. Effective, but limited pharmacotherapeutic options exist to address female sexual dysfunction. The FDA recently approved the first agent for treatment of hypoactive sexual desire disorder in pre-menopausal women. Off-label use of hormonal therapies, particularly oestrogen and testosterone, are the most widely employed for female sexual dysfunction, particularly in post-menopausal women. Other drugs currently under investigation include phosphodiesterase inhibitors and agents that modulate dopamine or melanocortin receptors. Copyright © 2016 Sociedad Española de Médicos de Atención Primaria (SEMERGEN). Publicado por Elsevier España, S.L.U. All rights reserved.

Economic potential of fuel recycling options: A lifecycle cost analysis of future nuclear system transition in China

International Nuclear Information System (INIS)

Gao, Ruxing; Choi, Sungyeol; Il Ko, Won; Kim, Sungki

2017-01-01

In today's profit-driven market, how best to pursue advanced nuclear fuel cycle technologies while maintaining the cost competitiveness of nuclear electricity is of crucial importance to determine the implementation of spent fuel reprocessing and recycling in China. In this study, a comprehensive techno-economic analysis is undertaken to evaluate the economic feasibility of ongoing national projects and the technical compatibility with China's future fuel cycle transition. We investigated the dynamic impacts of technical and economic uncertainties in the lifecycle of a nuclear system. The electricity generation costs associated with four potential fuel cycle transition scenarios were simulated by probabilistic and deterministic approaches and then compared in detail. The results showed that the total cost of a once-through system is lowest compared those of other advanced systems involving reprocessing and recycling. However, thanks to the consequential uncertainties caused by the further progress toward technology maturity, the economic potential of fuel recycling options was proven through a probabilistic uncertainty analysis. Furthermore, it is recommended that a compulsory executive of closed fuel cycle policy would pose some investment risk in the near term, though the execution of a series of R&D initiatives with a flexible roadmap would be valuable in the long run. - Highlights: • Real-time economic performance of the four scenarios of China's nuclear fuel cycle system transition until 2100. • Systematic assessments of techno-economic feasibility for ongoing national reprocessing projects. • Investigation the cost impact on nuclear electricity generation caused by uncertainties through probabilistic analysis. • Recommendation for sustainable implementation of fuel cycle R&D initiative ingrate with flexible roadmap in the long run.

Quantifying the potential impacts of fuel treatments on wildfire suppression costs

Science.gov (United States)

Matthew P. Thompson; Nicole M. Vaillant; Jessica R. Haas; Krista M. Gebert; Keith D. Stockmann

2013-01-01

Modeling the impacts and effects of hazardous fuel reduction treatments is a pressing issue within the wildfire management community. Prospective evaluation of fuel treatment effectiveness allows for comparison of alternative treatment strategies in terms of socioeconomic and ecological impacts and facilitates analysis of tradeoffs across land-management objectives....

Dynamic Simulations of Advanced Fuel Cycles

International Nuclear Information System (INIS)

Piet, Steven J.; Dixon, Brent W.; Jacobson, Jacob J.; Matthern, Gretchen E.; Shropshire, David E.

2011-01-01

Years of performing dynamic simulations of advanced nuclear fuel cycle options provide insights into how they could work and how one might transition from the current once-through fuel cycle. This paper summarizes those insights from the context of the 2005 objectives and goals of the U.S. Advanced Fuel Cycle Initiative (AFCI). Our intent is not to compare options, assess options versus those objectives and goals, nor recommend changes to those objectives and goals. Rather, we organize what we have learned from dynamic simulations in the context of the AFCI objectives for waste management, proliferation resistance, uranium utilization, and economics. Thus, we do not merely describe 'lessons learned' from dynamic simulations but attempt to answer the 'so what' question by using this context. The analyses have been performed using the Verifiable Fuel Cycle Simulation of Nuclear Fuel Cycle Dynamics (VISION). We observe that the 2005 objectives and goals do not address many of the inherently dynamic discriminators among advanced fuel cycle options and transitions thereof.

Assessment of options for the treatment of Sizewell PWR liquid effluent

International Nuclear Information System (INIS)

Hornby, J.; Allam, J.; Knibbs, R.H.

1992-01-01

This report describes the origins of PWR liquid waste streams, their composition and rates of arising. Data has been collected from operational PWRs and estimates obtained for Sizewell B PWR liquid waste streams. Current liquid waste treatment practices are reviewed and assessments made of established and novel treatment techniques which could be applicable to Sizewell B. A short list of treatment options is given and recommendations are made relating to established treatment technologies suitable for Sizewell B and also to development work on more novel treatments which could lead to a reduction in waste disposal volumes. (author)

Preliminary analysis of treatment strategies for transuranic wastes from reprocessing plants

International Nuclear Information System (INIS)

Ross, W.A.; Schneider, K.J.; Swanson, J.L.; Yasutake, K.M.; Allen, R.P.

1985-07-01

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

Preliminary analysis of treatment strategies for transuranic wastes from reprocessing plants

Energy Technology Data Exchange (ETDEWEB)

Ross, W.A.; Schneider, K.J.; Swanson, J.L.; Yasutake, K.M.; Allen, R.P.

1985-07-01

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

State-of-the-art and main options to improve fuel-energy complex of ferrous metallurgy

Energy Technology Data Exchange (ETDEWEB)

Rozenblit, G I; Pashkov, V D; Romanov, G M

1981-01-01

In 1980, the State Institute for the Design and Planning Metallury (Gripromez), elaborated ''The main options of Fuel and energy resources conservation (FERG) in ferrous metallurgy of the USSR program of works for the period 1981-1985 and up to 1990''. The Gipromez technical committee recommended: 1) elaborating feasibility studies and reports, developing branch schemes and starting complexes to separate out FERC measures; 2) inclusion of the FERC measures at the starting complexes as the first stages of main projects construction; 3) that the Ministy of Ferrous Metallurgy of the USSR, general designers and enterprises reconsider the starting complexes of the projects constructed during the present five-year period and incorporate in them the urgent FERC actions on heat-utilizing facilities. Changing the steel smelting process structure through more extensive use of the converter process and installation of continuous blank casting allows achievement of considerable fuel conservation, some 4 m trf per year as compared with its consumption in the scheme of open-hearth furnace - blooming mill (slabbing mill). During the 11th five-year-plan period introduction of metallurgy plant. An installation with discharge of the converter gas without its afterburning and successive utilization as a fuel in the converter shop of the Novolipetsk is planned.

Ragweed-induced allergic rhinoconjunctivitis: current and emerging treatment options

Directory of Open Access Journals (Sweden)

Ihler F

2015-02-01

Full Text Available Friedrich Ihler, Martin CanisDepartment of Otorhinolaryngology, University Medical Center Göttingen, Göttingen, GermanyAbstract: Ragweed (Ambrosia spp. is an annually flowering plant whose pollen bears high allergenic potential. Ragweed-induced allergic rhinoconjunctivitis has long been seen as a major immunologic condition in Northern America with high exposure and sensitization rates in the general population. The invasive occurrence of ragweed (A. artemisiifolia poses an increasing challenge to public health in Europe and Asia as well. Possible explanations for its worldwide spread are climate change and urbanization, as well as pollen transport over long distances by globalized traffic and winds. Due to the increasing disease burden worldwide, and to the lack of a current and comprehensive overview, this study aims to review the current and emerging treatment options for ragweed-induced rhinoconjunctivitis. Sound clinical evidence is present for the symptomatic treatment of ragweed-induced allergic rhinoconjunctivitis with oral third-generation H1-antihistamines and leukotriene antagonists. The topical application of glucocorticoids has also been efficient in randomized controlled clinical trials. Combined approaches employing multiple agents are common. The mainstay of causal treatment to date, especially in Northern America, is subcutaneous immunotherapy with the focus on the major allergen, Amb a 1. Beyond this, growing evidence from several geographical regions documents the benefit of sublingual immunotherapy. Future treatment options promise more specific symptomatic treatment and fewer side effects during causal therapy. Novel antihistamines for symptomatic treatment are aimed at the histamine H3-receptor. New adjuvants with toll-like receptor 4 activity or the application of the monoclonal anti-immunoglobulin E antibody, omalizumab, are supposed to enhance conventional immunotherapy. An approach targeting toll-like receptor 9 by

Vaccines against drugs of abuse: a viable treatment option?

Science.gov (United States)

Kantak, Kathleen M

2003-01-01

Drug addiction is a chronically relapsing brain disorder. There is an urgent need for new treatment options for this disease because the relapse rate among drug abusers seeking treatment is quite high. During the past decade, many groups have explored the feasibility of using vaccines directed against drugs of abuse as a means of eliminating illicit drug use as well as drug overdose and neurotoxicity. Vaccines work by inducing drug-specific antibodies in the bloodstream that bind to the drug of abuse and prevent its entry into the brain. The majority of work in this area has been conducted with vaccines and antibodies directed against cocaine and nicotine. On the basis of preclinical work, vaccines for cocaine and nicotine are now in clinical trials because they can offer long-term protection with minimal treatment compliance. In addition, vaccines and antibodies for phencyclidine, methamphetamine and heroin abuse are currently under development. An underlying theme in this research is the need for high concentrations of circulating drug-specific antibodies to reduce drug-seeking and drug-taking behaviour when the drug is repeatedly available, especially in high doses. Although vaccines against drugs of abuse may become a viable treatment option, there are several drawbacks that need to be considered. These include: a lack of protection against a structurally dissimilar drug that produces the same effects as the drug of choice;a lack of an effect on drug craving that predisposes an addict to relapse; and tremendous individual variability in antibody formation. Forced or coerced vaccination is not likely to work from a scientific perspective, and also carries serious legal and ethical concerns. All things considered, vaccination against a drug of abuse is likely to work best with individuals who are highly motivated to quit using drugs altogether and as part of a comprehensive treatment programme. As such, the medical treatment of drug abuse will not be radically

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

New treatment options for fibromyalgia: critical appraisal of duloxetine

Directory of Open Access Journals (Sweden)

Nurcan Üçeyler

2008-06-01

Full Text Available Nurcan Üçeyler1, Martin Offenbächer2, Frank Petzke3, Winfried Häuser4, Claudia Sommer11Department of Neurology, University of Würzburg, Germany; 2GRP – Generation Research Program, Human Science Center, University of Munich, Germany; 3Department of Anesthesiology, University of Cologne, Germany; 4Center of Pain Therapy, Klinikum Saarbrücken gGmbH, Winterberg 1, Saarbrücken, GermanyAbstract: Fibromyalgia syndrome (FMS is a chronic condition characterized by widespread pain, tender points, fatigue, and sleep disturbance. FMS leads to high disability levels, poor quality of life, and extensive use of medical care. Effective pharmacological treatment options are rare, and treatment effects are often of limited duration. Duloxetine is a new selective serotonin and norepinephrine reuptake inhibitor that is licensed for the treatment of pain in diabetic neuropathy. So far two randomized, placebo-controlled trials have investigated the short-term safety and efficacy of duloxetine 60 mg/day and 120 mg/day in patients suffering from FMS over a period of 12 weeks. Both dosages were superior to placebo in pain relief, and improvement in quality of life and depressive symptoms. The analgesic effect was largely independent of the antidepressant action of duloxetine. The higher dose of 120 mg/day further reduced the tender point count and elevated the tender point pain thresholds. Only mild to moderate adverse effects were reported. Duloxetine 60 mg/day and 120 mg/day has proven to be beneficial in the treatment of FMS symptoms. As true for other antidepressants further studies are needed to assess the long-term efficacy and safety of duloxetine as an additional pharmacological treatment option in FMS.Keywords: fibromyalgia syndrome, duloxetine, antidepressant, review, SNRI

Estimation of wildfire size and risk changes due to fuels treatments

Science.gov (United States)

Cochrane, M.A.; Moran, C.J.; Wimberly, M.C.; Baer, A.D.; Finney, M.A.; Beckendorf, K.L.; Eidenshink, J.; Zhu, Z.

2012-01-01

Human land use practices, altered climates, and shifting forest and fire management policies have increased the frequency of large wildfires several-fold. Mitigation of potential fire behaviour and fire severity have increasingly been attempted through pre-fire alteration of wildland fuels using mechanical treatments and prescribed fires. Despite annual treatment of more than a million hectares of land, quantitative assessments of the effectiveness of existing fuel treatments at reducing the size of actual wildfires or how they might alter the risk of burning across landscapes are currently lacking. Here, we present a method for estimating spatial probabilities of burning as a function of extant fuels treatments for any wildland fire-affected landscape. We examined the landscape effects of more than 72 000 ha of wildland fuel treatments involved in 14 large wildfires that burned 314 000 ha of forests in nine US states between 2002 and 2010. Fuels treatments altered the probability of fire occurrence both positively and negatively across landscapes, effectively redistributing fire risk by changing surface fire spread rates and reducing the likelihood of crowning behaviour. Trade offs are created between formation of large areas with low probabilities of increased burning and smaller, well-defined regions with reduced fire risk.

Pelvic radiation disease: Updates on treatment options

Science.gov (United States)

Frazzoni, Leonardo; La Marca, Marina; Guido, Alessandra; Morganti, Alessio Giuseppe; Bazzoli, Franco; Fuccio, Lorenzo

2015-01-01

Pelvic cancers are among the most frequently diagnosed neoplasms and radiotherapy represents one of the main treatment options. The irradiation field usually encompasses healthy intestinal tissue, especially of distal large bowel, thus inducing gastrointestinal (GI) radiation-induced toxicity. Indeed, up to half of radiation-treated patients say that their quality of life is affected by GI symptoms (e.g., rectal bleeding, diarrhoea). The constellation of GI symptoms - from transient to long-term, from mild to very severe - experienced by patients who underwent radiation treatment for a pelvic tumor have been comprised in the definition of pelvic radiation disease (PRD). A correct and evidence-based therapeutic approach of patients experiencing GI radiation-induced toxicity is mandatory. Therapeutic non-surgical strategies for PRD can be summarized in two broad categories, i.e., medical and endoscopic. Of note, most of the studies have investigated the management of radiation-induced rectal bleeding. Patients with clinically significant bleeding (i.e., causing chronic anemia) should firstly be considered for medical management (i.e., sucralfate enemas, metronidazole and hyperbaric oxygen); in case of failure, endoscopic treatment should be implemented. This latter should be considered the first choice in case of acute, transfusion requiring, bleeding. More well-performed, high quality studies should be performed, especially the role of medical treatments should be better investigated as well as the comparative studies between endoscopic and hyperbaric oxygen treatments. PMID:26677440

The Northeast heating fuel market: Assessment and options; TOPICAL

International Nuclear Information System (INIS)

None

2000-01-01

In response to a Presidential request, this study examines how the distillate fuel oil market (and related energy markets) in the Northeast behaved in the winter of 1999-2000, explains the role played by residential, commercial, industrial, and electricity generation sector consumers in distillate fuel oil markets and describes how that role is influenced by the structure of tie energy markets in the Northeast. In addition, this report explores the potential for nonresidential users to move away from distillate fuel oil and how this might impact future prices, and discusses conversion of distillate fuel oil users to other fuels over the next 5 years. Because the President's and Secretary's request focused on converting factories and other large-volume users of mostly high-sulfur distillate fuel oil to other fuels, transportation sector use of low-sulfur distillate fuel oil is not examined here

Electrometallurgical treatment of TMI-2 fuel debris

International Nuclear Information System (INIS)

Karell, E.J.; Gourishankar, K.V.; Johnson, G.K.

1997-01-01

Argonne National Laboratory (ANL) has developed an electrometallurgical treatment process suitable for conditioning DOE oxide spent fuel for long-term storage or disposal. The process consists of an initial oxide reduction step that converts the actinide oxides to a metallic form, followed by an electrochemical separation of uranium from the other fuel constituents. The final product of the process is a uniform set of stable waste forms suitable for long-term storage or disposal. The suitability of the process for treating core debris from the Three Mile Island-2 (TMI-2) reactor is being evaluated. This paper reviews the results of preliminary experimental work performed using simulated TMI-2 fuel debris

Methodology for the economic evaluation of the strategies for spent fuel

International Nuclear Information System (INIS)

Zouain, D.M.

1981-08-01

A methodology for the economic evaluation of the spent fuel and a comparative analysis of the various available strategies for its treatment, is developed. For the realization of the proposed studies a computer program METACIR was developed, which incorporates the necessary computational methodology, and it was performed a analysis of the present situation and future tendencies of the stages that constitute a PWR nuclear fuel cycle. According to the obtained results, the eternal disposal of the spent fuel is less advantageous than the reprocessing and recycle options; between the last options, the uranium recycle in PWR's is the most attractive until nearly the end of the 1990's, when the uranium and plutonium recycle in LMFBR's becomes the most convenient. The economic value of the spent fuel varies with the reactor discharge date, being considered a onus during the 1980's, and a bonus only in the next decade. (Author) [pt

Novel treatment options for portal hypertension

Science.gov (United States)

Laleman, Wim

2017-01-01

Abstract Portal hypertension is most frequently associated with cirrhosis and is a major driver for associated complications, such as variceal bleeding, ascites or hepatic encephalopathy. As such, clinically significant portal hypertension forms the prelude to decompensation and impacts significantly on the prognosis of patients with liver cirrhosis. At present, non-selective β-blockers, vasopressin analogues and somatostatin analogues are the mainstay of treatment but these strategies are far from satisfactory and only target splanchnic hyperemia. In contrast, safe and reliable strategies to reduce the increased intrahepatic resistance in cirrhotic patients still represent a pending issue. In recent years, several preclinical and clinical trials have focused on this latter component and other therapeutic avenues. In this review, we highlight novel data in this context and address potentially interesting therapeutic options for the future. PMID:28533907

Alternative energy options

International Nuclear Information System (INIS)

Bennett, K.F.

1983-01-01

It is accepted that coal will continue to play the major role in the supply of energy to the country for the remainder of the century. In this paper, however, emphasis has been directed to those options which could supplement coal in an economic and technically sound manner. The general conclusion is that certain forms of solar energy hold the most promise and it is in this direction that research, development and implementation programmes should be directed. Tidal energy, fusion energy, geothermal energy, hydrogen energy and fuel cells are also discussed as alternative energy options

On the nuclear fuel and fossil fuel reserves

International Nuclear Information System (INIS)

Fettweis, G.

1978-01-01

A short discussion of the nuclear fuel and fossil fuel reserves and the connected problem of prices evolution is presented. The need to regard fuel production under an economic aspect is emphasized. Data about known and assessed fuel reserves, world-wide and with special consideration of Austria, are reviewed. It is concluded that in view of the fuel reserves situation an energy policy which allows for a maximum of options seems adequate. (G.G.)

Fuels planning: science synthesis and integration; forest structure and fire hazard fact sheet 05: fuel treatment principles for complex landscapes

Science.gov (United States)

Rocky Mountain Research Station USDA Forest Service

2004-01-01

Appropriate types of thinning and surface fuel treatments are clearly useful in reducing surface and crown fire hazards under a wide range of fuels and topographic situations. This paper provides well-established scientific principles and simulation tools that can be used to adjust fuel treatments to attain specific risk levels.

Treatment Options for Severe Obesity in the Pediatric Population: Current Limitations and Future Opportunities.

Science.gov (United States)

Ryder, Justin R; Fox, Claudia K; Kelly, Aaron S

2018-06-01

Severe obesity is the only obesity classification increasing in prevalence among children and adolescents. Treatment options that produce meaningful and sustained weight loss and comorbidity resolution are urgently needed. The purpose of this review is to provide a brief overview of the current treatment options for pediatric severe obesity and offer suggestions regarding future opportunities for accelerating the development and evaluation of innovative treatment strategies. At present, there are three treatment options for youth with severe obesity: lifestyle modification therapy, pharmacotherapy, and bariatric surgery. Lifestyle modification therapy can be useful for improving many chronic disease risk factors and comorbid conditions but often fails to achieve clinically meaningful and sustainable weight loss. Pharmacotherapy holds promise as an effective adjunctive treatment but remains in the primordial stages of development in the pediatric population. Bariatric surgery provides robust weight loss and risk factor/comorbidity improvements but is accompanied by higher risks and lower uptake compared to lifestyle modification therapy and pharmacotherapy. New areas worth pursuing include combination pharmacotherapy, device therapy, identification of predictors of response aimed at precision treatment, and interventions in the postbariatric surgical setting to improve long-term outcomes. Treating pediatric severe obesity effectively and safely is extremely challenging. Some progress has been made, but substantially more effort and innovation are needed in the future to combat this serious and ongoing medical and public health issue. © 2018 The Obesity Society.

Study on partitioning and transmutation as a possible option for spent fuel management within a nuclear phase-out scenario

Energy Technology Data Exchange (ETDEWEB)

Fazion, C.; Rineiski, A.; Salvatores, M.; Schwenk-Ferrero, A.; Romanello, V.; Vezzoni, B.; Gabrielli, F. [Karlsruhe Institute of Technology - KIT, Hermann-von-Helmholtz Platz 1, 76344 Eggenstein-Leopoldshafen (Germany)

2013-07-01

Most Partitioning and Transmutation (PT) studies implicitly presuppose the continuous use of nuclear energy. In this case the development of new facilities or the modification of the fuel cycle can be justified in the long-term as an important feature in order to improve sustainability by minimizing radioactive waste and reducing the burden at waste disposal. In the case of a country with nuclear energy phase-out policy, the PT option might have also an important role for what concerns the final disposal strategies of the spent fuel. In this work three selected scenarios are analyzed in order to assess the impact of PT implementation in a nuclear energy phase out option. The scenarios are: -) Scenario 1: Identification of Research/Development activities needs for a technological development of PT while postponing the decision of PT implementation; -) Scenario 2: Isolated application of PT in a phase-out context; and -) Scenario 3: Implementation of PT in a European context. In order to facilitate the discrimination among the 3 scenarios, a number of figures of indicators have been evaluated for each scenario. The selected indicators are: the mass of High Level Waste (HLW), Uranium inventory, thermal output of HLW, Radiotoxicity, Fuel cycle secondary waste associated to the PT operation, and Facility capacity/number requirements. The reduction, due to PT implementation, of high level wastes masses and their associated volumes can be significant. For what concerns the thermal output and radiotoxicity a significant impact can be also expected. However, when assessing these two indicators the contribution coming from already vitrified waste should also not be neglected. Moreover, an increase of secondary waste inventory is also expected. On the contrary, the increase of fission product inventories due to the operation of the transmutation system has a relatively limited impact on the fuel cycle.

Modeling fuel treatment leverage: Encounter rates, risk reduction, and suppression cost impacts

Science.gov (United States)

Matthew P. Thompson; Karin L. Riley; Dan Loeffler; Jessica R. Haas

2017-01-01

The primary theme of this study is the cost-effectiveness of fuel treatments at multiple scales of investment. We focused on the nexus of fuel management and suppression response planning, designing spatial fuel treatment strategies to incorporate landscape features that provide control opportunities that are relevant to fire operations. Our analysis explored the...

Liquid Radioactive Wastes Treatment: A Review

Directory of Open Access Journals (Sweden)

Yung-Tse Hung

2011-05-01

Full Text Available Radioactive wastes are generated during nuclear fuel cycle operation, production and application of radioisotope in medicine, industry, research, and agriculture, and as a byproduct of natural resource exploitation, which includes mining and processing of ores, combustion of fossil fuels, or production of natural gas and oil. To ensure the protection of human health and the environment from the hazard of these wastes, a planned integrated radioactive waste management practice should be applied. This work is directed to review recent published researches that are concerned with testing and application of different treatment options as a part of the integrated radioactive waste management practice. The main aim from this work is to highlight the scientific community interest in important problems that affect different treatment processes. This review is divided into the following sections: advances in conventional treatment of aqueous radioactive wastes, advances in conventional treatment of organic liquid wastes, and emerged technological options.

Hydrothermal treatment of grape marc for solid fuel applications

International Nuclear Information System (INIS)

Mäkelä, Mikko; Kwong, Chi Wai; Broström, Markus; Yoshikawa, Kunio

2017-01-01

Highlights: • The effects of treatment temperature and liquid pH on char and liquid properties. • Liquid pH had a statistically significant effect only on liquid carbon yield. • Higher treatment temperature increased char volatiles that can enhance ignitability. • Char showed promising fuel properties if elevated ash phosphorus can be tolerated. - Abstract: The treatment and disposal of grape marc, a residue from grape processing, represents a significant economic and environmental challenge for the winemaking industry. Hydrothermal treatment of grape marc could be an efficient way for producing solid fuels on-site at the wineries. In this work the effects of treatment temperature and liquid pH on grape marc char and liquid properties were determined based on laboratory experiments and the combustion characteristics of char were assessed through thermogravimetric analysis and fuel ash classification. The results showed that hydrothermal treatment increased the energy and carbon contents and decreased the ash content of grape marc. The effect of liquid pH was statistically significant (p < 0.05) only for the determined carbon yield of liquid samples. The energy yield from grape marc was maximized at lower treatment temperatures, which also decreased the content of less thermally stable compounds in the attained char. Higher treatment temperatures decreased grape marc solid, carbon and energy yields and led to an increase in thermally labile compounds compared to lower temperatures likely due to the condensation of liquid compounds or volatiles trapped in the pores of char particles. The alkali metal contents of char ash were reduced coupled with an increase in respective phosphorus. Overall the results support the use of hydrothermally treated grape marc in solid fuel applications, if elevated levels of ash phosphorus can be tolerated.

Recent developments in spent fuel management in Norway - 59260

International Nuclear Information System (INIS)

Bennett, Peter J.; Oberlaender, Barbara C.

2012-01-01

Spent Nuclear Fuel (SNF) in Norway has arisen from irradiation of fuel in the NORA, Jeep I and Jeep II reactors at Kjeller, and in the Heavy Boiling Water Reactor (HBWR) in Halden. In total there is some 16 tonnes of SNF, with 12 tons of aluminium-clad fuel, of which 10 tonnes is metallic uranium fuel and the remainder oxide (UO 2 ). The portion of this fuel that is similar to commercial fuel (UO 2 clad in Zircaloy) may be suitable for direct disposal on the Swedish model or in other repository designs. However, metallic uranium and/or fuels clad in aluminium are chemically reactive and there would be risks associated with direct disposal. Two committees were established by the Government of Norway in January 2009 to make recommendations for the interim storage and final disposal of spent fuel in Norway. The Technical Committee on Storage and Disposal of Metallic Uranium Fuel and Al-clad Fuels was formed with the mandate to recommend treatment (i.e. conditioning) options for metallic uranium fuel and aluminium-clad fuel to render them stable for long term storage and disposal. This committee, whose members were drawn from the nuclear industry, reported in January 2010, and recommended commercial reprocessing as the best option for these fuels. The Phase-2 committee, which in part based its work on the work of previous committees and on the report of the Technical Committee, had the mandate to find the most suitable technical solution and localisation for intermediate storage for spent nuclear fuel and long-lived waste. The membership of this committee was chosen to represent a broad cross section of stakeholders. The committee evaluated different solutions and their associated costs, and recommended one of the options. The committee's report published in early 2011. This paper summarises the conclusions of the two committees, and thereby illustrates the steps taken by one country to formulate a strategy for the long-term management of its SNF. (authors)

Ustekinumab as an Alternative Treatment Option for Chronic Pityriasis Rubra Pilaris

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Mudit Chowdhary

2015-03-01

Full Text Available Pityriasis rubra pilaris (PRP is an exceptionally rare, chronic inflammatory dermatosis of unknown etiology. Patients classically present with small, follicular keratosis and salmon-colored plaques that begin at the head and neck and slowly progress to widespread erythroderma including the palms and soles. It is difficult to distinguish PRP from other inflammatory dermatoses; however, features that help aid in the diagnosis include ‘islands' of spared skin, orangish hue and typical findings on biopsy. There are no specific guidelines on therapy and treatment options include corticosteroids, vitamin D analogs, retinoids, methotrexate, cyclosporine, azathioprine and tumor necrosis factor alpha antagonists. Unfortunately options are limited for patients when these drugs do not work. We report a case of chronic PRP, refractory to conventional treatment, successfully treated with ustekinumab monotherapy. The patient was treated with 90 mg subcutaneous ustekinumab injections and began to show improvement within only 8 weeks. Long-term control of the disease has been attained without any significant side effects. We report this case to show that ustekinumab can be used as an alternative treatment method for patients with chronic, unremitting PRP. Treatment response is remarkably rapid and the infrequent dosing leads to patient compliance and a significantly improved quality of life.

Options of electric generation and sustainability

International Nuclear Information System (INIS)

Martin del Campo M, C.

2004-01-01

In this paper a study on the sustainability of the main electricity generation options is presented. The study is based on a matrix of sustainability indicators developed in Switzerland. A revision of some sustainability studies performed in countries with certain energy diversity and with experience in nuclear power plants operation, is done. Studies, in general, are performed for the power plant life cycle, taking into account economic aspects, fuel prices impact on electricity generation costs, fuel reserves indicators and material consumption. Air emission, waste production and human health impact data are also presented. All the results lead to confirm that nuclear energy has a high degree of sustainability vis a vis other options based on fossil fuels and renewable. Finally some comments are presented in order to highlight the importance that nuclear energy might have in the sustainable development of Mexico. (Author)

Tarapur's nuclear fuel uncertainty and India's policy options

International Nuclear Information System (INIS)

Subramanian, R.R.

1978-01-01

The Indo-US agreement over the turnkey Project of the Tarapur Atomic Power Station (TAPS) signed in 1963 is being reintepreted by the American Government from 'non-proliferation' aspect, particularly after the Pokharan peaceful nuclear explosion in 1974. With the ratification of the new Non-Proliferation Act by the American Congress, the supply of enriched uranium fuel for the TAPS has become uncertain, as India is not prepared to accept comprehensive safeguards on all domestic nuclear facilities. If the contractual obligations for fuel supply and transport of spent fuel back to U.S. are not fulfilled, it is pointed out, that India will have to start reprocessing spent fuel and recycle plutonium. (K.M.)

Generic waste management concepts for six LWR fuel cycles

International Nuclear Information System (INIS)

DePue, J.D.

1979-04-01

This report supplements the treatment of waste management issues provided in the Generic Environmental Statement on the use of recycle plutonium in mixed oxide fuel in light water cooled reactors (GESMO, NUREG-0002). Three recycle and three no-recycle options are described in this document. Management of the radioactive wastes that would result from implementation of either type of fuel cycle alternative is discussed. For five of the six options, wastes would be placed in deep geologic salt repositories for which thermal criteria are considered. Radiation doses to the workers at the repositories and to the general population are discussed. The report also covers the waste management schedule, the land and salt commitments, and the economic costs for the management of wastes generated

Treatment options for polycystic ovary syndrome

Directory of Open Access Journals (Sweden)

Ahmed Badawy

2011-02-01

Full Text Available Ahmed Badawy1 Abubaker Elnashar21Department of Obstetrics and Gynecology, Mansoura University, Mansoura, Egypt; 2Department of Obstetrics and Gynecology, Benha University, Benha, EgyptAbstract: Polycystic ovary syndrome (PCOS is the most common endocrine disorder in women. The clinical manifestation of PCOS varies from a mild menstrual disorder to severe disturbance of reproductive and metabolic functions. Management of women with PCOS depends on the symptoms. These could be ovulatory dysfunction-related infertility, menstrual disorders, or androgen-related symptoms. Weight loss improves the endocrine profile and increases the likelihood of ovulation and pregnancy. Normalization of menstrual cycles and ovulation could occur with modest weight loss as little as 5% of the initial weight. The treatment of obesity includes modifications in lifestyle (diet and exercise and medical and surgical treatment. In PCOS, anovulation relates to low follicle-stimulating hormone concentrations and the arrest of antral follicle growth in the final stages of maturation. This can be treated with medications such as clomiphene citrate, tamoxifen, aromatase inhibitors, metformin, glucocorticoids, or gonadotropins or surgically by laparoscopic ovarian drilling. In vitro fertilization will remain the last option to achieve pregnancy when others fail. Chronic anovulation over a long period of time is also associated with an increased risk of endometrial hyperplasia and carcinoma, which should be seriously investigated and treated. There are androgenic symptoms that will vary from patient to patient, such as hirsutism, acne, and/or alopecia. These are troublesome presentations to the patients and require adequate treatment. Alternative medicine has been emerging as one of the commonly practiced medicines for different health problems, including PCOS. This review underlines the contribution to the treatment of different symptoms.Keywords: treatment, polycystic ovary

Development of integrated waste management options for irradiated graphite

Energy Technology Data Exchange (ETDEWEB)

Wareing, Alan; Abrahamsen-Mills, Liam; Fowler, Linda; Jarvis, Richard; Banford, Anthony William [National Nuclear Laboratory, Warrington (United Kingdom); Grave, Michael [Doosan Babcock, Gateshead (United Kingdom); Metcalfe, Martin [National Nuclear Laboratory, Gloucestershire (United Kingdom); Norris, Simon [Radioactive Waste Management Limited, Oxon (United Kingdom)

2017-08-15

The European Treatment and Disposal of Irradiated Graphite and other Carbonaceous Waste project sought to develop best practices in the retrieval, treatment, and disposal of irradiated graphite including other irradiated carbonaceous waste such as structural material made of graphite, nongraphitized carbon bricks, and fuel coatings. Emphasis was given on legacy irradiated graphite, as this represents a significant inventory in respective national waste management programs. This paper provides an overview of the characteristics of graphite irradiated during its use, primarily as a moderator material, within nuclear reactors. It describes the potential techniques applicable to the retrieval, treatment, recycling/reuse, and disposal of these graphite wastes. Considering the lifecycle of nuclear graphite, from manufacture to final disposal, a number of waste management options have been developed. These options consider the techniques and technologies required to address each stage of the lifecycle, such as segregation, treatment, recycle, and ultimate disposal in a radioactive waste repository, providing a toolbox to aid operators and regulators to determine the most appropriate management strategy. It is noted that national waste management programs currently have, or are in the process of developing, respective approaches to irradiated graphite management. The output of the Treatment and Disposal of Irradiated Graphite and other Carbonaceous Waste project is intended to aid these considerations, rather than dictate them.

Fuels planning: science synthesis and integration; forest structure and fire hazard fact sheet 04: role of silviculture in fuel treatments

Science.gov (United States)

Rocky Mountain Research Station USDA Forest Service

2004-01-01

The principal goals of fuel treatments are to reduce fireline intensities, reduce the potential for crown fires, improve opportunities for successful fire suppression, and improve forest resilience to forest fires. This fact sheet discusses thinning, and surface fuel treatments, as well as challenges associated with those treatments.

Spent fuels conditioning and irradiated nuclear fuel elements examination: the STAR facility and its abilities

Energy Technology Data Exchange (ETDEWEB)

Boussard, F.; Huillery, R. [CEA Centre d`Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d`Etudes des Combustibles; Averseng, J.L.; Serpantie, J.P. [Novatome Industries, 92 - Le Plessis-Robinson (France)

1994-12-31

This paper is a presentation of the STAR facility, a high activity laboratory located in Cadarache Nuclear Research Center (France). The purpose of the STAR facility and of the associated processes, is the treatment, cleaning and conditioning of spent fuels from Gas Cooled Reactors (GCR) and in particular of about 2300 spent GCR fuel cartridges irradiated more than 20 years ago in Electricite de France (EDF) or CEA Uranium Graphite GCR. The processes are: to separate the nuclear fuel from the clad remains, to chemically stabilize the nuclear material and to condition it in sealed canisters. An additional objective of STAR consists in non-destructive or destructive examinations and tests on PWR rods or FBR pins in the frame of fuel development programs. The paper describes the STAR facility conceptual design (safety design rules, hot cells..) and the different options corresponding to the GCR reconditioning process and to further research and development works on various fuel types. (J.S.). 3 figs.

Spent fuels conditioning and irradiated nuclear fuel elements examination: the STAR facility and its abilities

International Nuclear Information System (INIS)

Boussard, F.; Huillery, R.

1994-01-01

This paper is a presentation of the STAR facility, a high activity laboratory located in Cadarache Nuclear Research Center (France). The purpose of the STAR facility and of the associated processes, is the treatment, cleaning and conditioning of spent fuels from Gas Cooled Reactors (GCR) and in particular of about 2300 spent GCR fuel cartridges irradiated more than 20 years ago in Electricite de France (EDF) or CEA Uranium Graphite GCR. The processes are: to separate the nuclear fuel from the clad remains, to chemically stabilize the nuclear material and to condition it in sealed canisters. An additional objective of STAR consists in non-destructive or destructive examinations and tests on PWR rods or FBR pins in the frame of fuel development programs. The paper describes the STAR facility conceptual design (safety design rules, hot cells..) and the different options corresponding to the GCR reconditioning process and to further research and development works on various fuel types. (J.S.). 3 figs

Advanced fuel cycles options for LWRs and IMF benchmark definition

International Nuclear Information System (INIS)

Breza, J.; Darilek, P.; Necas, V.

2008-01-01

In the paper, different advanced nuclear fuel cycles including thorium-based fuel and inert-matrix fuel are examined under light water reactor conditions, especially VVER-440, and compared. Two investigated thorium based fuels include one solely plutonium-thorium based fuel and the second one plutonium-thorium based fuel with initial uranium content. Both of them are used to carry and burn or transmute plutonium created in the classical UOX cycle. The inert-matrix fuel consist of plutonium and minor actinides separated from spent UOX fuel fixed in Yttria-stabilised zirconia matrix. The article shows analysed fuel cycles and their short description. The conclusion is concentrated on the rate of Pu transmutation and Pu with minor actinides cumulating in the spent advanced thorium fuel and its comparison to UOX open fuel cycle. Definition of IMF benchmark based on presented scenario is given. (authors)

Challenges and approaches in planning fuel treatments across fire-excluded forested landscapes

Science.gov (United States)

B.M. Collins; S.L. Stephens; J.J. Moghaddas; J. Battles

2010-01-01

Placing fuel reduction treatments across entire landscapes such that impacts associated with high-intensity fire are lessened is a difficult goal to achieve, largely because of the immense area needing treatment. As such, fire scientists and managers have conceptually developed and are refining methodologies for strategic placement of fuel treatments that...

Quantifying the potential impacts of fuel treatments on wildfire suppression costs volume

Science.gov (United States)

Matthew P. Thompson; Nicole M. Vaillant; Jessica R. Haas; Krista M. Gebert; Keith D. Stockmann

2013-01-01

Modeling the impacts and effects of hazardous fuel reduction treatments is a pressing issue within the wildfire management community. Prospective evaluation of fuel treatments allows for comparison of alternative treatment strategies in terms of socioeconomic and ecological impacts and facilitates analysis of tradeoffs across land management objectives (Stockmann et al...

Fuels planning: science synthesis and integration; environmental consequences fact sheet 04: wildlife responses to fuels treatments: key considerations

Science.gov (United States)

David Pilliod

2004-01-01

Managers face a difficult task in predicting the effects of fuels treatments on wildlife populations, mostly because information on how animals respond to fuels treatments is scarce or does not exist. This paper discusses key considerations-aspects of an animal's ecology and available information-that, despite the scarcity of information, may make predictions of...

Approved and Off-Label Uses of Obesity Medications, and Potential New Pharmacologic Treatment Options

Directory of Open Access Journals (Sweden)

Fernando Cordido

2010-01-01

Full Text Available Available anti-obesity pharmacotherapy options remain very limited and development of more effective drugs has become a priority. The potential strategies to achieve weight loss are to reduce energy intake by stimulating anorexigenic signals or by blocking orexigenic signals, and to increase energy expenditure. This review will focus on approved obesity medications, as well as potential new pharmacologic treatment options.

Spent fuel storage practices and perspectives for WWER fuel in Eastern Europe

International Nuclear Information System (INIS)

Takats, F.

1999-01-01

In this lecture the general issues and options in spent fuel management and storage are reviewed. Quantities of spent fuel world-wide and spent fuel amounts in storage as well as spent fuel capacities are presented. Selected examples of typical spent fuel storage facilities are discussed. The storage technologies applied for WWER fuel is presented. Description of other relevant storage technologies is included

The Effects of Accounting Treatment and Financial Crisis on the Stock Option Plans of Italian Companies

Directory of Open Access Journals (Sweden)

Francesco Avallone

2014-03-01

Full Text Available Many studies state that favourable accounting treatment has been one of the main reasons behind employee stock options. In addition, stock options have recently been the target of growing criticism with a possible influence on incentive effectiveness and outrage costs. In such a perspective, the main purpose of the paper is to explore the impact of IFRS 2 and of the recent financial crisis on stock option compensation. Empirical evidence suggests that: (i IFRS 2 did not have a significant effect on stock option granting, (ii the issue of stock options is less likely to occur during the financial crisis.

Pyrochemical head-end treatment for spent nuclear fuels

International Nuclear Information System (INIS)

Bowersox, D.F.

1977-01-01

A program based upon thermodynamic values and scouting experiments at Argonne National Laboratory is proposed for development of a pyrochemical head-end treatment of spent nuclear fuels to replace the proposed chopping and leaching operation in the Purex process. The treatment consists of separation of the cladding from the oxide fuel by dissolution into liquid zinc; oxide reduction of uranium and plutonium and dissolution into a zinc--magnesium alloy; separation of alkali, alkaline earth, and rare earth fission products into a molten salt; and, finally, separation and recovery of the plutonium and uranium in the alloy. Uranium and plutonium would be separated from the fuel cladding and selected fission products in a form readily dissolvable in nitric acid. The head-end process could be developed eventually into an optimum method for recovering uranium, plutonium, and selected fission products and for minimizing wastes as compact, stable solids. Developmental expenses are not known clearly, but the potential advantages of the process are impressive

Safety of treatment options for spondyloarthritis: a narrative review.

Science.gov (United States)

D'Angelo, Salvatore; Carriero, Antonio; Gilio, Michele; Ursini, Francesco; Leccese, Pietro; Palazzi, Carlo

2018-05-01

Spondyloarthritis (SpA) are chronic inflammatory diseases with overlapping pathogenic mechanisms and clinical features. Treatment armamentarium against SpA includes non-steroidal anti-inflammatory drugs, glucocorticoids, conventional disease-modifying antirheumatic drugs (DMARDs, including sulfasalazine, methotrexate, leflunomide, cyclosporine), targeted synthetic DMARDs (apremilast) and biological DMARDs (TNF inhibitors, anti-IL 12/23 and anti-IL-17 agents). Areas covered: A narrative review of published literature on safety profile of available SpA treatment options was performed. Readers will be provided with a comprehensive overview on frequent and rare adverse events associated with each drug listed in current SpA treatment recommendations. Expert opinion: The overall safety profile of such molecules is good and serious adverse events are rare but need to be promptly recognized and treated. However, the monitoring of adverse events is a major challenge for clinicians because it is not adequately addressed by current treatment recommendations. A tailored treatment is crucial and rheumatologists must accurately select patients in order to identify those more susceptible to develop adverse events.

Treatment options for diabetic foot osteomyelitis.

Science.gov (United States)

Senneville, Eric; Robineau, Olivier

2017-06-01

Diabetic foot osteomyelitis therapeutical options are based on antibiotic therapy and surgical resection of the infected bone(s). Surgical and medical approaches of patients suffering from a diabetic foot osteomyelitis do not oppose but are complementary and need to be discussed as a tailored manner. Areas covered: The aim of the present article is to discuss data issued from the most recent guidelines of the Infectious Diseases Society of America and the International Working Group on the Diabetic Foot on the management of the diabetic foot infection and from a search in the current literature using the terms diabetic foot osteomyelitis and treatment/therapy/therapeutical in both PubMed and Medline, restricted to the last five years. Expert opinion: Surgical removal of the entire infected bone(s) has been considered in the past as the standard treatment but medical approach of these patients has now proven efficacy in selected situations. The current emergence of bacteria, especially among Gram negative rods, resistant to almost all the available antibiotics gradually augments the complexity of the management of these patients and is likely to decrease the place of the medical approach and to worsen the outcome of these infections in the next future.

Nuclear fuel cycle system analysis

International Nuclear Information System (INIS)

Ko, W. I.; Kwon, E. H.; Kim, S. G.; Park, B. H.; Song, K. C.; Song, D. Y.; Lee, H. H.; Chang, H. L.; Jeong, C. J.

2012-04-01

The nuclear fuel cycle system analysis method has been designed and established for an integrated nuclear fuel cycle system assessment by analyzing various methodologies. The economics, PR(Proliferation Resistance) and environmental impact evaluation of the fuel cycle system were performed using improved DB, and finally the best fuel cycle option which is applicable in Korea was derived. In addition, this research is helped to increase the national credibility and transparency for PR with developing and fulfilling PR enhancement program. The detailed contents of the work are as follows: 1)Establish and improve the DB for nuclear fuel cycle system analysis 2)Development of the analysis model for nuclear fuel cycle 3)Preliminary study for nuclear fuel cycle analysis 4)Development of overall evaluation model of nuclear fuel cycle system 5)Overall evaluation of nuclear fuel cycle system 6)Evaluate the PR for nuclear fuel cycle system and derive the enhancement method 7)Derive and fulfill of nuclear transparency enhancement method The optimum fuel cycle option which is economical and applicable to domestic situation was derived in this research. It would be a basis for establishment of the long-term strategy for nuclear fuel cycle. This work contributes for guaranteeing the technical, economical validity of the optimal fuel cycle option. Deriving and fulfillment of the method for enhancing nuclear transparency will also contribute to renewing the ROK-U.S Atomic Energy Agreement in 2014

Economic Analysis of Several Nuclear Fuel Cycles

International Nuclear Information System (INIS)

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

2012-01-01

Economics is one of the essential criteria to be considered for the future deployment of the nuclear power. With regard to the competitive power market, the cost of electricity from nuclear power plants is somewhat highly competitive with those from the other electricity generations, averaging lower in cost than fossil fuels, wind, or solar. However, a closer look at the nuclear power production brings an insight that the cost varies within a wide range, highly depending on a nuclear fuel cycle option. The option of nuclear fuel cycle is a key determinant in the economics, and therefrom, a comprehensive comparison among the proposed fuel cycle options necessitates an economic analysis for thirteen promising options based on the material flow analysis obtained by an equilibrium model as specified in the first article (Modeling and System Analysis of Different Fuel Cycle Options for Nuclear Power Sustainability (I): Uranium Consumption and Waste Generation). The objective of the article is to provide a systematic cost comparison among these nuclear fuel cycles. The generation cost (GC) generally consists of a capital cost, an operation and maintenance cost (O and M cost), a fuel cycle cost (FCC), and a decontaminating and decommissioning (D and D) cost. FCC includes a frontend cost and a back-end cost, as well as costs associated with fuel recycling in the cases of semi-closed and closed cycle options. As a part of GC, the economic analysis on FCC mainly focuses on the cost differences among fuel cycle options considered and therefore efficiently avoids the large uncertainties of the Generation-IV reactor capital costs and the advanced reprocessing costs. However, the GC provides a more comprehensive result covering all the associated costs, and therefrom, both GC and FCC have been analyzed, respectively. As a widely applied tool, the levelized cost (mills/KWh) proves to be a fundamental calculation principle in the energy and power industry, which is particularly

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

Facial Pores: Definition, Causes, and Treatment Options.

Science.gov (United States)

Lee, Sang Ju; Seok, Joon; Jeong, Se Yeong; Park, Kui Young; Li, Kapsok; Seo, Seong Jun

2016-03-01

Enlarged skin pores refer to conditions that present with visible topographic changes of skin surfaces. Although not a medical concern, enlarged pores are a cosmetic concern for a large number of individuals. Moreover, clear definition and possible causes of enlarged pores have not been elucidated. To review the possible causes and treatment options for skin pores. This article is based on a review of the medical literature and the authors' clinical experience in investigating and treating skin pores. There are 3 major clinical causes of enlarged facial pores, namely high sebum excretion, decreased elasticity around pores, and increased hair follicle volume. In addition, chronic recurrent acne, sex hormones, and skin care regimen can affect pore size. Given the different possible causes for enlarged pores, therapeutic modalities must be individualized for each patient. Potential factors that contribute to enlarged skin pores include excessive sebum, decreased elasticity around pores, and increased hair follicle volume. Because various factors cause enlarged facial pores, it might be useful to identify the underlying causes to be able to select the appropriate treatment.

Answering Key Fuel Cycle Questions

International Nuclear Information System (INIS)

Piet, S.J.; Dixon, B.W.; Bennett, R.G.; Smith, J.D.; Hill, R.N.

2004-01-01

Given the range of fuel cycle goals and criteria, and the wide range of fuel cycle options, how can the set of options eventually be narrowed in a transparent and justifiable fashion? It is impractical to develop all options. We suggest an approach that starts by considering a range of goals for the Advanced Fuel Cycle Initiative (AFCI) and then posits seven questions, such as whether Cs and Sr isotopes should be separated from spent fuel and, if so, what should be done with them. For each question, we consider which of the goals may be relevant to eventually providing answers. The AFCI program has both ''outcome'' and ''process'' goals because it must address both waste already accumulating as well as completing the fuel cycle in connection with advanced nuclear power plant concepts. The outcome objectives are waste geologic repository capacity and cost, energy security and sustainability, proliferation resistance, fuel cycle economics, and safety. The process objectives are rea diness to proceed and adaptability and robustness in the face of uncertainties

Biocidal treatment and preservation of liquid fuels

Energy Technology Data Exchange (ETDEWEB)

Siegert, W.

1995-05-01

Strict microbiological limit values are the result of damage caused by microorganisms in fuels. With MAR 71, a biocide based on methylenebisoxazolidine, a product is available which has been tested and approved by leading car manufacturers, the mineral oil industry, and NATO. Depending on the degree of microbiological contamination, different decontamination concepts are presented, and recommendations for the treatment of fuels which are contaminated when purchased are given. In order to avoid recontamination, planning principles or the new design of tanks are necessary. The possibility of convenient, economical and regular drainage is a key factor.

Final Environmental Impact Statement for the Treatment and Management of Sodium-Bonded Spent Nuclear Fuel

International Nuclear Information System (INIS)

2000-01-01

DOE is responsible for the safe and efficient management of its sodium-bonded spent nuclear fuel. This fuel contains metallic sodium, a highly reactive material; metallic uranium, which is also reactive; and in some cases, highly enriched uranium. The presence of reactive materials could complicate the process of qualifying and licensing DOE's sodium-bonded spent nuclear fuel inventory for disposal in a geologic repository. Currently, more than 98 percent of this inventory is located at the Idaho National Engineering and Environmental Laboratory (INEEL), near Idaho Falls, Idaho. In addition, in a 1995 agreement with the State of Idaho, DOE committed to remove all spent nuclear fuel from Idaho by 2035. This EIS evaluates the potential environmental impacts associated with the treatment and management of sodium-bonded spent nuclear fuel in one or more facilities located at Argonne National Laboratory-West (ANL-W) at INEEL and either the F-Canyon or Building 105-L at the Savannah River Site (SRS) near Aiken, South Carolina. DOE has identified and assessed six proposed action alternatives in this EIS. These are: (1) electrometallurgical treatment of all fuel at ANL-W, (2) direct disposal of blanket fuel in high-integrity cans with the sodium removed at ANL-W, (3) plutonium-uranium extraction (PUREX) processing of blanket fuel at SRS, (4) melt and dilute processing of blanket fuel at ANL-W, (5) melt and dilute processing of blanket fuel at SRS, and (6) melt and dilute processing of all fuel at ANL-W. In addition, Alternatives 2 through 5 include the electrometallurgical treatment of driver fuel at ANL-W. Under the No Action Alternative, the EIS evaluates both the continued storage of sodium-bonded spent nuclear fuel until the development of a new treatment technology or direct disposal without treatment. Under all of the alternatives, the affected environment is primarily within 80 kilometers (50 miles) of spent nuclear fuel treatment facilities. Analyses indicate

Liquid fuel from biomass

International Nuclear Information System (INIS)

Breinholt, T.; Gylling, M.; Parsby, M.; Meyer Henius, U.; Sander Nielsen, B.

1992-09-01

Various options for Danish production of liquid motor fuels from biomass have been studied in the context of the impact of EEC new common agricultural policy on prices and production quantities of crops, processes and production economy, restraints concerning present and future markets in Denmark, environmental aspects, in particular substitution of fossil fuels in the overall production and end-use, revenue loss required to assure competition with fossil fuels and national competence in business, industry and research. The options studied are rapeseed oil and derivates, ethanol, methanol and other thermo-chemical conversion products. The study shows that the combination of fuel production and co-generation of heat and electricity carried out with energy efficiency and utilization of surplus electricity is important for the economics under Danish conditions. Considering all aspects, ethanol production seems most favorable but in the long term, pyrolyses with catalytic cracking could be an interesting option. The cheapest source of biomass in Denmark is straw, where a considerable amount of the surplus could be used. Whole crop harvested wheat on land otherwise set aside to be fallow could also be an important source for ethanol production. Most of the options contribute favorably to reductions of fossil fuel consumption, but variations are large and the substitution factor is to a great extent dependent on the individual case. (AB) (32 refs.)

Patients' Values Related to Treatment Options for Teeth with Apical Periodontitis.

Science.gov (United States)

Azarpazhooh, Amir; Dao, Thuan; Ungar, Wendy J; Da Costa, Jose; Figueiredo, Rafael; Krahn, Murray; Friedman, Shimon

2016-03-01

This study aimed to explore patients' values when selecting treatment for a tooth with apical periodontitis (AP), namely retention via root canal treatment (RCT) and extraction without replacement or replacement with implant-supported crowns or fixed or removable partial prostheses. Through 2 surveys of patients (800 university patients and 200 community patients, response rate = 43%) and dentists (498 Ontario endodontists, periodontists, prosthodontists, oral and maxillofacial surgeons, response rate = 40% and 1983 Ontario general dentists, response rate = 15%), the importance of values that might be considered important to patients when selecting treatment options for a tooth with AP were recorded. Chi-square and Kendall's tau tests were used to respectively compare the importance rating frequency by each surveyed group and its correlation to their demographic variables (P ≤ .05). Patients considered communication and trust (94%), tooth retention (90%), esthetic outcome (84% regardless of location), cost (83%), longevity (83%), and preoperative pain (81%) as the most important decision values. Dentists overrated the importance of patients' previous experience with the treatment options (94% vs. 72%), dental insurance (90% vs. 70%), and intraoperative pain (79% vs. 60%) while underestimating the importance of maintenance cost (60% vs. 79%). Dentists should respect patients' views about esthetic outcome, longevity, and cost associated with treatment options for a tooth with AP. In particular, this survey highlights the value of communication and trust between patient and dentist and preservation of the natural tooth through RCT over implant-supported crown replacement when planning treatment for a tooth with AP. Copyright © 2016 American Association of Endodontists. Published by Elsevier Inc. All rights reserved.

The conceptual flowsheet of effluent treatment during preparing spherical fuel elements of HTR

Energy Technology Data Exchange (ETDEWEB)

Ying, Quan, E-mail: quanying@tsinghua.edu.cn; Xiao-tong, Chen; Bing, Liu; Gen-na, Fu; Yang, Wang; You-lin, Shao; Zhen-ming, Lu; Ya-ping, Tang; Chun-he, Tang

2014-05-01

High temperature gas-cooled reactor (HTR) is one of the advanced nuclear reactors owing to its inherent safety and broad applications. For HTR, one of the key components is the ceramic fuel element. During the preparation of spherical fuel elements, the radioactive effluent treatment is necessary. Referring to the current treatment technologies and methods, the conceptual flowsheet of low-level radioactive effluent treatment during preparing spherical fuel elements was established. According to the above treatment process, the uranium concentration was decreased from 200 mg/l to the level of discharged standard.

Options for Healthcare Waste Management and Treatment in China

Institute of Scientific and Technical Information of China (English)

无

2006-01-01

Healthcare waste management and treatment is one of the national priority tasks of China's Tenth Five-Year Plan.Numerous installations disposing medical waste have already operated the project or under construction to the operation in 2006. This paper focuses on the assessment of existing and fu~re options to handle medical waste (MW). Internationally available and so far in China applied technologies and management practice are analysed, including the problems how to materials. Non-hazardous MW can be managed and treated in analogue to municipal solid waste (MSW). In most of the European countries decentralised hospital incinerators have been, because of high operation costs and pollution problems,widely banned and replaced by pre-treatment technologies at the source and centralised incineration plants for hazardous MW.Information for adapting and further developing MW management solutions and treatment technologies in China and applying the most appropriate MWM practice is provided.

Neutronics Study on LEU Nuclear Thermal Rocket Fuel Options

Energy Technology Data Exchange (ETDEWEB)

Venneri, Paolo; Kim, Yong Hee [KAIST, Daejeon (Korea, Republic of); Howe, Steven [CSNR, Idaho (United States)

2014-10-15

This has resulted in a non-trivial simplification of the tasks needed to develop such an engine and the quick initial development of the concept. There are, however, a series of key core-design choices that are currently under scrutiny in the field that have to be resolved in order for the LEU-NTR to be fully developed. The most important of these is the choice of fuel: carbide composite or tungsten cermet. This study presents a first comparison of the two fuel types specifically in the neutronic application to the LEU-NTR, keeping in mind the unique neutronic environment and the system requirements of the system. The scope of the study itself is limited to a neutronics study of the two fuels and only a cursory overview of the material properties of the fuels themselves... The results of this study have led to two major conclusions. First of all is that the carbide composite fuel is, from a neutronics standpoint, a much better fuel. It has a low absorption cross-section, is inherently a strong moderator, is able to achieve a higher reactivity using smaller amounts of fissile material, and can potentially enable a smaller reactor. Second is that despite its neutronic difficulties (high absorption, inferior moderating abilities, and lower k-infinity values) the tungsten cermet fuel is still able to perform satisfactorily in an LEU-NTR, largely due to its ability to have an extremely high fuel loading.