WorldWideScience

Sample records for long-term fuel supply

  1. Long term assurance of supply of back end of fuel cycle facilities and services

    International Nuclear Information System (INIS)

    1978-01-01

    The paper deals with the long-term assurance of supply of the back end of fuel cycle facilities and services. 11 fundamental questions are posed and commented on by representatives of 7 countries. Non-proliferation aspects are not considered as they will be discussed elsewhere

  2. Do we soon run out of uranium? Long-term concepts of nuclear fuel supply

    International Nuclear Information System (INIS)

    Prasser, Horst-Michael

    2008-01-01

    The extension of the worldwide light water reactor fleet will cause the demand for uranium to grow. The static reach of identified resources might soon fall below the life time of new nuclear power plants which are usually designed for 60 years of operation, if the exploration of new uranium deposits will stop resulting in exploitable resources. The article discusses, if, as frequently claimed, the energy consumption in the uranium mines renders impossible to secure the nuclear fuel supply in the long term. (orig.)

  3. Nuclear fuel cycle requirements and supply considerations, through the long-term

    International Nuclear Information System (INIS)

    1978-02-01

    The OECD Nuclear Energy Agency and the International Atomic Energy Agency have for many years published a joint report entitled ''Uranium Resources, Production and Demand'', and a revised edition of this work, dated December 1977, is now available. This report, on the other hand, is the result of a separate study of the supply and demand outlook for all fuel cycle services, as well as for uranium, through the long-term. The work was undertaken by the Nuclear Energy Agency's Working Party on Uranium Demand, whose members are listed in Appendix III. The intent here has been to contribute to the orderly development of nuclear power, by: 1. identifying potential problems in the supply of uranium and fuel cycle services, and possible areas for international co-operation in the resolution of such problems; 2. examining several long-range scenarios to determine the comparative needs of advanced reactors for uranium and for supporting services, thereby establishing the basis for the further development of uranium resources and specific reactor systems; and 3. assisting those having responsibilities in planning, forecasting, and programme management. This report is the work of a group of technical experts and does not necessarily reflect official policy or endorsement of the report's projections and conclusions by the Member Governments of the Nuclear Energy Agency

  4. 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

  5. Part I. Alternative fuel-cycle and deployment strategies: their influence on long-term energy supply and resource usage

    International Nuclear Information System (INIS)

    Till, C.E.; Chang, Y.I.; Rudolph, R.R.

    1980-01-01

    This report examines the implications of alternative fast breeder fuel cycles and deployment strategies on long-term energy supply and uranium resource utilization. An international-aggregate treatment for nuclear energy demand and resource base assumptions was adopted where specific assumptions were necessary for system analyses, but the primary emphasis was placed on understanding the general relationships between energy demand, uranium resource and breeder deployment option. The fast breeder deployment options studied include the reference Pu/U cycle as well as alternative cycles with varying degrees of thorium utilization

  6. Long term wet spent nuclear fuel storage

    International Nuclear Information System (INIS)

    1987-04-01

    The meeting showed that there is continuing confidence in the use of wet storage for spent nuclear fuel and that long-term wet storage of fuel clad in zirconium alloys can be readily achieved. The importance of maintaining good water chemistry has been identified. The long-term wet storage behaviour of sensitized stainless steel clad fuel involves, as yet, some uncertainties. However, great reliance will be placed on long-term wet storage of spent fuel into the future. The following topics were treated to some extent: Oxidation of the external surface of fuel clad, rod consolidation, radiation protection, optimum methods of treating spent fuel storage water, physical radiation effects, and the behaviour of spent fuel assemblies of long-term wet storage conditions. A number of papers on national experience are included

  7. Non-proliferation aspects of long term assurance of supply

    International Nuclear Information System (INIS)

    1978-01-01

    The meetings in this section deal with the non-proliferation aspects of long-term assurance of supply of the nuclear fuel cycle. A list of 12 fundamental questions concerning the observation and application of the non-proliferation regulations is followed by the comments made by representatives of 10 countries

  8. Long-term uranium supply-demand analyses

    International Nuclear Information System (INIS)

    1986-12-01

    It is the intention of this study to investigate the long-term uranium supply demand situation using a number of supply and demand related assumptions. For supply, these assumptions as used in the Resources and Production Projection (RAPP) model include country economic development status, and consequent lead times for exploration and development, uranium development status, country infrastructure, and uranium resources including the Reasonably Assured (RAR), Estimated Additional, Categories I and II, (EAR-I and II) and Speculative Resource categories. The demand assumptions were based on the ''pure'' reactor strategies developed by the NEA Working Party on Nuclear Fuel Cycle Requirements for the 1986 OECD (NEA)/IAEA reports ''Nuclear Energy and its Fuel Cycle: Prospects to 2025''. In addition for this study, a mixed strategy case was computed using the averages of the Plutonium (Pu) burning LWR high, and the improved LWR low cases. It is understandable that such a long-term analysis cannot present hard facts, but it can show which variables may in fact influence the long-term supply-demand situation. It is hoped that results of this study will provide valuable information for planners in the uranium supply and demand fields. Periodical re-analyses with updated data bases will be needed from time to time

  9. Long-term factors in oil supply

    Energy Technology Data Exchange (ETDEWEB)

    Banks, F E

    1984-01-01

    The Stanford Energy Supply Forum prediction that world oil demand in 1990 will press on supply and send prices into an irreversible climb assumes that the Organization of Economic Cooperation and Development (OECD) countries will control unemployment, that Third World population growth will require more energy, and that several oil exporters will be reducing their output. The author points out disappointing exploration results, OPEC's continued strength, downward projections of reserves by geological surveys, and other economic factors to show that oil supplies are likely to last less than 40 years, with remaining reserves concentrated in fewer producing countries. This will make it harder for non-OPEC countries to influence prices, in contrast to more positive forecasts from the oil industry.

  10. Long term assurance of supply of heavy water

    International Nuclear Information System (INIS)

    1978-01-01

    The answer of Switzerland and Great Britain to a number of questions concerning the long-term assurance of the supply of heavy water are presented. The original problems are seen in the wider context of raw materials supply and its assurance in general. Non-proliferation aspects are touched

  11. Long term assurance of supply of raw materials

    International Nuclear Information System (INIS)

    1978-01-01

    The working group discussed the long-term assurance of uranium supply. A number of key questions is presented along with the answers given by representatives of 10 countries and by EC commission. Emphasis is laid on market stability and on the difficulties in adopting to sudden changes in the supply and demand situation

  12. A cross cultural comparison of long-term supply relationships

    NARCIS (Netherlands)

    Jong, Gjalt de; Nooteboom, Bart

    2003-01-01

    This paper challenges the received view that long-term supply relationships are a typically Japanese feature, embedded and developed in a typically Japanese society characterized by high levels of trust and cooperation, and for that reason cannot be established in the typically a-cooperative,

  13. Long-term equilibrium effects of constraints in energy supply

    International Nuclear Information System (INIS)

    Brookes, L.G.

    1984-01-01

    The subject is covered in sections, entitled: introduction; the economic role of energy; the economics of energy price; a first attempt to model long term effects (energy consumption and economic activity); what is a price hike (energy supply and demand functions before and after price hike); modelling energy price hikes; implications and lessons for nuclear energy; the present reality. (U.K.)

  14. Long term contracts in portfolios of core LDC gas supply

    International Nuclear Information System (INIS)

    John, F.E.

    1992-01-01

    This paper recommends that local distribution companies (LDCs) should use a portfolio approach for their gas supply strategy. The author recommends that LDCs not rely on spot supplies to meet the peak needs of the core residential and commercial markets. He recommends that a secure supply through long-term contracts are better sources than spot or even intermediate term suppliers. The paper provides a brief outline format of the advantages to the use of a portfolio approach which include the rapid restructuring of the market, general changes in the market, and general market performance. By maintaining a portfolio, a list of available natural gas suppliers is always available. This portfolio also acts to compare pricing between short, medium, and long-term pricing for the LDCs

  15. Designing indicators of long-term energy supply security

    International Nuclear Information System (INIS)

    Jansen, J.C.; Van Arkel, W.G.; Boots, M.G.

    2004-01-01

    To our knowledge, so far amazingly little research work has been undertaken to construct meaningful indicators of long-run energy supply security for a particular nation or region. Currently, in addressing energy supply security, policy makers tend to emphasise short-term supply disruptions. In contrast, this pre-study accords with the broader Sustainability Outlook in considering the long-term perspective. This report starts with taking stock, in a concise way, of the official EU energy outlook and issues related to the opportunities to administer changes in the energy mix at the level of major energy use categories. Then a brief survey of relevant literature is made on long-term strategies to ensure survival of systems - be it biological, social, etc. - in an environment largely characterised by high uncertainty and a lot of unchartered territory. We found the work of Andrew Stirling very inspiring in this context. Based on his work and considering the limitations of the present research activity, we retained the Shannon index as the best 'simple' indicator of diversity. In the core of the report, the Shannon index is elaborated into four indicators of long-term energy supply security. Stepwise, additional aspects of long-term energy supply security are introduced. These aspects are: Diversification of energy sources in energy supply; Diversification of imports with respect to imported energy sources; Long-term political stability in regions of origin; The resource base in regions of origin, including the home region/country itself. After small adjustments to allow for data availability, these indicators were applied to the reference year 2030 of four long-term scenarios with data of base year 1995 and projections for underlying variables provided by the Netherlands Environmental Assessment Agency (MNP). Preliminary interpretation of the results suggests the usefulness of the indicators presented in this report. A second activity undertaken in this report was

  16. Global Uranium Supply Ensured for Long Term, New Report Shows

    International Nuclear Information System (INIS)

    2012-01-01

    (tU) at the end of 2010 to between 98 000 tU and 136 000 tU by 2035. The currently defined uranium resource base is more than adequate to meet high-case requirements through 2035 and well into the foreseeable future. Although ample resources are available, meeting projected demand will require timely investments in uranium production facilities. This is because of the long lead times (typically in the order of ten years or more in most producing countries) required to develop production facilities that can turn resources into refined uranium ready for nuclear fuel production. With uranium production ready to expand to new countries, efforts are being made to develop transparent and well-regulated operations similar to those used elsewhere to minimise potential environmental and local health impacts. Although not the primary focus of the Red Book, activity updates on the environmental aspects of the uranium production cycle are included in the national reports in this edition. While the status of supply and demand is considered from the perspective of technologies in use today, the deployment of advanced reactors and fuel cycle technologies can also positively affect the long-term availability of uranium, conceivably extending the time horizon of the currently defined resource base to thousands of years. These are some of the findings in the just-published Uranium 2011: Resources, Production and Demand, a joint study by the OECD/NEA and the IAEA, carried out in co-operation with their member countries. This is the 24th edition of this periodic assessment (currently every two years) which has been published since the mid-1960s. (IAEA)

  17. Long term contracts in portfolios of gas supply

    International Nuclear Information System (INIS)

    Burns, D.

    1992-01-01

    This paper promotes the idea of long-term contracting for natural gas local distributors and utilities. It presents a brief history of how the spot-market developed and the effects spot-marketing can have in times of supply shortages. This has also resulted in a drastic decrease in exploration and development in the gas industry as gas supplies have exceeding demand, driving the prices down. The paper proposes several methods to restabilize the long-term contracting of gas by considering volume and pricing flexibility. Some brief discussions of industry-wide statistics are presented to show reserve replacement costs which would be needed to preserve the industry in a profit-making situation

  18. Long-term strategies in world energy supply

    International Nuclear Information System (INIS)

    Haefele, W.

    1980-01-01

    The International Institute for Applied Systems Analysis of Laxenburg, Austria has carried out a comprehensive systems analysis in which the problems of the long-term world energy supply are treated first qualitatively and then quantiatively. The results of this five-year study have been published in a book entitled 'Energy in a Finite World: a Global Energy Systems Analysis.' This summary of the book indicates that the world's energy supply in the next fifty years will not be limited by resources, but the rates at which new technologies will be built up. (orig.) [de

  19. A long-term stable power supply μDMFC stack for wireless sensor node applications

    International Nuclear Information System (INIS)

    Wu, Z L; Wang, X H; Teng, F; Li, X Z; Wu, X M; Liu, L T

    2013-01-01

    A passive, air-breathing 4-cell micro direct methanol fuel cell (μDMFC) stack is presented featured by a fuel delivery structure for a long-term and stable power supply. The fuel is reserved in a T shape tank and diffuses through the porous diffusion layer to the catalyst at anode. The stack has a maximum power output of 110mW with 3M methanol at room temperature and output a stable power even thought 5% fuel is the remained in reservoir. Its performance decreases less than 3% for 100 hours continuous work. As such, it is believed to be more applicable for powering the wireless sensor nodes

  20. Latest data shows long-term security of uranium supply

    International Nuclear Information System (INIS)

    2010-01-01

    capacity projections developed in this edition, by the year 2035, world nuclear capacity is projected to grow to between 500 and 785 GWe net. Accordingly, world reactor- related uranium requirements are also projected to rise. As observed in the past, increased investment in exploration has resulted in important discoveries and the identification of new resources. It is foreseen that, if market conditions improve further, additional exploration will be stimulated leading to the identification of additional resources of economic interest. Even in the high-growth scenario to 2035, less than half of the identified resources described in this edition would be consumed. The challenge remains to develop mines in a timely and environmentally sustainable fashion as uranium demand increases. A strong market will be required for these resources to be developed within the time frame required to meet future uranium demand. In addition, current projections of uranium mine production capacities could satisfy projected high-case world uranium requirements until the late 2020s. However, given the challenges and length of time associated with increasing production at existing mines and opening new mines, it is unlikely that all production increases will proceed as planned. As a result, secondary sources of previously mined uranium will continue to be required, complemented to the extent possible by uranium savings achieved by specifying lower tails assays at enrichment facilities and technical developments in fuel cycle technology. While the status of supply and demand is considered from today's technologies perspective, it should be recognised that the deployment of advanced reactor and fuel cycle technologies can positively affect the long-term availability of uranium and could conceivably extend it to thousands of years. These are some of the findings from Uranium 2009: Resources, Production and Demand , a joint study by the OECD/NEA and the IAEA, carried out in co-operation with their

  1. World's trend of national nuclear power policy and long-term perspective of nuclear power and supply and demand of uranium fuels

    International Nuclear Information System (INIS)

    Matsuo, Yuji; Nishida, Naoki; Yamaguchi, Yuji; Shimogoori, Kei; Murakami, Tomoko

    2013-01-01

    Based on perspective of nuclear power reflecting latest trend of national nuclear policy, supply and demand of uranium resources until 2035 was evaluated based on latest data. After the Fukushima nuclear accident, Germany and Italy dramatically changed nuclear power to phase out, while United States, Russia, France and Korea as well as China and India continued to promote nuclear power with no essential change of policy. Thus world's nuclear power capacity was foreseen to expand from 389 GW (2010) to 471 GW (2035, low growth case) and 760 GW (2035, high growth case). Following sharp increase of uranium cost after 2005, investment on natural uranium development became active and new operation start of uranium enrichment plants was anticipated in US and Europe, and then both supply and demand of natural uranium and uranium enrichment service would tend to relax until around 2020 and until 2035 extreme tightness of supply and demand might not occur even for high growth case. Uranium demand of Asian region including China and India would be largely expanded with natural uranium from Africa and Australia and uranium enrichment services from US, and Asian high overseas dependence would be continued. (T. Tanaka)

  2. Long-term storage of spent nuclear fuel

    International Nuclear Information System (INIS)

    Kempe, T.F.; Martin, A.; Thorne, M.C.

    1980-06-01

    This report presents the results of a study on the storage of spent nuclear fuel, with particular reference to the options which would be available for long-term storage. Two reference programmes of nuclear power generation in the UK are defined and these are used as a basis for the projection of arisings of spent fuel and the storage capacity which might be needed. The characteristics of spent fuel which are relevant to long-term storage include the dimensions, materials and physical construction of the elements, their radioactive inventory and the associated decay heating as a function of time after removal from the reactor. Information on the behaviour of spent fuel in storage ponds is reviewed with particular reference to the corrosion of the cladding. The review indicates that, for long-term storage, both Magnox and AGR fuel would need to be packaged because of the high rate of cladding corrosion and the resulting radiological problems. The position on PWR fuel is less certain. Experience of dry storage is less extensive but it appears that the rate of corrosion of cladding is much lower than in water. Unit costs are discussed. Consideration is given to the radiological impact of fuel storage. (author)

  3. The role of nuclear energy for Korean long-term energy supply strategy : application of energy demand-supply model

    International Nuclear Information System (INIS)

    Chae, Kyu Nam

    1995-02-01

    An energy demand and supply analysis is carried out to establish the future nuclear energy system of Korea in the situation of environmental restriction and resource depletion. Based on the useful energy intensity concept, a long-term energy demand forecasting model FIN2USE is developed to integrate with a supply model. The energy supply optimization model MESSAGE is improved to evaluate the role of nuclear energy system in Korean long-term energy supply strategy. Long-term demand for useful energy used as an exogeneous input of the energy supply model is derived from the trend of useful energy intensity by sectors and energy carriers. Supply-side optimization is performed for the overall energy system linked with the reactor and nuclear fuel cycle strategy. The limitation of fossil fuel resources and the CO 2 emission constraints are reflected as determinants of the future energy system. As a result of optimization of energy system using linear programming with the objective of total discounted system cost, the optimal energy system is obtained with detailed results on the nuclear sector for various scenarios. It is shown that the relative importance of nuclear energy would increase especially in the cases of CO 2 emission constraint. It is concluded that nuclear reactor strategy and fuel cycle strategy should be incorporated with national energy strategy and be changed according to environmental restriction and energy demand scenarios. It is shown that this modelling approach is suitable for a decision support system of nuclear energy policy

  4. A long-term view of worldwide fossil fuel prices

    International Nuclear Information System (INIS)

    Shafiee, Shahriar; Topal, Erkan

    2010-01-01

    This paper reviews a long-term trend of worldwide fossil fuel prices in the future by introducing a new method to forecast oil, natural gas and coal prices. The first section of this study analyses the global fossil fuel market and the historical trend of real and nominal fossil fuel prices from 1950 to 2008. Historical fossil fuel price analysis shows that coal prices are decreasing, while natural gas prices are increasing. The second section reviews previously available price modelling techniques and proposes a new comprehensive version of the long-term trend reverting jump and dip diffusion model. The third section uses the new model to forecast fossil fuel prices in nominal and real terms from 2009 to 2018. The new model follows the extrapolation of the historical sinusoidal trend of nominal and real fossil fuel prices. The historical trends show an increase in nominal/real oil and natural gas prices plus nominal coal prices, as well as a decrease in real coal prices. Furthermore, the new model forecasts that oil, natural gas and coal will stay in jump for the next couple of years and after that they will revert back to the long-term trend until 2018. (author)

  5. The role of nuclear energy system for Korean long-term energy supply strategy

    International Nuclear Information System (INIS)

    Chae, K.N.; Lee, D.G.; Lim, C.Y.; Lee, B.W.

    1995-01-01

    The energy supply optimization model MESSAGE-III is improved to evaluate the role of nuclear energy system in Korean long-term energy supply strategy. Emphasis is placed on the potential contribution of nuclear energy in case of environmental constraints and energy resource limitation. The time horizon is 1993-2040. A program to forecast useful energy demand is developed, and optimization is performed from the overall energy system to the nuclear energy system. Reactor and fuel cycle strategy and the expanded utilization options for nuclear energy system are suggested. FBRs, HTGRs and thorium fuel cycle would play key roles in the long run. The most important factors for nuclear energy in Korean energy supply strategy would be the availability of fossil fuels, CO 2 reduction regulation, and the supply capability of nuclear energy. (author)

  6. Long term trends in world energy demand and supply

    International Nuclear Information System (INIS)

    Frisch, J.

    1992-01-01

    In this address, the author discusses projected changes in fuel use, shifts in energy consumption and projected increases in carbon dioxide emissions. He expects these energy issues to cause geopolitical uncertainties that will complicate attempts to reduce greenhouse gases. There is great concern for the poverty-stricken areas of Asia and Africa. Thirty-five to forty-five percent of their energy needs will be supplied by scarce fuelwood and poor animal and vegetal residues by the year 2020. International cooperation will be needed to alleviate the tensions caused by these inequities of energy supplies

  7. More efficient optimization of long-term water supply portfolios

    Science.gov (United States)

    Kirsch, Brian R.; Characklis, Gregory W.; Dillard, Karen E. M.; Kelley, C. T.

    2009-03-01

    The use of temporary transfers, such as options and leases, has grown as utilities attempt to meet increases in demand while reducing dependence on the expansion of costly infrastructure capacity (e.g., reservoirs). Earlier work has been done to construct optimal portfolios comprising firm capacity and transfers, using decision rules that determine the timing and volume of transfers. However, such work has only focused on the short-term (e.g., 1-year scenarios), which limits the utility of these planning efforts. Developing multiyear portfolios can lead to the exploration of a wider range of alternatives but also increases the computational burden. This work utilizes a coupled hydrologic-economic model to simulate the long-term performance of a city's water supply portfolio. This stochastic model is linked with an optimization search algorithm that is designed to handle the high-frequency, low-amplitude noise inherent in many simulations, particularly those involving expected values. This noise is detrimental to the accuracy and precision of the optimized solution and has traditionally been controlled by investing greater computational effort in the simulation. However, the increased computational effort can be substantial. This work describes the integration of a variance reduction technique (control variate method) within the simulation/optimization as a means of more efficiently identifying minimum cost portfolios. Random variation in model output (i.e., noise) is moderated using knowledge of random variations in stochastic input variables (e.g., reservoir inflows, demand), thereby reducing the computing time by 50% or more. Using these efficiency gains, water supply portfolios are evaluated over a 10-year period in order to assess their ability to reduce costs and adapt to demand growth, while still meeting reliability goals. As a part of the evaluation, several multiyear option contract structures are explored and compared.

  8. Waste transmutation with minimal fuel cycle long-term risk

    Energy Technology Data Exchange (ETDEWEB)

    Slessarev, I.; Salvatores, M.; Uematsu, M. [Direction des Reacteurs Nucleaires, Cadarache (France)

    1995-10-01

    Hybrid systems (source-driven subcritical reactors), are investigated at CEA, mainly from a conceptual point of view, in order to assess their potential to transmute radioactive wastes (mainly long-lived fission products, LLFP) and their potential to insure a minimal long-term radiological risk related both to the fuel inventory inside the system and to the full fuel cycle (mass flows, reprocessing transport, waste disposal). The physics of these systems has been explored and work is in progress both in the field of basic data and INC code validation, in the frame of international collaborations and in the field of conceptual design studies. The most interesting feature of subcritical source-driven system is related to the possibility to obtain an {open_quotes}excess{close_quotes} of neutrons per fission, which can be used to reduce the long-term radiological risk. A specific example will be discussed here.

  9. Safe transport of spent fuels after long-term storage

    International Nuclear Information System (INIS)

    Aritomi, M.; Takeda, T.; Ozaki, S.

    2004-01-01

    Considering the scarcity of energy resources in Japan, a nuclear energy policy pertaining to the spent fuel storage has been adopted. The nuclear energy policy sets the rules that spent fuels generated from LWRs shall be reprocessed and that plutonium and unburnt uranium shall be recovered and reused. For this purpose, a reprocessing plant, which has a reprocessing capability of 800 ton/yr, is under construction at Rokkasho Village. However, it is anticipated that the start of its operation will be delayed. In addition, the amount of spent fuels generated from nuclear power plants exceeds its reprocessing capability. Therefore, the establishment of storage technology for spent fuels becomes an urgent problem in Japan in order to continue smoothly the LWR operations. In this paper, the background of nuclear power generation in Japan is introduced at first. Next, the policy of spent fuel storage in Japan and circumstances surrounding the spent fuels in Japan are mentioned. Furthermore, the major subjects for discussions to settle and improve 'Standard for Safety Design and Inspection of Metal Casks for Spent Fuel Interim Storage Facility' in Atomic Energy Society of Japan are discussed, such as the integrity of fuel cladding, basket, shielding material and metal gasket for the long term storage for achieving safe transport of spent fuels after the storage. Finally, solutions to the unsolved subject in establishing the spent fuel interim storage technologies ase introduced accordingly

  10. The Canadian long-term experimental used fuel storage program

    International Nuclear Information System (INIS)

    Wasywich, K.M.; Taylor, P.

    1993-01-01

    The Canadian experimental fuel storage program consists of four components: (1) storage of used CANDU (CANadian Deuterium Uranium, registered trademark of AECL) fuel under water, with periodic examination; (2) storage of used CANDU fuel in dry air at seasonally varying temperatures, and in both dry and moisture-saturated air at 150 C, also with periodic examination; (3) underlying research on the oxidation of unused and used UO 2 in dry and moist air at temperatures up to 300 C; and (4) modeling of UO 2 oxidation in dry air. The primary objective of the fuel-storage experiments is to investigate the stability of used CANDU fuel during long-term storage. Burnup of the fuel in these experiments ranges from ∼43 to 582 MW h/kg U, while the outer-element linear power ratings range from 22 to 79 kW/m. The storage behavior of intact and intentionally defected fuel, and fuel that defected in-reactor, is being investigated in the above experiments. Since differences in UO 2 oxidation behavior were observed between dry-air, moisture-saturated air and wet storage of intentionally defected used CANDU fuel, underlying research was initiated on oxidation of unused and used fuel to develop a better understanding of the different mechanisms. Modeling of UO 2 oxidation based on the results of the dry-storage experiments is also under way

  11. Synthesis on the spent fuel long term evolution

    Energy Technology Data Exchange (ETDEWEB)

    Ferry, C.; Poinssot, Ch.; Lovera, P.; Poulesquen, A. [CEA Saclay, Dept. de Physico-Chimie (DEN/DPC), 91 - Gif sur Yvette (France); Broudic, V. [CEA Cadarache, Direction des Reacteurs Nucleaires (DRN), 13 - Saint Paul lez Durance (France); Cappelaere, Ch. [CEA Saclay, Dept. des Materiaux pour le Nucleaire(DMN), 91 - Gif-sur-Yvette (France); Desgranges, L. [CEA Cadarache, Direction des Reacteurs Nucleaires (DRN), 13 - Saint-Paul-lez-Durance (France); Garcia, Ph. [CEA Cadarache, Dept. d' Etudes des Combustibles (DEC), 13 - Saint Paul lez Durance (France); Jegou, Ch.; Roudil, D. [CEA Valrho, Dir. de l' Energie Nucleaire (DEN), 30 - Marcoule (France); Lovera, P.; Poulesquen, A. [CEA Saclay, Dept. de Physico-Chimie (DPC), 91 - Gif sur Yvette (France); Marimbeau, P. [CEA Cadarache, Dir. de l' Energie Nucleaire (DEN), 13 - Saint-Paul-lez-Durance (France); Gras, J.M.; Bouffioux, P. [Electricite de France (EDF), 75 - Paris (France)

    2005-07-01

    The French research on spent fuel long term evolution has been performed by CEA (Commissariat a l'Energie Atomique) since 1999 in the PRECCI project with the support of EDF (Electricite de France). These studies focused on the spent fuel behaviour under various conditions encountered in dry storage or in deep geological disposal. Three main types of conditions were discerned: - The evolution in a closed system which corresponds to the normal scenario in storage and to the first confinement phase in disposal; - The evolution in air which corresponds to an incidental loss of confinement during storage or to a rupture of the canister before the site re-saturation in geological disposal; - The evolution in water which corresponds to the normal scenario after the breaching of the canister in repository conditions. This document produced in the frame of the PRECCI project is an overview of the state of knowledge in 2004 concerning the long-term behavior of spent fuel under these various conditions. The state of the art was derived from the results obtained under the PRECCI project as well as from a review of the literature and of data acquired under the European project on Spent Fuel Stability under Repository Conditions. The main results issued from the French research are underlined. (authors)

  12. Synthesis on the spent fuel long term evolution

    International Nuclear Information System (INIS)

    Ferry, C.; Poinssot, Ch.; Lovera, P.; Poulesquen, A.; Broudic, V.; Cappelaere, Ch.; Desgranges, L.; Garcia, Ph.; Jegou, Ch.; Roudil, D.; Lovera, P.; Poulesquen, A.; Marimbeau, P.; Gras, J.M.; Bouffioux, P.

    2005-01-01

    The French research on spent fuel long term evolution has been performed by CEA (Commissariat a l'Energie Atomique) since 1999 in the PRECCI project with the support of EDF (Electricite de France). These studies focused on the spent fuel behaviour under various conditions encountered in dry storage or in deep geological disposal. Three main types of conditions were discerned: - The evolution in a closed system which corresponds to the normal scenario in storage and to the first confinement phase in disposal; - The evolution in air which corresponds to an incidental loss of confinement during storage or to a rupture of the canister before the site re-saturation in geological disposal; - The evolution in water which corresponds to the normal scenario after the breaching of the canister in repository conditions. This document produced in the frame of the PRECCI project is an overview of the state of knowledge in 2004 concerning the long-term behavior of spent fuel under these various conditions. The state of the art was derived from the results obtained under the PRECCI project as well as from a review of the literature and of data acquired under the European project on Spent Fuel Stability under Repository Conditions. The main results issued from the French research are underlined. (authors)

  13. Corrosion of Spent Nuclear Fuel: The Long-Term Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Rodney C. Ewing

    2004-10-07

    Spent nuclear fuel, essentially U{sub 2}, accounts for over 95% of the total radioactivity of all of the radioactive wastes in the United States that require disposal, disposition or remediation. The UO{sub 2} in SNF is not stable under oxiding conditions and may also be altered under reducing conditions. The alteration of SNF results in the formation of new uranium phases that can cause the release or retardation of actinide and fission product radionuclides. Over the long term, and depending on the extent to which the secondary uranium phases incorporate fission products and actinides, these alteration phases become the near-field source term.

  14. Corrosion of Spent Nuclear Fuel: The Long-Term Assessment

    International Nuclear Information System (INIS)

    Ewing, Rodney C.

    2004-01-01

    Spent nuclear fuel, essentially U 2 , accounts for over 95% of the total radioactivity of all of the radioactive wastes in the United States that require disposal, disposition or remediation. The UO 2 in SNF is not stable under oxiding conditions and may also be altered under reducing conditions. The alteration of SNF results in the formation of new uranium phases that can cause the release or retardation of actinide and fission product radionuclides. Over the long term, and depending on the extent to which the secondary uranium phases incorporate fission products and actinides, these alteration phases become the near-field source term

  15. Long Term Management of Spent Fuel from NEK

    International Nuclear Information System (INIS)

    Kegel, L.; Zeleznik, N.; Lokner, V.

    2012-01-01

    In 2008 Slovenian national agency for radioactive waste management ARAO started together with Croatian sister organization APO elaboration of a new revision of Decommissioning, Radioactive waste and Spent fuel management program for NPP Krsko. In scope of this work also new studies for spent fuel storage and disposal were prepared in which technical solutions were analyzed and proposed for specific spent fuel (SF) from NPP Krsko. Time schedules for main activities of SF disposal development were elaborated for two alternative scenarios which correspond to normal NPP Krsko operation and 20 - year lifetime extension. All technical activities were financially assessed and costs estimates of SF storage and geological disposal development provided. The prepared studies were verified by international experts in order to confirm the correctness of technical inputs, proposed solutions, time schedules of activities and costs evaluations. The calculated nominal and discounted costs of spent fuel management served for the recalculation of annuities in the integral scenarios of interrelated activities on NPP Krsko decommissioning, LILW and SF management. Besides new first proposal of long-term management of spent fuel from NPP Krsko the joint work also opened additional questions. One of this is time schedule of proposed activities for long term SF management - what were the criteria used in the determination of actions and are they optimal for both countries. How the process of site selection for SF storage or disposal should be prepared having in mind that it will bring many questions in both countries? Is direct disposal of SF still the best solution in current development of nuclear prospects? The paper will present the current development and solutions for SF management from NPP Krsko and will try to answer questions which need to be solved and future development in the SF management.(author).

  16. Spent Fuel Long Term Interim Storage: The Spanish Policy

    International Nuclear Information System (INIS)

    Fernandez-Lopez, Javier

    2014-01-01

    ENRESA is the Spanish organization responsible for long-term management of all categories of radioactive waste and nuclear spent fuel and for decommissioning nuclear installations. It is also in charge of the management of the funds collected from waste producers and electricity consumers. The national policy about radioactive waste management is established at the General Radioactive Waste Plan by the Government upon proposal of the Ministry of Industry, Energy and Tourism. Now the Plan in force is the Sixth Plan approved in 2006. The policy on spent nuclear fuel, after description of the current available options, is set up as a long term interim storage at a Centralized Temporary Storage facility (CTS, or ATC in Spanish acronym) followed by geologic disposal, pending technological development on other options being eligible in the future. After a site selection process launched in 2009, the site for the ATC has been chosen at the end of 2011. The first steps for the implementation of the facility are described in the present paper. (authors)

  17. Long-term global nuclear energy and fuel cycle strategies

    International Nuclear Information System (INIS)

    Krakowski, R.A.

    1997-01-01

    The Global Nuclear Vision Project is examining, using scenario building techniques, a range of long-term nuclear energy futures. The exploration and assessment of optimal nuclear fuel-cycle and material strategies is an essential element of the study. To this end, an established global E 3 (energy/economics/environmental) model has been adopted and modified with a simplified, but comprehensive and multi-regional, nuclear energy module. Consistent nuclear energy scenarios are constructed using this multi-regional E 3 model, wherein future demands for nuclear power are projected in price competition with other energy sources under a wide range of long-term demographic (population, workforce size and productivity), economic (price-, population-, and income-determined demand for energy services, price- and population-modified GNP, resource depletion, world-market fossil energy prices), policy (taxes, tariffs, sanctions), and top-level technological (energy intensity and end-use efficiency improvements) drivers. Using the framework provided by the global E 3 model, the impacts of both external and internal drivers are investigated. The ability to connect external and internal drivers through this modeling framework allows the study of impacts and tradeoffs between fossil- versus nuclear-fuel burning, that includes interactions between cost, environmental, proliferation, resource, and policy issues

  18. Long-term global nuclear energy and fuel cycle strategies

    Energy Technology Data Exchange (ETDEWEB)

    Krakowski, R.A. [Los Alamos National Lab., NM (United States). Technology and Safety Assessment Div.

    1997-09-24

    The Global Nuclear Vision Project is examining, using scenario building techniques, a range of long-term nuclear energy futures. The exploration and assessment of optimal nuclear fuel-cycle and material strategies is an essential element of the study. To this end, an established global E{sup 3} (energy/economics/environmental) model has been adopted and modified with a simplified, but comprehensive and multi-regional, nuclear energy module. Consistent nuclear energy scenarios are constructed using this multi-regional E{sup 3} model, wherein future demands for nuclear power are projected in price competition with other energy sources under a wide range of long-term demographic (population, workforce size and productivity), economic (price-, population-, and income-determined demand for energy services, price- and population-modified GNP, resource depletion, world-market fossil energy prices), policy (taxes, tariffs, sanctions), and top-level technological (energy intensity and end-use efficiency improvements) drivers. Using the framework provided by the global E{sup 3} model, the impacts of both external and internal drivers are investigated. The ability to connect external and internal drivers through this modeling framework allows the study of impacts and tradeoffs between fossil- versus nuclear-fuel burning, that includes interactions between cost, environmental, proliferation, resource, and policy issues.

  19. Corrosion of Spent Nuclear Fuel: The Long-Term Assessment

    International Nuclear Information System (INIS)

    Ewing, Rodney C.

    2003-01-01

    The successful disposal of spent nuclear fuel (SNF) is one of the most serious challenges to the successful completion of the nuclear fuel cycle and the future of nuclear power generation. In the United States, 21 percent of the electricity is generated by 107 commercial nuclear power plants (NPP), each of which generates 20 metric tons of spent nuclear fuel annually. In 1996, the total accumulation of spent nuclear fuel was 33,700 metric tons of heavy metal (MTHM) stored at 70 sites around the country. The end-of-life projection for current nuclear power plants (NPP) is approximately 86,000 MTHM. In the proposed nuclear waste repository at Yucca Mountain over 95% of the radioactivity originates from spent nuclear fuel. World-wide in 1998, approximately 130,000 MTHM of SNF have accumulated, most of it located at 236 NPP in 36 countries. Annual production of SNF is approximately 10,000 MTHM, containing about 100 tons of ''reactor grade'' plutonium. Any reasonable increase in the proportion of energy production by NPP, i.e., as a substitute for hydrocarbon-based sources of energy, will significantly increase spent nuclear fuel production. Spent nuclear fuel is essentially UO 2 with approximately 4-5 atomic percent actinides and fission product elements. A number of these elements have long half-lives hence, the long-term behavior of the UO 2 is an essential concern in the evaluation of the safety and risk of a repository for spent nuclear fuel. One of the unique and scientifically most difficult aspects of the successful disposal of spent nuclear fuel is the extrapolation of short-term laboratory data (hours to years) to the long time periods (10 3 to 10 5 years) as required by the performance objectives set in regulations, i.e. 10 CFR 60. The direct verification of these extrapolations or interpolations is not possible, but methods must be developed to demonstrate compliance with government regulations and to satisfy the public that there is a reasonable basis for

  20. Corrosion of Spent Nuclear Fuel: The Long-Term Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Ewing, Rodney C.

    2003-09-14

    The successful disposal of spent nuclear fuel (SNF) is one of the most serious challenges to the successful completion of the nuclear fuel cycle and the future of nuclear power generation. In the United States, 21 percent of the electricity is generated by 107 commercial nuclear power plants (NPP), each of which generates 20 metric tons of spent nuclear fuel annually. In 1996, the total accumulation of spent nuclear fuel was 33,700 metric tons of heavy metal (MTHM) stored at 70 sites around the country. The end-of-life projection for current nuclear power plants (NPP) is approximately 86,000 MTHM. In the proposed nuclear waste repository at Yucca Mountain over 95% of the radioactivity originates from spent nuclear fuel. World-wide in 1998, approximately 130,000 MTHM of SNF have accumulated, most of it located at 236 NPP in 36 countries. Annual production of SNF is approximately 10,000 MTHM, containing about 100 tons of ''reactor grade'' plutonium. Any reasonable increase in the proportion of energy production by NPP, i.e., as a substitute for hydrocarbon-based sources of energy, will significantly increase spent nuclear fuel production. Spent nuclear fuel is essentially UO{sub 2} with approximately 4-5 atomic percent actinides and fission product elements. A number of these elements have long half-lives hence, the long-term behavior of the UO{sub 2} is an essential concern in the evaluation of the safety and risk of a repository for spent nuclear fuel. One of the unique and scientifically most difficult aspects of the successful disposal of spent nuclear fuel is the extrapolation of short-term laboratory data (hours to years) to the long time periods (10{sup 3} to 10{sup 5} years) as required by the performance objectives set in regulations, i.e. 10 CFR 60. The direct verification of these extrapolations or interpolations is not possible, but methods must be developed to demonstrate compliance with government regulations and to satisfy the

  1. Safety Aspects of Long Term Spent Fuel Dry Storage

    International Nuclear Information System (INIS)

    Botsch, Wolfgang; Smalian, S.; Hinterding, P.; Drotleff, H.; Voelzke, H.; Wolff, D.; Kasparek, E.

    2014-01-01

    As a consequence of the lack of a final repository for spent nuclear fuel (SF) and high level waste (HLW), long term interim storage of SF and HLW will be necessary. As with the storage of all radioactive materials, the long term storage of SF and HLW must conform to safety requirements. Safety aspects such as safe enclosure of radioactive materials, safe removal of decay heat, sub-criticality and avoidance of unnecessary radiation exposure must be achieved throughout the complete storage period. The implementation of these safety requirements can be achieved by dry storage of SF and HLW in casks as well as in other systems such as dry vault storage systems or spent fuel pools, where the latter is neither a dry nor a passive system. After the events of Fukushima, the advantages of passively and inherently safe dry storage systems have become more obvious. In Germany, dry storage of SF in casks fulfils both transport and storage requirements. Mostly, storage facilities are designed as concrete buildings above the ground; one storage facility has also been built as a rock tunnel. In all these facilities the safe enclosure of radioactive materials in dry storage casks is achieved by a double-lid sealing system with surveillance of the sealing system. The safe removal of decay heat is ensured by the design of the storage containers and the storage facility, which also secures to reduce the radiation exposure to acceptable levels. TUV and BAM, who work as independent experts for the competent authorities, inform about spent fuel management and issues concerning dry storage of spent nuclear fuel, based on their long experience in these fields. All relevant safety issues such as safe enclosure, shielding, removal of decay heat and sub-criticality are checked and validated with state-of-the-art methods and computer codes before the license approval. In our presentation we discuss which of these aspects need to be examined closer for a long term interim storage. It is shown

  2. High estimates of supply constrained emissions scenarios for long-term climate risk assessment

    International Nuclear Information System (INIS)

    Ward, James D.; Mohr, Steve H.; Myers, Baden R.; Nel, Willem P.

    2012-01-01

    The simulated effects of anthropogenic global warming have become important in many fields and most models agree that significant impacts are becoming unavoidable in the face of slow action. Improvements to model accuracy rely primarily on the refinement of parameter sensitivities and on plausible future carbon emissions trajectories. Carbon emissions are the leading cause of global warming, yet current considerations of future emissions do not consider structural limits to fossil fuel supply, invoking a wide range of uncertainty. Moreover, outdated assumptions regarding the future abundance of fossil energy could contribute to misleading projections of both economic growth and climate change vulnerability. Here we present an easily replicable mathematical model that considers fundamental supply-side constraints and demonstrate its use in a stochastic analysis to produce a theoretical upper limit to future emissions. The results show a significant reduction in prior uncertainty around projected long term emissions, and even assuming high estimates of all fossil fuel resources and high growth of unconventional production, cumulative emissions tend to align to the current medium emissions scenarios in the second half of this century. This significant finding provides much-needed guidance on developing relevant emissions scenarios for long term climate change impact studies. - Highlights: ► GHG emissions from conventional and unconventional fossil fuels modelled nationally. ► Assuming worst-case: large resource, high growth, rapid uptake of unconventional. ► Long-term cumulative emissions align well with the SRES medium emissions scenario. ► High emissions are unlikely to be sustained through the second half of this century. ► Model designed to be easily extended to test other scenarios e.g. energy shortages.

  3. Corrosion of Spent Nuclear Fuel: The Long-Term Assessment

    International Nuclear Information System (INIS)

    Ewing, Rodney C.

    2003-01-01

    This research program is a broadly based effort to understand the long-term behavior of spent nuclear fuel (SNF) and its alteration products in a geologic repository. We have established by experiments and field studies that natural uraninite, UO2+x, and its alteration products are excellent ''natural analogues'' for the study of the corrosion of UO2 in SNF. This on-going research program has addressed the following major issues: (1) What are the long-term corrosion products of natural UO2+x, uraninite, under oxidizing and reducing conditions? (2) What is the paragenesis or the reaction path for the phases that form during alteration? (3) What is the radionuclide content in the corrosion products as compared with the original UO2+x? Do the trace element contents substantiate models developed to predict radionuclide incorporation into the secondary phases? Are the corrosion products accurately predicted from geochemical codes (e.g., EQ3/6 or Geochemist's Workbench) that are used in performance assessments? Can these codes be tested by studies of natural analogue sites (e.g., Oklo, Cigar Lake or Pena Blanca)

  4. Long term assurance of supply of uranium enrichment

    International Nuclear Information System (INIS)

    1978-01-01

    After elaborating a number of key questions on uranium enrichment, the representatives of 10 countries and of the EC commission present their answers. Attention is paid to the assurance of uranium supply, to uranium enrichment, market trends and flexibility in enrichment agreements

  5. Factors influencing long term dynamics of health care supply and demand

    NARCIS (Netherlands)

    Smits, M.T.; Roos, E.; Pries-Heje, J.; Chiasson, M.; Wareham, J.; Busquets, X.; Valor, J.

    2012-01-01

    Governments and other policy makers use long-term planning models to support workforce planning decisions for regulating care markets and to ensure accurate balancing between care supply and demand. Our aim is to understand long-term effects of workforce planning decisions on care markets, in order

  6. Long-term energy supply programs in West Germany

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt-Kuester, W J; Wagner, H F

    1977-07-01

    A discussion of the energy research and development plans, priorities, strategies, timetables, and current projects of the West German Government covers the measures aimed at the rational use of energy for home heating, expanded electricity production by light-water reactors, and solar energy use for hot-water production by 1985; at energy savings in industry and transport, improvements in secondary energy technology, large-scale production of gas, electricity, liquids, and coke from coal, underground gasification, construction of fast breeder reactors, solar heating in industrial applications, and local use of geothermal and wind energy by 2000; and at complete reliance on coal, nuclear fission, controlled nuclear fusion, and solar sources after the year 2000; the changes in the energy supply and demand structure in these periods; the share of the various projects in the B.R.D. budget for energy; and the status of current pilot-plant activity in the areas of, e.g., liquefaction, gasification, fission, and energy conversion and storage.

  7. Medium- and long-term consequences of pollution on labor supply: evidence from Indonesia

    Directory of Open Access Journals (Sweden)

    Younoh Kim

    2017-04-01

    Full Text Available Abstract We use a natural experiment in Indonesia to study the medium- and long-term effects of air pollution on labor supply. We find that exposure to air pollution reduces hours worked and while the medium-term effects are larger in magnitude, some effects do persist in the long term. More interestingly, we are able to provide some insight regarding the underlying channels that contribute to the reduced labor supply. Own health seems to be the only responsible channel in the long term, while in the medium term, a different channel based on dependent caregiving is the most important. JEL Classification: J22, Q53

  8. A long-term stable power supply µDMFC stack for wireless sensor node applications

    International Nuclear Information System (INIS)

    Wu, Zonglin; Wang, Xiaohong; Li, Xiaozhao; Xu, Manqi; Liu, Litian

    2014-01-01

    In this paper, a passive, air-breathing four-cell micro direct methanol fuel cell (µDMFC) stack featuring a fuel delivery structure for long-term and stable power supply is designed, fabricated and tested. The fuel is reserved in a T-shaped tank and diffuses through the porous diffusion layer to the catalyst at the anode. A peak power density of 25.7 mW cm −2 and a maximum power output of 113 mW are achieved with 3 M methanol at room temperature, and the stack can produce 60 mW of power, even though only 5% fuel remains in the reservoir. Combined with a low-input dc–dc convertor, the stack can realize a stable and optional constant voltage output from 1 V–6 V. The stack successfully powered a heavy metal sensor node for water environment monitoring 12 d continuously, with consumption of 10 mL 5 M methanol solution. As such, it is believed to be applicable for powering wireless sensor nodes. (paper)

  9. Effect of long-term storage of LWR spent fuel on Pu-thermal fuel cycle

    International Nuclear Information System (INIS)

    Kurosawa, Masayoshi; Naito, Yoshitaka; Suyama, Kenya; Itahara, Kuniyuki; Suzuki, Katsuo; Hamada, Koji

    1998-01-01

    According to the Long-term Program for Research, Development and Utilization of Nuclear Energy (June, 1994) in Japan, the Rokkasho Reprocessing Plant will be operated shortly after the year 2000, and the planning of the construction of the second commercial plant will be decided around 2010. Also, it is described that spent fuel storage has a positive meaning as an energy resource for the future utilization of Pu. Considering the balance between the increase of spent fuels and the domestic reprocessing capacity in Japan, it can be expected that the long-term storage of UO 2 spent fuels will be required. Then, we studied the effect of long-term storage of spent fuels on Pu-thermal fuel cycle. The burnup calculation were performed on the typical Japanese PWR fuel, and the burnup and criticality calculations were carried out on the Pu-thermal cores with MOX fuel. Based on the results, we evaluate the influence of extending the spent fuel storage term on the criticality safety, shielding design of the reprocessing plant and the core life time of the MOX core, etc. As the result of this work on long-term storage of LWR spent fuels, it becomes clear that there are few demerits regarding the lifetime of a MOX reactor core, and that there are many merits regarding the safety aspects of the fuel cycle facilities. Furthermore, long-term storage is meaningful as energy storage for effective utilization of Pu to be improved by technological innovation in future, and it will allow for sufficient time for the important policymaking of nuclear fuel cycle establishment in Japan. (author)

  10. Committing to coal and gas: Long-term contracts, regulation, and fuel switching in power generation

    Science.gov (United States)

    Rice, Michael

    Fuel switching in the electricity sector has important economic and environmental consequences. In the United States, the increased supply of gas during the last decade has led to substantial switching in the short term. Fuel switching is constrained, however, by the existing infrastructure. The power generation infrastructure, in turn, represents commitments to specific sources of energy over the long term. This dissertation explores fuel contracts as the link between short-term price response and long-term plant investments. Contracting choices enable power plant investments that are relationship-specific, often regulated, and face uncertainty. Many power plants are subject to both hold-up in investment and cost-of-service regulation. I find that capital bias is robust when considering either irreversibility or hold-up due to the uncertain arrival of an outside option. For sunk capital, the rental rate is inappropriate for determining capital bias. Instead, capital bias depends on the regulated rate of return, discount rate, and depreciation schedule. If policies such as emissions regulations increase fuel-switching flexibility, this can lead to capital bias. Cost-of-service regulation can shorten the duration of a long-term contract. From the firm's perspective, the existing literature provides limited guidance when bargaining and writing contracts for fuel procurement. I develop a stochastic programming framework to optimize long-term contracting decisions under both endogenous and exogenous sources of hold-up risk. These typically include policy changes, price shocks, availability of fuel, and volatility in derived demand. For price risks, the optimal contract duration is the moment when the expected benefits of the contract are just outweighed by the expected opportunity costs of remaining in the contract. I prove that imposing early renegotiation costs decreases contract duration. Finally, I provide an empirical approach to show how coal contracts can limit

  11. Short, medium and long term consequences of inadequate defect fuel management

    International Nuclear Information System (INIS)

    Roberts, J.G.; McQueen, M.; Nashiem, R.; Ma, G.

    2011-01-01

    Defect fuel pencils result in short, medium and long term consequences to the environment within and external to the nuclear power station. The paper will describe these consequences and specify the Defect Fuel Management Practices required to avoid these consequences.

  12. Short, medium and long term consequences of inadequate defect fuel management

    Energy Technology Data Exchange (ETDEWEB)

    Roberts, J.G. [CANTECH Associates Ltd., Burlington, ON (Canada); McQueen, M.; Nashiem, R.; Ma, G. [Bruce Power, Tiverton, ON (Canada)

    2011-07-01

    Defect fuel pencils result in short, medium and long term consequences to the environment within and external to the nuclear power station. The paper will describe these consequences and specify the Defect Fuel Management Practices required to avoid these consequences.

  13. False security: the effects of long-term oil supply disruptions in a slack oil market

    Energy Technology Data Exchange (ETDEWEB)

    Kah, M; Kruvant, W J

    1984-01-01

    The authors contention that the US should continue to be concerned about energy emergency preparedness, in the event of a long-term disruption of oil supplies, despite current slack economic conditions on the international market is outlined. One quarter of the world's total supply still comes from politically volatile areas of North Africa and the Middle East, and although oil imports have fallen off, the US is still vulnerable.

  14. Criticality evaluation of long term for spent fuel, using Scale

    International Nuclear Information System (INIS)

    Esquivel E, J.; Vargas E, S.; Ramirez S, J. R.

    2013-10-01

    Once carried out the spent fuel discharge, of the reactor core, this continues generating decay heat and diverse fission products, reason why is important to store this fuel inside containers able to dissipate the heat generated by the isotopes decay of the fuel and to maintain the fuels arrangement in subcritical condition. This means that: is necessary to assure the sub-criticality of those fuel assemblies in the time. This work, presents a criticality evaluation of fuel assemblies type PWR in a storage generic container. For this purpose have been used two codes: GeeWiz, to carry out the geometric model of the container with the fuel assemblies, and Keno, with which, the criticality of the full container with fuel is determined until a 10 6 years period. These codes are part of the package Scale. The specifications for each one of the analyzed components are based on a Benchmark document of the Nea/OECD, of where, the results that reports are compared with the obtained results by the realized analysis. (Author)

  15. Long-term climate policy implications of phasing out fossil fuel subsidies

    International Nuclear Information System (INIS)

    Schwanitz, Valeria Jana; Piontek, Franziska; Bertram, Christoph; Luderer, Gunnar

    2014-01-01

    It is often argued that fossil fuel subsidies hamper the transition towards a sustainable energy supply as they incentivize wasteful consumption. We assess implications of a subsidy phase-out for the mitigation of climate change and the low-carbon transformation of the energy system, using the global energy–economy model REMIND. We compare our results with those obtained by the International Energy Agency (based on the World Energy Model) and by the Organization for Economic Co-Operation and Development (OECD-Model ENV-Linkages), providing the long-term perspective of an intertemporal optimization model. The results are analyzed in the two dimensions of subsidy phase-out and climate policy scenarios. We confirm short-term benefits of phasing-out fossil fuel subsidies as found in prior studies. However, these benefits are only sustained to a small extent in the long term, if dedicated climate policies are weak or nonexistent. Most remarkably we find that a removal of fossil fuel subsidies, if not complemented by other policies, can slow down a global transition towards a renewable based energy system. The reason is that world market prices for fossil fuels may drop due to a removal of subsidies. Thus, low carbon alternatives would encounter comparative disadvantages. - Highlights: • We assess implications of phasing out fossil fuel subsidies on the mitigation of climate change. • The removal of subsidies leads to a net-reduction in the use of energy. • Emission reductions contribute little to stabilize greenhouse gases at 450 ppm if not combined with climate policies. • Low carbon alternatives may encounter comparative disadvantages due to relative price changes at world markets

  16. Behaviour of Spent WWER fuel under long term storage conditions

    Energy Technology Data Exchange (ETDEWEB)

    Kadarmetov, I M [A.A.Bochvar All-Russia Research Institute of Inorganic Materials, Moscow (Russian Federation)

    1999-07-02

    Results of experimental investigation into thermomechanical properties of pre-irradiated Zr-1%Nb alloy over a range temperatures 500-570 grad C are presented. Safety examination of the Ventilation Storage Casks dry storage system has been carried out. Preliminary safety criteria under dry storage conditions in an environment of inert gas are follows: maximum cladding temperature under normal conditions of dry storage should not exceed 330 grad C after 5-year cooling in water-filled pools; maximum allowable temperature of spent fuel rod cladding under operational mode with infringement of heat removal should not exceed 440 grad C over 8 hours. As each SFA dry storage project comprises its individual technology of spent fuel management, it is necessary to evaluate allowable parameters (terms of storage, maximum temperatures of fuel) for each project respectively. The programme of experimental investigations for the justification of safety criteria for WWER-1000 dry spent fuel storage systems is underway. (author)

  17. Long-term alternatives for nuclear fuel cycles

    International Nuclear Information System (INIS)

    Vira, J.; Vieno, T.

    1981-07-01

    Several technical alternatives have been proposed to the nuclear spent fuel management but the practical experience on any of these is small or totally lacking. Since the management method is also connected with the composition of fresh fuel, the comparison of the alternatives must include the whole fuel cycle of a nuclear power plant. In the planning of the nuclear fuel cycle over a time range of several decades a consideration must be given, in addition, to the potential of the new reactor types with increased efficiency of uranium utilization. For analyses and mutual comparisons of the fuel cycle alternatives a number of computer models have been designed and implemented at the Technical Research Centre of Finland. Given the estimated boundary conditions the models can be used to study the impact of different goals and requirements on the fuel cycle decisions. Further, they facilitate cost predictions and display information on the role of the intrinsic uncertainties in the decision-making. The conclusions of the study are tied to the questions of price and availability of uranium. Hence, for instance, the benefits from the reprocessing of spent fuel might prove to be small when compared to the costs required, especially as the current reprocessing contracts do not allow the custemer to dismiss the duty of building the final disposal facilities for high level radioactive waste. For a few decades the final decisions can be postponed by extending the interim storage period. Farther in the future the decisions in the nuclear fuel cycle arrangements will more link to the introduction of the fast breeder reactors. (author)

  18. New long-term plan of nuclear development and perspectives of nuclear fuel cycle policy

    International Nuclear Information System (INIS)

    Uchiyama, Yohji

    2005-01-01

    Japan's nuclear fuel cycle policy, recently issued as an interim report of the Council to Formulate the New Long-Term Nuclear Program of the Atomic Energy Commission, is summarized and briefly explained together with the concluding remarks from the sub-committee for discussing technical and economical problems on the spent nuclear fuels with the present state of the Rokkasho reprocessing plant in mind. As for the nuclear fuel treatment, the panel considered four scenarios: (1) total reprocessing (the reprocessing for spent fuel after an appropriate period of storage); (2) partial reprocessing (spent fuel is reprocessed, with direct disposal of any spent fuel in excess of reprocessing capacity); (3) total direct disposal (direct disposal of all spent fuel); and (4) temporary storage (spent fuel is temporarily stored, and in about 2060 a choice will be made about whether to reprocess it or directly dispose of it). These four scenarios were studied from various perspectives, namely: (1) ensuring safety; (2) energy security; (3) environmental compatibility; (4) economic efficiency; (5) nuclear nonproliferation; (6) technical feasibility; (7) social acceptance; (8) securing choices; (9) issues concerning change in policy; and (10) overseas trends. Regarding economic efficiency, the council in particular conducted detailed studies and reassessment of nuclear fuel cycle costs. Scenario 1 (total reprocessing) is about 0.5-0.7 yen/kWh higher than scenario 3 (total direct disposal). However, looking at the situation from the perspectives of energy security, that is the stable supply and moderate use of resources, and environmental compatibility, scenario 1 (total reprocessing) can be evaluated as superior to the other scenarios. And more importantly, if the fast-breeder reactor cycle is commercialized, this superiority increases considerably. (S. Ohno)

  19. Long term outlook for gas supply and demand 2007-2030

    International Nuclear Information System (INIS)

    2010-05-01

    Given the economic crisis and the even greater focus of energy policy in recent years on energy efficiency and renewables, earlier expectations in respect of gas demand have to be lowered. Nonetheless, there are still good prospects for gas expanding its position in the EU energy market in the medium to long term. Environmental friendliness and highly efficient technologies in all areas of energy supply give gas a key role in a realistic EU climate policy, the goals of which cannot be achieved solely through increased use of renewables. Its green qualities make gas attractive in direct utilisation in homes and businesses, in centralised power generation, in local CHP plant (including micro-CHP), and - in some member states - in the transport sector too. The current slump in demand is accompanied by strong supply pressure on European procurement markets. Experts do not predict that the present excess supply situation will continue in the long term. It is expected that imports to Europe will rise in order to compensate for the impending fall in domestic European production and to supply additional gas. The procurement challenge cannot be considered in isolation from global developments. The increasing demand for gas worldwide will intensify the competition for global gas reserves on international markets. The European gas industry emphasises the importance of fostering long-term relationships with major suppliers, transit countries and key partners in the EU as well as with multilateral organisations and structures.

  20. Report on the possibilities of long-term storage of irradiated nuclear fuels

    International Nuclear Information System (INIS)

    2001-01-01

    This report aims at giving a legislative aspect to the many rules that govern the activities of the back-end of the fuel cycle in France. These activities concern the unloading of spent nuclear fuels, their reprocessing, storage, recycling and definitive disposal. The following points are reviewed and commented: the management of non-immediately reprocessed fuels (historical reasons of the 'all wastes reprocessing' initial choice, evolution of the economic and political context, the future reprocessing or the definitive disposal of spent fuels in excess); the inevitable long-term storage of part of the spent fuels (quantities and required properties of long-term stored fuels, the eventuality of a definitive disposal of spent fuels); the criteria that long-term storage facilities must fulfill (confinement measures, reversibility, surveillance and control during the whole duration of the storage); storage concept to be retained (increase of storage pools capacity, long-term storage in pools of reprocessing plants, centralized storage in pools, surface dry-storage on power plant sites, reversible underground storage, subsurface storage and storage/disposal in galleries, surface dry-storage facilities); the preliminary studies for the creation of long-term storage facilities (public information, management by a public French organization, clarifying of the conditions of international circulation of spent fuels); problems linked with the presence of foreign spent fuels in France (downstream of the reprocessing cycle, foreign plutonium and wastes re-shipment); conclusions and recommendations. (J.S.)

  1. Analysis of fuel oxidation for long-term dry storage

    International Nuclear Information System (INIS)

    Dehaudt, Ph.

    1999-01-01

    Dry storage is one of the temporary end of life channels for PWR fuel assemblies after leaving the reactor. According to results of currently available digital simulations, the residual power will maintain at a temperature of over 150 degrees Celsius for several years for UO 2 and several decades for MOX. At such temperatures, the UO 2 , which constitutes the fuel wholly or partially (MOX) can oxidise in the presence of air to form the compound U 3 O 8 . The paper discusses parameters that influence the evolution of compounds formed as the reaction progresses, the morphological transformations accompanying their formation and the kinetic conditions according to the temperature and the nature of the initial products

  2. Report on the possibilities of long-term storage of irradiated nuclear fuels; Rapport sur les possibilites d'entreposage a long terme de combustibles nucleaires irradies

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    This report aims at giving a legislative aspect to the many rules that govern the activities of the back-end of the fuel cycle in France. These activities concern the unloading of spent nuclear fuels, their reprocessing, storage, recycling and definitive disposal. The following points are reviewed and commented: the management of non-immediately reprocessed fuels (historical reasons of the 'all wastes reprocessing' initial choice, evolution of the economic and political context, the future reprocessing or the definitive disposal of spent fuels in excess); the inevitable long-term storage of part of the spent fuels (quantities and required properties of long-term stored fuels, the eventuality of a definitive disposal of spent fuels); the criteria that long-term storage facilities must fulfill (confinement measures, reversibility, surveillance and control during the whole duration of the storage); storage concept to be retained (increase of storage pools capacity, long-term storage in pools of reprocessing plants, centralized storage in pools, surface dry-storage on power plant sites, reversible underground storage, subsurface storage and storage/disposal in galleries, surface dry-storage facilities); the preliminary studies for the creation of long-term storage facilities (public information, management by a public French organization, clarifying of the conditions of international circulation of spent fuels); problems linked with the presence of foreign spent fuels in France (downstream of the reprocessing cycle, foreign plutonium and wastes re-shipment); conclusions and recommendations. (J.S.)

  3. Report on the possibilities of long-term storage of irradiated nuclear fuels; Rapport sur les possibilites d'entreposage a long terme de combustibles nucleaires irradies

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    This report aims at giving a legislative aspect to the many rules that govern the activities of the back-end of the fuel cycle in France. These activities concern the unloading of spent nuclear fuels, their reprocessing, storage, recycling and definitive disposal. The following points are reviewed and commented: the management of non-immediately reprocessed fuels (historical reasons of the 'all wastes reprocessing' initial choice, evolution of the economic and political context, the future reprocessing or the definitive disposal of spent fuels in excess); the inevitable long-term storage of part of the spent fuels (quantities and required properties of long-term stored fuels, the eventuality of a definitive disposal of spent fuels); the criteria that long-term storage facilities must fulfill (confinement measures, reversibility, surveillance and control during the whole duration of the storage); storage concept to be retained (increase of storage pools capacity, long-term storage in pools of reprocessing plants, centralized storage in pools, surface dry-storage on power plant sites, reversible underground storage, subsurface storage and storage/disposal in galleries, surface dry-storage facilities); the preliminary studies for the creation of long-term storage facilities (public information, management by a public French organization, clarifying of the conditions of international circulation of spent fuels); problems linked with the presence of foreign spent fuels in France (downstream of the reprocessing cycle, foreign plutonium and wastes re-shipment); conclusions and recommendations. (J.S.)

  4. Mexico's long-term energy outlook : results of a detailed energy supply and demand simulation

    International Nuclear Information System (INIS)

    Conzelmann, G.; Quintanilla, J.; Conde, L.A.; Fernandez, J.; Mar, E.; Martin del Campo, C.; Serrato, G.; Ortega, R.

    2006-01-01

    This article discussed the results of a bottom-up analysis of Mexico's energy markets which was conducted using an energy and power evaluation program. The program was used to develop energy market forecasts to the year 2025. In the first phase of the study, dynamic optimization software was used to determine the optimal, least-cost generation system expansion path to meet growing demand for electricity. A separate model was used to determine the optimal generating strategy of mixed hydro-thermal electric power systems. In phase 2, a nonlinear market-based approach was used to determine the energy supply and demand balance for the entire energy system, as well as the response of various segments of the energy system to changes in energy price and demand levels. Basic input parameters included information on the energy system structure; base-year energy statistics; and, technical and policy constraints. A total of 14 scenarios were modelled to examine variations in load growth, sensitivities to changes in projected fuel prices, variations in assumed natural gas availability, system reliability targets, and the potential for additional nuclear capacity. Forecasts for the entire energy system were then developed for 4 scenarios: (1) reference case; (2) limited gas scenario; (3) renewable energy; and (4) additional nuclear power generation capacity. Results of the study showed that Mexico's crude oil production is projected to increase annually by 1 per cent to 2025. Imports of petroleum products resulting from the country's rapidly growing transportation sector will increase. Demand for natural gas is expected to outpace projected domestic production. The long-term market outlook for Mexico's electricity industry shows a heavy reliance on natural gas-based generating technologies. It was concluded that alternative results for a constrained-gas scenario showed a substantial shift to coal-based generation and associated effects on the natural gas market. 4 refs., 26

  5. Long-term energy supply contracts in European competition policy: Fuzzy not crazy

    International Nuclear Information System (INIS)

    Hauteclocque, Adrien de; Glachant, Jean-Michel

    2009-01-01

    Long-term supply contracts often have ambiguous effects on the competitive structure, investment and consumer welfare in the long term. In the new market context, these effects are likely to be worsened and thus even harder to assess. Since liberalization and especially since the release of the Energy Sector Inquiry in early 2007, the portfolio of long-term supply contracts of the former incumbents have become a priority for review by the European Commission and the national competition authorities. It is widely believed that European Competition authorities take a dogmatic view on these contracts and systemically emphasize the risk of foreclosure over their positive effects on investment and operation. This paper depicts the methodology that has emerged in the recent line of cases and argues that this interpretation is largely misguided. It shows that a multiple-step approach is used to reduce regulation costs and balance anti-competitive effects with potential efficiency gains. However, if an economic approach is now clearly implemented, competition policy is constrained by the procedural aspect of the legal process and the remedies imposed remain open for discussion.

  6. Long Term Performance Study of a Direct Methanol Fuel Cell Fed with Alcohol Blends

    OpenAIRE

    Teresa J. Leo; Miguel A. Raso; Emilio Navarro; Eleuterio Mora

    2013-01-01

    The use of alcohol blends in direct alcohol fuel cells may be a more environmentally friendly and less toxic alternative to the use of methanol alone in direct methanol fuel cells. This paper assesses the behaviour of a direct methanol fuel cell fed with aqueous methanol, aqueous ethanol and aqueous methanol/ethanol blends in a long term experimental study followed by modelling of polarization curves. Fuel cell performance is seen to decrease as the ethanol content rises, and subsequent opera...

  7. Canada's plan for the long-term management of used nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Shaver, K. [Nuclear Waste Management Organization, Toronto, ON (Canada)

    2015-07-01

    Our mission is to develop and implement collaboratively with Canadians, a management approach for the long-term care of Canada's used nuclear fuel that is socially acceptable, technically sound, environmentally responsible, and economically feasible. The technical method is for Isolation of used nuclear fuel in deep geological repository with continuous monitoring and potential for retrievability.

  8. Short, medium and long term consequences of inadequate defect fuel management

    Energy Technology Data Exchange (ETDEWEB)

    Roberts, J.G. [CANTECH Associates Limited, Burlington, Ontario (Canada); Nashiem, R.; McQueen, M.; Ma, G. [Bruce Power, Tiverton, Ontario (Canada)

    2011-07-01

    Defect fuel pencils result in short, medium and long term consequences to the environment within and external to the nuclear power station. The paper will describe these consequences and specify the Defect Fuel Management Practices required to avoid these consequences. (author)

  9. Short, medium and long term consequences of inadequate defect fuel management

    International Nuclear Information System (INIS)

    Roberts, J.G.; Nashiem, R.; McQueen, M.; Ma, G.

    2011-01-01

    Defect fuel pencils result in short, medium and long term consequences to the environment within and external to the nuclear power station. The paper will describe these consequences and specify the Defect Fuel Management Practices required to avoid these consequences. (author)

  10. Short, medium and long term consequences of inadequate defect fuel management

    Energy Technology Data Exchange (ETDEWEB)

    Roberts, J.G., E-mail: alchemy@tnt21.com [CANTECH Associates Ltd., Burlington, Ontario (Canada); Nashiem, R.; McQueen, M.; Ma, G., E-mail: Rod.nashiem@brucepower.com, E-mail: Maureen.mcqueen@brucepower.com, E-mail: guoping.ma@brucepower.com [Bruce Power, Tiverton (Canada)

    2010-07-01

    Defect fuel pencils result in short, medium and long term consequences to the environment within and external to the nuclear power station. The paper will describe these consequences and specify the Defect Fuel Management Practices required to avoid these consequences. (author)

  11. Short, medium and long term consequences of inadequate defect fuel management

    International Nuclear Information System (INIS)

    Roberts, J.G.; Nashiem, R.; McQueen, M.; Ma, G.

    2010-01-01

    Defect fuel pencils result in short, medium and long term consequences to the environment within and external to the nuclear power station. The paper will describe these consequences and specify the Defect Fuel Management Practices required to avoid these consequences. (author)

  12. Spent fuel, plutonium and nuclear waste: long-term management; Le combustible use et le plutonium en tant que dechets nucleaires: gestion a long terme

    Energy Technology Data Exchange (ETDEWEB)

    Collard, G

    1998-11-01

    Different options for the management of nuclear waste arising from the nuclear fuel cycle are discussed. Special emphasis is on reprocessing followed by geological disposal, geological disposal of reprocessing waste, direct geological disposal of spent nuclear fuel, long term storage. Particular emphasis is on the management of plutonium including recycling, immobilisation and disposal, partitioning and transmutation.

  13. A review of 'long-term energy supply and demand outlook'

    International Nuclear Information System (INIS)

    Hoshino, Yuko; Hamagata, Sumio; Nagata, Yutaka

    2016-01-01

    In this paper, we reviewed the 'Long-term Energy Supply and Demand Outlook' based on our original Japan's Economy and Energy Outlook toward 2030. 'The Long-term Energy Supply and Demand Outlook' was based on the following three basic policies: (1) Energy self-sufficiency rate in 2030 should be around 25 percent. (2) Electricity Costs in 2030 should be lower than the current level in 2013. (3) Emissions target of GHGs in 2030 should not be lower than that of EU and the US. Moreover, there were many assumptions or constraints, such as assumed economic growth rate consistent to the government's macro-economic policy and the share of renewable energy more than 20 percent. In order to satisfy the above mentioned conditions, an extraordinary energy saving should be implemented in the scenario. The assumed intensity of energy saving is as much as that after the two oil crises. We estimated the cost of that magnitude of energy saving based on our model simulation, which revealed that in order to achieve the energy saving target, the electricity price should be 80% higher than the business as usual case. In addition, we reviewed the long-term energy supply and demand scenarios of major developed countries such as the UK, the US, Italy, Germany and Australia. We found that most of the scenarios depend on a large scale of energy saving in order to achieve the GHG emissions reductions targets. The reality of those energy saving targets should be carefully re-examined under the low oil price environment. (author)

  14. The role and position of nuclear energy in the long-term energy supply of China

    International Nuclear Information System (INIS)

    Bao Yunqiao

    1992-03-01

    The history for development of world nuclear energy and policies in various countries are retrospected, and the development of world nuclear energy is reviewed. On the basis of analysis for the economy of nuclear power in abroad, it is verified that the cost of nuclear power is cheaper than that of coal-fired power. In the future, the nuclear power is still competitive in economy. The prospect for long-term energy supply in China is predicted on the present situation of energy industry. It is estimated that the gap between energy demands and supply will become larger and larger. The solution is to develop nuclear energy in south-east area. The long-term demands of electricity and electrical resources are estimated in China, and if nuclear energy is utilized, it will optimize the constitution of electricity. The economy of nuclear power is also evaluated. It is expected that the nuclear power will be cheaper than that of coal-fired power in China after equipment are made domestically and serially. From the analysis of the conditions of communication, transportation and pollution, the development of nuclear energy will reduce the tension of transportation and improve the environmental quality. Finally, the prospect of developing nuclear heating and the supply level of uranium resources in China are analyzed

  15. Backup Sourcing Decisions for Coping with Supply Disruptions under Long-Term Horizons

    Directory of Open Access Journals (Sweden)

    Jing Hou

    2016-01-01

    Full Text Available This paper studies a buyer’s inventory control problem under a long-term horizon. The buyer has one major supplier that is prone to disruption risks and one backup supplier with higher wholesale price. Two kinds of sourcing methods are available for the buyer: single sourcing with/without contingent supply and dual sourcing. In contingent sourcing, the backup supplier is capacitated and/or has yield uncertainty, whereas in dual sourcing the backup supplier has an incentive to offer output flexibility during disrupted periods. The buyer’s expected cost functions and the optimal base-stock levels using each sourcing method under long-term horizon are obtained, respectively. The effects of three risk parameters, disruption probability, contingent capacity or uncertainty, and backup flexibility, are examined using comparative studies and numerical computations. Four sourcing methods, namely, single sourcing with contingent supply, dual sourcing, and single sourcing from either of the two suppliers, are also compared. These findings can be used as a valuable guideline for companies to select an appropriate sourcing strategy under supply disruption risks.

  16. Electricity and long term supply security. Search for power market respectful legal instruments

    International Nuclear Information System (INIS)

    Finon, D.; Pignon, V.

    2006-01-01

    This paper, also published in 'ISMEA Economie et Societe' Journal (Energy series 2006, no.10), deals with theoretical aspects of long term electricity supply security. Market prices and contractual arrangements on the physical and financial electricity markets do not allow to create sufficient incentives to invest in adequate capacity for guaranteeing the appropriate level of supply in every circumstance. The long term security of supply by capacity adequacy must be conceptualized as a collective good. Alternative solutions to reach capacity adequacy which have been adopted in different markets are successively considered: public procurement of strategic reserves, capacity payment, capacity obligation with exchangeable rights. Each one presents theoretical limits and practical drawbacks when implemented in complex markets. That brings out the interest of mechanism of centralized auctions for forward capacity contracts (or reliability options); it combines controls by quantity and by price while stabilizing investment in peak power plants and is compatible with energy and reserves markets, that is not the case of the three other instruments. (authors)

  17. Criteria for recladding of spent light water reactor fuel before long term pool storage

    International Nuclear Information System (INIS)

    Pettersson, K.; Jansson, L.

    1979-01-01

    The question of the need for any special treatment of failed fuel elements prior to long term pool storage has been studied. It is concluded that the main problem appears to be hydride embrittlement of failed fuel rods, which may lead to increased damage during handling and transport of the failed fuel. Some mechanisms for the degradation of failed fuel rods have been identified. They can all be considered as relatively improbable, but further experimental evidence is needed before it can be concluded that these degradation mechanisms are insignificant during pool storage. The report also contains a review of methods for identification of leaking fuel bundles and fuel rods. (Auth.)

  18. Criteria for recladding of spent light water reactor fuel before long term pool storage

    International Nuclear Information System (INIS)

    Pettersson, K.; Jansson, L.

    1979-06-01

    The question of the need for any special treatment of failed fuel elements prior to long term pool storage has been studied. It is concluded that the main problem appears to be hydride embrittlement of failed fuel rods, which may lead to increased damage during handling and transport of the failed fuel. Some mechanisms for the degradation of failed fuel rods have been identified. They can all be considered as relatively improbable, but further experimental evidence is needed before it can be concluded that thede degradation mechanisms are insignificant during pool storage. The report also contains a review of methods for identification of leaking fuel bundles and fuel rods.(author)

  19. Medium and long-term supply of the FRG with natural uranium

    Energy Technology Data Exchange (ETDEWEB)

    Stephany, M

    1976-08-01

    A short survey is presented of the situation concerning the FRG's uranium supply taking into special consideration the economical aspects. Characteristic for the demand-supply-situation is the fact that the development of prices does not influence the costs as much as this is the case with other fuels, and that assurance of supply for the FRG is underpinned by participation in foreign enterprises.

  20. Formulating an optimal long-term energy supply strategy for Syria using MESSAGE model

    International Nuclear Information System (INIS)

    Hainoun, A.; Seif Aldin, M.; Almoustafa, S.

    2010-01-01

    An optimal long-term energy supply strategy has been formulated based on minimizing the total system costs for the entire study period 2003-2030. The national energy chain was modelled covering all energy levels and conversion technologies. The results indicate that the primary energy will grow at annual average rate of 4.8% arriving 68 Mtoe in 2030. The total installed electric capacity will be optimally expanded from 6885 to 19500 MW in 2030. Furthermore, to ensure supply security the future national energy system will rely mainly upon oil and natural gas (NG) with limited contribution of renewables and nuclear to the end of study period. The share of NG will increase gradually up to 2020 and then retreat. Owing to the continuous decrease of oil production, oil export is expected to vanish in 2012 and the country will import about 63% of its primary energy demand in 2030. Thus, the expected long-term development of national energy sector indicates a hard challenge for the future national economy. The employing of sensitivity analysis clarifies the importance of wind turbines operation time and discount rate. The analysis proves that nuclear option is insensitive to overnight cost increase up to 85% of the reference case value.

  1. Long term natural gas supply in North America: prospects for mexican exports

    International Nuclear Information System (INIS)

    Elizalde Baltierra, A.

    1999-01-01

    The aim of this work is to discuss the most important factors and uncertainties likely to affect future Mexican natural gas exports to the United States. Firstly, we study the long term natural gas supply/demand balance in North America over the period from 2000 to 2020. Secondly, we analyze the main driving forces determining future natural gas supply and demand in Mexico, which also allows us to discuss the prospects for Mexican gas exports. Finally, our analysis suggests that: in the short and medium term (2000-2010), Mexico will probably continue to increase imports of USA gas in order to satisfy increasing demand and will probably not export large volumes of gas to the USA; in the long term (2020-2020), Mexico could resume exports to the USA in sizeable quantities. Two main conditions appear necessary to resume exports: Premex's budgetary constraints should be relaxed and/or new foreign investment should be able to participate in the Mexican upstream oil and gas sector. (author)

  2. Development of oil supply and demand planning model for mid- and long-term

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sung Hyun [Korea Energy Economics Institute, Euiwang (Korea)

    1997-10-01

    Despite the liberalization of oil market, a systematic model is required for reasonable supply and demand of oil, which still has an important influence on industry and state economy. It is required a demand model deriving prospects of each sector and product and a supply model examining the optimum rate of operation, production mix of products, stock, export and import, and the size of equipment investment to meet given demand. As the first phase for the development of supply and demand model, the existing oil and energy models in domestic and overseas were reviewed and recommendations for establishing a Korean oil supply and demand model were derived in this study. Based on these, a principle for establishing a model and a rough framework were set up. In advance of mid- and long-term prospects, a short-term prospect model was established and the short-term prospects for the first quarter of 1999 and for the year 1999 were presented on trial. Due to the size and characters of a supply model, a plan for an ideal model was first explained and then a plan for creating a model step by step was presented as a realistic scheme. (author). 16 refs., 9 figs., 19 tabs.

  3. Long-Term Groundwater Monitoring Optimization, Clare Water Supply Superfund Site, Permeable Reactive Barrier and Soil Remedy Areas, Clare, Michigan

    Science.gov (United States)

    This report contains a review of the long-term groundwater monitoring network for the Permeable Reactive Barrier (PRB) and Soil Remedy Areas at the Clare Water Supply Superfund Site in Clare, Michigan.

  4. Long term integrity of spent fuel and construction materials for dry storage facilities

    Energy Technology Data Exchange (ETDEWEB)

    Saegusa, T [CRIEPI (Japan)

    2012-07-01

    In Japan, two dry storage facilities at reactor sites have already been operating since 1995 and 2002, respectively. Additionally, a large scale dry storage facility away from reactor sites is under safety examination for license near the coast and desired to start its operation in 2010. Its final storage capacity is 5,000tU. It is therefore necessary to obtain and evaluate the related data on integrity of spent fuels loaded into and construction materials of casks during long term dry storage. The objectives are: - Spent fuel rod: To evaluate hydrogen migration along axial fuel direction on irradiated claddings stored for twenty years in air; To evaluate pellet oxidation behaviour for high burn-up UO{sub 2} fuels; - Construction materials for dry storage facilities: To evaluate long term reliability of welded stainless steel canister under stress corrosion cracking (SCC) environment; To evaluate long term integrity of concrete cask under carbonation and salt attack environment; To evaluate integrity of sealability of metal gasket under long term storage and short term accidental impact force.

  5. High level radioactive wastes storage characterization and long-term behaviour of spent fuels

    International Nuclear Information System (INIS)

    Diaz Arocas, P.P.; Garcia Serrano, J.; Mendez Martin, F.J.; Quinones Diez, J.; Rodriguez Almazan, J.L.; Serrano Agejas, J.A.; Esteban Hernandez, J.A.

    1997-04-01

    The knowledge of long term spent fuel behaviour in a repository is one of the main goals in the waste management assessment due to its influence on repository design topics and on the performance assessment. At the moment, Spain has not selected a geological formation for a final repository. Therefore, R AND D activities are performed by considering granite, salt and clay as candidate options. This report summarises the activities carried out in CIEMAT from 1991 to 1995 in the frame of the Agreement between CIEMAT and ENRESA in the Area of spent fuel direct disposed. Experimental activities include leaching experiments of spent fuel, UO 2 and SIMFUEL and co-precipitation/solubility experiments of relevant secondary solid phases expected under repository conditions. The objective of leaching studies is to understand the processes which will occur when the underground water accede to the source term and to provide leaching rates of spent fuel and the influence of several variables as pH, Eh, etc. The co-precipitation/solubility experiments are focused on the knowledge of the formation conditions of relevant secondary phases, to characterise these phases and to determine their solubility, which could control the leaching of spent fuel. One of the main items to carry out the objectives before indicated in both leaching and co-precipitation/solubility experiments is to perform a extensive solid phases characterisation in order to facilitate the understanding of the processes involved. This report is structured in three parts, the first include experimental procedures, characterisation techniques and solid and solution analyses. The second shows the leaching results obtained by considering the effect of pH, complex formation, redox conditions, surface/volume ratio, etc. The third supply the results of the co-precipitation/solubility studies. The conclusions obtained in this work are considered as the start point of going on and more extensive studies on the mechanisms

  6. Metabolic modelling to support long term strategic decisions on water supply systems

    Science.gov (United States)

    Ciriello, Valentina; Felisa, Giada; Lauriola, Ilaria; Pomanti, Flavio; Di Federico, Vittorio

    2017-04-01

    Water resources are essential for the economic development and sustenance of anthropic activities belonging to the civil, agricultural and industrial sectors. Nevertheless, availability of water resources is not uniformly distributed in space and time. Moreover, the increasing water demand, mainly due to population growth and expansion of agricultural crops, may cause increasing water stress conditions, if combined with the effects of climate change. Under these circumstances, it is necessary to improve the resilience of water supply systems both in terms of infrastructures and environmental compliance. Metabolic modelling approaches represent a flexible tool able to provide support to decision making in the long term, based on sustainability criteria. These approaches mimic the water supply network through a set of material and energy fluxes that interact and influence each other. By analyzing these fluxes, a suite of key performance indicators is evaluated in order to identify which kind of interventions may be applied to increase the sustainability of the system. Here, we adopt these concepts to analyze the water supply network of Reggio-Emilia (Italy) which is supported by water withdrawals from both surface water and groundwater bodies. We analyze different scenarios, including possible reduction of water withdrawals from one of the different sources as a consequence of a decrease in water availability under present and future scenarios. On these basis, we identify preventive strategies for a dynamic management of the water supply system.

  7. Long term Gas Supply Security in an Enlarged Europe. Final Report ENGAGED Project

    International Nuclear Information System (INIS)

    Van Oostvoorn, F.; Likachev, V.; Morgan, T.

    2004-12-01

    The title project concerned a study on the long-term gas supply security in Europe with a focus on the developments, risks and policies in the candidate countries in Eastern Europe. For that reason the report not only includes a European and EU-30 wide scenario analysis but also chapters on specific topics. One study (a chapter in this report) concerns the gas market and regulation developments in a number of relevant candidate countries. Another chapter presents a Russian vision on gas demand, production and supplies from Russia and also includes a paragraph on the supplies from other neighbours and the transit issues in the Ukraine. Finally, the report contains a chapter discussing the required network infrastructure for bringing the gas from external gas suppliers to the EU-30 markets. Hereby it analysis and tests the network flexibility to cope with some unlikely and unexpected supply interruptions in main pipelines to EU markets. The background information of the studies underlying the chapters can be partly found in the annexes and in the individual task reports. During the project the results of the study were discussed at several seminars in candidate countries and particularly on the final seminar in Prague, in June 2003, with different and important stakeholders and market actors

  8. Practice variation in the Dutch long-term care and the role of supply-sensitive care: Is access to the Dutch long-term care equitable?

    Science.gov (United States)

    Duell, Daisy; Koolman, Xander; Portrait, France

    2017-12-01

    Universal access and generous coverage are important goals of the Dutch long-term care (LTC) system. It is a legal requirement that everyone eligible for LTC should be able to receive it. Institutional care (IC) made up for 90% of Dutch LTC spending. To investigate whether access to IC is as equitable as the Dutch government aspires, we explored practice variation in entitlements to IC across Dutch regions. We used a unique dataset that included all individual applications for Dutch LTC in January 2010-December 2013 (N = 3,373,358). This dataset enabled an accurate identification of the need for care. We examined the local variation in the probability of being granted long-term IC and in the intensity of the care granted given that individuals have applied for LTC. We also investigated whether the variation observed was related to differences in the local availability of care facilities. Although our analyses indicated the presence of some practice variation, its magnitude was very small by national and international standards (up to 3%). Only a minor part of the practice variation could be accounted for by local supply differences in care facilities. Overall, we conclude that, unlike many other developed countries, the Dutch system ensured equitable access to long-term IC. © 2017 The Authors. Health Economics Published by John Wiley & Sons Ltd.

  9. Automatic estimation of aquifer parameters using long-term water supply pumping and injection records

    Science.gov (United States)

    Luo, Ning; Illman, Walter A.

    2016-09-01

    Analyses are presented of long-term hydrographs perturbed by variable pumping/injection events in a confined aquifer at a municipal water-supply well field in the Region of Waterloo, Ontario (Canada). Such records are typically not considered for aquifer test analysis. Here, the water-level variations are fingerprinted to pumping/injection rate changes using the Theis model implemented in the WELLS code coupled with PEST. Analyses of these records yield a set of transmissivity ( T) and storativity ( S) estimates between each monitoring and production borehole. These individual estimates are found to poorly predict water-level variations at nearby monitoring boreholes not used in the calibration effort. On the other hand, the geometric means of the individual T and S estimates are similar to those obtained from previous pumping tests conducted at the same site and adequately predict water-level variations in other boreholes. The analyses reveal that long-term municipal water-level records are amenable to analyses using a simple analytical solution to estimate aquifer parameters. However, uniform parameters estimated with analytical solutions should be considered as first rough estimates. More accurate hydraulic parameters should be obtained by calibrating a three-dimensional numerical model that rigorously captures the complexities of the site with these data.

  10. Prediction of the Long Term Cooling Performance for the 3-Pin Fuel Test Loop

    Energy Technology Data Exchange (ETDEWEB)

    Park, S. K.; Chi, D. Y.; Sim, B. S.; Park, K. N.; Ahn, S. H.; Lee, J. M.; Lee, C. Y.; Kim, H. R

    2005-12-15

    In the long term cooling phase that the emergency cooling water injection ends, the performance of the residual heat removal for the 3-pin fuel test loop has been predicted by a simplified heat transfer model. In the long term cooling phase the residual heat is 1323W for PWR fuel test mode and 1449W for CANDU fuel test mode. The each residual heat is assumed as 2% of the fission power of the test fuel used in the anticipated operational occurrence and design basis accident analyses. The each fission power used for the analyses is 105% of the rated fission power in the normal operation. In the long term cooling phase the residual heat is removed to the HANARO pool through the double pressure vessels of the in-pile test section. Saturate pooling boiling is assumed on the test fuel and condensation heat transfer is expected on the inner wall of the fuel carrier and the flow divider. Natural convection heat transfer on a heated vertical wall is also assumed on the outer wall of the outer pressure vessel. The conduction heat transfer is only considered in the gap between the double pressure vessels charged with neon gas and in the downcomer filled with coolant. The heat transfer rate between the coolant temperature of 152 .deg. C in the in-pile test section and the water temperature of 45 .deg. C in the HANARO pool is predicted as about 1666W. The 152 .deg. C is the saturate temperature of the coolant pressure predicted from the MARS code. The cooling capacity of 1666W is greater than the residual heats of 1323W and 1449W. Consequently the long term cooling performance of the 3-pin fuel test loop is sufficient for the anticipated operational occurrences and design basis accidents.

  11. MTR spent fuel back-end - Cogema's long-term commitment

    International Nuclear Information System (INIS)

    Thomasson, J.

    1998-01-01

    MTR spent fuel back end has been subject to many reversal and uncertainties in the past 10 years. Until the end of 1988, US obligated materials were subject to the Off site Fuels Policy (OFP). Under this policy, spent fuels were returned to USA, and were reprocessed there. This OFP took end the 31th of December 1988, and Research Reactor's operators had to implement others solutions: On site storage or Reprocessing in Europe. Meanwhile the RERTR Program was leading to a new LEU fuel to replace HEU aluminide. This new silicide fuel has one main drawback: it cannot be reprocessed in working plants without some process main line modifications. Fortunately, a new Research Reactors spent fuels return policy has been set up by the US in the early 1996. This new policy applies to all reactors converted or that have agreed to convert to LEU, and reactors operating with HEU for which no suitable LEU is available. It covers all the spent fuels discharged until 2006/05/12. But after that period of time, each reactor will be fully responsible for its spent fuels. Since the end of 1996, COGEMA is proposing reprocessing services for Aluminides spent fuels, based on the La Hague capability. This COGEMA answer is for the long term, as the La Hague plant has a good load for the coming years, including the first decade of the next century. Further, this activity benefits from a strong R and D support, that allowed fulfilling the evolutive needs of our customers, and gives us the ability to adapt the plant to the future market. Taking advantage of this flexibility, COGEMA offers Research Reactors' operators a long-term commitment. Already two reactors' operators have chosen to contract with COGEMA for the whole life of their reactors. The contracts execution is under progress and the first transportation will take place soon. Beside today's services, COGEMA is involved in R and D activities to support new fuels development enhancing present LEU performances and having the ability to

  12. Assessment of spent WWER-440 fuel performance under long-term storage conditions

    Energy Technology Data Exchange (ETDEWEB)

    Takats, F [TS Enercon Kft. (Hungary)

    2012-07-01

    Paks Nuclear Power Plant is the only NPP in Hungary. It has four WWER-440 type reactor units. The fresh fuel is imported from Russia so far. The spent fuel assemblies were shipped back to Russia until 1997 after about 6 years cooling at the plant. A dry storage facility (MVDS type) has been constructed and is operational since then. By 1 January 2008, there were 5107 assemblies in dry storage. The objectives are: 1) Wet AR storage of spent fuel from the NPP Paks: Measurements of conditions for spent fuel storage in the at-reactor (AR) storage pools of Paks NPP (physical and chemical characteristics of pool water, corrosion product data); Measurements and visual control of storage pool component characteristics; Evaluation of storage characteristics and conditions with respect to long-term stability (corrosion of fuel cladding, construction materials); 2) Dry AFR storage at Paks NPP: Calculation and measurement of spent fuel conditions during the transfer from the storage pool to the modular vault dry storage (MVDS) on the site; Calculation and measurement of spent fuel conditions during the preparation of fuel for dry storage (drying process), such as crud release, activity build-up; Measurement of spent fuel conditions during the long-term dry storage, activity data in the storage tubes and amount of crud.

  13. Synthesis on the long term behavior of spent nuclear fuel. Vol.1,2

    International Nuclear Information System (INIS)

    Poinssot, Ch.; Toulhoat, P.; Grouiller, J.P.; Pavageau, J.; Piron, J.P.; Pelletier, M.; Dehaudt, Ph.; Cappelaere, Ch.; Limon, R.; Desgranges, L.; Jegou, Ch.; Corbel, C.; Maillard, S.; Faure, M.H.; Cicariello, J.C.; Masson, M.

    2001-01-01

    The aim of this report is to present the major objectives, the key scientific issues, and the preliminary results of the research conducted in France in the framework of the third line of the 1991 Law, on the topic of the long term behavior of spent nuclear fuel in view of long term storage or geological disposal. Indeed, CEA launched in 1998 the Research Program on the Long Term Behavior of Spent Nuclear Fuel (abbreviated and referred to as PRECCI in French; Poinssot, 1998) the aim of which is to study and assess the ability of spent nuclear fuel packages to keep their initially allocated functions in interim storage and geological disposal: total containment and recovery functions for duration up to hundreds of years (long term or short-term interim storage and/or first reversible stages of geological disposal) and partial confinement function (controlled fluxes of RN) for thousands of years in geological disposal. This program has to allow to obtain relevant and reliable data concerning the long term behavior of the spent fuel packages so that feasibility of interim storage and/or geological disposal can be assessed and demonstrated as well as optimized. Within this framework, this report presents for every possible scenario of evolution (closed system, in Presence of water in presence of gases) what are estimated to be the most relevant evolution mechanism. For the most relevant scientific issues hence defined, a complete scientific review of the best state of knowledge is subsequently here given thus allowing to draw a clear guideline of the major R and D issues for the next years. (authors)

  14. The long-term forecast of Taiwan's energy supply and demand: LEAP model application

    International Nuclear Information System (INIS)

    Huang, Yophy; Bor, Yunchang Jeffrey; Peng, Chieh-Yu

    2011-01-01

    The long-term forecasting of energy supply and demand is an extremely important topic of fundamental research in Taiwan due to Taiwan's lack of natural resources, dependence on energy imports, and the nation's pursuit of sustainable development. In this article, we provide an overview of energy supply and demand in Taiwan, and a summary of the historical evolution and current status of its energy policies, as background to a description of the preparation and application of a Long-range Energy Alternatives Planning System (LEAP) model of Taiwan's energy sector. The Taiwan LEAP model is used to compare future energy demand and supply patterns, as well as greenhouse gas emissions, for several alternative scenarios of energy policy and energy sector evolution. Results of scenarios featuring 'business-as-usual' policies, aggressive energy-efficiency improvement policies, and on-schedule retirement of Taiwan's three existing nuclear plants are provided and compared, along with sensitivity cases exploring the impacts of lower economic growth assumptions. A concluding section provides an interpretation of the implications of model results for future energy and climate policies in Taiwan. - Research highlights: → The LEAP model is useful for international energy policy comparison. → Nuclear power plants have significant, positive impacts on CO 2 emission. → The most effective energy policy is to adopt demand-side management. → Reasonable energy pricing provides incentives for energy efficiency and conservation. → Financial crisis has less impact on energy demand than aggressive energy policy.

  15. The long term storage of advanced gas-cooled reactor (AGR) fuel

    International Nuclear Information System (INIS)

    Standring, P.N.

    1999-01-01

    The approach being taken by BNFL in managing the AGR lifetime spent fuel arisings from British Energy reactors is given. Interim storage for up to 80 years is envisaged for fuel delivered beyond the life of the Thorp reprocessing plant. Adopting a policy of using existing facilities, to comply with the principles of waste minimisation, has defined the development requirements to demonstrate that this approach can be undertaken safely and business issues can be addressed. The major safety issues are the long term integrity of both the fuel being stored and structure it is being stored in. Business related issues reflect long term interactions with the rest of the Sellafield site and storage optimisation. Examples of the development programme in each of these areas is given. (author)

  16. Long term performance degradation analysis and optimization of anode supported solid oxide fuel cell stacks

    International Nuclear Information System (INIS)

    Parhizkar, Tarannom; Roshandel, Ramin

    2017-01-01

    Highlights: • A degradation based optimization framework is developed. • The cost of electricity based on degradation of solid oxide fuel cells is minimized. • The effects of operating conditions on degradation mechanisms are investigated. • Results show 7.12% lower cost of electricity in comparison with base case. • Degradation based optimization is a beneficial concept for long term analysis. - Abstract: The main objective of this work is minimizing the cost of electricity of solid oxide fuel cell stacks by decelerating degradation mechanisms rate in long term operation for stationary power generation applications. The degradation mechanisms in solid oxide fuel cells are caused by microstructural changes, reactions between lanthanum strontium manganite and electrolyte, poisoning by chromium, carburization on nickel particles, formation of nickel sulfide, nickel coarsening, nickel oxidation, loss of conductivity and crack formation in the electrolyte. The rate of degradation mechanisms depends on the cell operating conditions (cell voltage and fuel utilization). In this study, the degradation based optimization framework is developed which determines optimum operating conditions to achieve a minimum cost of electricity. To show the effectiveness of the developed framework, optimization results are compared with the case that system operates at its design point. Results illustrate optimum operating conditions decrease the cost of electricity by 7.12%. The performed study indicates that degradation based optimization is a beneficial concept for long term performance degradation analysis of energy conversion systems.

  17. Managing aging effects on used fuel dry cask for very long-term storage - 59067

    International Nuclear Information System (INIS)

    Chopra, Omesh; Diercks, Dwight; Ma, David; Shah, Vikram; Tam, Shiu-Wing; Fabian, Ralph; Liu, Yung; Nutt, Mark

    2012-01-01

    The cancellation of the Yucca Mountain repository program in the Unites States raises the prospect of very long-term storage (i.e., >120 years) and deferred transportation of used fuel at the nuclear power plant sites. While long-term storage of used nuclear fuel in dry cask storage systems (DCSSs) at Independent Spent Fuel Storage Installations (ISFSIs) is already a standard practice among U.S. utilities, recent rule-making activities of the U.S. Nuclear Regulatory Commission (NRC) indicated additional flexibility for the NRC licensees of ISFSIs and certificate holders of the DCSSs to request initial and renewal terms for up to 40 years. The proposed rule also adds a requirement that renewal applicants must provide descriptions of aging management programs (AMPs) and time-limited aging analyses (TLAAs) to ensure that the structures, systems, and components (SSCs) that are important to safety in the DCSSs will perform as designed under the extended license terms. This paper examines issues related to managing aging effects on DCSSs for very long-term storage (VLTS) of used fuels, capitalizing on the extensive knowledge and experience accumulated from the work on aging research and life cycle management at Argonne National Laboratory (ANL) over the last 30 years. The technical basis for acceptable AMPs and TLAAs is described, as are generic AMPs and TLAAs that are being developed by Argonne under the support of the U.S. Department of Energy (DOE) Used Fuel Disposition Campaign for R and D on extended long-term storage and transportation. (authors)

  18. The COMURHEX 2 project. Investing in UF6 long-term security of supply

    International Nuclear Information System (INIS)

    Bouzon, Pierre; Lacombe, Philippe; Durante, Pierre; Teyssier, Patrick

    2008-01-01

    The front-end nuclear fuel supply chain for LWRs encompasses four major industrial stages that are mining and concentration, conversion, enrichment, and eventually fuel fabrication. The different stages involve uranium in different chemical and physical forms. Enrichment of the 235-U fissile isotope requires gaseous UF6. As the standard output of mine is U3O8, referred to as ''yellow cake'', a purely chemical stage is therefore needed to fluorinate U3O8 and turn it into UFe: this is the conversion stage. U3O8 inventories management is thus performed at the conversion sites.Purification of the mining concentrates is also needed prior to actual conversion into UFe. This step is important because the front-end supply chain facilities have strict specifications concerning impurities. The conversion stage may involve intermediary products, namely UO3 and/or UF4, depending on the industrial scheme implemented. With the Comurhex 2 project, AREVA is not only shaping the future of conversion market and contributing to the security of supply of its customers, but it is also developing innovative techniques and reorganizing the conversion process steps. Providing such guaranteed and valuable conversion supply with a brand new plant is our strong commitment to a sustainable nuclear fuel cycle. And AREVA is the first that has launched such a project, looking further ahead. The three main axes of sustainable development, economical, social, and environmental, are truly taken into account in the development of the new project.

  19. Developing and analyzing long-term fuel management strategies for an advanced Small Modular PWR

    Energy Technology Data Exchange (ETDEWEB)

    Hedayat, Afshin, E-mail: ahedayat@aeoi.org.ir

    2017-03-15

    Highlights: • Comprehensive introduction and supplementary concepts as a review paper. • Developing an integrated long-term fuel management strategy for a SMR. • High reliable 3-D core modeling over fuel pins against the traditional LRM. • Verifying the expert rules of large PWRs for an advanced small PWR. • Investigating large numbers of safety parameters coherently. - Abstract: In this paper, long-term fuel management (FM) strategies are introduced and analyzed for a new advanced Pressurized Light Water Reactor (PWR) type of Small Modular Reactors (SMRs). The FM strategies are developed to be safe and practical for implementation as much as possible. Safety performances, economy of fuel, and Quality Assurance (QA) of periodic equilibrium conditions are chosen as the main goals. Flattening power density distribution over fuel pins is the major method to ensure safety performance; also maximum energy output or permissible discharging burn up indicates economy of fuel fabrication costs. Burn up effects from BOC to EOC have been traced, studied, and highly visualized in both of transport lattice cell calculations and diffusion core calculations. Long-term characteristics are searched to gain periodical equilibrium characteristics. They are fissile changes, neutron spectrum, refueling pattern, fuel cycle length, core excess reactivity, average, and maximum burn up of discharged fuels, radial Power Peaking Factors (PPF), total PPF, radial and axial power distributions, batch effects, and enrichment effects for fine regulations. Traditional linear reactivity model have been successfully simulated and adapted via fine core and burn up calculations. Effects of high burnable neutron poison and soluble boron are analyzed. Different numbers of batches via different refueling patterns have been studied and visualized. Expert rules for large type PWRs have been influenced and well tested throughout accurate equilibrium core calculations.

  20. Perspective of long term demand and supply of energy and general inspection of energy policy

    International Nuclear Information System (INIS)

    1983-01-01

    Since the oil crisis, Japanese energy policy was promoted to get rid of the excess dependence on petroleum and to attain energy security, but energy situation largely changed during the past ten years, and it has become necessary to make general inspection on the long term demand and supply of energy and the energy policy. After the second oil crisis, the worldwide demand of petroleum decreased drastically due to the rapid price rise, and the base price of crude oil was lowered for the first time. It is necessary to positively endeavor to reduce energy cost with new idea. The points of the general inspection are the correspondence of the energy policy to the large structural change of energy, the most desirable system for attaining the optimum structure of energy demand and supply and the utilization of market mechanism as far as possible. This report is the results of discussion held eight times since April, 1983. The change of energy situation in Japan and abroad and the perspective, the new problems in energy countermeasures and the trend of response, the preferential and effective promotion of general energy countermeasures and so on are reported. This report shows the fundamental direction of energy countermeasures hereafter, and the concrete and special examination must be made on many remaining problems. (Kako, I.)

  1. Assessment of spent WWER-440 fuel performance under long-term storage conditions

    Energy Technology Data Exchange (ETDEWEB)

    Kupca, L [VUJE Inc. (Slovakia)

    2012-07-01

    In the Slovak Republic are under operation 6 units (4 in the Jaslovske Bohunice site, and 2 in the Mochovce), 2 units are under construction in Mochovce site. All units are WWER-440 type. The fresh fuel is imported from the Russian Federation. The spent fuel assemblies are stored in wet conditions in Bohunice Interim Storage Spent Fuel Facility (SFIS). By 15 July 2008, there were 8413 assemblies in SFIS. The objectives are: 1) Wet AR storage of spent fuel from the NPP Bohunice and Mochovce: Surveillance of conditions for spent fuel storage in the at-reactor (AR) storage pools of both NPP's (characteristics of pool water, corrosion product data); Visual control of storage pool components; Evaluation of storage conditions with respect to long-term stability (corrosion of fuel cladding, structural materials); 2) Wet SFIS storage at Bohunice: Measurement of spent fuel conditions during the long-term wet storage, activity data in the storage casks and amount of crud; Surveillance program for SFIS structural materials.

  2. Untangling Risk in Water Supply Systems: What Factors Drive Long-term Adaptation?

    Science.gov (United States)

    Zeff, H. B.; Lin, L.; Band, L. E.; Reed, P. M.; Characklis, G. W.

    2016-12-01

    Deeply uncertain factors like climate change, the hydrologic impacts of urbanization, forest evolution, and long-term demand forecasts make water supply planning a `wicked' problem. The traditional technique of assessing risk based on historical observations can be inadequate in the face of environmental non-stationarity. However, competing models and limited observational data make it difficult for decision makers and experts to agree on how much uncertainty should be built into analyses of risk, particularly at the timescales relevant to long-term investments in water infrastructure. Further, the physical connectivity of these deeply uncertain processes create inter-related systems, amplifying the challenges of a `worst case scenario'. The development of adaptive systems and planning processes provide solutions that have been shown to meet technical, environmental, and social objectives at lower costs. Instead of developing plans with fixed targets for the timing of actions, adaptive plans develop risk metrics and thresholds that are able to integrate new information to determine when conditions reach a `tipping point' which necessitates action. It is an open question as to how new information can be best integrated into the decision-making process (i.e. how much weight do we give new observations relative to the historical record), but a better understanding of the way the relevant systems are expected to evolve and change over time could inform these decisions. In this study, we use linked, dynamic models of temperature and precipitation changes, forest evolution, urbanization, hydrology, and water demand to develop scenarios for an adaptive water management framework that uses risk-based metrics to make short- and long-term decisions. The impact of individual environmental processes on the adaptive capability of this management framework is evaluated through problem formulations that successively increase the complexity of the uncertainty scenarios. Although

  3. Technoeconomic assumptions adopted for the development of a long-term electricity supply model for Cyprus.

    Science.gov (United States)

    Taliotis, Constantinos; Taibi, Emanuele; Howells, Mark; Rogner, Holger; Bazilian, Morgan; Welsch, Manuel

    2017-10-01

    The generation mix of Cyprus has been dominated by oil products for decades. In order to conform with European Union and international legislation, a transformation of the supply system is called for. Energy system models can facilitate energy planning into the future, but a large volume of data is required to populate such models. The present data article provides information on key modelling assumptions and input data adopted with the aim of representing the electricity supply system of Cyprus in a separate research article. Data in regards to renewable energy technoeconomic characteristics and investment cost projections, fossil fuel price projections, storage technology characteristics and system operation assumptions are described in this article.

  4. Implications of alpha-decay for long term storage of advanced heavy water reactor fuels

    International Nuclear Information System (INIS)

    Pencer, J.; McDonald, M.H.; Roubtsov, D.; Edwards, G.W.R.

    2017-01-01

    Highlights: •Alpha decays versus storage time are calculated for examples of advanced heavy water reactor fuels. •Estimates are made for fuel swelling and helium bubble formation as a function of time. •These predictions are compared to predictions for natural uranium fuel. •Higher rates of damage are predicted for advanced heavy water reactor fuels than natural uranium. -- Abstract: The decay of actinides such as 238 Pu, results in recoil damage and helium production in spent nuclear fuels. The extent of the damage depends on storage time and spent fuel composition and has implications for the integrity of the fuels. Some advanced nuclear fuels intended for use in pressurized heavy water pressure tube reactors have high initial plutonium content and are anticipated to exhibit swelling and embrittlement, and to accumulate helium bubbles over storage times as short as hundreds of years. Calculations are performed to provide estimates of helium production and fuel swelling associated with alpha decay as a function of storage time. Significant differences are observed between predicted aging characteristics of natural uranium and the advanced fuels, including increased helium concentrations and accelerated fuel swelling in the latter. Implications of these observations for long term storage of advanced fuels are discussed.

  5. Characterizing and packaging BN-350 spent fuel for long-term dry storage

    International Nuclear Information System (INIS)

    Lambert, J. D. B.; Bolshinsky, I.; Haues, S.L.; Allen, K.J.; Howden, E.A.; Hill, R.N.; Planchon, H.P.; Staples, P.; Karaulov, V.N.; Blynskij, A.P.; Yakovlev, I.K.; Maev, V.; Dumchev, I. A.

    2000-01-01

    The Republic of Kazakhstan is being assisted by the U.S. Department of Energy in preparing spent fuel from the BN-350 fast reactor for long term dry storage. Argonne National Laboratory was assigned responsibility for the physical and nuclear characterization of the spent fuel, for the design and safety analysis of 6-pac and 4-pac canisters used to contain spent fuel assemblies for storage, and for the design, testing and installation of a closure station at the reactor in which the canisters of fuel are dried, filled with inert gas and welded shut. This paper briefly describes the specialized components and equipment used, the process followed, and experience gained in packaging the spent fuel. Olsen et al and Schaefer separately discuss overall safety and criticality considerations of the packaging process in parallel papers to this conference

  6. Long Term Performance Study of a Direct Methanol Fuel Cell Fed with Alcohol Blends

    Directory of Open Access Journals (Sweden)

    Eleuterio Mora

    2013-01-01

    Full Text Available The use of alcohol blends in direct alcohol fuel cells may be a more environmentally friendly and less toxic alternative to the use of methanol alone in direct methanol fuel cells. This paper assesses the behaviour of a direct methanol fuel cell fed with aqueous methanol, aqueous ethanol and aqueous methanol/ethanol blends in a long term experimental study followed by modelling of polarization curves. Fuel cell performance is seen to decrease as the ethanol content rises, and subsequent operation with aqueous methanol only partly reverts this loss of performance. It seems that the difference in the oxidation rate of these alcohols may not be the only factor affecting fuel cell performance.

  7. Super long-term scenario of world nuclear power generation and uranium supply and demand until 2030 and further 2100

    International Nuclear Information System (INIS)

    Komiyama, Ryoichi; Kakinoki, Tatsuro

    2007-01-01

    Based on latest nuclear policy and development trend in each country in the world, quantity of nuclear power generation and the uranium supply and demand until 2030 and further 2100 were predicted. As a result, the introduction of nuclear power stations spreads around Asia until 2030. The limitation on the uranium resources clearly does not exist until 2030, but a development period of around 10 years is necessary for exploitation of uranium resources. If timely development investment does not advance, it may invite shortage of uranium supply and promote a remarkable rise of uranium supply price. If the reinforcement of the anti-global warming measure and the diversification of the energy source advance at the super long-term time span called 2100, the world coal power largely decreases and the introduction of the nuclear power enlarges steadily. Introduction of the light water reactor (LWR) extends until 2080 since the fuel uses uranium resources of about 70 year ratio of reserves to production, but quantity of LWR power stations and power generation changes for the decrease due to the limitation of uranium resources after it. On the other hand, sustained expansion of the plutonium utilization by the fuel cycle technology and the introduction of the fast breeder reactor (FBR) advance after 2050. Then the sustained expansion of nuclear power is surely expected to occupy the first share of power generation in 2100. On this account it is necessary to push forward the plutonium use, backend technology and FBR development globally, and Japan is expected to carry a positive role to lead international nuclear energy technology development as a nuclear energy developed nation. (T. Tanaka)

  8. Real option valuation of free destination in long-term liquefied natural gas supplies

    International Nuclear Information System (INIS)

    Yepes Rodriguez, Ramon

    2008-01-01

    This paper presents a real option model for the valuation of destination flexibility in long-term LNG supplies. Stochastic price dynamics in the different markets is modelled through geometric Brownian motion processes. Mean reversion is considered as well as correlation between markets, but instead of the usual correlation in return shocks, a price convergence term is introduced representing the arbitrage streams between markets. Model parameters are estimated from market data on LNG prices by maximum log-likelihood. The goodness of the fit for the proposed model is tested as well as for two alternative models. Confidence intervals for the parameters are given. Results for the model are calculated by Monte Carlo simulation. Frequency distributions for the main results are plotted. The effect of the main parameters of the model is studied (i.e. price volatilities, price convergence, initial prices in the markets, mean reversion, extra transportation costs, number of alternative markets). The value of destination flexibility is found to be an important share of the value of LNG

  9. Long-term dynamics of dissolved organic carbon: implications for drinking water supply.

    Science.gov (United States)

    Ledesma, José L J; Köhler, Stephan J; Futter, Martyn N

    2012-08-15

    Surface waters are the main source of drinking water in many regions. Increasing organic carbon concentrations are a cause for concern in Nordic countries since both dissolved and particulate organic carbon can transport contaminants and adversely affect drinking water treatment processes. We present a long-term study of dynamics of total (particulate and dissolved) organic carbon (TOC) concentrations in the River Fyris. This river supplies drinking water to approximately 200000 people in Uppsala, Sweden. The River Fyris is a main tributary to Lake Mälaren, which supplies drinking water to approximately 2 million people in the greater Stockholm area. Utilities responsible for drinking water supply in both Uppsala and Stockholm have expressed concerns about possible increases in TOC. We evaluate organic carbon dynamics within the Fyris catchment by calculating areal mass exports using observed TOC concentrations and modeled flows and by modeling dissolved organic carbon (as a proxy for TOC) using the dynamic, process based INCA-C model. Exports of TOC from the catchment ranged from 0.8 to 5.8 g m(-2) year(-1) in the period 1995-2010. The variation in annual exports was related to climatic variability which influenced seasonality and amount of runoff. Exports and discharge uncoupled at the end of 2008. A dramatic increase in TOC concentrations was observed in 2009, which gradually declined in 2010-2011. INCA-C successfully reproduced the intra- and inter-annual variation in concentrations during 1996-2008 and 2010-2011 but failed to capture the anomalous increase in 2009. We evaluated a number of hypotheses to explain the anomaly in 2009 TOC values, ultimately none proved satisfactory. We draw two main conclusions: there is at least one unknown or unmeasured process controlling or influencing surface water TOC and INCA-C can be used as part of the decision-making process for current and future use of rivers for drinking water supply. Copyright © 2012 Elsevier B

  10. Criticality safety evaluation for long term storage of FFTF fuel in interim storage casks

    International Nuclear Information System (INIS)

    Richard, R.F.

    1995-01-01

    It has been postulated that a degradation phenomenon, referred to as ''hot cell rot'', may affect irradiated FFTF mixed plutonium-uranium oxide (MOX) fuel during dry interim storage. ''Hot cell rot'' refers to a variety of phenomena that degrade fuel pin cladding during exposure to air and inert gas environments. It is thought to be a form of caustic stress corrosion cracking or environmentally assisted cracking. Here, a criticality safety analysis was performed to address the effect of the ''hot cell rot'' phenomenon on the long term storage of irradiated FFTF fuel in core component containers. The results show that seven FFTF fuel assemblies or six Ident-69 pin containers stored in core component containers within interim storage casks will remain safely subcritical

  11. Parametric Analysis of PWR Spent Fuel Depletion Parameters for Long-Term-Disposal Criticality Safety

    International Nuclear Information System (INIS)

    DeHart, M.D.

    1999-01-01

    Utilization of burnup credit in criticality safety analysis for long-term disposal of spent nuclear fuel allows improved design efficiency and reduced cost due to the large mass of fissile material that will be present in the repository. Burnup-credit calculations are based on depletion calculations that provide a conservative estimate of spent fuel contents (in terms of criticality potential), followed by criticality calculations to assess the value of the effective neutron multiplication factor (k(sub)eff) for the a spent fuel cask or a fuel configuration under a variety of probabilistically derived events. In order to ensure that the depletion calculation is conservative, it is necessary to both qualify and quantify assumptions that can be made in depletion models

  12. Risk assessment in long-term storage of spent nuclear fuel

    International Nuclear Information System (INIS)

    Ahn, T.; Guttmann, J.; Mohseni, A.

    2013-01-01

    This paper presents probabilistic risk-informed approaches that the Nuclear Regulatory Commission (NRC) staff is planning to consider in preparing regulatory bases for long-term storage of spent nuclear fuel (SNF) for up to 300 years. Due to uncertainties associated with long-term SNF storage, the NRC is considering a probabilistic risk-informed approach as well as a deterministic design-based approach. The uncertainties considered here are primarily associated with materials aging of the canister and SNF in the cask system during long-term storage of SNF. This paper discusses some potential risk contributors involved in long-term SNF storage. Methods of performance evaluation are presented that assess the various types of risks involved. They include deterministic evaluation, probabilistic evaluation, and consequence assessment under normal conditions and the conditions of accidents and natural hazards. Some potentially important technical issues resulting from the consideration of a probabilistic risk-informed evaluation of the cask system performance are discussed for the canister and SNF integrity. These issues are also discussed in comparison with the deterministic approach for comparison purposes, as appropriate. Probabilistic risk-informed methods can provide insights that deterministic methods may not capture. Two specific examples include stress corrosion cracking of the canister and hydrogen-induced cladding failure. These examples are discussed in more detail, in terms of their effects on radionuclide release and nuclear subcriticality associated with the failure. The plan to consider the probabilistic risk-informed approaches is anticipated to provide helpful regulatory insights for long-term storage of SNF that provide reasonable assurance for public health and safety. (authors)

  13. The long-term forecast of Pakistan's electricity supply and demand: An application of long range energy alternatives planning

    International Nuclear Information System (INIS)

    Perwez, Usama; Sohail, Ahmed; Hassan, Syed Fahad; Zia, Usman

    2015-01-01

    The long-term forecasting of electricity demand and supply has assumed significant importance in fundamental research to provide sustainable solutions to the electricity issues. In this article, we provide an overview of structure of electric power sector of Pakistan and a summary of historical electricity demand & supply data, current status of divergent set of energy policies as a framework for development and application of a LEAP (Long-range Energy Alternate Planning) model of Pakistan's electric power sector. Pakistan's LEAP model is used to analyze the supply policy selections and demand assumptions for future power generation system on the basis of economics, technicality and implicit environmental implications. Three scenarios are enacted over the study period (2011–2030) which include BAU (Business-As-Usual), NC (New Coal) & GF (Green Future). The results of these scenarios are compared in terms of projected electricity demand & supply, net present cost analysis (discount rate at 4%, 7% and 10%) and GHG (greenhouse gas) emission reductions, along with sensitivity analysis to study the effect of varying parameters on total cost. A concluding section illustrates the policy implications of model for futuristic power generation and environmental policies in Pakistan. - Highlights: • Pakistan-specific electricity demand model is presented. • None of the scenarios exceeded the price of 12 US Cents/kWh. • By 2030, fuel cost is the most dominant factor to influence electricity per unit cost. • By 2030, CO_2 emissions per unit electricity will increase significantly in coal scenario relative to others. • By 2030, the penetration of renewable energy and conservation policies can save 70.6 tWh electricity.

  14. Long term durability tests of small engines fueled with bio-ethanol / gasoline blends

    International Nuclear Information System (INIS)

    Tippayawong, N.; Kundhawiworn, N.; Jompakdee, W.

    2006-01-01

    The paper presents the result of an ongoing research to evaluate performance and wear of small, single cylinder, naturally aspirated, agricultural spark ignition engines using biomass-derived ethanol and gasoline blends. The reference gasoline fuel was selected to be representative of gasoline typically available in Thailand. Long-term engine tests of 10% and 20% ethanol / gasoline blends as well as the reference fuel were performed at a constant speed of 2300 rpm under part load condition up to 200 operation hours for each fuel type. Engine brake power, specific fuel consumption, carbon deposits and surface wear were measured and compared between neat gasoline and ethanol/ gasoline blends. It was found that blended fuels appeared to affect the engine performance in a similar way and compared well with the base gasoline fuel. From the results obtained, it was found that engine brake power and specific fuel consumption changed slightly with running time and were not found to have any significant change between different fuel blends. There were carbon deposits buildup on the spark plug, the intake port and exhaust valve stem for all fuels used. Surface wear was not significantly different in the test engines between neat gasoline or ethanol/gasoline blend fuelling

  15. Long-term tradeoffs between nuclear- and fossil-fuel burning

    International Nuclear Information System (INIS)

    Krakowski, R.A.

    1996-01-01

    A global energy/economics/environmental (E 3 ) model has been adapted with a nuclear energy/materials model to understand better open-quotes top-levelclose quotes, long-term trade offs between civilian nuclear power, nuclear-weapons proliferation, fossil-fuel burning, and global economic welfare. Using a open-quotes business-as-usualclose quotes (BAU) point-of-departure case, economic, resource, proliferation-risk implications of plutonium recycle in LAIRs, greenhouse-gas-mitigating carbon taxes, and a range of nuclear energy costs (capital and fuel) considerations have been examined. After describing the essential elements of the analysis approach being developed to support the Los Alamos Nuclear Vision Project, preliminary examples of parametric variations about the BAU base-case scenario are presented. The results described herein represent a sampling from more extensive results collected in a separate report. The primary motivation here is: (a) to compare the BAU basecase with results from other studies; (b) to model on a regionally resolved global basis long-term (to year ∼2100) evolution of plutonium accumulation in a variety of forms under a limited range of fuel-cycle scenarios; and (c) to illustrate a preliminary connectivity between risks associated with nuclear proliferation and fossil-fuel burning (e.g., greenhouse-gas accumulations)

  16. Long term fuel price elasticity: effects on mobility tool ownership and residential location choice - Final report

    Energy Technology Data Exchange (ETDEWEB)

    Erath, A.; Axhausen, K. W.

    2010-04-15

    This comprehensive final report for the Swiss Federal Office of Energy (SFOE) examines the long-term effects of fuel price elasticity. The study analyses how mobility tool usage and ownership as well as residence location choice are affected by rising fuel costs. Based on econometric models, long-term fuel price elasticity is derived. The authors quote that the demand reactions to higher fuel prices mainly observed are the reduction of mileage and the consideration of smaller-engined and diesel-driven cars. As cars with natural gas powered engines and electric drives were hardly considered in the survey, the results of the natural gas model can, according to the authors, only serve as a trend. No stable model could be estimated for the demand and usage of electric cars. A literature overview is presented and the design of the survey is discussed, whereby socio-demographical variables and the effects of price and residence changes are discussed. Modelling of mobility tool factors and results obtained are looked at. Finally, residence choice factors are modelled and discussed. Several appendices complete the report.

  17. Technoeconomic assumptions adopted for the development of a long-term electricity supply model for Cyprus

    Directory of Open Access Journals (Sweden)

    Constantinos Taliotis

    2017-10-01

    Full Text Available The generation mix of Cyprus has been dominated by oil products for decades. In order to conform with European Union and international legislation, a transformation of the supply system is called for. Energy system models can facilitate energy planning into the future, but a large volume of data is required to populate such models. The present data article provides information on key modelling assumptions and input data adopted with the aim of representing the electricity supply system of Cyprus in a separate research article. Data in regards to renewable energy technoeconomic characteristics and investment cost projections, fossil fuel price projections, storage technology characteristics and system operation assumptions are described in this article.

  18. Methodology of fuel cycles long-term safety assessment of SNF/HLW geological disposal

    International Nuclear Information System (INIS)

    Pritrsky, J.

    2008-02-01

    Methodology for the long-term safety assessment of nuclear fuel cycles is given in the presented doctoral thesis. The aim of work was to develop a geological repository model for disposal of spent nuclear fuel (SNF) and high level waste (HLW) using an appropriate software code able to calculate the influence of partitioning and transmutation in advanced fuel cycles. The first step in this process was specifying of indicators which can be used to quantify the radiological impact of each fuel cycle. Indicators such as annual effective dose and radiotoxicity of inventory have been quantitatively analysed to determine the potential risk and radiological consequences associated with production of SNF/HLW. Advanced fuel types bring a number of advantages in comparison to uranium oxide fuel UO 2 used worldwide nowadays in terms of safety improvement due to minor actinides transmutation and non-proliferation aspects as well. Within the scope of work, three different fuel cycles are compared from the point of view of long-term safety of deep geological repository. The first considered fuel cycle is the currently used open fuel cycle (UOX) which uses only U-FA (Uranium Fuel Assembly). The second assessed cycle is a closed fuel cycle (MOX) with MOX-FA (Mixed OXides Fuel Assembly) and the third considered one is a partially closed fuel cycle (IMF) with IMC-FA (Inert Matrix Combined Fuel Assembly). Description and input data of advanced fuel cycles have been gained by participation in the EC project RED-IMPACT. Results were calculated using code AMBER, which is a flexible software tool that allows building dynamic compartmental models to represent the migration and fate of contaminants in a system, for example in the surface and sub-surface environment. Contaminants in solid, liquid and gaseous phases can be considered. AMBER gives the user the flexibility to define any number of compartments; any number of contaminants and associated decays; deterministic, probabilistic and

  19. Methodology of fuel cycles long-term safety assessment of SNF/HLW geological disposal

    International Nuclear Information System (INIS)

    Pritrsky, J.

    2008-01-01

    Methodology for the long-term safety assessment of nuclear fuel cycles is given in the presented doctoral thesis. The aim of work was to develop a geological repository model for disposal of spent nuclear fuel (SNF) and high level waste (HLW) using an appropriate software code able to calculate the influence of partitioning and transmutation in advanced fuel cycles. The first step in this process was specifying of indicators which can be used to quantify the radiological impact of each fuel cycle. Indicators such as annual effective dose and radiotoxicity of inventory have been quantitatively analysed to determine the potential risk and radiological consequences associated with production of SNF/HLW. Advanced fuel types bring a number of advantages in comparison to uranium oxide fuel UO 2 used worldwide nowadays in terms of safety improvement due to minor actinides transmutation and non-proliferation aspects as well. Within the scope of work, three different fuel cycles are compared from the point of view of long-term safety of deep geological repository. The first considered fuel cycle is the currently used open fuel cycle (UOX) which uses only U-FA (Uranium Fuel Assembly). The second assessed cycle is a closed fuel cycle (MOX) with MOX-FA (Mixed OXides Fuel Assembly) and the third considered one is a partially closed fuel cycle (IMF) with IMC-FA (Inert Matrix Combined Fuel Assembly). Description and input data of advanced fuel cycles have been gained by participation in the EC project RED-IMPACT. Results were calculated using code AMBER, which is a flexible software tool that allows building dynamic compartmental models to represent the migration and fate of contaminants in a system, for example in the surface and sub-surface environment. Contaminants in solid, liquid and gaseous phases can be considered. AMBER gives the user the flexibility to define any number of compartments; any number of contaminants and associated decays; deterministic, probabilistic and

  20. International long-term interim storage for spent fuel. An independent storage service investor model

    International Nuclear Information System (INIS)

    Leister, P.

    1999-01-01

    Thinking globally the obvious world-wide demands for large storage capacities for spent fuel within the next decades and the newly arising demands for long-term interim storage of spent fuel urges to respond by international interim storage facilities of high capacity. Low cost storage can be achieved only by arranging the storage facility underground in a suitable host rock formation and by selecting the geographical are by an international competition under those countries, who are willing to offer their land. The investor and operator of an international storage facility selected and realised by a competition on the free market as well as the country where the storage is built are both bound by two different kinds of contacts. The main contract is between the offering country/region and the independent operator. The independent operator has in addition a series of contracts with various utilities, which are interested to have their spent fuel stored for a longer period

  1. Establishing the long-term fuel management scheme using point reactivity model

    International Nuclear Information System (INIS)

    Park, Yong-Soo; Kim, Jae-Hak; Lee, Young-Ouk; Song, Jae-Woong; Zee, Sung-Kyun

    1994-01-01

    A new approach to establish the long-term fuel management scheme is presented in this paper. The point reactivity model is used to predict the core average reactivity. An attempt to calculate batchwise power fraction is introduced through the two-dimensional nodal power algorithm based on the modified one-group diffusion equation and the number of fuel assemblies on the core periphery. Suggested is an empirical formula to estimate the radial leakage reactivity with ripe core design experience reflected. This approach predicts the cycle lengths and the discharge burnups of individual fuel batches up to an equilibrium core when the proper input data such as batch enrichment, batch size, type and content of burnable poison and reloading strategies are given. Eight benchmark calculations demonstrate that the new approach used in this study is reasonably accurate and highly efficient for the purpose of scoping calculation when compared with design code predictions. (author)

  2. Analysis of long-term guarantee of supply in power markets: Application of the marginal theory

    International Nuclear Information System (INIS)

    Parrilla, Ernesto; Vazquez, Carlos

    2005-06-01

    In this paper the marginal theory is applied to discuss the different long-term equilibria that could be reached in an electricity market depending on the market participants' (generators, consumers and the regulator) goals and constraints. The aim is to identify the key elements of a possible market failure in providing generation adequacy - immature demand, regulated tariffs, long-term contracting, different agents perception of the market risks, etc - and to study their influence in the long-term market equilibrium. Furthermore, we analyze several of the different capacity mechanisms that could be used to ensure generation adequacy, such as: short-term capacity payments, long-term capacity payments and capacity markets. This final analysis includes an estimation of how useful each method is to compensate the market failures that we have previously identified

  3. Advanced surveillance technologies for used fuel long-term storage and transportation - 59032

    International Nuclear Information System (INIS)

    Tsai, Hanchung; Liu, Yung Y.; Nutt, Mark; Shuler, James

    2012-01-01

    Utilities worldwide are using dry-cask storage systems to handle the ever-increasing number of discharged fuel assemblies from nuclear power plants. In the United States and possibly elsewhere, this trend will continue until an acceptable disposal path is established. The recent Fukushima nuclear power plant accident, specifically the events with the storage pools, may accelerate the drive to relocate more of the used fuel assemblies from pools into dry casks. Many of the newer cask systems incorporate dual-purpose (storage and transport) or multiple-purpose (storage, transport, and disposal) canister technologies. With the prospect looming for very long term storage - possibly over multiple decades - and deferred transport, condition- and performance-based aging management of cask structures and components is now a necessity that requires immediate attention. From the standpoint of consequences, one of the greatest concerns is the rupture of a substantial number of fuel rods that would affect fuel retrievability. Used fuel cladding may become susceptible to rupture due to radial-hydride-induced embrittlement caused by water-side corrosion during the reactor operation and subsequent drying/transfer process, through early stage of storage in a dry cask, especially for high burnup fuels. Radio frequency identification (RFID) is an automated data capture and remote-sensing technology ideally suited for monitoring sensitive assets on a long-term, continuous basis. One such system, called ARG-US, has been developed by Argonne National Laboratory for the U.S. Department of Energy's Packaging Certification Program for tracking and monitoring drums containing sensitive nuclear and radioactive materials. The ARG-US RFID system is versatile and can be readily adapted for dry-cask monitoring applications. The current built-in sensor suite consists of seal, temperature, humidity, shock, and radiation sensors. With the universal asynchronous receiver/transmitter interface in

  4. Development of an evaluation method for long-term sealability of the spent fuel storage cask

    International Nuclear Information System (INIS)

    Kato, Osamu; Ito, Chihiro; Saegusa, Toshiari

    1996-01-01

    One of the characteristics of the cask storage method of spent fuel is that containment of radioactive materials is assured by the storage cask itself. Thus, the seal structure of the cask is designed to have a highly reliable multi-barrier system using metallic gaskets instead of the conventional rubber gaskets. Although, it has been reported that the containment feature of the metallic gaskets is influenced by the plastic deformation and stress relaxation of the gaskets for a short-term usage, no research report has been published on the containment feature of the metallic gaskets for a long-term usage. In this paper, the stress relaxation features of the metallic gaskets is investigated which will directly influence the long-term sealability of the storage cask, at first. Next, the relationship between the temperature/time dependence of the plastic deformation and the containment features of the metallic gaskets. Finally, an evaluation method of the long-term sealability from experimental data of a short-term behavior of the metallic gaskets is proposed. (author)

  5. Recycling versus Long-Term Storage of Nuclear Fuel: Economic Factors

    Directory of Open Access Journals (Sweden)

    B. Yolanda Moratilla Soria

    2013-01-01

    Full Text Available The objective of the present study is to compare the associated costs of long-term storage of spent nuclear fuel—open cycle strategy—with the associated cost of reprocessing and recycling strategy of spent fuel—closed cycle strategy—based on the current international studies. The analysis presents cost trends for both strategies. Also, to point out the fact that the total cost of spent nuclear fuel management (open cycle is impossible to establish at present, while the related costs of the closed cycle are stable and known, averting uncertainties.

  6. Standard for supply security. A minimum standard to guarantee the balance between electricity demand and supply for the long term

    International Nuclear Information System (INIS)

    Scheepers, M.J.J.; Van Werven, M.J.N.; Seebregts, A.J.; Poort, J.P.; De Nooij, M.; Baarsma, B.E.

    2004-05-01

    The development and use of a minimum reliability standard in the Dutch electricity market to guarantee an adequate balance between electricity demand and supply in the longer term are discussed. This standard can be based on the duration of a power outage and the related costs for society relative to the costs to prevent the power outage. The reliability standard can be translated in an adequacy standard when the reliability of foreign electricity supply to the Dutch market is taken into account. With a theoretical analysis and an assessment of the use of standards in foreign electricity markets and other sectors this study provides a survey of the use of standards in securing public interests. In electricity markets reliability standards can be used obligatory or only to inform market participants of the adequacy of supply preferred by consumers. If no standard is used, the market should rely on the economic incentives provided by contracts and liability. This study proposes to use a reliability standard for calculating the required generation capacity in an ex-ante market analysis using different future scenarios. On the basis of several market indicators, expected market developments can be monitored. Assessment of the market developments relative to the required generation capacity will give a signal to market participants with respect to the expected adequacy in the longer term (7 to 10 years). The assessment and the resulting signal should help to improve market transparency and assist producers, suppliers and consumers in their decisions towards an effective and efficient response on long-term market developments. Market monitoring results can be used by the government to take specific action, if necessary, to reduce barriers to invest. However, more general policy measures should not be linked to the monitoring results since this could provoke strategic behaviour [nl

  7. Simple analysis of very long term proceses without operational and emergency energy supply in the PWR power plant

    International Nuclear Information System (INIS)

    Benedek, S.

    1983-01-01

    Published calculational methods are cited and used for examination of PWR transients after a loss-of-coolant accident. For different sizes of breaks and breakdown of the pumps the long term transients - without operational and emergency power supply - were calculated. The results show the critical time interval until the operational or emergency/safety water pump/supply should be made into operation to avoid the core heat-up, melt down and the large radioactive issue. (orig.)

  8. Fuel supply security

    International Nuclear Information System (INIS)

    Wakabayashi, Hiroaki

    1987-01-01

    Stable fuel supply is a prerequisite for any nuclear power program including ISER-PIUS. It encompasses procurement of uranium ore, enriched uranium and fuel elements. Uranium is different from oil in that it can be stockpiled for more than a decade besides the fact that the core residence time is as long as six years, for example in the case of ISER-PIUS. These basic fuel characteristics are favoring nuclear fuel over others in terms of supply security. The central concern will be a gradual increase in prices of uranium and enrichment. Under the present glut situation with the worldwide prevalence of LWRs, fuel supply security seems ensured for the time being till the middle of 21st century. It is estimated that by the turn of the century, the free world will have roughly 450 GWe capacity of nuclear power. If 10 % is supplied for ISER-PIUS, more than 200 modules of 200 MWe ISER-PIUS may be deployed all over the world probably starting around 2000. As part of the fuel supply security consideration, heavy water reactor (HWR) may seem interesting to such a country as Indonesia where there is uranium resources but no enrichment capability. But it needs heavy water instead and the operation is not so easy as of LWR, because of the positive void coefficient as was seen at the Chernobyl-4. Safeguarding of the fuel is also difficult, because it lends itself to on line refueling. The current and future situation of the fuel supply security for LWR seem well founded and established long into the future. (Nogami, K.)

  9. Development of nuclear fuel cycle technologies - bases of long-term provision of fuel and environmental safety of nuclear power

    International Nuclear Information System (INIS)

    Solonin, M.I.; Polyakov, A.S.; Zakharkin, B.S.; Smelov, V.S.; Nenarokomov, E.A.; Mukhin, I.V.

    2000-01-01

    To-day nuclear power is one of the options, however, to-morrow it may become the main source of the energy, thus, providing for the stable economic development for the long time to come. The availability of the large-scale nuclear power in the foreseeable future is governed by not only the safe operation of nuclear power plants (NPP) but also by the environmentally safe management of spent nuclear fuel, radioactive waste conditioning and long-term storage. More emphasis is to be placed to the closing of the fuel cycle in view of substantial quantities of spent nuclear fuel arisings. The once-through fuel cycle that is cost effective at the moment cannot be considered to be environmentally safe even for the middle term since the substantial build-up of spent nuclear fuel containing thousands of tons Pu will require the resolution of the safe management problem in the nearest future and is absolutely unjustified in terms of moral ethics as a transfer of the responsibility to future generations. The minimization of radioactive waste arisings and its radioactivity is only feasible with the closed fuel cycle put into practice and some actinides and long-lived fission radionuclides burnt out. The key issues in providing the environmentally safe fuel cycle are efficient processes of producing fuel for NPP, radionuclide after-burning included, a long-term spent nuclear fuel storage and reprocessing as well as radioactive waste management. The paper deals with the problems inherent in producing fuel for NPP with a view for the closed fuel cycle. Also discussed are options of the fuel cycle, its effectiveness and environmental safety with improvements in technologies of spent nuclear fuel reprocessing and long-lived radionuclide partitioning. (authors)

  10. Development of nuclear fuel cycle technologies - bases of long-term provision of fuel and environmental safety of nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Solonin, M I; Polyakov, A S; Zakharkin, B S; Smelov, V S; Nenarokomov, E A; Mukhin, I V [SSC, RF, A.A. Bochvar ALL-Russia Research Institute of Inorganic Materials, Moscow (Russian Federation)

    2000-07-01

    To-day nuclear power is one of the options, however, to-morrow it may become the main source of the energy, thus, providing for the stable economic development for the long time to come. The availability of the large-scale nuclear power in the foreseeable future is governed by not only the safe operation of nuclear power plants (NPP) but also by the environmentally safe management of spent nuclear fuel, radioactive waste conditioning and long-term storage. More emphasis is to be placed to the closing of the fuel cycle in view of substantial quantities of spent nuclear fuel arisings. The once-through fuel cycle that is cost effective at the moment cannot be considered to be environmentally safe even for the middle term since the substantial build-up of spent nuclear fuel containing thousands of tons Pu will require the resolution of the safe management problem in the nearest future and is absolutely unjustified in terms of moral ethics as a transfer of the responsibility to future generations. The minimization of radioactive waste arisings and its radioactivity is only feasible with the closed fuel cycle put into practice and some actinides and long-lived fission radionuclides burnt out. The key issues in providing the environmentally safe fuel cycle are efficient processes of producing fuel for NPP, radionuclide after-burning included, a long-term spent nuclear fuel storage and reprocessing as well as radioactive waste management. The paper deals with the problems inherent in producing fuel for NPP with a view for the closed fuel cycle. Also discussed are options of the fuel cycle, its effectiveness and environmental safety with improvements in technologies of spent nuclear fuel reprocessing and long-lived radionuclide partitioning. (authors)

  11. Perinatal long chain polyunsaturated fatty acid supply Are there long term consequences?

    Directory of Open Access Journals (Sweden)

    Demmelmair Hans

    2007-05-01

    , according to the concept of “metabolic programming” during the perinatal period a dietary factor, such as the availability of LC-PUFA, might have long term consequences. From the available data it has to be assumed that LC-PUFA are conditionally essential substrates during early life and a further investigation of the biological mechanisms related to their availability for the infant and of potential life long effects on cognitive function and potentially also risk factors for cardiovascular diseases and allergy are certainly warranted.

  12. LPG consumption in the long term: supply, pricing demand with particular reference to the petrochemical sector

    International Nuclear Information System (INIS)

    Shammas, P.

    1996-01-01

    Supply of LPG is forecast to grow over the next decade from the present level of 180 million t/y to about 185-190 million t/y, depending on demand in Asia which is rising rapidly and on new LPG export projects. Most of the increase in supply will come from new gas and crude oil production, from new LPG ventures, and from refineries reducing the n-butane content of motor gasoline. Pricing will remain volatile as a result of crude oil price volatility, variations in the winter weather in the Northern Hemisphere, and as result of competition between ethane, PPG, naphtha and condensate as ethylene cracker feedstocks. Demand for LPG in OECD countries will continue to show steady growth. The increase in demand will be more rapid in the relatively less developed OECD countries, as the trend in Spain has shown in recent years. Provided that the LPG price is competitive, demand in China, South-East Asia and the Indian sub-continent could grow beyond current projections. Consumption in these countries will depend on the installation of distribution facilities and the rate at which LPG can substitute for traditional fuels and kerosene as well as compete for limited disposable incomes. (author)

  13. Long-term fuel cycle scenarios for advanced utilization of plutonium from LWRs

    International Nuclear Information System (INIS)

    Sato, Osamu; Tatematsu, Kenji

    2005-01-01

    The Innovative Water Reactor for Flexible fuel cycle (FLWR) realizes multiple recycling and breeding of Pu, which enables effective utilization of the uranium resource, and is based on well-developed LWR technologies. This reactor offers flexibility for the future nuclear fuel cycle situation. Three scenarios were defined for future deployment of nuclear power generation and fuel cycle systems in Japan and analyzed from the view point of Pu recycle, natural uranium consumption and stock of spent fuels. The LWR with long-term Pu recycle with or without MOX fuel reprocessing needs uranium of about 9 thousands tons per year and accumulated uranium consumption of 1.5 million tons in 2150. If the FLWR with net conversion ratio of 0.89 and 1.04 would be introduced in 2025 and 2050 or 2030, it would suppress ultimate required natural uranium and control the uranium consumption about less than 1.2 million tons in 2150, while the FLWR in 2025 and FBR with breeding ratio of 1.16 in 2050 will at 0.9 million tons after in 2100. (T. Tanaka)

  14. 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)

  15. Diesel fuel long term storage and treatment- recommended tests and practices (U)

    Energy Technology Data Exchange (ETDEWEB)

    Gross, R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2009-06-05

    The Clean Air Act (1970) is the comprehensive federal law that regulates air emissions from stationary and mobile sources. Among other things, this law authorized the Environmental Protection Agency (EPA) to establish National Ambient Air Quality Standards to protect public health and public welfare and to regulate emissions of hazardous air pollutants. In recent years, EPA regulations have forced oil refineries into producing a very low sulfur diesel fuel and incentives for adding up to 5% bio-diesel. These changes to the fuel oil formulation are beneficial to air quality and to energy conservation, but adversely impact heat content, long term storage stability, engine power, and injection system reliability. Diesel engines typically have a high incidence of injector failure resulting from poor diesel fuel quality. Since standby diesel engines do not run continuously it is necessary to implement periodic surveillance's to ensure the quality of diesel fuel is acceptable for reliable operation when a loss of power occurs. The information contained in this document is a compilation of best practices to be used as a guide for maintenance of a reliable diesel fuel system.

  16. High-level radioactive wastes storage characterization and behaviour of spent fuels in long-term

    International Nuclear Information System (INIS)

    Diaz Arocas, P.; Cobos, J.; Quinones, J.; Rodriguez Almazan, J. L.; Serrano, J.

    2001-01-01

    In order to understand the long term spent fuel dissolution under repository this report shows the study performed by considering spent fuel as a part of the multi barriers containment system. The study takes into account that the oxidative alteration/dissolution of spent fuel matrix is influenced by the intrinsic spent fuel physicochemical characteristics and the repository environmental parameters. Experimental and modelling results for granite and saline repositories are reported. Parameters considered in this work were pH, pCO 2 , S/V ratio, redox conditions and the influence of the container material in the redox conditions. The influence of alpha, beta and gamma radiation and the resulting radiolytic products formed remains as one of the main uncertainties to quantify the spent fuel behaviour under repository conditions. It was studied in a first approach through dose calculations, modelling of radiolytic products formation and leaching experiments in the presence of external gamma irradiation source and leaching experiments of alpha doped UO 2 pellets. Materials considered are LWR spent fuel (UO 2 and MOX fuel) and their chemical analogues non irradiated UO 2 , SIMFUEL and alpha doped UO 2 . Lea chants were granite groundwater, synthetic granite groundwater, synthetic granite groundwater saturated in bentonite, and high concentrated saline solutions. The matrix dissolution rate and release rate of key radionuclides (i. e. actinides and fission products) obtained through the several experimental techniques and methodologies (dissolution, co-dissolution, precipitation and co-precipitation) together with modelling studies supported in geochemical codes are proposed. Moreover, secondary phases formed that could control release and retention of key nuclides are identified. Maximum concentration values for these radionuclides are reported. The data provided by this study were used in ENRESA-2000 performance assessment. (Author)

  17. Nuclear fuel supply: challenges and opportunities

    International Nuclear Information System (INIS)

    Lowen, S.

    2006-01-01

    Prices of uranium, conversion services and enrichment services have all significantly increased in the last few years. These price increases have generally been driven by a tightening in the supply of these products and services, mostly due to long lead times required to bring these products and services to the market. This paper will describe the various steps in the nuclear fuel cycle for natural and enriched uranium fuel, will discuss the development of the front-end fuel cycle for low void reactivity fuel, and will address the challenges faced in the long-term supply of each component, particularly in the light of potential demand increases as a result of a nuclear renaissance. The opportunities for new capacity and uranium production will be outlined and the process required to achieve sufficient new supply will be discussed. (author)

  18. Test plan for long-term, low-temperature oxidation of spent fuel, Series 1

    International Nuclear Information System (INIS)

    Einziger, R.E.

    1986-06-01

    Preliminary studies indicated the need for more spent fuel oxidation data in order to determine the probable behavior of spent fuel in a tuff repository. Long-term, low-temperature testing was recommended in a comprehensive technical approach to: (1) confirm the findings of the short-term thermogravimetric analyses scoping experiments; (2) evaluate the effects of variables such as burnup, atmospheric moisture and fuel type on the oxidation rate; and (3) extend the oxidation data base ot representative repository temperatures and better define the temperature dependence of the operative oxidation mechanisms. This document presents the Series 1 test plan to study, on a large number of samples, the effects of atmospheric moisture and temperature on oxidation rate and phase formation. Tests will run for up to two years, use characterized fragmented, and pulverized fuel samples, cover a temperature range of 110 0 C to 175 0 C and be conducted with an atmospheric moisture content rangeing from 0 C to approx. 80 0 C dew point. After testing, the samples will be examined and made available for leaching testing

  19. Post-Irradiation Examinations for Resolving Fuel Issues in Long Term Storage

    International Nuclear Information System (INIS)

    Karlsson, Joakim K.H.; Alvarez Holston, Anna-Maria

    2014-01-01

    In many countries extended long term dry storage is the solution for storage of spent nuclear fuel for the foreseeable future. The expected storage times have increased over the last years and today storage times of up to 300 years is anticipated. With such long storage times, requirements on transportability and retrievability of the fuel have become more important. Hitherto most investigations on fuel behaviour during dry storage have been focused on cladding creep and the impact of hydrogen and hydrides in the cladding. Creep data gives input to creep models and creep to rupture data helps to set criteria for maximum allowable internal rod pressure. Hydrides lower the ductility of the cladding and this is more pronounced with radially oriented hydrides. As the temperature decreases over time in a dry storage cask dissolved hydrogen will precipitate forming hydrides in addition to hydrides already present. Assuming there is sufficient hoop stress in the cladding, the new hydrides would be radially oriented. Together with lost ductility Delayed Hydride Cracking (DHC) could be a potential mechanism for rod failure over tens of years of dry storage as the temperature drops from about 350 deg. C to 150 deg. C. Hydride embrittlement and the DHC mechanism have been studied in the first Studsvik Cladding Integrity Project (SCIP), although the focus in this program has mainly been on higher temperatures relevant for operating conditions rather than on dry storage conditions. In addition to the mechanisms mentioned there are other failure mechanisms that could potentially threaten the cladding fuel integrity and retrievability. In case there is residual water or moisture available in the cask, or even in the fuel due to existing fuel failures, radiolysis gives free hydrogen and oxygen. In failed fuel this may cause fuel oxidation and swelling affecting fuel integrity. The hydrogen gas pressure will not threaten the cask but be available for cladding uptake. Furthermore

  20. Copper current collectors reduce long-term fouling of air cathodes in microbial fuel cells

    KAUST Repository

    Myung, Jaewook; Yang, Wulin; Saikaly, Pascal; Logan, Bruce E

    2018-01-01

    Long-term operation of wastewater-fed, microbial fuel cells (MFCs) with cathodes made of activated carbon and stainless steel (SS) current collectors can result in decreased performance due to cathode fouling. Copper has good antimicrobial properties, and it is more electrically conductive than SS. To demonstrate that a copper current collector could produce a more fouling resistant cathode, MFCs with air cathodes using either SS or copper current collectors were operated using domestic wastewater for 27 weeks. The reduction in biofouling over time was shown by less biofilm formation on the copper cathode surface compared to SS cathodes, due to the antimicrobial properties of copper. Maximum power densities from 17–27 weeks were 440 ± 38 mW/m2 using copper and 370 ± 21 mW/m2 using SS cathodes. The main difference in the microbial community was a nitrifying community on the SS cathodes, which was not present on the copper cathodes.

  1. Copper current collectors reduce long-term fouling of air cathodes in microbial fuel cells

    KAUST Repository

    Myung, Jaewook

    2018-02-05

    Long-term operation of wastewater-fed, microbial fuel cells (MFCs) with cathodes made of activated carbon and stainless steel (SS) current collectors can result in decreased performance due to cathode fouling. Copper has good antimicrobial properties, and it is more electrically conductive than SS. To demonstrate that a copper current collector could produce a more fouling resistant cathode, MFCs with air cathodes using either SS or copper current collectors were operated using domestic wastewater for 27 weeks. The reduction in biofouling over time was shown by less biofilm formation on the copper cathode surface compared to SS cathodes, due to the antimicrobial properties of copper. Maximum power densities from 17–27 weeks were 440 ± 38 mW/m2 using copper and 370 ± 21 mW/m2 using SS cathodes. The main difference in the microbial community was a nitrifying community on the SS cathodes, which was not present on the copper cathodes.

  2. Transmutation technologies to solve the problem of long-term spent nuclear fuel storage

    International Nuclear Information System (INIS)

    Hosnedl, P.; Valenta, V.; Blahut, O.

    2000-01-01

    The paper gives a brief description of the transmutation process for actinides and long-lived fission products which are present in spent nuclear fuel. Transmutation technologies can solve the problem of long-term spent nuclear fuel storage and reduce the requirements for storage time and conditions. The basic data and requirements for the detailed design of the transmutor are summarized, and the views upon how to address the fuel purification and dry reprocessing issues are discussed. The results of activities of SKODA JS are highlighted; these include, for instance, the fluoride salt-resistant material MONICR, test loops, and electrowinners. The preliminary design of the transmutor is also outlined. Brief information regarding activities in the field of transmutation technologies in the Czech Republic and worldwide is also presented. The research and design activities to be developed for the whole design of the demonstration and basic units are summarized. It is emphasized that SKODA JS can join in international cooperation without constraints. The Attachment presents a simple assessment of how the radioactivity balance can be reduced, based on the actinide and long-lived fission product transmutation half-lives, is presented in the Attachment. (author)

  3. Evaluation of limiting mechanisms for long-term spent fuel dry storage

    Energy Technology Data Exchange (ETDEWEB)

    Rashid, J. [ANATECH Research Corp., San Diego, CA (United States); Machiels, A. [EPRI, Palo Alto, CA (United States)

    2001-07-01

    Several failure mechanisms have been postulated that could become limiting for spent fuel in dry storage. These are: stress Corrosion Cracking (SCC), Delayed Hydride Cracking (DHC) and Creep Rupture (CR). These mechanisms are examined in some detail from two perspectives: their initial environments in which they were developed and applied, and in relation to their applicability to dry storage. Extrapolation techniques are used to transfer the mechanisms from their initial in-reactor and laboratory domains to out-of-reactor spent fuel dry storage environments. This transfer is accomplished both qualitatively where necessary and quantitatively when possible, with fracture toughness used as the transfer function. In this regard, the paper provides useful information on cladding fracture toughness estimates that recognize the specific physical conditions of the cladding, which would not be found elsewhere in the literature. The arguments presented in this paper confirm the general technical consensus that creep is the governing mechanism for spent fuel in long-term dry storage. (author)

  4. Assessments of long term mechanical behavior of CANDU fuel channel by means of PFEM analysis

    International Nuclear Information System (INIS)

    Florea, S.; Pavelescu, M.

    2005-01-01

    Structural analysis with finite elements method is today a usual way to evaluate and predict the behavior of structural assemblies exposed to severe conditions, in order to ensure their safety end reliability. CANDU 600 fuel channel is an example in which long time irradiation with implicit consequences on material properties evolution interfere with the corrosion and thermal aggression. A high degree of uncertainty in the evolution of the material's properties must be considered. These are the reasons for developing, in association with deterministic evaluations with computer codes, the probabilistic and statistical methods, in order to predict the structural components response. In INR (Institute of Nuclear Research) in the past years, a code for thermo-mechanical analysis of the fuel channel from CANDU 600 nuclear power plant of Cernavoda was developed using finite element methods (FEM). The CANTUP code evaluate the stress and strain state of the mechanical assembly of fuel channel, considered to be divided into pressure tube, calandria tube and four spacers, supposed to be equidistantly distributed along the pressure tube. The main achievement obtained with this code was the prediction of the long-term behavior of the sag of the pressure tube, by analysis in which the creep phenomenon and the contact between the spacers and calandria tube were considered. This reason has sustained the attempt to estimate the possibility to use this code in order to perform probabilistic evaluations. (authors)

  5. Assessments of long term mechanical behavior of CANDU fuel channel by means of PFEM analysis

    International Nuclear Information System (INIS)

    Florea, S.; Pavelescu, M.

    2005-01-01

    Full text: Structural analysis with finite elements method is today a usual way to evaluate and predict the behavior of structural assemblies exposed to severe conditions, in order to ensure their safety end reliability. CANDU 600 fuel channel is an example in which long time irradiation with implicit consequences on material properties evolution interfere with the corrosion and thermal aggression. A high degree of uncertainty in the evolution of the material's properties must be considered. These are the reasons for developing, in association with deterministic evaluations with computer codes, the probabilistic and statistical methods, in order to predict the structural components response. In INR (Institute of Nuclear Research) in the past years, a code for thermo-mechanical analysis of the fuel channel from CANDU 600 nuclear power plant of Cernavoda was developed using finite element methods (FEM). The CANTUP code evaluate the stress and strain state of the mechanical assembly of fuel channel, considered to be divided into pressure tube, calandria tube and four spacers, supposed to be equidistantly distributed along the pressure tube. The main achievement obtained with this code was the prediction of the long-term behavior of the sag of the pressure tube, by analysis in which the creep phenomenon and the contact between the spacers and calandria tube were considered. This reason has sustained the attempt to estimate the possibility to use this code in order to perform probabilistic evaluations. (authors)

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

    International Nuclear Information System (INIS)

    Wilcox, P.; Conboy, T.M.

    1994-01-01

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

  7. Evaluation of limiting mechanisms for long-term spent fuel dry storage

    International Nuclear Information System (INIS)

    Rashid, J.; Machiels, A.

    2001-01-01

    Several failure mechanisms have been postulated that could become limiting for spent fuel in dry storage. These are: stress Corrosion Cracking (SCC), Delayed Hydride Cracking (DHC) and Creep Rupture (CR). These mechanisms are examined in some detail from two perspectives: their initial environments in which they were developed and applied, and in relation to their applicability to dry storage. Extrapolation techniques are used to transfer the mechanisms from their initial in-reactor and laboratory domains to out-of-reactor spent fuel dry storage environments. This transfer is accomplished both qualitatively where necessary and quantitatively when possible, with fracture toughness used as the transfer function. In this regard, the paper provides useful information on cladding fracture toughness estimates that recognize the specific physical conditions of the cladding, which would not be found elsewhere in the literature. The arguments presented in this paper confirm the general technical consensus that creep is the governing mechanism for spent fuel in long-term dry storage. (author)

  8. Optimization strategies for cask design and container loading in long term spent fuel storage

    International Nuclear Information System (INIS)

    2006-12-01

    As delays are incurred in implementing reprocessing and in planning for geologic repositories, storage of increasing quantities of spent fuel for extended durations is becoming a growing reality. Accordingly, effective management of spent fuel continues to be a priority topic. In response, the IAEA has organized a series of meetings to identify cask loading optimisation issues in preparation for a technical publication on Optimization Strategies for Cask/Container Loading in Long Term Spent Fuel Storage. This publication outlines the optimisation process for cask design, licensing and utilization, describing three principal groups of optimization activities in terms of relevant technical considerations such as criticality, shielding, structural design, operations, maintenance and retrievability. The optimization process for cask design, licensing, and utilization is outlined. The general objectives for the design of storage casks, including storage casks that are intended to be transportable, are summarized. The nature of optimization within the design process is described. The typical regulatory and licensing process is outlined, focusing on the roles of safety regulations, the regulator, and the designer/applicant in the optimization process. Based on the foregoing, a description of the three principal groups of optimization activities is provided. The subsequent chapters of this document then describe the specific optimization activities within these three activity groups, in each of the several design disciplines

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-12-31

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

  10. An interim report on the outlook of long-term energy supply and demand

    International Nuclear Information System (INIS)

    1982-01-01

    An interim report was presented by the supply/demand committee in Over-all Energy Council concerning the energy demand and supply outlook for fiscal 1990 as compared with fiscal 1980. The background for deciding the outlook of energy supply and demand and basic ideas for energy policy, and the outlook for energy supply and demand are outlined. The outlook was prepared, assuming yearly economic growth of about 5 % in 1980s and the utmost efforts by people in energy situation. The energy situation both domestic and abroad is largely changing, including energy saving efforts and petroleum price. The aggregate energy demand for fiscal 1990 was put at about 590 million kl in terms of crude oil. Then, concerning nuclear power generation, the power supply by nuclear energy in fiscal 1990 was estimated at 46 million kw accounting for 11.3 % of the total power supply. (Mori, K.)

  11. Short Term Cyber Attacks with Long Term Effects and Degradation of Supply Chain Capability

    Science.gov (United States)

    2016-09-01

    Artificial Intelligence Research Society Conference, 271–275, St. Augustine: Florida. Goetschalckx, Marc. 2011. Supply Chain Engineering. New York: Springer...term risks in a network supply chain to establish the existence of black swan events. 14. SUBJECT TERMS cybersecurity , supply chain risk...Mission, and Information System View (NIST SP 800–39) .....50 6. Cybersecurity Instruction for the DOD (DODI 8500.01) .........51 7. Risk Management

  12. CRP on Demonstrating Performance of Spent Fuel and Related Storage Systems beyond the Long Term

    International Nuclear Information System (INIS)

    Bevilacqua, Arturo

    2014-01-01

    At the initial Coordinated Research Project (CRP) planning meeting held in August 2011, international experts in spent fuel performance confirmed the value of further coordination and development of international efforts to demonstrate the performance of spent fuel and related storage system components as durations extend. Furthermore, in recognition that the Extended Storage Collaboration Program (ESCP) managed by the Electric Power Research Institute (EPRI) in the USA, from now on ESCP, provided a broad context for the research and development work to be performed in the frame of this CRP, it was agreed that its objectives should target specific ESCP needs in order to make a relevant contribution. Accordingly, the experts examined on-going gap analyses - gaps between anticipated technical needs and existing technical data - for identify the specific research objectives. Additionally, during the planning meeting it was pointed out the need to coordinate and cooperate with the OECD/NEA counterparts involved in the organization of the International Workshop planned in autumn 2013 and with the on-going third phase of the CRP on Spent Fuel Performance Assessment and Research (SPAR-III). Given the importance to assess the performance of spent fuel and related important storage system components in order to confirm the viability of very long term storage for supporting the need to extend or renew licenses for storage facilities the CRP was approved by the IAEA in November 2011. While a full range of spent fuel types and storage conditions are deployed around the world, this CRP is focused on existing systems and, more specifically, water reactor fuel in dry storage with the overall research objective to support the technical basis for water reactor spent fuel management as dry storage durations extend. In March 2012 the group of international experts who participated at the initial CRP planning meeting in August 2011 evaluated and recommended for approval 9 research

  13. A Specific Long-Term Plan for Management of U.S. Nuclear Spent Fuel

    International Nuclear Information System (INIS)

    Levy, Salomon

    2006-01-01

    A specific plan consisting of six different steps is proposed to accelerate and improve the long-term management of U.S. Light Water Reactor (LWR) spent nuclear fuel. The first step is to construct additional, centralized, engineered (dry cask) spent fuel facilities to have a backup solution to Yucca Mountain (YM) delays or lack of capacity. The second step is to restart the development of the Integral Fast Reactor (IFR), in a burner mode, because of its inherent safety characteristics and its extensive past development in contrast to Acceleration Driven Systems (ADS). The IFR and an improved non-proliferation version of its pyro-processing technology can burn the plutonium (Pu) and minor actinides (MA) obtained by reprocessing LWR spent fuel. The remaining IFR and LWR fission products will be treated for storage at YM. The radiotoxicity of that high level waste (HLW) will fall below that of natural uranium in less than one thousand years. Due to anticipated increased capital, maintenance, and research costs for IFR, the third step is to reduce the required number of IFRs and their potential delays by implementing multiple recycles of Pu and Neptunium (Np) MA in LWR. That strategy is to use an advanced separation process, UREX+, and the MIX Pu option where the role and degradation of Pu is limited by uranium enrichment. UREX+ will decrease proliferation risks by avoiding Pu separation while the MIX fuel will lead to an equilibrium fuel recycle mode in LWR which will reduce U. S. Pu inventory and deliver much smaller volumes of less radioactive HLW to YM. In both steps two and three, Research and Development (R and D) is to emphasize the demonstration of multiple fuel reprocessing and fabrication, while improving HLW treatment, increasing proliferation resistance, and reducing losses of fissile material. The fourth step is to license and construct YM because it is needed for the disposal of defense wastes and the HLW to be generated under the proposed plan. The

  14. Radiation characteristics of spent nuclear fuel at accumulation in long-term storage

    International Nuclear Information System (INIS)

    Bergelson, Boris R.; Gerasimov, Aleksander S.

    1999-01-01

    Time dependence of a decay heat power and radiotoxicity of a single spent nuclear fuel unloading of VVER-1000 reactors at its storage or the same characteristics in accumulation mode with annual addition of spent nuclear fuel in long-term storage are investigated. At calculations of decay heat power, the contributions of alpha-, beta-, and gamma- irradiations were taken into account, at calculations of a radiotoxicity - maximum permissible activity of nuclides in air and in water were taken into account. It is determined that at accumulation less than 100 years, the main contribution to decay heat power is given by fission products, at further storage the power is determined in greater degree by actinides. The radiotoxicity of actinides by air is rich greater than that of fission products - more than 50 times in beginning of a storage and by 2-3 orders of magnitude after 100 and more years. A radiotoxicity of fission products by water at accumulation less than 20 years is a little bit more than actinides, at further accumulation the contribution of fission products decreases. At time of accumulation 100 years, the fission products give the contribution in total radiotoxicity about 40%, at time 1000 years - about 7%. (author)

  15. Behavior of high burnup fuel rod cladding during long-term dry storage in CASTOR casks

    International Nuclear Information System (INIS)

    Schaberg, A.; Spilker, H.; Goll, W.

    2000-01-01

    Short-time creep and rupture tests were performed to assess the strain potential of cladding of high burnt rods under conditions of dry storage. The tests comprised optimized Zr y-4 cladding samples from fuel rods irradiated to burnups of up to 64 MWd/kg U and were carried out at temperatures of 573 and 643 K at cladding stresses of about 400 and 600 MPa. The stresses, much higher than those occurring in a fuel rod, were chosen to reach circumferential elongations of about 2% within an envisaged testing time of 3-4 days. The creep tests were followed by a low temperature test at 423 K and 100 MPa to assess the long-term behavior of the cladding ductility especially with regard to the effect of a higher hydrogen content in the cladding due to the high burnup. The creep tests showed considerable uniform plastic elongations at these high burnups. It was demonstrated that around 600 K a uniform plastic strain of a least 2% is reached without cladding failure. The low temperature tests at 423 K for up to 5 days revealed no cladding failure under these conditions of reduced cladding ductility. It can be concluded that the increased hydrogen content has no adverse effect on cladding performance. (Authors)

  16. An assessment method for long-term management of Canada's used nuclear fuel

    International Nuclear Information System (INIS)

    Leiss, W.

    2006-01-01

    The nine-member Assessment Team, assembled by the Nuclear Waste Management Organization in early 2004, reported the results of its work in the NWMO document, 'Assessing the Options: Future Management of Used Nuclear Fuel in Canada (June 2004). The team was responding to the challenge to develop a rigorous and credible evaluation of multiple options, and one which would also satisfy a complex set of objectives: a solution that would be 'socially acceptable, technically sound, environmentally responsible, and economically feasible.' This paper describes the special challenges faced by the Assessment Team in seeking to respond to this multifaceted assignment. I open by discussing the implications of the institutional and legal framework inherited by the NWMO from the Seaborn Panel (including the government's response to the Seaborn Panel report), which in effect set a new standard for the practice of risk management decision making in Canada. I then review the highlights of the Assessment Team's report, including its chosen method, namely, multi-objective utility analysis. I conclude with a discussion of the longer term implications of the assessment work done to date for the next stages in the process of finding a credible solution for the long-term management of used nuclear fuel in Canada. (author)

  17. Interim report on the long-term outlook of energy demands and supplies

    International Nuclear Information System (INIS)

    1982-01-01

    The supply/demand committee on Overall Energy Council has long deliberated on the outlook of energy demands and supplies, and finalized its report, assuming a yearly economic growth of about 5% in 1980s and utmost efforts by both the people and the government: the background and basic ideas to decide the outlook, the outlook of energy demands and supplies, and conclusions. The energy demand for fiscal 1990 is put at 590 million kl (crude oil equivalent) and for fiscal 2000 at 770 million kl with energy saving ratios 15.5% and 25%, respectively. The energy supply by nuclear power for fiscal 1990 is then put at 46,000 MW with 11.3% of the total. In the energy supply outlook for fiscal 1990, the aspects of the economy and stability as well as the quantity of respective energy sources are considered, overall to reduce the reliance on petroleum. (Mori, K.)

  18. The Tasse concept (thorium based accelerator driven system with simplified fuel cycle for long term energy production)

    International Nuclear Information System (INIS)

    Berthou, V.; Slessarev, I.; Salvatores, M.

    2001-01-01

    Within the framework of the nuclear waste management studies, the ''one-component''. concept has to be considered as an attractive option in the long-term perspective. This paper proposes a new system called TASSE (''Thorium based Accelerator driven System with Simplified fuel cycle for long term Energy production''.), destined to the current French park renewal. The main idea of the TASSE concept is to simplify both the front and the back end of the fuel cycle, and his major goals are to provide electricity with low waste production, and with an economical competitiveness. (author)

  19. Long-term α-hazard of high activity waste from nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Girardi, F.; Bertozzi, G.

    1974-01-01

    The concentration and decay of α-emitters in high activity waste arising from spent nuclear fuel reprocessing was calculated under specified reference conditions. An attempt to evaluate the long-term hazard of such waste is being made by applying the ''barrier'' approach derived from reactor safety studies. Four barriers were identified, which could be evaluated in a probabilistic way by taking into account the great uncertainties present in each of them. The barriers are: 1) quality of the segregation afforded by deep geological formations, 2) stability of conditioned waste (chemical and physical), 3) retention by immediate surrounding, 4) distribution pattern of actinides in the environment. The analysis of a fictional accident showed that the uncertainties connected with the evaluation of the barriers' value are rather large. Additional studies particularly on the stability of conditioned waste and ecological properties of the environment towards actinides, would considerably improve our knowledge of the value of the barrier system. Chemical separation of actinides from high activity waste would be an additional option of undoubted value for the disposal of high activity waste. Its value for the overall safety of the entire waste inventory depends on many factors which need better evaluation, such as safety of the disposal of the separated actinides and the amount and quality of the additional waste generated by the separation process. An analysis of various levels of possible separations suggests that a reasonable target might be: Pu, Am and Cm, decontamination factor 10 3 ; Np, coextraction with U and Pu with a 90% yield

  20. Long Term Fuel Sustainable Fission Energy Perspective Relevant for Combating Climate Change

    International Nuclear Information System (INIS)

    Knapp, V.; Matijevic, M.; Pevec, D.; Crnobrnja, B.; Lale, D.

    2016-01-01

    In recent research we outlined climate relevant and immediately available proven light water nuclear strategy with a potential to contribute essentially and timely to reduction of carbon dioxide emission to the year 2065. We consider in this paper what is the perspective of fission energy after that year should its contribution be needed. Singling out two technologies with long term perspective which need no or small amounts of uranium, fast breeders and molten salt thorium reactors, we consider their main technical and safety characteristics. In both of these technologies it is essential to have starter nuclides as neither U238 nor Th232 are fissile. We investigated whether plutonium from spent fuel of light water reactors generated to the year 2065 would be present in quantities sufficient to continue operation on the same or similar level in both technologies. However in operational safety, proliferation risks, waste production, in our judgement we must give preference to thorium technology, if it would be ready in second half of the century.(author).

  1. Outlook for world nuclear power generation and long-term energy supply and demand situations

    International Nuclear Information System (INIS)

    Matsuo, Yuhji

    2012-01-01

    In this article, the author presents a long-term outlook for the world's nuclear generating capacity, taking into account the nuclear policy changes after Fukushima Daiichi nuclear power plant accident. World primary energy demand will grow from 11.2 billion tons of oil equivalent (toe) in 2009 to 17.3 billion toe in 2035. Along with this rapid increase in global energy consumption, the world's nuclear generating capacity will grow from 392 GW in 2010 to 484 GW in 2020 and 574 GW in 2035 in the 'Reference scenario'. Even in the 'Low nuclear scenario', where the maximum impact of Fukushima accident to the nuclear policies of each government is assumed, it will continue to grow in the future, exceeding 500 GW in 2035. In particular, Asian countries such as China and India will lead the growth both in the energy demand and in the nuclear power capacity. Therefore, it is essential to better ensure the safety of nuclear power generation. It is important for technologically developed countries, including Japan, to make active contributions to the establishment of a global nuclear safety control system. On the other hand, energy security and global warming will continue to be major issues, which will make it indispensable to make the best effort to save energy and expand renewable energy utilization. Japan is competitive in energy-saving and environmental conservation technologies, thus further development and utilization of there technologies should be a key option of Japan's growth growth strategy in the future. (author)

  2. Nuclear energy and ensuring the long-term energy supply in the German Federal Republic

    International Nuclear Information System (INIS)

    Koenig, H.H.

    1975-01-01

    The author reports on the papers read at the Reactor Conference in 1975. He pays special attention to the development of energy supply from nuclear stations, investigates the motives behind the growing resistance of the public, and shows that the acceptance procedure ensures the construction and operation of safe nuclear power installations. He also discusses the possibilities of improved energy utilisation, the climatic changes in coming generations, the characteristics of supply with nuclear district heating and process heat, as well as the state of building projects with high-temperature reactors and fast breeders. (orig.) [de

  3. Nuclear fuel supplies

    International Nuclear Information System (INIS)

    1960-01-01

    When the International Atomic Energy Agency was set up nearly three years ago, it was widely believed that it would soon become a world bank or broker for the supply of nuclear fuel. Some observers now seem to feel that this promise has been rather slow to come to fruition. A little closer analysis would, however, show that the promise can be fulfilled only in a certain objective context, and to the extent that this context exists, the development of the Agency's role has been commensurate with the actual needs of the situation

  4. Perspectives on long-term Eurasian energy supply: the role of the energy charter

    International Nuclear Information System (INIS)

    Kemper, R.

    2004-01-01

    This paper examines Croatian energy outlook in the broader 'Eurasian' context, taking into consideration the prospect of increasing energy import dependency in Western and Central Europe, and assesses the contribution that multilateral instruments, such as the Energy Charter Treaty, can make in promoting security of supply.(author)

  5. Japan revises its long-term energy supply and demand outlook

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    A report, published recently by the Japanese Ministry of International Trade and Industry, revises earlier official views about how the industrial colossus plans to meet its energy needs to the end of century and beyond. A small chapter is devoted to the role of nuclear power in Japans energy supply. (qui)

  6. Contribution to a proposition for a long term development of nuclear energy: the TASSE concept (Thorium based Accelerator driven System with Simplified fuel cycle for long term Energy Production); Contribution a une proposition d'un developpement a long terme de l'energie nucleaire: le concept TASSE (Thorium based Accelerator driven System with Simplified fuel cycle for long term Energy Production)

    Energy Technology Data Exchange (ETDEWEB)

    Berthou, V

    2000-10-30

    Nuclear industry creates waste which are in the middle of the discussion concerning the Nuclear Energy future. At this time, important decisions for the Energy production must be taken, so numerous researches are conducted within the framework of the Bataille law. The goal of these studies is to find a range of solutions concerning the waste management. An innovative system, called TASSE (Thorium based Accelerator driven System with Simplified fuel cycle for long term Energy production), is studied in this thesis. This reactor is included in a long term strategy, and is destined for the renewal of the reactor park. In the first part of this work, the main characteristics of TASSE have been defined. They are commensurate with some specific requirements such as: to insure a large time to the Nuclear Energy, to reduce the waste production in an important way, to eliminate waste already stocked in the present park, to insure the non proliferation, and to be economically competitive. Neutronics studies of TASSE have been done. A calculation procedure has been developed to reach the system equilibrium state. Several types of molten salts as well as a pebble-bed fuel have been studied. Thus, an optimal fuel has been brought out in regard to some parameters such as the burn up level, the spectrum, the waste toxicity, the cycle type. Eventually, various TASSE core layout have been envisaged. (author)

  7. Contribution to a proposition for a long term development of nuclear energy: the TASSE concept (Thorium based Accelerator driven System with Simplified fuel cycle for long term Energy Production); Contribution a une proposition d'un developpement a long terme de l'energie nucleaire: le concept TASSE (Thorium based Accelerator driven System with Simplified fuel cycle for long term Energy Production)

    Energy Technology Data Exchange (ETDEWEB)

    Berthou, V

    2000-10-30

    Nuclear industry creates waste which are in the middle of the discussion concerning the Nuclear Energy future. At this time, important decisions for the Energy production must be taken, so numerous researches are conducted within the framework of the Bataille law. The goal of these studies is to find a range of solutions concerning the waste management. An innovative system, called TASSE (Thorium based Accelerator driven System with Simplified fuel cycle for long term Energy production), is studied in this thesis. This reactor is included in a long term strategy, and is destined for the renewal of the reactor park. In the first part of this work, the main characteristics of TASSE have been defined. They are commensurate with some specific requirements such as: to insure a large time to the Nuclear Energy, to reduce the waste production in an important way, to eliminate waste already stocked in the present park, to insure the non proliferation, and to be economically competitive. Neutronics studies of TASSE have been done. A calculation procedure has been developed to reach the system equilibrium state. Several types of molten salts as well as a pebble-bed fuel have been studied. Thus, an optimal fuel has been brought out in regard to some parameters such as the burn up level, the spectrum, the waste toxicity, the cycle type. Eventually, various TASSE core layout have been envisaged. (author)

  8. Long-term fertilisation causes excess supply and loss of phosphorus in purple paddy soil.

    Science.gov (United States)

    Zhang, Yue-Qiang; Wen, Ming-Xia; Li, Xue-Ping; Shi, Xiao-Jun

    2014-04-01

    Phosphorus (P) loss from cropland is accelerating the eutrophication of waters around the world such as the Three Gorges Reservoir (TGR) in China. We investigated whether purple paddy soil under long-term P applications was a major source of P efflux to the TGR. Substantial surplus P in the plough layer (0-20 cm) was evident after 15-year P applications. Available P (Olsen-P) in the plough layer ranged from 1.9 to 42.4 mg kg(-1) and some of which will exceed the threshold of 30 mg kg(-1) for environmental concern within 7 years of P application (inorganic NPK with or without organic fertiliser). Between 30 and 70% of Olsen-P was leached out of the 0-30 cm soil layer. Surplus P resulted in high P concentrations in the surface water during the rice cropping season, and these concentrations exceeded those in most waters of the TGR and exceeded the critical level for eutrophication (0.1 mg L(-1)) during the first 10 days after rice planting. Furthermore, total P in run-off due to rainfall events exceeded the level for eutrophication, with a total loss of 43.2-147.9 g P ha(-1) depending on the fertilisation. Current agronomic P management in purple paddy soil is environmentally unsustainable in terms of the adverse impact on surface water quality. Integrated P management practices are urgently required to optimise crop yield while minimising P loss in order to protect surface water quality in the TGR region. © 2013 Society of Chemical Industry.

  9. Modeling sustainable long-term electricity supply-demand in Africa

    International Nuclear Information System (INIS)

    Ouedraogo, Nadia S.

    2017-01-01

    Highlights: • This study is one of the first detailed and complete representation of the African power system. • It models, within LEAP, possible future paths for the regional power systems. • All the end-users and supply side activities and actors are considered. • Three scenarios are examined: the baseline, the renewable energy, and the energy efficiency. • The energy efficiency scenario has allowed to draw a sustainable pathway for electrification. - Abstract: This paper develops a scenario-based model to identify and provide an array of electricity demand in Africa, and to derive them from the African power system of development. A system-based approach is performed by applying the scenario methodology developed by Schwartz in the context of the energy-economic modeling platform ‘Long-range Energy Alternative Planning’. Four scenarios are investigated. The Business as Usual scenario (BAU) replicates the regional and national Master Plans. The renewable-promotion scenario increases the share of renewable energy in the electricity mix. The demand and supply side efficiency scenarios investigate the impact of energy efficiency measures on the power system. The results show an increase in electricity demand by 4% by 2040, supply shortages and high emissions of Greenhouse Gases. Contrary to expectations, the renewable energy scenario did not emerge as the best solution to a sustainable electrification of the region. The energy efficiency scenarios have allowed us to draw a sustainable pathway for electrification.

  10. Will the short-term capital crisis have long-term effects on supply and infrastructure?

    International Nuclear Information System (INIS)

    Theal, C.

    2003-01-01

    Natural gas supply and infrastructure is influenced by market segmentation and capital crises. The dynamics of market segmentation was highlighted and the implications for growth in the pipeline business were outlined. It was noted that the strategy for growth must mirror exploration and production trends in frontier gas and in oil sands growth. Acquisitions will likely shift from traditional regulated companies to energy infrastructure companies such as non-regulated midstream assets, natural gas liquids facilities, and liquefied natural gas infrastructure. In 2001, U.S. companies had a significant influence on the Canadian market by acquiring several Canadian assets. Several graphs were included with this presentation depicting: evolving U.S. based presence; distribution of Canadian exploration and production assets; changing composition of acquirers in 2002; increased U.S. presence from 1999; Canadian consolidation trends; the American advantage; the capital crisis; year to year activity levels by the independents; impact on industry activity levels; capital spending trends; growth spending outside the Western Canada Sedimentary Basin; Royalty Trusts as the new intermediate sub-sector; and, reshaping the landscape. A final section of the presentation described the impact on supply and infrastructure of both oil and natural gas with reference to gas storage and pipelines. In particular the economics of developing frontier gas and shipping it via the Alaska pipeline and the proposed Mackenzie Delta pipeline was discussed. 3 tabs., 28 figs

  11. Potential of thorium-based fuel cycle for PWR core to reduce plutonium and long-term toxicity

    Energy Technology Data Exchange (ETDEWEB)

    Joo, Hyung Kook; Kim, Taek Kyum; Kim, Young Jin [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-01-01

    The cross section libraries and calculation methods of the participants were inter-compared through the first stage benchmark calculation. The multiplication factor of unit cell benchmark are in good agreement, but there is significant discrepancies of 2.3 to 3.5 %k at BOC and at EOC between the calculated infinite multiplication factors of each participants for the assembly benchmark. Our results with HELIOS show a reasonable agreement with the others except the MTC value at EOC. To verify the potential of the thorium-based fuel to consume the plutonium and to reduce the radioactivity from the spent fuel, the conceptual core with ThO{sub 2}-PuO{sub 2} or MOX fuel were constructed. The composition and quantity of plutonium isotopes and the radioactivity level of spent fuel for conceptual cores were analyzed, and the neutronic characteristics of conceptual cores were also calculated. The nuclear characteristics for ThO{sub 2}-PuO{sub 2} thorium fueled core was similar to MOX fueled core, mainly due to the same seed fuel material, plutonium. For the capability of plutonium consumption, ThO{sub 2}-PuO{sub 2} thorium fuel can consume plutonium 2.1-2.4 times MOX fuel. The fraction of fissile plutonium in the spent ThO{sub 2}-PuO{sub 2} thorium fuel is more favorable in view of plutonium consumption and non-proliferation than MOX fuel. The radioactivity of spent ThO{sub 2}-PuO{sub 2} thorium and MOX fuel batches were calculated. Since plutonium isotopes are dominant for the long-term radioactivity, ThO{sub 2}-PuO{sub 2} thorium has almost the same level of radioactivity as in MOX fuel for a long-term perspective. (author). 22 figs., 11 tabs.

  12. Supply assurance in the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Neff, T.L.; Jacoby, H.D.

    1979-01-01

    Nuclear fuel assurance, in the face of world and political uncertainties, is interrelated with nuclear technology development plans and international safeguards considerations. This has led some countries to accelerate their commitments to nuclear commercialization faster than necessary and has made non-proliferation policies harder to enforce. Fuel assurance is described on a national basis in three time scales: short-term, or resilience to supply interruptions; mid-term, or contract conditions in which governments make commitments to purchase or deliver; and long-term, or resource adequacy. A review of former assurance problems and current trends in the enrichment and uranium markets indicates that supplier concentration is no longer the major problem so much as non-proliferation actions. The present state of unstable equilibrium is expected to move in the direction of less fuel-supply assurance for countries having a small market or not subscribing to non-proliferation criteria. The authors, while generally optimistic that the fuel-supply system will function, express concern that policies for fuel stockpiles and the condition of uranium markets need improvement. 21 references

  13. Novel remote electronic medication supply model for opioid-dependent outpatients with polypharmacy--first long-term case study.

    Science.gov (United States)

    Allemann, Samuel S; Dürsteler, Kenneth M; Strasser, Johannes; Vogel, Marc; Stoeckle, Marcel; Hersberger, Kurt E; Arnet, Isabelle

    2017-08-16

    Patients with substance use disorders grow older thanks to effective treatments. Together with a high prevalence of comorbidities, psychological problems, and low social support, these patients are at high risk for medication non-adherence. Established treatment facilities face challenges to accommodate these complex patients within their setting. Electronic medication management aids (e-MMAs) might be appropriate to simultaneously monitor and improve adherence for these patients. We report the first long-term experiences with a novel remote electronic medication supply model for two opioid-dependent patients with HIV. John (beginning dementia, 52 years, 6 tablets daily at 12 am) and Mary (frequent drug holidays, 48 years, 5-6 tablets daily at 8 pm) suffered from disease progression due to non-adherence. We electronically monitored adherence and clinical outcomes during 659 (John) and 953 (Mary) days between July 2013 and April 2016. Both patients retrieved over 90% of the pouches within 75 min of the scheduled time. Technical problems occurred in 4% (John) and 7.2% (Mary) of retrievals, but on-site support was seldom required. Viral loads fell below detection limits during the entire observation period. Continuous medication supply and persistence with treatment of over 1.7 years, timing adherence of more than 90%, and suppressed HIV viral load are first results supporting the feasibility of the novel supply model for patients on opioid-assisted treatment and polypharmacy.

  14. Development of Integrity Evaluation Technology for the Long-term Spent Fuel Dry Storage System (1st year Report)

    International Nuclear Information System (INIS)

    Choi, Jong Won; Kook, Dong Hak; Kim, Jun Sub

    2010-05-01

    Korea has operated 16 Pressurized Water Reactors(PWR) and has a plan to construct additional nuclear power reactors as only PWR. This causes a big issue of PWR spent fuel accumulation problem now and in the future. KRMC(Korea Radioactive waste Management Coorporation) which was established in 2009 is charged with managing all kinds of radioactive waste that is produced in Korea. KRMC is considering spent fuel dry storage as an option to solve this spent fuel problem and developing the related engineering techniques. KAERI(Korea Atomic Energy Research Institute) also participated in this development and focused on evaluating the spent fuel dry storage system integrity for a long term operation. This report is the first year research product. The aims of the first year work scope are surveying and analyzing models which could anticipate degradation phenomena of the all dry storage components(spent fuel, structure materials, and equipment materials) and selecting items of the tests which are planned to perform in the next project stage. The major work areas consist of 'spent fuel degradation evaluation model development', 'test senario development', 'long-term evaluation of structural material characteristics', and 'dry storage system structure degradation model development'. These works were successfully achieved. This report is expected to contribute for the second year work which includes degradation model development and test senario development, and next project stage

  15. Comparing multi-criteria decision analysis and integrated assessment to support long-term water supply planning.

    Directory of Open Access Journals (Sweden)

    Lisa Scholten

    Full Text Available We compare the use of multi-criteria decision analysis (MCDA-or more precisely, models used in multi-attribute value theory (MAVT-to integrated assessment (IA models for supporting long-term water supply planning in a small town case study in Switzerland. They are used to evaluate thirteen system scale water supply alternatives in four future scenarios regarding forty-four objectives, covering technical, social, environmental, and economic aspects. The alternatives encompass both conventional and unconventional solutions and differ regarding technical, spatial and organizational characteristics. This paper focuses on the impact assessment and final evaluation step of the structured MCDA decision support process. We analyze the performance of the alternatives for ten stakeholders. We demonstrate the implications of model assumptions by comparing two IA and three MAVT evaluation model layouts of different complexity. For this comparison, we focus on the validity (ranking stability, desirability (value, and distinguishability (value range of the alternatives given the five model layouts. These layouts exclude or include stakeholder preferences and uncertainties. Even though all five led us to identify the same best alternatives, they did not produce identical rankings. We found that the MAVT-type models provide higher distinguishability and a more robust basis for discussion than the IA-type models. The needed complexity of the model, however, should be determined based on the intended use of the model within the decision support process. The best-performing alternatives had consistently strong performance for all stakeholders and future scenarios, whereas the current water supply system was outperformed in all evaluation layouts. The best-performing alternatives comprise proactive pipe rehabilitation, adapted firefighting provisions, and decentralized water storage and/or treatment. We present recommendations for possible ways of improving water

  16. Integrated scheme of long-term for spent fuel management of power nuclear reactors

    International Nuclear Information System (INIS)

    Ramirez S, J. R.; Palacios H, J. C.; Martinez C, E.

    2015-09-01

    After of irradiation of the nuclear fuel in the reactor core, is necessary to store it for their cooling in the fuel pools of the reactor. This is the first step in a processes series before the fuel can reach its final destination. Until now there are two options that are most commonly accepted for the end of the nuclear fuel cycle, one is the open nuclear fuel cycle, requiring a deep geological repository for the fuel final disposal. The other option is the fuel reprocessing to extract the plutonium and uranium as valuable materials that remaining in the spent fuel. In this study the alternatives for the final part of the fuel cycle, which involves the recycling of plutonium and the minor actinides in the same reactor that generated them are shown. The results shown that this is possible in a thermal reactor and that there are significant reductions in actinides if they are recycled into reactor fuel. (Author)

  17. Feeding the nuclear fuel cycle with a long term view; AREVA's front-end business units, uranium mining, UF6 conversion and isotopic enrichment

    International Nuclear Information System (INIS)

    Capus, G.A.P.; Autegert, R.

    2005-01-01

    As a leading provider of technological solutions for nuclear power generation and electricity transmission, the AREVA group has the unique capability of offering a fully integrated fuel supply, when requested by its customers. At the core of the AREVA group, COGEMA Front End Division is an essential part of the overall fuel supply chain. Composed of three Business Units and gathering several subsidiaries and joint 'ventures, this division enjoys several leading positions as shown by its market shares and historical production records. Current Uranium market evolutions put the natural uranium supply under focus. The uranium conversion segment also recently revealed some concerning evolutions. And no doubt, the market pressure will soon be directed also at the enrichment segment. Looking towards the long term, AREVA strongly believes that a nuclear power renewal is needed, especially to help limiting green house effect gas release. Therefore, to address future supplies needed to fuel the existing fleet of nuclear power plants, but also new ones, the AREVA group is planning very significant investments to build new facilities in all the three front-end market segments. As far as uranium mining is concerned, these new mines will be based upon uranium reserves of outstanding quality. As for uranium conversion and enrichment, two large projects will be based on the most advanced technologies. This paper is aimed at recalling COGEMA Front End Division experience, the current status of its plants and operating entities and will provide a detailed overview of its major projects. (authors)

  18. The long-term forecast of Taiwan's energy supply and demand: LEAP model application

    Energy Technology Data Exchange (ETDEWEB)

    Huang, Yophy, E-mail: yohuanghaka@gmail.com [Deptartment of Public Finance and Tax Administration, National Taipei College of Business, Taipei Taiwan, 10051 (China); Bor, Yunchang Jeffrey [Deptartment of Economics, Chinese Culture University, Yang-Ming-Shan, Taipei, 11114, Taiwan (China); Peng, Chieh-Yu [Statistics Department, Taoyuan District Court, No. 1 Fazhi Road, Taoyuan City 33053, Taiwan (China)

    2011-11-15

    The long-term forecasting of energy supply and demand is an extremely important topic of fundamental research in Taiwan due to Taiwan's lack of natural resources, dependence on energy imports, and the nation's pursuit of sustainable development. In this article, we provide an overview of energy supply and demand in Taiwan, and a summary of the historical evolution and current status of its energy policies, as background to a description of the preparation and application of a Long-range Energy Alternatives Planning System (LEAP) model of Taiwan's energy sector. The Taiwan LEAP model is used to compare future energy demand and supply patterns, as well as greenhouse gas emissions, for several alternative scenarios of energy policy and energy sector evolution. Results of scenarios featuring 'business-as-usual' policies, aggressive energy-efficiency improvement policies, and on-schedule retirement of Taiwan's three existing nuclear plants are provided and compared, along with sensitivity cases exploring the impacts of lower economic growth assumptions. A concluding section provides an interpretation of the implications of model results for future energy and climate policies in Taiwan. - Research Highlights: > The LEAP model is useful for international energy policy comparison. > Nuclear power plants have significant, positive impacts on CO{sub 2} emission. > The most effective energy policy is to adopt demand-side management. > Reasonable energy pricing provides incentives for energy efficiency and conservation. > Financial crisis has less impact on energy demand than aggressive energy policy.

  19. Safety aspects in the dry storage of spent nuclear fuel in long term operation

    Energy Technology Data Exchange (ETDEWEB)

    Nodarim, Claudir J.; Silva, Viviane B. da; Fontes, Gladson S. [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil); Saldanha, Pedro L.C., E-mail: claudirnodari@gmail.com, E-mail: vivisborges@gmail.com, E-mail: gsfontes@hotmail.com, E-mail: Saldanha@cnen.gov.br [Comissão Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    The purpose of the present paper is to discuss the safety assessment of the Dry Storage Unit (DSU), taking into account the long term operation and the operational experience already evidenced in similar facilities. In this sense, the RIDM (Risk-Informed Decision-Making) concept will be adopted for the regulatory decision-making process. Potential technical issues associated with the aging of materials from the dry storage unit will be considered. The work will be done using the rules and requirements of 10 CFR Part 72 and the U.S. NRC (United States Nuclear Regulatory Commission) regulatory guides. (author)

  20. On the Properties and Long-Term Stability of Infiltrated Lanthanum Cobalt Nickelates (LCN) in Solid Oxide Fuel Cell Cathodes

    DEFF Research Database (Denmark)

    Kiebach, Wolff-Ragnar; Zielke, Philipp; Veltzé, Sune

    2017-01-01

    Infiltration as a fabrication method for solid oxide fuel cells (SOFC) electrodes is offering significant improvements in cell performance at reduced materials and fabrication costs, especially when combined with co-sintering. However, important questions regarding the long-term performance...... and microstructural stability remain unanswered. Here, we present the results of a three-year project, where large footprint anode-supported SOFCs with a co-sintered cathode backbone and infiltrated La0.95Co0.4Ni0.6O3 (LCN) cathodes were developed and thoroughly characterized. The initial long-term performance...... in the electrode properties using SEM, BET area, and in-plane conductivity measurements. Finally, the mechanical properties of co-sintered cathode backbone cells were determined in four-point bending tests carried out both at room temperature and at 800°C in air. Based on these results, degradation mechanisms were...

  1. Activity release from the damaged spent VVER-fuel during long-term wet storage

    Energy Technology Data Exchange (ETDEWEB)

    Slonszki, E.; Hozer, Z. [Hungarian Academy of Sciences, KFKI Atomic Energy Research Inst., Budapest (Hungary); Pinter, T.; Baracska Varju, I. [Nuclear Power Plant Paks, Paks (Hungary)

    2010-07-01

    An ex-core fuel damage incident took place at Unit 2 of Paks Nuclear Power Plant in Hungary on the 10{sup th} April 2003. After this event the damaged fuel assemblies were stored under water for four years. During wet storage a continuous activity release was observed. The evaluation of the measured activity concentration showed that the UO{sub 2} mass released from the fuel into the coolant was {approx} 1.8% of the total fuel mass. Furthermore this paper contains the calculation methods and the calculated activity release of the main analysed isotopes. (orig.)

  2. Activity release from the damaged spent VVER-fuel during long-term wet storage

    International Nuclear Information System (INIS)

    Slonszki, E.; Hozer, Z.; Pinter, T.; Baracska Varju, I.

    2010-01-01

    An ex-core fuel damage incident took place at Unit 2 of Paks Nuclear Power Plant in Hungary on the 10 th April 2003. After this event the damaged fuel assemblies were stored under water for four years. During wet storage a continuous activity release was observed. The evaluation of the measured activity concentration showed that the UO 2 mass released from the fuel into the coolant was ∼ 1.8% of the total fuel mass. Furthermore this paper contains the calculation methods and the calculated activity release of the main analysed isotopes. (orig.)

  3. Introduction of Thorium in the Nuclear Fuel Cycle. Short- to long-term considerations

    International Nuclear Information System (INIS)

    Allibert, M.; Merle-Lucotte, E.; Ghetta, V.; Ault, T.; Krahn, S.; Wymer, R.; Croff, A.; Baron, P.; Chauvin, N.; Eschbach, R.; Rimpault, G.; Serp, J.; Bergeron, A.; Bromley, B.; Floyd, M.; Hamilton, H.; Hyland, B.; Wojtaszek, D.; McDonald, M.; Collins, E.; Cornet, S.; Michel-Sendis, F.; ); Feinberg, O.; Ignatiev, V.; Hesketh, K.; Kelly, J.F.; Porsch, D.; Vidal, J.; Taiwo, T.; Uhlir, J.; Van Den Durpel, L.; Van Den Eynde, G.; Vitanza, C.; Butler, Gregg; Cornet, Stephanie; Dujardin, Thierry; Greneche, Dominique; Nordborg, Claes; Rimpault, Gerald; Van Den Durpel, Luc; Michel-Sendis, Franco

    2015-01-01

    Since the beginning of the nuclear era, significant scientific attention has been given to thorium's potential as a nuclear fuel. Although the thorium fuel cycle has never been fully developed, the opportunities and challenges that might arise from the use of thorium in the nuclear fuel cycle are still being studied in many countries and in the context of diverse international programmes around the world. This report provides a scientific assessment of thorium's potential role in nuclear energy both in the short to longer term, addressing diverse options, potential drivers and current impediments to be considered if thorium fuel cycles are to be pursued. (authors)

  4. The role of long-term geologic changes in the regulation of the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Flavelle, P.

    1996-01-01

    It is recognized that the geosphere is a dynamic system over the long time frames of nuclear fuel waste disposal. This paper describes how consideration of a dynamic geosphere has impacted upon the evolving regulatory environment in Canada, and how the approach taken to comply with the regulatory requirements can affect the evaluation of long-term geologic changes. AECB staff opinion is that if the maximum possible effect of geologic changes can be demonstrated to have negligible impact on the safety of a nuclear fuel waste repository, then further consideration of a dynamic geosphere is unnecessary for the current review of the Canadian Nuclear Fuel Waste Management Program. (authors). 7 refs., 4 figs

  5. Relative toxicity and long-term problems of actinide bearing wastes from fuel reprocessing

    International Nuclear Information System (INIS)

    Haug, H.O.

    1976-01-01

    Waste management systems are being developed that are capable of adequate protection during operational phases and providing the necessary long-term isolation for the long-lived radioisotopes to decay. For the assessment of the safety of proposed systems for managing wastes, methods for risk analysis are being developed in several countries. Risk analysis identifies the most likely sequences of failure events (for example by fault free analysis) possibly leading to release of radioactive material into man's environment, and evaluates the probabilities of these sequences. However, parts of the risk analysis are not yet developed to the necessary degree and will be a difficult task for the years ahead. We have therefore looked into some models and approaches which give no risk analysis but may be useful for entering into the magnitude and correlations of some of the problems

  6. Corrosion inhibition studies in support of the long term storage of AGR fuel

    Energy Technology Data Exchange (ETDEWEB)

    Standring, P [Sellafield Limited (United Kingdom)

    2012-07-01

    Thorp Receipt and Storage (at Sellafield, UK) is currently being investigated as a bridging solution for the storage of AGR fuel pending the out-come of a national review into spent fuel management. AGR spent fuel is known to be susceptible to corrosion through inter-granular attack. To avoid this, the chosen storage regime for AGR fuel is sodium hydroxide dosed pond water to pH 11.4; now 22 years of operating experience. The conversion of TR and S will require a phased transition. During this transition sodium hydroxide cannot be used due to materials compatibility issues. Alternative corrosion inhibitors have been investigated as an interim measure and sodium nitrate has been selected as a suitable candidate. The efficiency of sodium nitrate to inhibit propagating inter-granular attack of active AGR materials has yet to be established. In the longer term sodium hydroxide will be deployed along with a move to a closed loop pond water management system. Given that carbon dioxide is known to be absorbed by sodium hydroxide dosed water and can affect fuel integrity, in the case of Magnox fuel, there is a need to establish its impact on AGR fuel. The objectives are: To establish the impact of carbonate on AGR fuel corrosion; To establish the efficiency of sodium nitrate to inhibit propagating inter-granular attack of irradiated AGR materials.

  7. The French program on the spent nuclear fuel long term evolution: Major results, uncertainties and new requirements

    International Nuclear Information System (INIS)

    Ferry, Cecile; Poinssot, Christophe; Gras, Jean-Marie

    2006-01-01

    The 1991 Radioactive Waste Management Act established a framework in France for research activities on nuclear waste. Within this context, the Commissariat a l'Energie Atomique initiated a research program in 1999 to investigate the long-term behaviour of commercial spent nuclear fuel under the PRECCI project (from the French acronym for Research Project on Long-Term Evolution of Spent Fuel Packages), supported by the French electrical utility EDF and partially by FRAMATOME ANP. The scientific and technical studies performed within the project aim to address the operational issues of the spent fuel end-of-life. Within the context of the law which ends in 2006, the major part of the studies focused on the behaviour of the spent fuel (SF) in interim long-term dry storage and deep geological disposal. The operational questions initially identified concern (i) the retrievability of spent fuel assemblies at the end of the interim period of storage, (ii) the feasibility of treatment after the period of storage, (iii) the radionuclide source terms for SF in storage and geological disposal and (iv) the compatibility between storage and a subsequent geological disposal. Therefore the long-term evolution of the irradiated fuel is studied under the various boundary conditions encountered during storage and geological disposal: - in a closed system; this condition corresponds to the nominal scenario during storage and to the first confinement phase in disposal conditions (with a duration of 10,000 years in the reference scenario); - it consists in assessing the effects of the residual temperature and high radioactivity on the chemical and physical properties of the spent fuel pellets; - some of the studies are also dedicated to the mechanical behaviour of the cladding and structural materials of the assemblies; - in air, it refers to an incidental loss of confinement during storage or to a breaching of the canister before the site re-saturation in geological disposal

  8. Data needs for long-term dry storage of LWR fuel. Interim report

    International Nuclear Information System (INIS)

    Einziger, R.E.; Baldwin, D.L.; Pitman, S.G.

    1998-04-01

    The NRC approved dry storage of spent fuel in an inert environment for a period of 20 years pursuant to 10CFR72. However, at-reactor dry storage of spent LWR fuel may need to be implemented for periods of time significantly longer than the NRC's original 20-year license period, largely due to uncertainty as to the date the US DOE will begin accepting commercial spent fuel. This factor is leading utilities to plan not only for life-of-plant spent-fuel storage during reactor operation but also for the contingency of a lengthy post-shutdown storage. To meet NRC standards, dry storage must (1) maintain subcriticality, (2) prevent release of radioactive material above acceptable limits, (3) ensure that radiation rates and doses do not exceed acceptable limits, and (4) maintain retrievability of the stored radioactive material. In light of these requirements, this study evaluates the potential for storing spent LWR fuel for up to 100 years. It also identifies major uncertainties as well as the data required to eliminate them. Results show that the lower radiation fields and temperatures after 20 years of dry storage promote acceptable fuel behavior and the extension of storage for up to 100 years. Potential changes in the properties of dry storage system components, other than spent-fuel assemblies, must still be evaluated

  9. Forest industry wood fuel supply

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

    The potential for wood fired energy production in the UK is significant. Large scale developments are currently underway which could utilise over 100,000 green tonnes of forest residues. The fuel supply chain is likely to be complicated and there are perceived risks in its organisation and security. This report sets out to address some of these perceived risks and suggest suitable measures to reduce it. Six areas of the fuel supply chain have been studied, namely; Extraction, Comminution, Transport, Assessment and payment of wood fuel; Environmental impact; Nutrient recycling (ash disposal). (author)

  10. Long-term testing of HTR fuel elements in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Nickel, H.

    1986-12-01

    The extensive results from irradiation experiments carried out on coated particles, on graphitic matrices of different composition and on integral fuel elements have shown that the spherical fuel elements with high-enriched uranium/thorium mixed-oxide particles and optimized graphitic matrix are available for use in the planned HTR facilities. A concentrated qualification programme is on the way in order to bring the fuel elements with particles from low-enriched uranium dioxide (LEU) and TRISO coating to a comparable level of experience and knowledge, i.e. to make them licensable for the planned HTR facilities. (orig.) [de

  11. Corrosion issues in the long term storage of aluminum-clad spent nuclear fuels

    International Nuclear Information System (INIS)

    Louthan, M.R. Jr.; Peacock, H.B. Jr.; Sindelar, R.L.; Iyer, N.C.

    1996-01-01

    Approximately 8% of the spent nuclear fuel owned by the US Department of Energy is clad with aluminum alloys. The spent fuel must be either reprocessed or temporarily stored in wet or dry storage systems until a decision is made on final disposition in a repository. There are corrosion issues associated with the aluminum cladding regardless of the disposition pathway selected. This paper discusses those issues and provides data and analysis to demonstrate that control of corrosion induced degradation in aluminum clad spent fuels can be achieved through relatively simple engineering practices

  12. Synthesis on the long term behavior of spent nuclear fuel. Vol.1,2; Synthese sur l'evolution a long terme des colis de combustibles irradies. Tome 1,2

    Energy Technology Data Exchange (ETDEWEB)

    Poinssot, Ch.; Toulhoat, P.; Grouiller, J.P.; Pavageau, J.; Piron, J.P.; Pelletier, M.; Dehaudt, Ph.; Cappelaere, Ch.; Limon, R.; Desgranges, L.; Jegou, Ch.; Corbel, C.; Maillard, S.; Faure, M.H.; Cicariello, J.C.; Masson, M. [CEA Saclay, DEN/DDIN/DPRGD, 91 - Gif sur Yvette (France)

    2001-07-01

    The aim of this report is to present the major objectives, the key scientific issues, and the preliminary results of the research conducted in France in the framework of the third line of the 1991 Law, on the topic of the long term behavior of spent nuclear fuel in view of long term storage or geological disposal. Indeed, CEA launched in 1998 the Research Program on the Long Term Behavior of Spent Nuclear Fuel (abbreviated and referred to as PRECCI in French; Poinssot, 1998) the aim of which is to study and assess the ability of spent nuclear fuel packages to keep their initially allocated functions in interim storage and geological disposal: total containment and recovery functions for duration up to hundreds of years (long term or short-term interim storage and/or first reversible stages of geological disposal) and partial confinement function (controlled fluxes of RN) for thousands of years in geological disposal. This program has to allow to obtain relevant and reliable data concerning the long term behavior of the spent fuel packages so that feasibility of interim storage and/or geological disposal can be assessed and demonstrated as well as optimized. Within this framework, this report presents for every possible scenario of evolution (closed system, in Presence of water in presence of gases) what are estimated to be the most relevant evolution mechanism. For the most relevant scientific issues hence defined, a complete scientific review of the best state of knowledge is subsequently here given thus allowing to draw a clear guideline of the major R and D issues for the next years. (authors)

  13. MOX fuel cycle technologies for medium and long term deployment. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    More than thirty years of reactor experience using MOX fuel as well as the fabrication of 2000 MOX assemblies with the use of 85 t of Pu separated from spent fuel from power reactors indicates that the recycling of plutonium as MOX fuel in LWRs has become a mature industry. The number of countries engaged in plutonium recycling could be increasing in the near future, aiming for the reduction of stockpiles of separated plutonium from earlier and existing reprocessing contracts. Economic and strategic considerations are the main factors on which to base such a decision to use MOX. Transport of MOX fuel assemblies is a vital element in these recycle programmes but could have the potential to be a weak link in the chain. To avoid problems, it is essential that sufficient numbers of transport flasks of the required types, licensed for the increasing Pu contents, be made available in a timely manner to keep pace with the planned increases in fabrication rates. Despite the excellent safety records for radioactive and MOX transports over many decades, continuous attention should be drawn to establishing the transport modalities, buffer stores, secure vehicles, and transport routes, at the same time accounting for public sensitivities on radioactive transports in general and MOX transport in particular. A large number of technical presentations updated and reconfirmed the good and almost defect-free performance of MOX fuel at increasingly high burn-up levels. MOX fuel is designed to meet the same operational and safety criteria as uranium fuels under equivalent conditions. This is also confirmed by the parallel development of design codes to accommodate the special characteristics of MOX. Integral and specific parameter testing of MOX fuel in normal and off-normal operation is under way in a number of countries with particular emphasis on high burnup behaviour. Here the important contributions of the OECD/NEA Halden BWR programme should be mentioned. The reactor

  14. MOX fuel cycle technologies for medium and long term deployment. Proceedings

    International Nuclear Information System (INIS)

    2000-01-01

    More than thirty years of reactor experience using MOX fuel as well as the fabrication of 2000 MOX assemblies with the use of 85 t of Pu separated from spent fuel from power reactors indicates that the recycling of plutonium as MOX fuel in LWRs has become a mature industry. The number of countries engaged in plutonium recycling could be increasing in the near future, aiming for the reduction of stockpiles of separated plutonium from earlier and existing reprocessing contracts. Economic and strategic considerations are the main factors on which to base such a decision to use MOX. Transport of MOX fuel assemblies is a vital element in these recycle programmes but could have the potential to be a weak link in the chain. To avoid problems, it is essential that sufficient numbers of transport flasks of the required types, licensed for the increasing Pu contents, be made available in a timely manner to keep pace with the planned increases in fabrication rates. Despite the excellent safety records for radioactive and MOX transports over many decades, continuous attention should be drawn to establishing the transport modalities, buffer stores, secure vehicles, and transport routes, at the same time accounting for public sensitivities on radioactive transports in general and MOX transport in particular. A large number of technical presentations updated and reconfirmed the good and almost defect-free performance of MOX fuel at increasingly high burn-up levels. MOX fuel is designed to meet the same operational and safety criteria as uranium fuels under equivalent conditions. This is also confirmed by the parallel development of design codes to accommodate the special characteristics of MOX. Integral and specific parameter testing of MOX fuel in normal and off-normal operation is under way in a number of countries with particular emphasis on high burnup behaviour. Here the important contributions of the OECD/NEA Halden BWR programme should be mentioned. The reactor

  15. Long-term effects of neutron absorber and fuel matrix corrosion on criticality

    International Nuclear Information System (INIS)

    Culbreth, W.G.; Zielinski, P.R.

    1994-01-01

    Proposed waste package designs will require the addition of neutron absorbing material to prevent the possibility of a sustained chain reaction occurring in the fuel in the event of water intrusion. Due to the low corrosion rates of the fuel matrix and the Zircaloy cladding, there is a possibility that the neutron absorbing material will corrode and leak from the waste container long before the subsequent release of fuel matrix material. An analysis of the release of fuel matrix and neutron absorber material based on a probabilistic model was conducted and the results were used to prepare input to KENO-V, an neutron criticality code. The results demonstrate that, in the presence of water, the computed values of k eff exceeded the maximum of 0.95 for an extended period of time

  16. Development of comprehensive long-term-dry stored Spent Fuel INtegrity EvaLuator [SFINEL] - I

    International Nuclear Information System (INIS)

    Kwon, H. M.; Yang, Y. S.; Kim, Y. S.; You, K. S.; Min, D. K.; No, S. K.

    1999-01-01

    Safe management of spent nuclear fuels is socially, technically, and economically very important in terms of environmental protection and utilization of recyclable resources. One of the most critical parts in the management is to establish the comprehensive monitoring system which can maintain and confirm the integrity of the spent fuels, whenever necessary, until final policy is determined on the their treatment and disposal. Especially in the first stage of maturing up the system, it is essential to secure a computing tool or code which can evaluate the integrity of the fuel cladding based on its power history and cladding degradation mechanisms. SFINEL code, an integrated computer program for predicting the spent fuel rod integrity based on burn-up history and major degradation mechanisms, has been developed in this research. This code can sufficiently simulate the power history of a fuel rod during the reactor operation and estimate the degree of deterioration of spent fuel cladding using the recently-developed models on the degradation mechanisms

  17. Modeling generation expansion in the context of a security of supply mechanism based on long-term auctions. Application to the Colombian case

    International Nuclear Information System (INIS)

    Rodilla, P.; Batlle, C.; Salazar, J.; Sanchez, J.J.

    2011-01-01

    In an attempt to provide electricity generation investors with appropriate economic incentives so as to maintain quality of supply at socially optimal levels, a growing number of electricity market regulators have opted for implementing a security of supply mechanism based on long-term auctions. In this context, the ability to analyze long-term investment dynamics is a key issue not only for market agents, but also for regulators. This paper describes a model developed to serve this purpose. A general system-dynamics-inspired methodology has been designed to be able to simulate these long-term auction mechanisms in the formats presently in place. A full-scale simulation based on the Colombian system was conducted to illustrate model capabilities. (author)

  18. Modeling generation expansion in the context of a security of supply mechanism based on long-term auctions. Application to the Colombian case

    Energy Technology Data Exchange (ETDEWEB)

    Rodilla, P.; Batlle, C. [Institute for Research in Technology, University Pontificia Comillas, Sta. Cruz de Marcenado 26, 28015 Madrid (Spain); Salazar, J. [Empresas Publicas de Medellin, Carrera 58 No. 42-125 Edificio Inteligente, Medellin (Colombia); Sanchez, J.J. [Secretaria de Estado de Cambio Climatico, Ministerio de Medio Ambiente, Rural y Marino. Plaza San Juan de la Cruz, 28071 Madrid (Spain)

    2011-01-15

    In an attempt to provide electricity generation investors with appropriate economic incentives so as to maintain quality of supply at socially optimal levels, a growing number of electricity market regulators have opted for implementing a security of supply mechanism based on long-term auctions. In this context, the ability to analyze long-term investment dynamics is a key issue not only for market agents, but also for regulators. This paper describes a model developed to serve this purpose. A general system-dynamics-inspired methodology has been designed to be able to simulate these long-term auction mechanisms in the formats presently in place. A full-scale simulation based on the Colombian system was conducted to illustrate model capabilities. (author)

  19. The strategy of the long-term back-end nuclear fuel cycle in the Czech Republic

    International Nuclear Information System (INIS)

    Palagyi, S.; Fajman, V.

    2002-01-01

    The present status of the strategy of the long-term back-end nuclear fuel cycle in the Czech Republic is briefly outlined in this paper. This strategy is based on the once-through option in the use of the nuclear fuel with subsequent interim storage of the spent fuel and its final disposal as a declared high level waste. However, other technologies for the management of the back-end of the nuclear fuel cycle are not excluded at all. Besides the first already existing and the second interim spent fuel storage facility being sited at Dukovany Nuclear Power Plant, an interim spent fuel storage facility at Temelin Nuclear Power Plant is also under the siting process. To cover the total storing needs a central spent nuclear fuel interim storage facility at Skalka in the Czech-Moravian Highlands is also under consideration. These facilities are or will be equipped with dry-storage containers of cask-type placed in the concrete building and cooled by natural air ventilation. Since 1993 there is a joint effort of several governmental organisations and institutions and private companies to study the scientific, technical and economical possibilities of the construction of the deep geological repository for spent nuclear fuel disposal. A horizontal repository facility with vertical access was selected and a reference project has been accepted. A time horizon for construction in about the year of 2035 was scheduled. The necessary legal and administrative basis of the spent fuel and radioactive waste management was laid down by the law No. 18/1997 (Atomic Act) passed in 1997. This basic law with its implementing regulations fully reflects the internationally accepted principles of the provision of nuclear safety and radiation protection in this respect and it also strongly supports the policy and strategy of the back-end of the nuclear fuel cycle. (author)

  20. Long-term estradiol-17β administration changes the population of paracervical ganglion neurons supplying the ovary in adult gilts.

    Science.gov (United States)

    Jana, Barbara; Palus, Katarzyna; Czarzasta, Joanna; Całka, Jarosław

    2013-07-01

    The aim of this study was to determine the influence of estradiol-17β (E(2)) overdose on the number and distribution of ovarian parasympathetic neurons in the paracervical ganglion (PCG) in adult pigs. To identify the neurons innervating gonads on day 3 of the estrous cycle, the ovaries of both the control and experimental gilts were injected with retrograde neuronal tracer Fast Blue. From next day to the expected day 20 of the second studied cycle, experimental gilts were injected with E(2), while control gilts received oil. The PCG were then collected and processed for double-labeling immunofluorescence. Injections of E(2) increased the E(2) level in the peripheral blood approximately four- to fivefold and reduced the following in the PCG: the total number of Fast Blue-positive neurons; the number of perikarya in the lateral part of the PCG; the numbers of vesicular acetylcholine transporter (VAChT)(+)/somatostatin(+), VAChT(+)/vasoactive intestinal polypeptide (VIP)(+), VAChT(+)/neuronal isoform of nitric oxide synthase(+), VAChT(+)/VIP(-), VAChT(+)/dopamine β-hydroxylase (DβH)(-), VAChT(-)/VIP(-), and VAChT(-)/DβH(-) perikarya; and the total number of perikarya expressing estrogen receptors (ERs) subtype α and/or β. In summary, long-term E(2) treatment of adult gilts downregulates the population of both cholinergic and ERs expressing the PCG ovary-projecting neurons. Our results suggest that elevated E(2) levels occurring during pathological states may regulate gonadal function(s) by affecting ovary-supplying neurons.

  1. Long-term contracts for European gas supply - an empirical analysis of the changing nature of pipeline and LNG-contracts

    International Nuclear Information System (INIS)

    Neumann, Anne

    2005-01-01

    As the structure of the European natural gas market is evolving towards more competition and more diverse market structures than before, the nature of the long-term contracts for European natural gas supply is also undergoing change. Experience from other liberalization processes, such as in the U.S. or the UK, suggests that the importance of long-term contracts diminishes over time, but that they remain an important element of supply. In Europe long-term contracts are still considered as a firm basis for investment and financing of capital-intensive infrastructure with a high degree of asset and relationship-specificity. Literature on institutional economics also suggests that long-term contracts act as a device to overcome the ''hold-up'' problem of relationship-specific investments in infrastructure (Klein, Crawford, and Alchian, 1987; Williamson, 1975, 1985). On the other hand, Hartley and Brito (2002) show that more flexible markets also imply a lower degree of asset specificity, thus requiring less fixed contracts. This paper explores the changing nature of long-term contracts for European natural gas supply, with a particular focus on differences between contracts for pipeline gas and liquefied natural gas (LNG). Traditionally, Europe relied on very long-term contracts for pipeline gas (Russia, Norway, Algeria). More recently, increasing LNG supplies are contemplated as a more flexible source of natural gas: The international LNG market is becoming more flexible, LNG can be sourced from a variety of sellers, and the cost of LNG supplies and infrastructure is coming down rapidly (Jensen, 2004). Thus, the evaluation of investing in LNG infrastructure (and the so bought flexibility and possibility of arbitraging profits) may be higher than committing to fixed/predetermined flows of pipeline gas. We ask whether this is reflected in the observed contracts. The paper is based on standard contract theory (Bolton and Dewatripont, 2005). We apply a microeconomic

  2. 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.)

  3. Decay heat power of spent nuclear fuel of power reactors with high burnup at long-term storage

    Science.gov (United States)

    Ternovykh, Mikhail; Tikhomirov, Georgy; Saldikov, Ivan; Gerasimov, Alexander

    2017-09-01

    Decay heat power of actinides and fission products from spent nuclear fuel of power VVER-1000 type reactors at long-term storage is calculated. Two modes of storage are considered: mode in which single portion of actinides or fission products is loaded in storage facility, and mode in which actinides or fission products from spent fuel of one VVER reactor are added every year in storage facility during 30 years and then accumulated nuclides are stored without addition new nuclides. Two values of fuel burnup 40 and 70 MW·d/kg are considered for the mode of storage of single fuel unloading. For the mode of accumulation of spent fuel with subsequent storage, one value of burnup of 70 MW·d/kg is considered. Very long time of storage 105 years accepted in calculations allows to simulate final geological disposal of radioactive wastes. Heat power of fission products decreases quickly after 50-100 years of storage. The power of actinides decreases very slow. In passing from 40 to 70 MW·d/kg, power of actinides increases due to accumulation of higher fraction of 244Cm. These data are important in the back end of fuel cycle when improved cooling system of the storage facility will be required along with stronger radiation protection during storage, transportation and processing.

  4. Decay heat power of spent nuclear fuel of power reactors with high burnup at long-term storage

    Directory of Open Access Journals (Sweden)

    Ternovykh Mikhail

    2017-01-01

    Full Text Available Decay heat power of actinides and fission products from spent nuclear fuel of power VVER-1000 type reactors at long-term storage is calculated. Two modes of storage are considered: mode in which single portion of actinides or fission products is loaded in storage facility, and mode in which actinides or fission products from spent fuel of one VVER reactor are added every year in storage facility during 30 years and then accumulated nuclides are stored without addition new nuclides. Two values of fuel burnup 40 and 70 MW·d/kg are considered for the mode of storage of single fuel unloading. For the mode of accumulation of spent fuel with subsequent storage, one value of burnup of 70 MW·d/kg is considered. Very long time of storage 105 years accepted in calculations allows to simulate final geological disposal of radioactive wastes. Heat power of fission products decreases quickly after 50-100 years of storage. The power of actinides decreases very slow. In passing from 40 to 70 MW·d/kg, power of actinides increases due to accumulation of higher fraction of 244Cm. These data are important in the back end of fuel cycle when improved cooling system of the storage facility will be required along with stronger radiation protection during storage, transportation and processing.

  5. Durability and regeneration of activated carbon air-cathodes in long-term operated microbial fuel cells

    Science.gov (United States)

    Zhang, Enren; Wang, Feng; Yu, Qingling; Scott, Keith; Wang, Xu; Diao, Guowang

    2017-08-01

    The performance of activated carbon catalyst in air-cathodes in microbial fuel cells was investigated over one year. A maximum power of 1722 mW m-2 was produced within the initial one-month microbial fuel cell operation. The air-cathodes produced a maximum power >1200 mW m-2 within six months, but gradually became a limiting factor for the power output in prolonged microbial fuel cell operation. The maximum power decreased by 55% when microbial fuel cells were operated over one year due to deterioration in activated carbon air-cathodes. While salt/biofilm removal from cathodes experiencing one-year operation increased a limiting performance enhancement in cathodes, a washing-drying-pressing procedure could restore the cathode performance to its original levels, although the performance restoration was temporary. Durable cathodes could be regenerated by re-pressing activated carbon catalyst, recovered from one year deteriorated air-cathodes, with new gas diffusion layer, resulting in ∼1800 mW m-2 of maximum power production. The present study indicated that activated carbon was an effective catalyst in microbial fuel cell cathodes, and could be recovered for reuse in long-term operated microbial fuel cells by simple methods.

  6. A risk-based monitoring framework for the long term management of used fuel

    International Nuclear Information System (INIS)

    Garisto, N.C.

    2006-01-01

    The Nuclear Waste Management Organization has a mandate from the Government of Canada to consult with the public and to recommend an approach for managing Canada's used nuclear fuel. Three main fuel management methods are being explored and evaluated by the Nuclear Waste Management Organization: disposal in a Deep Geological Repository (DGR); reactor-site extended storage (RES); and centralized extended storage (CES), either above ground or below ground. The used nuclear fuel management system, whether a DGR or an extended storage system will require monitoring. In this study, a risk-based monitoring framework was developed for the used fuel management program. The proposed approach addresses the unique challenges of used fuel management being implemented in a multi-stakeholder process, including: (i) the complexity of the facilities; (ii) the need to consider both science-based risk and perceived risk in the monitoring plans; and (iii) the difficulty in conducting 'invasive' measurements of sealed systems, particularly over a very long time frame. (author)

  7. Oxidation of nuclear fuel below 400 deg. Consequence on long-term dry storage

    International Nuclear Information System (INIS)

    Dehaudt, Ph.

    2000-01-01

    This document reviews the status of the knowledge on the oxidation of fuels below 400 deg C, in all its forms, including fuel rods, by examining the consequences of this reaction on the strength or ruin of the fuel rods during dry storage in air for a hundred years. The data available in the scientific literature, and the data acquired by CEA, are abundant on irradiated powders and pellets, but sparser for irradiated fuel fragments and for rods or sections of fuel rods. A bibliographic review is made to identify the morphological and structural changes, as well as the kinetic laws. An analysis and a summary is made with a concern to evaluate the risks of rod ruin by oxidation. The final section, in a few pages, addresses the essential lessons from this study. It presents: first, a summary of the main results of this review and its analysis, recommendations and remedies for storage; proposed research guidelines as well as precise topics, in order to fill out our knowledge and, even better, to identify the acceptable limits for storage. (author)

  8. Long-term ocean oxygen depletion in response to carbon dioxide emissions from fossil fuels

    DEFF Research Database (Denmark)

    Shaffer, G.; Olsen, S.M.; Pedersen, Jens Olaf Pepke

    2009-01-01

    Ongoing global warming could persist far into the future, because natural processes require decades to hundreds of thousands of years to remove carbon dioxide from fossil-fuel burning from the atmosphere(1-3). Future warming may have large global impacts including ocean oxygen depletion and assoc......Ongoing global warming could persist far into the future, because natural processes require decades to hundreds of thousands of years to remove carbon dioxide from fossil-fuel burning from the atmosphere(1-3). Future warming may have large global impacts including ocean oxygen depletion...... solubility from surface-layer warming accounts for most of the enhanced oxygen depletion in the upper 500 m of the ocean. Possible weakening of ocean overturning and convection lead to further oxygen depletion, also in the deep ocean. We conclude that substantial reductions in fossil-fuel use over the next...

  9. Radiation characteristics of spent fuel of heavy-water research reactor during long-term storage

    International Nuclear Information System (INIS)

    Gerasimov, A.S.; Kiselev, G.V.; Myrtsymova, L.A.; Zaritskaya, T.S.

    2002-01-01

    Decay heat power and radiotoxicity by water of actinides and fission products from spent fuel of heavy-water research reactor RA were calculated for period of storage during 300000 years. Three variants of fuel enrichment by 235 U were considered: 2%, 21%, and 80%. The mass of 235 U in one fuel element was supposed to be the same for all variants of enrichment. The decay heat power of fission products in initial period is about 20 times higher than that of actinides. Decay heat power and radiotoxicity of actinides do not practically decrease during long period of time as they are determined by nuclides with very long half-life periods. (author)

  10. Lanthanide based conversion coatings for long term wet storage of aluminium-clad spent fuel

    International Nuclear Information System (INIS)

    Fernandes, S.M.C.; Correa, O.V.; De Souza, J.A.; Ramanathan, L.V.

    2010-01-01

    Spent fuels from research reactors are stored in basins with water of less than desirable quality at many facilities around the world and instances of cladding failure caused by pitting corrosion have been reported. Conversion coatings have been used in many industries to protect different metals, including aluminium alloys. This paper presents the results of an ongoing investigation in which the corrosion resistance of lanthanide (cerium, lanthanum and praseodymium) based conversion coated RR fuel cladding alloys has been studied. Electrochemical tests in the laboratory revealed higher corrosion resistance of CeO 2 , La 2 O 3 and Pr 2 O 3 coated AA 1100 and AA 6061 alloys in NaCl solutions. Uncoated and CeO 2 coated coupons of these alloys exposed for 50 days to the spent fuel basin of the IEA-R1 research reactor in IPEN, Brazil, revealed marked reductions in the extent of pitting corrosion. (author)

  11. Long term storage effects of irradiated fuel elements on power distribution and reactivity

    Energy Technology Data Exchange (ETDEWEB)

    Ponzoni Filho, P.; Sato, Sadakatu; Santos, Teresinha Ipojuca Cardoso T.I.C.; Fernandes Vanderlei Borba [FURNAS, Rio de Janeiro, RJ (Brazil); Fetterman, R.J. [Westinghouse Electric Corp., Pittsburgh, PA (United States)

    1995-12-31

    The ALPHA/PHOENIX-P/ANC (APA) code package was used to calculate the pin by pin power distribution and reactivity for Angra 1 Power Plant, Cycle 5. The Angra 1 Cycle 5 core was loaded with several irradiated fuel elements which were stored in the Spent Fuel Pool (SFP) for more than 8 years. Generally, neutronic codes take into account the buildup and depletion of just a few key fission, products such as Sm-149. In this paper it is shown that the buildup effects of other fission products must be considered for fuel which has been out of the core for significant periods of time. Impacts of these other fission products can change core reactivity and power distribution. (author). 3 refs, 4 figs, 4 tabs.

  12. Long term storage effects of irradiated fuel elements on power distribution and reactivity

    International Nuclear Information System (INIS)

    Ponzoni Filho, P.; Sato, Sadakatu; Santos, Teresinha Ipojuca Cardoso T.I.C.; Fernandes Vanderlei Borba; Fetterman, R.J.

    1995-01-01

    The ALPHA/PHOENIX-P/ANC (APA) code package was used to calculate the pin by pin power distribution and reactivity for Angra 1 Power Plant, Cycle 5. The Angra 1 Cycle 5 core was loaded with several irradiated fuel elements which were stored in the Spent Fuel Pool (SFP) for more than 8 years. Generally, neutronic codes take into account the buildup and depletion of just a few key fission, products such as Sm-149. In this paper it is shown that the buildup effects of other fission products must be considered for fuel which has been out of the core for significant periods of time. Impacts of these other fission products can change core reactivity and power distribution. (author). 3 refs, 4 figs, 4 tabs

  13. Compact approach to long-term monitored retrievable storage of spent fuel

    International Nuclear Information System (INIS)

    Muir, D.W.

    1986-01-01

    We examine a new approach to monitored retrievable storage (MRS) that is extremely compact in terms of total land use and may offer increased security and reduced environmental impact, relative to current designs. This approach involves embedding the spent fuel assemblies in monolithic blocks of metallic aluminum. While this would clearly require increased effort in the spent-fuel packaging phase, it would offer in return the above-mentioned environmental advantages, plus the option of easily extending the surface-storage time scale from several years to several decades if a need for longer storage times should arise in the future

  14. Fuel consumption: short term and long term price impacts per population type

    International Nuclear Information System (INIS)

    2011-01-01

    This report presents assessments of the price sensitivity of household fuel consumption. After a literature review on price-elasticity assessments and the use of pseudo-panels, the investigation analyses the deciding factors of the household fuel expense and its evolution between 1985 and 2006. It proposes a short term price-elasticity assessment based on the most recent survey, and also proposes price-elasticity assessments for sub-populations, notably in terms of income level or location (rural or urban areas)

  15. Long-term outlook of energy demand and supply in Japan. Estimation of energy demand and supply for 'Nuclear Energy Vision 2100' of JAEA

    International Nuclear Information System (INIS)

    Tatematsu, Kenji; Kawasaki, Hirotsugu; Nemoto, Masahiro; Murakami, Masakazu

    2009-06-01

    In this study, we showed an energy demand and supply scenario toward the year 2100 in Japan, which underlies JAEA's 'Nuclear Energy Vision 2100' published in October 2008. This energy demand and supply scenario aimed at the coexistence of the reduction of the carbon dioxide emission and the energy security through reduction of the fossil fuel usage, positive electrification and the nuclear energy usage. We reduced the ratio of the fossil fuel in the primary energy supply to about 1/3 and extend the share of renewable and nuclear energy to 70% from current 15%. As a result, the carbon dioxide emission was reduced to current 10%, and it developed that the half was the contribution of the nuclear energy. (author)

  16. Short and long-term carbon balance of bioenergy electricity production fueled by forest treatments

    Science.gov (United States)

    Katherine C. Kelsey; Kallie L. Barnes; Michael G. Ryan; Jason C. Neff

    2014-01-01

    Forests store large amounts of carbon in forest biomass, and this carbon can be released to the atmosphere following forest disturbance or management. In the western US, forest fuel reduction treatments designed to reduce the risk of high severity wildfire can change forest carbon balance by removing carbon in the form of biomass, and by altering future potential...

  17. Scientific reference on the long time evolution of spent fuels; Referentiel scientifique sur l'evolution a long terme des combustibles uses

    Energy Technology Data Exchange (ETDEWEB)

    Ferry, C.; Poinssot, Ch.; Broudic, V.; Jegou, Ch.; Roudil, D.; Poulesquen, A.; Miserque, F. [CEA Saclay, Dept. de Physico-Chimie, 91 - Gif sur Yvette (France); Cappelaere, Ch. [CEA Saclay, Dept. des Materiaux pour le Nucleaire, 91 - Gif-sur-Yvette (France); Desgranges, L.; Garcia, Ph.; Piron, J.P. [CEA Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d' Etudes des Combustibles; Lovera, P.; Marimbeau, P. [CEA Cadarache, 13 - Saint Paul lez Durance (France). Dept. d' Etudes des Reacteurs; Corbel, C. [CEA Saclay, Dept. de Recherche sur l' Etat Condense, les Atomes et les Molecules, 91 - Gif sur Yvette (France)

    2005-03-15

    This report is published in the framework of the 1991 French law for the nuclear waste management. The state of the art reported here concerns the long term evolution of spent fuel in the various environmental conditions corresponding to dry storage and geological disposal: closed system, air and water saturated medium. This review is based on the results of the french PRECCI project (Research Program on Long term Evolution of Spent Nuclear Fuel) and on literature data. (authors)

  18. Influence of high burnup on the decay heat power of spent fuel at long-term storage

    International Nuclear Information System (INIS)

    Bergelson, B.; Gerasimov, A.; Tikhomirov, G.

    2005-01-01

    Development and application of advanced fuel with higher burnup is now in practice of NPP with light water reactors in an increasing number of countries. High burnup allows to decrease significantly consumption of uranium. However, spent fuel of this type contains increased amount of high active actinides and fission products in comparison with spent fuel of common-type burnup. Therefore extended time of storage, improved cooling system of the storage facility will be required along with more strong radiation protection during storage, transportation and processing. Calculated data on decay heat power of spent uranium fuel of light water VVER-1000 type reactor are discussed in the paper. Long-term storage of discharged fuel during 100000 years is considered. Calculations were made for burnups of 40-70 MW d/kg. In the initial 50-year period of storage, power of fission products is much higher than that of actinides. Power of gamma-radiation is mainly due to fission products. During subsequent storage power of fission products quickly decreases, the main contribution to the power is given by actinides rather than by fission products. (author)

  19. Fuel consumption: short term and long term price impacts per population type; Consommation de carburant: effets des prix a court et a long termes par type de population

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This report presents assessments of the price sensitivity of household fuel consumption. After a literature review on price-elasticity assessments and the use of pseudo-panels, the investigation analyses the deciding factors of the household fuel expense and its evolution between 1985 and 2006. It proposes a short term price-elasticity assessment based on the most recent survey, and also proposes price-elasticity assessments for sub-populations, notably in terms of income level or location (rural or urban areas)

  20. Long-term kinetic effects and colloid formations in dissolution of LWR spent fuels

    International Nuclear Information System (INIS)

    Ahn, T.M.

    1996-11-01

    This report evaluates continuous dissolution and colloid formation during spent-fuel performance under repository conditions in high-level waste disposal. Various observations suggest that reprecipitated layers formed on spent-fuel surfaces may not be protective. This situation may lead to continuous dissolution of highly soluble radionuclides such as C-14, Cl-36, Tc-99, I-129, and Cs-135. However, the diffusion limits of various species involved may retard dissolution significantly. For low-solubility actinides such as Pu-(239+240) or Am-(241+243), various processes regarding colloid formation have been analyzed. The processes analyzed are condensation, dispersion, and sorption. Colloid formation may lead to significant releases of low-solubility actinides. However, because there are only limited data available on matrix dissolution, colloid formation, and solubility limits, many uncertainties still exist. These uncertainties must be addressed before the significance of radionuclide releases can be determined. 118 refs

  1. Long-term kinetic effects and colloid formations in dissolution of LWR spent fuels

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, T.M.

    1996-11-01

    This report evaluates continuous dissolution and colloid formation during spent-fuel performance under repository conditions in high-level waste disposal. Various observations suggest that reprecipitated layers formed on spent-fuel surfaces may not be protective. This situation may lead to continuous dissolution of highly soluble radionuclides such as C-14, Cl-36, Tc-99, I-129, and Cs-135. However, the diffusion limits of various species involved may retard dissolution significantly. For low-solubility actinides such as Pu-(239+240) or Am-(241+243), various processes regarding colloid formation have been analyzed. The processes analyzed are condensation, dispersion, and sorption. Colloid formation may lead to significant releases of low-solubility actinides. However, because there are only limited data available on matrix dissolution, colloid formation, and solubility limits, many uncertainties still exist. These uncertainties must be addressed before the significance of radionuclide releases can be determined. 118 refs.

  2. Potential long-term impacts of changes in US vehicle fuel efficiency standards

    International Nuclear Information System (INIS)

    Bezdek, Roger H.; Wendling, Robert M.

    2005-01-01

    Changes in corporate average fuel economy (CAFE) standards have not been made due, in part, to concerns over their negative impact on the economy and jobs. This paper simulates the effects of enhanced CAFE standards through 2030 and finds that such changes could increase GDP and create 300,000 jobs distributed widely across states, industries, and occupations. In addition, enhanced CAFE standards could, each year, reduce US oil consumption by 30 billion gallons, save drivers $40 billion, and reduce US greenhouse gas emissions by 100 million tons. However, there is no free lunch. There would be widespread job displacement within many industries, occupations, and states, and increased CAFE standards require that fuel economy be given priority over other vehicle improvements, increase the purchase price of vehicles, require manufacturers to produce vehicles that they otherwise would not, and require consumers to purchase vehicles that would not exist except for CAFE

  3. Short and long-term carbon balance of bioenergy electricity production fueled by forest treatments

    OpenAIRE

    Kelsey, Katharine C; Barnes, Kallie L; Ryan, Michael G; Neff, Jason C

    2014-01-01

    Background Forests store large amounts of carbon in forest biomass, and this carbon can be released to the atmosphere following forest disturbance or management. In the western US, forest fuel reduction treatments designed to reduce the risk of high severity wildfire can change forest carbon balance by removing carbon in the form of biomass, and by altering future potential wildfire behavior in the treated stand. Forest treatment carbon balance is further affected by the fate of this biomass ...

  4. A long term radiological risk model for plutonium-fueled and fission reactor space nuclear system

    International Nuclear Information System (INIS)

    Bartram, B.W.; Dougherty, D.K.

    1987-01-01

    This report describes the optimization of the RISK III mathematical model, which provides risk assessment for the use of a plutonium-fueled, fission reactor in space systems. The report discusses possible scenarios leading to radiation releases on the ground; distinctions are made for an intact reactor and a dispersed reactor. Also included are projected dose equivalents for various accident situations. 54 refs., 31 figs., 11 tabs

  5. Coal investment and long term supply and demand outlook for coal in the Asia-Pacific Region

    International Nuclear Information System (INIS)

    Johnson, C.J.

    1997-01-01

    The theme of this symposium to look ahead almost a quarter century to 2020 gives one the freedom to speculate more than usual in projections for coal. It is important to attempt to take a long term look into the future of coal and energy, so that one can begin to prepare for major changes on the horizon. However, it would be a mistake to believe that the crystal ball for making long term projections is accurate for 2020. Hopefully it can suggest plausible changes that have long term strategic importance to Asia's coal sector. This paper presents the medium scenario of long term projects of coal production, consumption, imports and exports in Asia. The second part of the paper examines the two major changes in Asia that could be most important to the long term role of coal. These include: (1) the impact of strict environmental legislation on energy and technology choices in Asia, and (2) the increased role of the private sector in all aspects of coal in Asia

  6. Long-term scenarios for global energy demand and supply. Four global greenhouse mitigation scenarios. Final report

    International Nuclear Information System (INIS)

    Soerensen, B.; Meibom, P.; Kuemmel, B.

    1999-01-01

    The scenario method is used to investigate energy demand and supply systems for the 21st century. A geographical information system (GIS) is employed to assess the spatial match between supply and demand, and the robustness of the scenario against changes in assumptions is discussed, for scenarios using fossil fuels without carbon dioxide emissions, nuclear fuels with reduced accident and proliferation risks, and renewable energy from local and from more centralised installations: The year 2050 demand scenario is based on a very high goal satisfaction in all regions of the world, for the middle UN population projection. All energy efficiency measures that are technically ready and economic today are assumed in effect by year 2050. An increased fraction of total activities are assumed to occur in non-material sectors. Technical, economic and implementation issues are discussed, including the resilience to changes in particularly demand assumptions and the type of framework that would allow energy policy to employ any of (or a mix of) the scenario options. Results are presented as average energy flows per unit of land area. This geographically based presentation method gives additional insights, particularly for the dispersed renewable energy systems, but in all cases it allows to identify the need for energy transmission and trade between regions, and to display it in a visually suggestive fashion. The scenarios are examples of greenhouse mitigation scenarios, all characterised by near-zero emissions of greenhouse gases to the atmosphere. All are more expensive than the present system, but only if the cost of the negative impacts from the current system is neglected. As options for global energy policy during the next decades, the clean fossil and the renewable energy options (possibly in combination) are the only realistic ones, because the safe nuclear option requires research and development that most likely will take longer time, if it can at all be carried

  7. Long-term scenarios for global energy demand and supply. Four global greenhouse mitigation scenarios. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Soerensen, B; Meibom, P [Technical Univ. of Denmark, Lyngby (Denmark); Kuemmel, B [Royal Agricultural and Veterinary Univ., Tastrup (Denmark)

    1999-01-01

    The scenario method is used to investigate energy demand and supply systems for the 21st century. A geographical information system (GIS) is employed to assess the spatial match between supply and demand, and the robustness of the scenario against changes in assumptions is discussed, for scenarios using fossil fuels without carbon dioxide emissions, nuclear fuels with reduced accident and proliferation risks, and renewable energy from local and from more centralised installations: The year 2050 demand scenario is based on a very high goal satisfaction in all regions of the world, for the middle UN population projection. All energy efficiency measures that are technically ready and economic today are assumed in effect by year 2050. An increased fraction of total activities are assumed to occur in non-material sectors. Technical, economic and implementation issues are discussed, including the resilience to changes in particularly demand assumptions and the type of framework that would allow energy policy to employ any of (or a mix of) the scenario options. Results are presented as average energy flows per unit of land area. This geographically based presentation method gives additional insights, particularly for the dispersed renewable energy systems, but in all cases it allows to identify the need for energy transmission and trade between regions, and to display it in a visually suggestive fashion. The scenarios are examples of greenhouse mitigation scenarios, all characterised by near-zero emissions of greenhouse gases to the atmosphere. All are more expensive than the present system, but only if the cost of the negative impacts from the current system is neglected. As options for global energy policy during the next decades, the clean fossil and the renewable energy options (possibly in combination) are the only realistic ones, because the safe nuclear option requires research and development that most likely will take longer time, if it can at all be carried

  8. Short and long-term carbon balance of bioenergy electricity production fueled by forest treatments.

    Science.gov (United States)

    Kelsey, Katharine C; Barnes, Kallie L; Ryan, Michael G; Neff, Jason C

    2014-01-01

    Forests store large amounts of carbon in forest biomass, and this carbon can be released to the atmosphere following forest disturbance or management. In the western US, forest fuel reduction treatments designed to reduce the risk of high severity wildfire can change forest carbon balance by removing carbon in the form of biomass, and by altering future potential wildfire behavior in the treated stand. Forest treatment carbon balance is further affected by the fate of this biomass removed from the forest, and the occurrence and intensity of a future wildfire in this stand. In this study we investigate the carbon balance of a forest treatment with varying fates of harvested biomass, including use for bioenergy electricity production, and under varying scenarios of future disturbance and regeneration. Bioenergy is a carbon intensive energy source; in our study we find that carbon emissions from bioenergy electricity production are nearly twice that of coal for the same amount of electricity. However, some emissions from bioenergy electricity production are offset by avoided fossil fuel electricity emissions. The carbon benefit achieved by using harvested biomass for bioenergy electricity production may be increased through avoided pyrogenic emissions if the forest treatment can effectively reduce severity. Forest treatments with the use of harvested biomass for electricity generation can reduce carbon emissions to the atmosphere by offsetting fossil fuel electricity generation emissions, and potentially by avoided pyrogenic emissions due to reduced intensity and severity of a future wildfire in the treated stand. However, changes in future wildfire and regeneration regimes may affect forest carbon balance and these climate-induced changes may influence forest carbon balance as much, or more, than bioenergy production.

  9. Safety indicators adopted in the Finnish regulations for long-term safety of spent fuel disposal

    International Nuclear Information System (INIS)

    Ruokola, E.

    2002-01-01

    A regulatory guide for the safety of spent fuel disposal has recently been issued to guide the implementer's programme in the preconstruction phase. The guide is based on dose criteria in the time frame, which is reasonably predictable with respect to assessment of human exposure. For the time frame that involves major climate changes such as permafrost and glaciation, the guide defines constraints for the activity releases to the environment. This paper discusses the rationale for the selected approach and the derivation of the activity release constraints. (author)

  10. Long-term management of Canada's spent nuclear fuel: the nuclear waste management organizations recommendation to government

    International Nuclear Information System (INIS)

    Shaver, K.

    2006-01-01

    Full text: Like many countries with nuclear power programs, Canada is in the process of addressing the long-term management of its spent fuel. The Nuclear Waste Management Organization (NWMO) was tasked through federal legislation to conduct a three-year study of approaches for the long-term management of spent fuel, and to recommend a preferred approach to the Government of Canada. Legislation required NWMO to compare at least three approaches -approaches based on deep geological disposal in the Canadian Shield, storage at nuclear reactor sites, and centralized storage either above or below ground. In assessing the options, NWMO sought a recommendation that would be socially acceptable, technically sound, environmentally responsible and economically feasible. The study drew on a vast base of social, technical, engineering, and financial research, and included an extensive engagement program with the public and Aboriginal peoples. The recommendation emerged from a collaborative dialogue with specialists and citizens, for an approach that is built on sound science and technology and responsive to citizen values. NWMO submitted its completed options study, with recommendation, to the Government in November 2005. NWMO has proposed an alternative approach, Adaptive Phased Management, which has as its key attributes: central containment and isolation of spent fuel in a deep repository, in an appropriate geological formation; contingency provision for central shallow storage; monitoring and retrievability; and a staged, adaptive process of concept implementation, reflecting the complex nature of the task and the desire of citizens to proceed through cautious, deliberate steps of technical demonstration and social acceptance. This paper will review: 1) the development of the assessment framework for comparing the technical options, which incorporated social and ethical considerations expressed by citizens; 2) findings of the assessment; and 3) features of the proposed

  11. Safety aspects of long-term dry interim storage of Type B spent fuel and high-level transport casks

    International Nuclear Information System (INIS)

    Wolff, D.; Probst, U.; Voelzke, H.; Droste, B.; Roedel, R.

    2004-01-01

    Based on the German decision to minimise transport of spent fuel casks between nuclear power plants, reprocessing plants and central storage facilities several on-site storage facilities were licensed until the end of 2003. Because of the large amount of Type B(U) transport casks which are going to be used for long-term interim storage the question of time-limited Type B(U) licence maintenance during the storage period of up to 40 years has been discussed under different aspects. This paper describes present technical aspects of the discussion. A main aspect of qualification of transport casks for interim storage is the long-term behaviour of the metallic seal-lid system. Here we present results from current long-term experimental tests with metallic 'Helicoflex' seals in which pool water is enclosed. This series of tests has been performed by the Federal Institute for Materials Research and Testing (BAM) on behalf of the Federal Office for Radiation Protection (BfS) since 2001. Finally, the paper presents a German concept for an exchange of experience, know-how and state-of-the-art between authorities and technical experts with regard to cask dispatch in nuclear facilities. BAM has taken over a central role in this so-called 'coordinating institution for cask dispatching information' ('KOBAF') which entails management of an online database of cask-specific documents and a technical working group meeting twice a year. The goal is to keep comparable technical standards for all nuclear sites and storage facilities which are going to load and dispatch casks of the same or similar types under the responsibility of different German state governments for the coming decades. (author)

  12. Safety aspects of long-term dry interim storage of type-B spent fuel and HLW transport casks

    International Nuclear Information System (INIS)

    Wolff, D.; Probst, U.; Voelzke, H.; Droste, B.; Roedel, R.

    2004-01-01

    Based on the German decision to minimise transports of spent fuel casks between nuclear power plants, reprocessing plants and central storage facilities several on-site storage facilities have been licensed till the end of 2003. Because of the large amount of type-B transport casks which are going to be used for long-term interim storage the question of time limited type-B license maintenance during the storage period of up to 40 years has been discussed under different aspects. This paper describes present technical aspects of the discussion. A main aspect of transport cask qualification for interim storage is the long-term behaviour of the metallic seal lid system. Concerning this results from current experimental long-term tests with metallic ''Helicoflex''-seals in which pool water is enclosed are presented. The test series has been performed by the Federal Institute for Materials Research and Testing (BAM) on behalf of the Federal Office for Radiation Protection (BfS) since 2001. Finally, the paper presents a German concept for an authorities' and technical experts' exchange of experience, know-how and state of the art referring to cask dispatch in nuclear facilities. BAM has taken over a central role in this so-called ''co-ordinating institution for cask dispatching information'' (''KOBAF'') which contains an online data base and a technical working group meeting twice a year. The goal is to keep comparable technical standards for all nuclear sites and storage facilities which are going to load and dispatch casks of the same or similar types under the responsibility of different German state governments for the next decades

  13. Study on component interface evolution of a solid oxide fuel cell stack after long term operation

    Science.gov (United States)

    Yang, Jiajun; Huang, Wei; Wang, Xiaochun; Li, Jun; Yan, Dong; Pu, Jian; Chi, Bo; Li, Jian

    2018-05-01

    A 5-cell solid oxide fuel cell (SOFC) stack with external manifold structure is assembled and underwent a durability test with an output of 250 W for nearly 4400 h when current density and operating temperature are 355 mA/cm2 and 750 °C. Cells used in the stack are anode-supported cells (ASC) with yttria-stabilized zirconia (YSZ) electrolytes, Ni/YSZ hydrogen electrodes, and YSZ based composite cathode. The dimension of the cell is 150 × 150 mm (active area: 130 × 130 mm). Ceramic-glass sealant is used in the stack to keep the gas tightness between cells, interconnects and manifolds. Pure hydrogen and dry air are used as fuel and oxidant respectively. The stack has a maximum output of 340 W at 562 mA/cm2 current density at 750 °C. The stack shows a degradation of 1.5% per 1000 h during the test with 2 thermal cycles to room temperature. After the test, the stack was dissembled and examined. The relationship between microstructure changes of interfaces and degradation in the stack are discussed. The microstructure evolution of interfaces between electrode, contact material and current collector are unveiled and their relationship with the degradation is discussed.

  14. Long-term scenarios of power reactors and fuel cycle development and the role of reduced moderation water reactors

    International Nuclear Information System (INIS)

    Sato, Osamu; Tatematsu, Kenji; Tanaka, Yoji

    2000-01-01

    Reduced moderation spectrum reactor is one of water cooled type reactors in future, which is based on the advanced technology of conventional nuclear power plants. The reduced moderation water reactor (RMWR) has various advantages, such as effective utilization of uranium resources, high conversion ratio, high burn-up, long-term cycle operation, and multiple recycle of plutonium. The RMWR is expected to be a substitute of fast breeder reactor (FBR) of which the development encounters with some technical and financial difficulties, and discontinues in many countries. The role of the RMWR on long-term scenarios of power reactor and fuel cycle development in Japan is investigated from the point of view of uranium resource needed. The consumption of natural uranium needed up to the year 2200 is calculated on various assumptions for the following three cases: (1) no breeder reactor; plutonium-thermal cycle in conventional light water reactor, (2) introduction of the FBR, and (3) introduction of the RMWR. The amounts of natural uranium consumption depends largely on the conversion ratio and plutonium quantity needed of a reactor type. The RMWR has a possibility as a substitute technology of the FBR with the improvement of conversion ratio and high burn-up. (Suetake, M.)

  15. Long-term scenarios of power reactors and fuel cycle development and the role of reduced moderation water reactors

    Energy Technology Data Exchange (ETDEWEB)

    Sato, Osamu; Tatematsu, Kenji; Tanaka, Yoji [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2000-06-01

    Reduced moderation spectrum reactor is one of water cooled type reactors in future, which is based on the advanced technology of conventional nuclear power plants. The reduced moderation water reactor (RMWR) has various advantages, such as effective utilization of uranium resources, high conversion ratio, high burn-up, long-term cycle operation, and multiple recycle of plutonium. The RMWR is expected to be a substitute of fast breeder reactor (FBR) of which the development encounters with some technical and financial difficulties, and discontinues in many countries. The role of the RMWR on long-term scenarios of power reactor and fuel cycle development in Japan is investigated from the point of view of uranium resource needed. The consumption of natural uranium needed up to the year 2200 is calculated on various assumptions for the following three cases: (1) no breeder reactor; plutonium-thermal cycle in conventional light water reactor, (2) introduction of the FBR, and (3) introduction of the RMWR. The amounts of natural uranium consumption depends largely on the conversion ratio and plutonium quantity needed of a reactor type. The RMWR has a possibility as a substitute technology of the FBR with the improvement of conversion ratio and high burn-up. (Suetake, M.)

  16. Choice evaluation of power supply composition using the mapping method of the long-term energy demand-and-supply scenario

    International Nuclear Information System (INIS)

    Tatematsu, Kenji

    2013-03-01

    Long-term energy demand-and-supply were analyzed for our country using the MARKAL model, supposing six kinds of energy demand-and-supply scenarios where different installed capacity of nuclear power generation and the emission standard of carbon-dioxide were employed. It was shown that even when nuclear power generation was not used, the carbon-dioxide emissions in the whole country and a power generation sector are reducible by 37% and 47% in 2050 from the 1990 level, respectively. However, when nuclear power generation was phase-out and renewable energy and natural gas were substituted, it was found that an average power generating cost was higher than the case where use of nuclear or coal was continued, 3.7 yen/kWh or more. Moreover, in the case where immediate cessation of the nuclear power generation was carried out, it was also shown that a current average power generating cost rose by 4.4 yen/kWh. In order to evaluate and visualize the influence of power supply composition change on both the average power generating cost and the carbon-dioxide emissions, a new mapping method was proposed where diversity of an energy source, the carbon-dioxide emissions, and the average power generating cost were used as indexes. Based on the result of model analysis, when nuclear power generation was substituted with renewable energy, natural gas, or coal, oligopoly of an energy source was shown to increase sharply by abolition of nuclear power generation. These results showed that by continuing use of the nuclear power generation with a fixed scale, less carbon-dioxide emissions, avoiding oligopolization of an energy source and suppressing the steep rise of an average power generating cost were possible. (author)

  17. Long term immersion test of aluminum alloy AA 6061 used for fuel cladding in MTR type reactors

    International Nuclear Information System (INIS)

    Linardi, Evelina M.; Rodriguez, Sebastian; Haddad, Roberto; Lanzani, Liliana

    2009-01-01

    In this work we present the results of long term immersion tests performed in the aluminum alloy AA 6061, used for fuel cladding in MTR type reactors. The tests were performed at open circuit potential in high purity water (ρ = 18.2 MΩ.cm) and in 10 -3 M NaCl solution. Two kinds of assemblies were studied: simple sheets and artificial crevices, immersed during 6, 12 and 18 months at room temperature. In both media and both assemblies, the aluminum hydroxide phases crystalline bayerite and bohemite were identified. It was found that a kind of localized attack named alkaline attack occurs around the iron-rich intermetallics. These particles were confirmed to control the corrosion of the AA 6061 alloy in an aerated medium. Immersion times for up to 18 months did not increase the oxide growth or the alkaline attack on the AA 6061 alloy. (author)

  18. Long-term cathode performance and the microbial communities that develop in microbial fuel cells fed different fermentation endproducts

    KAUST Repository

    Kiely, Patrick D.

    2011-01-01

    To better understand how cathode performance and substrates affected communities that evolved in these reactors over long periods of time, microbial fuel cells were operated for more than 1year with individual endproducts of lignocellulose fermentation (acetic acid, formic acid, lactic acid, succinic acid, or ethanol). Large variations in reactor performance were primarily due to the specific substrates, with power densities ranging from 835±21 to 62±1mW/m3. Cathodes performance degraded over time, as shown by an increase in power of up to 26% when the cathode biofilm was removed, and 118% using new cathodes. Communities that developed on the anodes included exoelectrogenic families, such as Rhodobacteraceae, Geobacteraceae, and Peptococcaceae, with the Deltaproteobacteria dominating most reactors. Pelobacter propionicus was the predominant member in reactors fed acetic acid, and it was abundant in several other MFCs. These results provide valuable insights into the effects of long-term MFC operation on reactor performance. © 2010 Elsevier Ltd.

  19. Engaging aboriginal peoples in Canada's plan for the long-term management of used nuclear fuel

    International Nuclear Information System (INIS)

    Patton, P.

    2011-01-01

    The interests and concerns of Aboriginal peoples are integral to development and implementation of Canada's plans for the long-term management of used nuclear fuel. The Nuclear Waste Management Organization (NWMO) has an ongoing statutory obligation and a commitment to active and meaningful participation with Aboriginal peoples. The organization has worked with Aboriginal organizations and individuals to develop long-term engagement and dialogue processes that respect traditional Aboriginal practices, culture, protocols and approaches to decision-making. Aboriginal peoples were significant participants in the 2003-2005 study that resulted in the recommendation for Adaptive Phased Management (APM). After the Canadian government agreed to proceed with APM, Aboriginal peoples provided valuable input into development of the process for selecting a site for a deep geological repository (DGR) for the long-term management of Canada's used nuclear fuel. The involvement of Aboriginal stakeholders continues to be important as Canada moves into the siting process. Engagement of Aboriginal peoples is guided by principles that respond to the unique interests, perspectives and culture of Aboriginal peoples. These principles recognize and honour the special relationship that Aboriginal peoples have with the natural environment, their unique stewardship responsibilities, and the fact that Aboriginal peoples are holders of Aboriginal Traditional Knowledge (ATK), which brings value to planning processes. The NWMO has been working with Aboriginal Elders and others to learn about ATK and to interweave this knowledge into its work. ATK includes important knowledge about the land, ecology and intergenerational decision-making. The NWMO and Aboriginal peoples have given life to engagement principles and the wisdom of ATK by collaboratively developing a number of programs including agreements with national, regional and local Aboriginal organizations. Additionally, the NWMO has

  20. A comparative physics study of alternative long-term strategies for closure of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Cometto, M.; Wydler, P.; Chawla, R.

    2004-01-01

    The appropriate management of radioactive waste arising from the nuclear fuel cycle is considered to be a key issue in the development of future, more sustainable nuclear energy systems. In this context, the partitioning and transmutation of actinides could play an important role through the achievement of very significant reductions in the actinide content and radiotoxicity of the high-level waste requiring geological disposal. The current paper reports on the results of a detailed physics study carried out to compare the pros and cons of alternative strategies for closure of the nuclear fuel cycle. Different long-term 'steady-state' scenarios have been considered, involving the deployment, to varying degrees, of light water reactors (LWRs) and advanced fast-spectrum systems. The same nuclear data and calculation methods have been used throughout, so that a consistent and reliable comparison of the relative performance of the three basic fuel cycle options (once-through, plutonium recycle, and recycling of all actinides) has been made possible. In addition, with transmutation having been considered employing both critical and accelerator-driven fast-spectrum systems, the study has provided an evaluation of the advantages and disadvantages of these two different advanced system types

  1. Performance and long term degradation of 7 W micro-tubular solid oxide fuel cells for portable applications

    Science.gov (United States)

    Torrell, M.; Morata, A.; Kayser, P.; Kendall, M.; Kendall, K.; Tarancón, A.

    2015-07-01

    Micro-tubular SOFCs have shown an astonishing thermal shock resistance, many orders of magnitude larger than planar SOFCs, opening the possibility of being used in portable applications. However, only few studies have been devoted to study the degradation of large-area micro-tubular SOFCs. This work presents microstructural, electrochemical and long term degradation studies of single micro-tubular cells fabricated by high shear extrusion, operating in the intermediate range of temperatures (T∼700 °C). A maximum power of 7 W per cell has been measured in a wide range of fuel utilizations between 10% and 60% at 700 °C. A degradation rate of 360 mW/1000 h (8%) has been observed for cells operated over more than 1500 h under fuel utilizations of 40%. Higher fuel utilizations lead to strong degradations associated to nickel oxidation/reduction processes. Quick thermal cycling with heating ramp rates of 30 °C /min yielded degradation rates of 440 mW/100 cycles (9%). These reasonable values of degradation under continuous and thermal cycling operation approach the requirements for many portable applications including auxiliary power units or consumer electronics opening this typically forbidden market to the SOFC technology.

  2. Economic comparison of long-term nuclear fuel cycle management scenarios: The influence of the discount rate

    International Nuclear Information System (INIS)

    Le Dars, Aude; Loaec, Christine

    2007-01-01

    This article presents some main economic results obtained by the CEA in the DERECO project, which aimed to evaluate the global cost of contrasted and long-term nuclear fuel cycle scenarios. The scenarios have been studied for the period 2000-2150 in the French context. They all assume a sustainable nuclear development. These scenarios must not be considered as forecasts and do not reflect any industrial strategy. The article focuses on the comparison of five scenarios including the Generation IV fast reactors and their associated fuel cycles. Common trends as well as specific features can be identified. The article describes the scenarios with the replacement of the nuclear power and the associated fuel cycle. It details the main technical and economic assumptions common to all the scenarios, and exposes some main key results, concerning the flows and inventories as well as concerning economic evaluation. Economic results are given in a comparative manner due to the level of uncertainties at this time horizon. The key economic elements described in the article deal with the sensitivity of the results to the choice of the discount rate

  3. The coupling of coal and nuclear energy for the long-term supply of energy and raw materials

    International Nuclear Information System (INIS)

    Knizia, K.

    1986-10-01

    In view of the limited world reserves of fossil fuels and the increase in demand to be expected because of the continued growth of the world population, coal and nuclear energy will have to make an increasing contribution to the energy supply. Their contribution will range from electricity generation to the heat sector and to the raw materials market via various gases obtained from them. The further development towards this field of tasks will lead first via the gasification of coal. It will be carried out autothermally in the first stage of development. The gas produced is suitable for realising considerable improvements in efficiency as compared to coal-fired power stations of present-day design since it will permit the generation of electricity via combined gas turbine/steam turbine processes. Efforts are being made to take further the processes based on this technology by introducing a sodium circuit in addition to the coal gasification, which will make it possible to keep the plants required for coal gasification small. In later stages, this technology will also be suitable for producing a considerable improvement in the diversion of heat at high temperatures from high-temperature reactor nuclear power stations for several purposes. (author)

  4. Impact of long-term climate change on a deep geological repository for spent nuclear fuel

    International Nuclear Information System (INIS)

    Boulton, G.S.; Kautsky, U.; Moren, L.; Wallroth, T.

    2001-05-01

    The radioactivity of spent nuclear fuel will decay over a period of time (100,000 years or longer) in which we expect major environmental change. Climatically driven changes such as glaciation, permafrost and changes in sea level will affect the subsurface environment and must therefore be considered in performance and safety assessments. We regard the state of climate to be determined by the climate system, comprising the atmosphere, the biosphere, the oceans, the ice sheets and the surface of the lithosphere. Climate can change as a consequence of external forcing or as a consequence of the internal dynamics. The changes in the past show a complex cyclical pattern with repetitive periodicities and magnitudes of change. On the relatively long time scale which is of concern in this report climate changes are believed to be triggered by changes in insolation due to cyclical changes in the earth's orbit around the sun. This is referred to as the Milankovitch theory or the astronomical climate theory. A brief review of our knowledge of the climate system, proxy records and observations of past climate change is presented in the report. The most extreme departures from modern environmental conditions in Sweden have occurred during the cold, glacial cycles with ice sheets covering the whole of Sweden. As part of SKB's palaeohydrogeological research programme a time-dependent, thermo-mechanically coupled model of ice sheet behaviour has been developed in order to simulate past fluctuations of the Scandinavian ice sheet and forecast its future. The ice sheet model can calculate the temperature field and isostatic response of the underlying bedrock, subglacial and proglacial permafrost and the subglacial melt rates. By connecting the glaciation model with hydrogeological and rock mechanical models, the response of the subsurface to climate change can be investigated. In this report the climate-driven environmental changes are represented as a series of successive climate

  5. Impact of long-term climate change on a deep geological repository for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Boulton, G.S. [Edinburgh Univ. (United Kingdom); Kautsky, U.; Moren, L. [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Wallroth, T. [Bergab Consulting Geologists (Sweden)

    2001-05-01

    The radioactivity of spent nuclear fuel will decay over a period of time (100,000 years or longer) in which we expect major environmental change. Climatically driven changes such as glaciation, permafrost and changes in sea level will affect the subsurface environment and must therefore be considered in performance and safety assessments. We regard the state of climate to be determined by the climate system, comprising the atmosphere, the biosphere, the oceans, the ice sheets and the surface of the lithosphere. Climate can change as a consequence of external forcing or as a consequence of the internal dynamics. The changes in the past show a complex cyclical pattern with repetitive periodicities and magnitudes of change. On the relatively long time scale which is of concern in this report climate changes are believed to be triggered by changes in insolation due to cyclical changes in the earth's orbit around the sun. This is referred to as the Milankovitch theory or the astronomical climate theory. A brief review of our knowledge of the climate system, proxy records and observations of past climate change is presented in the report. The most extreme departures from modern environmental conditions in Sweden have occurred during the cold, glacial cycles with ice sheets covering the whole of Sweden. As part of SKB's palaeohydrogeological research programme a time-dependent, thermo-mechanically coupled model of ice sheet behaviour has been developed in order to simulate past fluctuations of the Scandinavian ice sheet and forecast its future. The ice sheet model can calculate the temperature field and isostatic response of the underlying bedrock, subglacial and proglacial permafrost and the subglacial melt rates. By connecting the glaciation model with hydrogeological and rock mechanical models, the response of the subsurface to climate change can be investigated. In this report the climate-driven environmental changes are represented as a series of successive

  6. The restructuring of institutional long-term care in St. John's: impact of supply-induced demand on planning.

    Science.gov (United States)

    Wilson, Robert C; McDonald, Jacqueline; Barrett, Brendan; Parfrey, Patrick S

    2011-01-01

    Restructuring of institutional long-term care was undertaken using predictions of future bed need with assumptions made on incidence rates of clients defined by type of disability, survival, and demographic changes. Recent substantial increase in the population rate of clients seeking placement across all degrees of disability, coincident with new facilities for those with modest disability, occurred. Consequently, more appropriate housing and supervised care beds, and more limited downsizing of nursing homes will be required.

  7. Acclimation of Arabidopsis thaliana to long-term CO{sub 2} enrichment and nitrogen supply is basically a matter of growth rate adjustment

    Energy Technology Data Exchange (ETDEWEB)

    Tocquin, P.; Ormenese, S.; Pieltain, A.; Detry, N.; Bernier, G.; Perilleux, C. [Univ. of Liege, Dept. of Life Sciences, Lab. of Plant Physiology, Liege (Belgium)

    2006-12-15

    The long-term response of Arabidopsis thaliana to increasing CO{sub 2} was evaluated in plants grown in 800 {mu}l l{sup -1} CO{sub 2} from sowing and maintained, in hydroponics, on three nitrogen supplies: 'low', 'medium' and 'high'. The global response to high CO{sub 2} and N-supply was evaluated by measuring growth parameters in parallel with photosynthetic activity, leaf carbohydrates, ribulose-1,5-bisphosphate carboxylase/oxygenase (Rubisco) messenger RNA and protein, stomatal conductance (g-s) and density. CO{sub 2} enrichment was found to stimulate biomass production, whatever the N-supply. This stimulation was transient on low N-supply and persisted throughout the whole vegetative growth only in high N-supply. Acclimation on low N-high C0{sub 2} was not associated with carbohydrate accumulation or with a strong reduction in Rubisco amount or activity. At high N-supply, growth stimulation by high CO{sub 2} was mainly because of the acceleration of leaf production and expansion while other parameters such as specific leaf area, root/shoot ratio and g{sub s} appeared to be correlated with total leaf area. Our results thus suggest that, in strictly controlled and stable growing conditions, acclimation of A. thaliana to long-term CO{sub 2} enrichment is mostly controlled by growth rate adjustment. (au)

  8. Effects of long-term coal supply contracts on technology adoption and improvements in the mining of coal. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    Walton, D.R.; Hawkins, S.A.; Webb, P.F.; Kauffman, P.W.

    1979-08-01

    The relationship between long-term coal supply contracts and the adoption of new technology in the coal mining industry is a complex one. From this study certain conclusions can be drawn. New technologies and improvements in the mining of coal can be logically categorized into three areas: evolutionary technology, transitional technology, or innovative technology. Evolutionary improvements in technology can be categorized as improvements, or increased production capacities, in existing equipment. Transitional technology involves the adoption of existing or proven technologies into new conditions, or, proceeding from one technology type to a newer type for the same function. Innovative technology includes equipment, concepts, and systems not readily available, or untried, in the existing mining environment (seam conditions, etc.). Technology adoption is an economic decision. This point was repeatedly emphasized by industry representatives contacted during the study. The long-term coal supply contract influences the decision to adopt new technology and mining improvements in several ways depending on the technology type (i.e., evolutionary, transitional, or innovative), and also the coal supplier type (i.e., captive or independent producer). Several examples of the adoption of new technologies in mines under long-term coal supply contracts are discussed. (LTN)

  9. Overview of technical Issues Associated with the Long Term Storage of Light Water Reactor used Nuclear Fuel

    International Nuclear Information System (INIS)

    Sorenson, Ken B.

    2014-01-01

    The nuclear power technical community is developing the technical basis for demonstrating the safety of storing used nuclear fuel for extended periods of time. The combination of reactor operations that off-load spent fuel to interim storage, coupled with delays in repository construction, has resulted in the expectation that storage periods may be for longer periods of time than originally intended. As more fuel continues to be off-loaded from operating reactors, the need for expanded interim storage also increases. As repository programs are delayed, interim storage requirements will likely exceed licensing term limits. To address these operational realities, there has been a concerted international effort to identify and prioritize the technical issues that need to be addressed in order to demonstrate the safety of storing used nuclear fuel for extended periods of time. Since this is an international effort, different storage systems, regulations, and policies need to be considered. This results in differences in technical issues, as well as differences in priorities. However, this effort also identifies important commonalities in some technical areas that need to be addressed. A broad-based international evaluation of these technical issues provides a better understanding of technical concerns as they relate to individual storage systems and specific national regulatory frameworks. While there are several international activities underway that are focused on long term storage, this paper will discuss the activities of the Electric Power Research Institute (EPRI)/Extended Storage Collaboration Program (ESCP) International Subcommittee. A status report detailing the identification and prioritization of the technical issues was presented at the PSAM11 Conference in June 2012 (1). Since that conference, a final report has been completed by the EPRI/ESCP International Subcommittee (2). This paper will provide important results of the final report as well as

  10. Dry Storage at long term of nuclear fuels: Influence of the fuel design and commercial irradiation conditions

    International Nuclear Information System (INIS)

    Marino, Armando C

    2009-01-01

    The BaCo code was applied to simulate the behaviour for a PHWR fuel under storage conditions showing a strong dependence on the original design of the fuel and the irradiation history. In particular, the results of the statistical analysis of BaCo indicate that the integrity of the fuel is influenced by the manufacture tolerances and the solicitations during the NPP irradiation. The main conclusion of the present study is that the fuel temperature of the device should be carefully controlled in order to ensure safe storage conditions. [es

  11. Investigation of nuclide importance to functional requirements related to transport and long-term storage of LWR spent fuel

    International Nuclear Information System (INIS)

    Broadhead, B.L.; DeHart, M.D.; Ryman, J.C.; Tang, J.S.; Parks, C.V.

    1995-06-01

    This study investigates the relative importances of the various actinide, fission-product, and light-element isotopes associated with LWR spent fuel with respect to five analysis areas: criticality safety (absorption fractions), shielding (dose rate fractions), curies (fractional curies levels), decay heat (fraction of total watts), and radiological toxicity (fraction of potential committed effective dose equivalent). These rankings are presented for up to six different burnup/enrichment scenarios and at decay times from 2 to 100,000 years. Ranking plots for each of these analysis areas are given in an Appendix for completeness, as well as summary tables in the main body of the report. Summary rankings are presented in terms of high (greater than 10% contribution to the total), medium (between 1% and 10% contribution), and low (less than 1% contribution) for both short- and long-term cooling. When compared with the expected measurement accuracies, these rankings show that most of the important isotopes can be characterized sufficiently for the purpose of radionuclide generation/depletion code validation in each of the analysis areas. Because the main focus of this work is on the relative importances of isotopes associated with L at sign spent fuel, some conclusions may not be applicable to similar areas such as high-level waste (HLW) and nonfuel-bearing components (NFBC)

  12. Contribution to a proposition for a long term development of nuclear energy: the TASSE concept (Thorium based Accelerator driven System with Simplified fuel cycle for long term Energy Production)

    International Nuclear Information System (INIS)

    Berthou, V.

    2000-01-01

    Nuclear industry creates waste which are in the middle of the discussion concerning the Nuclear Energy future. At this time, important decisions for the Energy production must be taken, so numerous researches are conducted within the framework of the Bataille law. The goal of these studies is to find a range of solutions concerning the waste management. An innovative system, called TASSE (Thorium based Accelerator driven System with Simplified fuel cycle for long term Energy production), is studied in this thesis. This reactor is included in a long term strategy, and is destined for the renewal of the reactor park. In the first part of this work, the main characteristics of TASSE have been defined. They are commensurate with some specific requirements such as: to insure a large time to the Nuclear Energy, to reduce the waste production in an important way, to eliminate waste already stocked in the present park, to insure the non proliferation, and to be economically competitive. Neutronics studies of TASSE have been done. A calculation procedure has been developed to reach the system equilibrium state. Several types of molten salts as well as a pebble-bed fuel have been studied. Thus, an optimal fuel has been brought out in regard to some parameters such as the burn up level, the spectrum, the waste toxicity, the cycle type. Eventually, various TASSE core layout have been envisaged. (author)

  13. Improvement of the long term stability in the high temperature solid oxide fuel cell using functional layers

    Energy Technology Data Exchange (ETDEWEB)

    Brueckner, B.; Guenther, C.; Ruckdaeschel, R. [Siemens AG, Erlangen (Germany)] [and others

    1996-12-31

    In the planar Siemens design of the solid oxide fuel cell a metallic interconnector is used to seperate the ceramic single cells. A disadvantage of the metallic bipolar plate which consists of a chromium alloy is the formation of high volatile Cr-oxides and hydroxides at the surface at the cathode side. The reaction products evaporate and are reduced at the cathode/electrolyte interface to form new crystalline phases. This process gives rise to long term cell degradation. Protective coatings might be successful in preventing the chromium oxide evaporation. The required properties of the protective layers are (I) high electrical conductivity, (II) similar coefficients of thermal expansion to the bipolar plate (III), chemical compatibility to the bipolar plate and cathode material, (IV) a low diffusion coefficient of Cr and (V) chemical stability up to 1223K under oxygen atmosphere. Furthermore, during operation at 1223K an electrical contact between the metallic plate and the electrodes has to be maintained. This problem could be solved using ceramic layer between the metallic plate and the single cells.

  14. Long-term performance of activated carbon air cathodes with different diffusion layer porosities in microbial fuel cells

    KAUST Repository

    Zhang, Fang

    2011-08-01

    Activated carbon (AC) air-cathodes are inexpensive and useful alternatives to Pt-catalyzed electrodes in microbial fuel cells (MFCs), but information is needed on their long-term stability for oxygen reduction. AC cathodes were constructed with diffusion layers (DLs) with two different porosities (30% and 70%) to evaluate the effects of increased oxygen transfer on power. The 70% DL cathode initially produced a maximum power density of 1214±123mW/m 2 (cathode projected surface area; 35±4W/m 3 based on liquid volume), but it decreased by 40% after 1 year to 734±18mW/m 2. The 30% DL cathode initially produced less power than the 70% DL cathode, but it only decreased by 22% after 1 year (from 1014±2mW/m 2 to 789±68mW/m 2). Electrochemical tests were used to examine the reasons for the degraded performance. Diffusion resistance in the cathode was found to be the primary component of the internal resistance, and it increased over time. Replacing the cathode after 1 year completely restored the original power densities. These results suggest that the degradation in cathode performance was due to clogging of the AC micropores. These findings show that AC is a cost-effective material for oxygen reduction that can still produce ~750mW/m 2 after 1 year. © 2011 Elsevier B.V.

  15. Long-term performance of a 20-L continuous flow microbial fuel cell for treatment of brewery wastewater

    Science.gov (United States)

    Lu, Mengqian; Chen, Shing; Babanova, Sofia; Phadke, Sujal; Salvacion, Michael; Mirhosseini, Auvid; Chan, Shirley; Carpenter, Kayla; Cortese, Rachel; Bretschger, Orianna

    2017-07-01

    Microbial fuel cells (MFCs) have been shown as a promising technology for wastewater treatment. Integration of MFCs into current wastewater treatment plant have potential to reduce the operational cost and improve the treatment performance, and scaling up MFCs will be essential. However, only a few studies have reported successful scale up attempts. Fabrication cost, treatment performance and operational lifetime are critical factors to optimize before commercialization of MFCs. To test these factors, we constructed a 20 L MFC system containing two 10 L MFC reactors and operated the system with brewery wastewater for nearly one year. Several operational conditions were tested, including different flowrates, applied external resistors, and poised anodic potentials. The condition resulting in the highest chemical oxygen demand (COD) removal efficiency (94.6 ± 1.0%) was a flow rate of 1 mL min-1 (HRT = 313 h) and an applied resistor of 10 Ω across each MFC circuit. Results from each of the eight stages of operation (325 days total) indicate that MFCs can sustain treatment rates over a long-term period and are robust enough to sustain performance even after system perturbations. possible ways to improve MFC performance were discussed for future studies.

  16. Long-Term Performance of Chemically and Physically Modified Activated Carbons in Air Cathodes of Microbial Fuel Cells

    KAUST Repository

    Zhang, Xiaoyuan

    2014-07-31

    © 2014 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim. Activated carbon (AC) is a low-cost and effective catalyst for oxygen reduction in air cathodes of microbial fuel cells (MFCs), but its performance must be maintained over time. AC was modified by three methods: 1)pyrolysis with iron ethylenediaminetetraacetic acid (AC-Fe), 2)heat treatment (AC-heat), and 3)mixing with carbon black (AC-CB). The maximum power densities after one month with these AC cathodes were 35% higher with AC-Fe (1410±50mW m-2) and AC-heat (1400±20mW m-2), and 16% higher with AC-CB (1210±30mW m-2) than for plain AC (1040±20mW m-2), versus 1270±50mW m-2 for a Pt control. After 16months, the Pt cathodes produced only 250±10mW m-2. However, the AC-heat and AC-CB cathodes still produced 960-970mW m-2, whereas plain AC produced 860±60mW m-2. The performance of the AC cathodes was restored to >85% of the initial maximum power densities by cleaning with a weak acid solution. Based on cost considerations among the AC materials, AC-CB appears to be the best choice for long-term performance.

  17. Long-term cathode performance and the microbial communities that develop in microbial fuel cells fed different fermentation endproducts.

    Science.gov (United States)

    Kiely, Patrick D; Rader, Geoffrey; Regan, John M; Logan, Bruce E

    2011-01-01

    To better understand how cathode performance and substrates affected communities that evolved in these reactors over long periods of time, microbial fuel cells were operated for more than 1 year with individual endproducts of lignocellulose fermentation (acetic acid, formic acid, lactic acid, succinic acid, or ethanol). Large variations in reactor performance were primarily due to the specific substrates, with power densities ranging from 835 ± 21 to 62 ± 1mW/m(3). Cathodes performance degraded over time, as shown by an increase in power of up to 26% when the cathode biofilm was removed, and 118% using new cathodes. Communities that developed on the anodes included exoelectrogenic families, such as Rhodobacteraceae, Geobacteraceae, and Peptococcaceae, with the Deltaproteobacteria dominating most reactors. Pelobacter propionicus was the predominant member in reactors fed acetic acid, and it was abundant in several other MFCs. These results provide valuable insights into the effects of long-term MFC operation on reactor performance. Copyright © 2010 Elsevier Ltd. All rights reserved.

  18. Long-term safety of radioactive waste disposal. Radioactive analysis of samples from spent fuel leaching experiments

    International Nuclear Information System (INIS)

    Geckeis, H.; Degering, D.; Goertzen, A.; Geyer, F.W.; Dressler, P.

    1995-09-01

    In order to assess the long-term performance of spent fuel during direct disposal, high burnup fuel (50 MWd/kg U) has been exposed to non-buffered brine solutions and to deionized water under static anaerobic conditions at 25 C. The leaching behaviour of several radionuclides has been observed over periods of approximately 500 d. Currently used radiometric methods (α-, β-, γ-spectrometry) were applied to the analysis of sample solutions. Due to its low specific activity, uranium was determined using ICP-mass-spectrometry (ICP-MS) or laser induced fluorescence spectrometry (LFS). In order to determine radionuclide concentrations without interferences a preceeding radiochemical separation by ion-exchange, solvent-extraction or extraction chromatography was necessary in most cases. The Sc-isotopes 134/137, which are present in a high excess over other γ-emitting nuclides, were separated using the inorganic ion exchanger ammonium molybdato phosphate (AMP). This step allowed the subsequent γ-spectrometric determination of Am-241, Ag-110m, Ru-106, Sb-125 and Eu-154/155. Activity concentrations of pure β-emitters like Sr-90, Tc-99, I-129 and Pu-241 were determined by liquid scintillation counting (LSC) after selective separation using extraction chromatography or solvent extraction. The actinides Am-241, Cm-242/244, Pu-238/239/240 and Np-237 were analysed by α-spectrometry again after selective separation. The direct analysis of uranium by LFS or ICP-MS was hampered by high salt concentrations. Therefore a separation by extraction chromatography turned out to be necessary, too. The analytical procedures used throughout this work are described in detail. (orig.) [de

  19. Durability and efficiency tests for direct methanol fuel cell's long-term performance assessment

    International Nuclear Information System (INIS)

    Yeh, Pulin; Chang, Chu Hsiang; Shih, Naichien; Yeh, Naichia

    2016-01-01

    This research assessed the long-term performance of direct methanol fuel cells. The experiment was performed at room temperature using 0.51 mol/L ∼0.651 mol/L methanol with a fuel consumption rate of 0.8 ± 0.1 cc/Wh at stack temperature of 60 °C–70 °C. DuPont Nafion115 proton exchange membrane was used as the base material of MEA (membrane electrode assembly), which is then examined via a series of processes that include I−V curve test, humidity cycle test, load cycle test, and hydrogen penetration test. The study employs membrane modification and cell structure adjustment approaches to reduce the methanol crossover in the cathode and identify the cell performance effect of the carbon paper gas diffusion layer. The test results indicated an efficiency of 25% can be achieved with a three-piece MEA assembly. According to the durability test, the stack power-generation efficiency has maintained at 15%–25% level. With such efficiency, the stack voltage output has been able to stay above 7.8-V for over 5000 h. This result is in line with industry standard. - Highlights: • Assess DMFC performance under non-optimal conditions for production readiness. • Output of 26-cell DMFC stack stays beyond 7.8v after 5000 operation hours. • Power-generation efficiency of 26-cell DMFC stack maintains between 15%–20%.

  20. Supply of biofuels in short term and long term; Utbudet av biobraenslen paa kort och laang sikt

    Energy Technology Data Exchange (ETDEWEB)

    Lundmark, Robert (Luleaa Univ. of Technology, Luleaa (Sweden))

    2009-07-01

    The report aims to assess the economics of biofuels-supply in Sweden. This is done by constructing supply curves for the relevant categories of biomass. Further assessment is made on the future supply with a 10- and 25-year perspective, inter alia, to allow the adaptation of forest and agricultural sector technologies to more efficient use of biomass. The presence of regional and international markets is also included in the analysis. The model allows an estimate of a range for each category of biomass. These then form the basis for constructing different aggregate supply curves. The results indicate economic opportunities to increase the harvesting of biomass for a given cost. This increase is dependent on the prevailing cost. However, the results indicate that previous studies overestimate the potential reasons, why a higher degree of confidence is needed in order to formulate various policy measures

  1. Firewood harvest from forests of the Murray-Darling Basin, Australia. Part 1: Long-term, sustainable supply available from native forests

    International Nuclear Information System (INIS)

    West, P.W.; Cawsey, E.M.; Stol, J.; Freudenberger, D.

    2008-01-01

    The Murray-Darling Basin is a 1 million km 2 agricultural region of south-eastern Australia, although 29% of it retains native forests. Some are mallee eucalypt types, whilst the 'principal' types are dominated mainly by other eucalypt species. One-third of the 6-7 million oven-dry tonne of firewood burnt annually in Australia is obtained from these forests, principally through collection of coarse woody debris. There are fears that removal of this debris may prejudice the floral and faunal biodiversity of the Basin. The present work considers what silvicultural management practices will allow the long-term maintenance of the native forests of the Basin and their continued contribution to its biodiversity. It then estimates that the maximum, long-term, annual, sustainable yield of firewood which could be harvested, by collection of coarse woody debris, from principal forest types of the Basin would be 10 million oven-dry tonne yr -1 . An alternative, harvest of firewood from live trees by thinning the principal forests and clear-felling mallee forests, would be able to supply 2.3 million tonne yr -1 sustainably. Whilst coarse woody debris harvests could supply far more than the present demand for firewood from the Basin, they would lead to substantial reductions of the debris remaining in the forests; this may be detrimental to biodiversity maintenance. Live tree harvest does not lead to this problem, but would barely be able to supply existing firewood demand

  2. Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Broadhead, B.L.

    1995-01-01

    100,000 years. Ranking plots for each of these analysis areas are given in an Appendix for completeness, as well as summary tables in the main body of the report. Summary rankings are presented in terms of high (greater than 10% contribution to the total), medium (between 1% and 10% contribution), and low (less than 1% contribution) for both short- and long-term cooling. When compared with the expected measurement accuracies, these rankings show that most of the important isotopes can be characterized sufficiently for the purpose of radionuclide generation/depletion code validation in each of the analysis areas. Because the main focus of this work is on the relative importances of isotopes associated with LWR spent fuel, some conclusions may not be applicable to similar areas such as high-level waste (HLW) and nonfuel-bearing components (NFBC).

  3. The possibilities are very limited - The supply of electricity in Switzerland cannot be guaranteed in the long-term

    International Nuclear Information System (INIS)

    Veit, J.

    2004-01-01

    This article discusses the various factors influencing the security of supply of electricity in Switzerland. The author briefly reviews the present-day situation with power being produced by hydroelectric and nuclear power stations. Five possible options for action for ensuring electricity supply in the future are proposed: The increased import of power from neighbouring countries is looked at, the replacement or refurbishment of existing nuclear plant is considered, as is the augmentation and replacement of hydropower installations. A fourth option - the building of gas-fired, combined-cycle plant is discussed, as is the possibility of using renewable forms of energy such as solar, wind and geothermal energy

  4. Long-term stability analysis and effect evaluation of energy supply and demand in asia and pacific regions

    Energy Technology Data Exchange (ETDEWEB)

    Choi, B.R. [Korea Energy Economics Institute, Euiwang (Korea, Republic of)

    1998-06-01

    The competition in the supply of energy in Northeast Asian countries including Korea is forecasted to be intensively unfolded because of the soaring energy consumption the region. It is because the consumption of coal in Asia will be curtailed due to heightened global attention to environment, the import of Middle Eastern crude oil will be largely increasing since crude oil production in China and Indonesia is experiencing a slow-down. Therefore, close international cooperation is requested for the smooth supply of crude oil and natural gas to back up the economic growth. This study checked the energy supply and demand status in the Asian region that is changing since the 1990s, and analyzed the pressure factors in the energy supply sector. It needs to develop the Far Eastern region of Russia intensively as the energy supply base together with the Middle Eastern oil- producing regions as the plan to alleviate the energy competition within the region and seek economic development concurrently. Since this region requires large- scale investment as an never-expedited area, multilateral cooperation including neighboring countries that need energy and international enterprises who are interested in the profitability of the business are urgently required. Therefore, it is necessary to form and operate Northeast Asia Energy Forum (NAEF) which is a centripetal point that will actually carry out the resources development of Northeast Asia. Korea who is at the centripetal point of Northeast Asian tension should actively participate and support in the formation of this organization within the region in order to utilize it as the cornerstone of national north and south unification. 41 refs., 7 figs., 53 tabs.

  5. Kinetic and thermodynamic studies of uranium minerals. Assessment of the long-term evolution of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Casas, I; Bruno, J; Cera, E [MBT Tecnologia Ambiental, Cerdanyola (Spain); Finch, R J; Ewing, R C [Department of Earth and Planetary Sciences, University of New Mexico, Albuquerque, NM (United States)

    1994-10-01

    We have studied the dissolution behavior of uraninite, becquerelite, schoepite and uranophane. The information obtained under a variety of experimental conditions has been combined with extensive solid phase characterizations, performed in both leached and unleached samples. The overall objective is to construct a thermodynamic and kinetic model for the long-term oxidation alteration of UO{sub 2}(s), as an analogy of the spent nuclear fuel matrix. We have determined the solubility product for becquerelite (logK{sub s0} 32.7{+-}1.3) and uranophane (logK{sub s0} = 7.8{+-}0.8). In some experiments, the reaction progress has shown initial dissolution of uranophane followed by precipitation of a secondary solid phase, characterized as soddyite. The solubility production for this phase has been determined (logK{sub s0} = 3.0{+-}2.9). We have studied the kinetics of dissolution of uraninite, uranophane and schoepite under oxidizing conditions in synthetic granitic groundwater. BET measurements have been performed for uraninite and uranophane. For schoepite, the measurement has not been performed due to lack of sufficient amount of sample. The normalized rates of dissolution of uraninite and uranophane have been calculated referred to the uranium release, as 1.97x10{sup -8} moles h{sup -1} m{sup -2} and 4.0x 10{sup -9} moles h{sup -1} m{sup -2}, respectively. For schoepite, the dissolution process has shown two different rates, with a relatively fast initial dissolution rate of 1.97x10{sup -8} moles h{sup -1} followed, after approximately 1000 hours, by a slower one of 1.4x10{sup -9} moles h{sup -1}. No formation of secondary phases has been observed in those experiments, although final uranium concentrations have in all cases exceeded the solubility of uranophane, the thermodynamically more stable phase under the experimental conditions. 24 refs, 45 figs.

  6. Kinetic and thermodynamic studies of uranium minerals. Assessment of the long-term evolution of spent nuclear fuel

    International Nuclear Information System (INIS)

    Casas, I.; Bruno, J.; Cera, E.; Finch, R.J.; Ewing, R.C.

    1994-10-01

    We have studied the dissolution behavior of uraninite, becquerelite, schoepite and uranophane. The information obtained under a variety of experimental conditions has been combined with extensive solid phase characterizations, performed in both leached and unleached samples. The overall objective is to construct a thermodynamic and kinetic model for the long-term oxidation alteration of UO 2 (s), as an analogy of the spent nuclear fuel matrix. We have determined the solubility product for becquerelite (logK s0 32.7±1.3) and uranophane (logK s0 = 7.8±0.8). In some experiments, the reaction progress has shown initial dissolution of uranophane followed by precipitation of a secondary solid phase, characterized as soddyite. The solubility production for this phase has been determined (logK s0 = 3.0±2.9). We have studied the kinetics of dissolution of uraninite, uranophane and schoepite under oxidizing conditions in synthetic granitic groundwater. BET measurements have been performed for uraninite and uranophane. For schoepite, the measurement has not been performed due to lack of sufficient amount of sample. The normalized rates of dissolution of uraninite and uranophane have been calculated referred to the uranium release, as 1.97x10 -8 moles h -1 m -2 and 4.0x 10 -9 moles h -1 m -2 , respectively. For schoepite, the dissolution process has shown two different rates, with a relatively fast initial dissolution rate of 1.97x10 -8 moles h -1 followed, after approximately 1000 hours, by a slower one of 1.4x10 -9 moles h -1 . No formation of secondary phases has been observed in those experiments, although final uranium concentrations have in all cases exceeded the solubility of uranophane, the thermodynamically more stable phase under the experimental conditions. 24 refs, 45 figs

  7. Chances for a long-term securing of the raw material supply to the FRG. Pt. 1

    International Nuclear Information System (INIS)

    1975-09-01

    The Federal Republic of Germany is almost completely dependent on raw material imports. Growing raw material consumption and an imminent increase in supply uncertainties will require intensified research and development work in the field of raw material safeguarding. Initial approaches to possible technical solutions are being indicated in connection with four raw materials (aluminium, copper, phosphate and carbon carriers). The material balances of these raw materials are shown and the technical and economic interrelations illustrated in the light of world-wide trends. It is being demonstrated that two essential objectives are to be pursued for securing raw material supplies: 1) extension of the raw material basis for primary and secondary raw materials, 2) improvement of raw material utilization in all sectors of economy. To provide a solution for the wide spectrum of tasks it will be necessary to establish adequate analytical methods and procedures. (orig.) [de

  8. Long-term security in energy supplies - the contribution of coal; Dlugofalowe bezpieczenstwo w dostawach energii - udzial wegla

    Energy Technology Data Exchange (ETDEWEB)

    Schiffer, W. [RWE Power AG, Essen (Germany)

    2004-07-01

    The paper presents the case for coal as an important pillar in a wide and balanced mix of energy sources. Both domestic lignite and hard coal can be made available at relatively low cost. With coal powering power plants it is possible to achieve all energy policy goals of economic efficiency, security of supply and environmental compatibility. The paper includes much information on the global coal trade, particularly seaborne trade. 4 refs., 26 figs.

  9. Hybrid Electricity Markets with Long-Term Risk-Sharing Arrangements: Adapting Market Design to Security of Supply and decarbonization Objectives

    International Nuclear Information System (INIS)

    ROQUES, Fabien; FINON, Dominique

    2017-01-01

    The re-emergence of policy interventionism in electricity markets raises questions as to how market design can best be adapted to meeting the investment challenge associated with security of supply (SoS) and decarbonization objectives. This paper takes an institutionalist approach in terms of modularity of the market design, and reviews the standard historical approach towards competitive markets, in order to analyse the roles and interactions of the initial and additional market 'modules'. We argue that a number of additional modules is required to achieve long-term policy objectives, such as decarbonization and security of supply (SoS). But, in turn, they destabilise the initial modules of the market design, in particular by the entries of renewables. We review the international experience with hybrid market design and draw a number of policy recommendations at to best practices, as well as suggesting ways in which the initial market modules can be improved to prevent inconsistencies with the new modules. The move towards a hybrid market regime, which relies on a combination of planning, long-term risk sharing arrangements and improved markets entrenched in a function of short-term coordination, appears to be unavoidable where decarbonization policies are adopted. (authors)

  10. Long-term impacts due to sediment supply changes towards the San Francisco Bay-Delta system

    Science.gov (United States)

    Achete, F.; Van der Wegen, M. V.; Jaffe, B. E.

    2012-12-01

    The Sacramento-San Joaquin Delta and Watershed is the main source of fresh water and sediment to San Francisco Bay. Mid 19th century hydraulic mining in the catchment caused an excessive supply of sediment. After mining activities stopped, in the first part of the 20th century several hydraulic structures were built deviating fresh water and trapping sediment upstream. The main purpose of most of these structures is water storage for irrigation and/or water supply Wright and Schoellhamer (2004) show that from 1957 to 2001 the sediment load carried to San Francisco Bay has decreased by about one half. The lack of sediments may lead to a different erosion/deposition pattern in the Bay-Delta system causing problems like mud flat erosion, shift in navigation channel, land subsidence and changing habitat for endemic species. The objective of this work is to identify and quantify morphological shifts in the Bay-Delta system due to variation in fresh water and sediment supply. In this study, we couple the Delta and Bay in a unique model network (the Delta-Bay model). This coupling allows tracking of sediment from Sacramento via the Delta and Bay and through the Golden Gate, making it possible to identify erosion and deposition areas. The numerical model applied is an unstructured, process-based model (D-Flow Flexible Mesh developed by Deltares). It simulates the hydrodynamics and morphodynamics of the area on a detailed, 64000-node mesh (10-200m mesh length scale) on a timescale of minutes. The morphological impact is assessed for multiple scenarios with different input of sediment and fresh water. A statistical analysis is performed to account for uncertainty of model parameters and climate change impacts. The fresh water discharge already has a strong natural seasonal and inter-annual variation. The human impact by foreseen different water pumping strategies due to the peripheral canal will be considered. Jaffe et al. (2007) has shown that substantial morphological

  11. The Role of the Government and the Public in the Planning of Long Term Management for Nuclear Fuel Wastes in Canada

    International Nuclear Information System (INIS)

    Diah Hidayanti; Yudi Pramono

    2007-01-01

    The generation of electricity from nuclear power has the consequence of producing some wastes that are radioactive, especially in the form of spent fuels which are classified as high level nuclear wastes. Nuclear fuel wastes must be managed properly in order to protect public and environment from its big potential hazard. One type of long term management for nuclear fuel wastes is the final disposal in a permanent storage. Because of the importance of safety aspects for final disposal, it needs the involvement of government and the public to determine the reliability and the acceptance of final disposal concept. Those involvements can be implemented in some aspects such as regulation aspect, review and assessment process, and the public feedback. The evaluation on the plan of long term management for nuclear fuel wastes in Canada provides Indonesia an overview of its long term management plans for all radioactive materials, including nuclear fuel wastes generated from the nuclear power plant which is planned to be in service by 2016. (author)

  12. The long-term supply/demand trend of world energy and the current oil situation in the Asia

    International Nuclear Information System (INIS)

    Okamoto, Hiroyuki

    1996-01-01

    Total world primary energy consumption excluding the FSU increased by 2.9% in 1995, which is somewhat above the 10 year average rate of 2.4%. This reflected strong economic growth in most parts of the world. The increase in demand confirmed the recovery of the link between the economic growth and consumption of primary energy, which broke down in the period of oil crises. Oil demand in the Asian Emerging Market Economies has continued to be very strong. Oil demand has doubled in a decade in this region and is now one sixth of world consumption. Malaysia was the fastest growing oil market in the world in 1995 at 15.5%. In volume terms, S. Korea grew the most in the world by 170,000 b/d, closely followed by China and India. Because of the fast growing oil demand, many energy economists expect a tight supply situation in the Asian oil market in the early 21st Century. However, recent technological developments would be able to supply crude oil appropriate for an increase in oil demand. (author)

  13. Offshore Brazil: forcing the path to the future managing supply chain challenges to ensure long-term growth

    Energy Technology Data Exchange (ETDEWEB)

    Hillegeist, Paul H.; Pickard, Matt [Quest Offshore Resources, Inc., Sugar Land, TX (United States)

    2008-07-01

    Over the last 10 years, worldwide demand for energy has seen a significant increase. This accelerated growth has placed a tremendous strain on the offshore oil and gas E and P industry, as operators strive to find and develop new accumulations to help meet rising global energy demand, while overcoming many substantial challenges. Whether those challenges come from limited manufacturing and construction supply or limited human capital, these issues will need to be addressed in order for the industry to continue to push forward at a record pace. Additionally, the industry will have to rely heavily on new and emerging technologies, some of which are largely unproven. Nowhere is this dedication to technological achievement more evident than in the deep waters offshore Brazil. Recent discoveries have placed an added degree of focus on the technologies that will be needed to help develop these fields in a commercially viable manner. Given Brazil's track record for innovation and accomplishment, the region is poised to present a number of industry-wide advancements over the next 10 to 15 years as Brazil continues to be a trend setter for worldwide energy security. A thorough understanding of these issues, as well as the potential solutions to overcoming them, is critical to companies wishing to participate in the highly rewarding Brazilian offshore sector. This presentation will strive to detail the underlying factors that drive industry activity, including burgeoning commercial opportunities for service and supply companies, as well as addressing the technologies currently in progress that will help move the industry into ultra-deep water exploration and development. (author)

  14. Long-term concepts for the energy supply of developing countries, with a detailed discussion of Brazil

    International Nuclear Information System (INIS)

    Koenig, C.

    1975-01-01

    The possibilities of meeting the energy requirements by nuclear energy are scrutinized after giving a survey about today's energy situation in Brazil and the beginnings of an eventual development until the year 2000. An analysis of energy-intensive industry branches and of the electro-energy economy shows a primary need of energy until the year 2000 which can substantially be met using nuclear energy. Especially the use of high-temperature reactors appears an optimal solution. The effects of HTR application on the structure of primary energy sources, on the pollution of the environment, and on the balance of foreign exchange payments are examined in detail. The nuclear power plants should be constructed in such a way that a number of additional products (fuel gases, reduction gases, synthesis gas, hydrocarbons) should be produced besides current generation by utilizing process heat. (UA) [de

  15. The assessment of the long-term evolution of the spent nuclear fuel matrix by kinetic, thermodynamic and spectroscopic studies of uranium minerals

    International Nuclear Information System (INIS)

    Bruno, J.; Casas, I.; Cera, E.; Ewing, R.C.; Finch, R.J.

    1995-01-01

    The long term behavior of spent nuclear fuel is discussed in the light of recent thermodynamic and kinetic data on mineralogical analogues related to the key phases in the oxidative alteration of uraninite. The implications for the safety assessment of a repository of the established oxidative alteration sequence of the spent fuel matrix are illustrated with Pagoda calculations. The application to the kinetic and thermodynamic data to source term calculations indicates that the appearance and duration of the U(VI) oxyhydroxide transient is critical for the stability of the fuel matrix

  16. Sulfur poisoning of Ni/Gadolinium-doped ceria anodes: A long-term study outlining stable solid oxide fuel cell operation

    Science.gov (United States)

    Riegraf, Matthias; Zekri, Atef; Knipper, Martin; Costa, Rémi; Schiller, Günter; Friedrich, K. Andreas

    2018-03-01

    This work presents an analysis of the long-term behavior of nickel/gadolinium-doped ceria (CGO) anode-based solid oxide fuel cells (SOFC) under sulfur poisoning conditions. A parameter study of sulfur-induced irreversible long-term degradation of commercial, high-performance single cells was carried out at 900 °C for different H2/N2/H2S fuel gas atmospheres, current densities and Ni/CGO anodes. The poisoning periods of the cells varied from 200 to 1500 h. The possibility of stable long-term Ni/CGO anode operation under sulfur exposure is established and the critical operating regime is outlined. Depending on the operating conditions, two degradation phenomena can be observed. Small degradation of the ohmic resistance was witnessed for sulfur exposure times of approximately 1000 h. Moreover, degradation of the anode charge transfer resistance was observed to be triggered by the combination of a small anodic potential step and high sulfur coverage on Ni. The microstructural evolution of altered Ni/CGO anodes was examined post-mortem by means of SEM and FIB/SEM, and is correlated to the anode performance degradation under critical operating conditions, establishing Ni depletion, porosity increase and a tripe phase boundary density decrease in the anode functional layer. It is shown that short-term sulfur poisoning behavior can be used to assess long-term stability.

  17. High polymer composites for containers for the long-term storage of spent nuclear fuel and high level radioactive waste

    International Nuclear Information System (INIS)

    Bonin, H.W.; Vui, V.T.; Legault, J.-F.

    1997-01-01

    The feasibility of using polymeric composite materials as an alternative to metals in the design of a nuclear waste disposal container was examined. The disposal containers would be stored in deep underground vaults in plutonic rock formations within the Canadian Shield for several thousands of years. The conditions of disposal considered in the evaluation of the polymeric composite materials were based on the long-term disposal concept proposed by Atomic Energy of Canada Limited. Four different composites were considered for this work, all based on boron fibre as reinforcing material, imbedded in polymeric matrices made of polystyrene (PS), polymethyl methacrylate (PMMA), Devcon 10210 epoxy, and polyetheretherketone (PEEK). Both PS and PMMA were determined as unsuitable for use in the fabrication of the storage container because of thermal failure. This was determined following thermal analysis of the materials in which heat transfer calculations yielded the temperature of the container wall and of the surroundings resulting from the heat generated by the spent nuclear fuel stored inside the container. In the case of the PS, the temperature of the container, the buffer and the backfill would exceed the 100 degrees C imposed in the AECL's proposal as the maximum allowable. In the case of the PMMA, the 100 degrees temperature is too close to the glass transition temperature of this material (105 degrees C) and would cause structural degradation of the container wall. The other two materials present acceptable thermal characteristics for this application. An important concern for polymeric materials in such use is their resistance to radiations. The Devcon 10210 epoxy has been the object of research at the Royal Military College in the past years and fair, but limited, resistance to both neutrons and gamma radiation has been demonstrated, with the evidence of increased mechanical strength when subjected to moderate doses. Provided that the container wall could be

  18. Utilization of Plutonium and Higher Actinides in the HTGR as Possibility to Maintain Long-Term Operation on One Fuel Loading

    International Nuclear Information System (INIS)

    Tsvetkova, Galina V.; Peddicord, Kenneth L.

    2002-01-01

    Promising existing nuclear reactor concepts together with new ideas are being discussed worldwide. Many new studies are underway in order to identify prototypes that will be analyzed and developed further as systems for Generation IV. The focus is on designs demonstrating full inherent safety, competitive economics and proliferation resistance. The work discussed here is centered on a modularized small-size High Temperature Gas-cooled Reactor (HTGR) concept. This paper discusses the possibility of maintaining long-term operation on one fuel loading through utilization of plutonium and higher actinides in the small-size pebble-bed reactor (PBR). Acknowledging the well-known flexibility of the PBR design with respect to fuel composition, the principal limitations of the long-term burning of plutonium and higher actinides are considered. The technological challenges and further research are outlined. The results allow the identification of physical features of the PBR that significantly influence flexibility of the design and its applications. (authors)

  19. Proceedings of the 13th forum: Croatian Energy Day: Long-term planning and consumer supply safety in open market conditions

    International Nuclear Information System (INIS)

    Granic, G.; Jelavic, B.

    2004-01-01

    The process of opening up the energy market has been proceeding at an accelerating pace; legislative and institutional prerequisites have come into existence for a transparent and nondiscriminatory approach to energy systems (networks), and for an easy market access to suppliers by granting customers the right of supplier choice. National borders - once an obstacle to energy market development - are thus eliminated. Advantages of this sort of development strategy for energy markets include top-quality competition and market de-monopolization, which in turn, as a rule, imply a more favorable position for the users of energy system services, for energy buyers / purchasers, and for consumers. However, the coexistence of internal (national) and international competitions raises the issue of the framework and contents of long-term planning, as well as of the liability of states and government institutions for the adequacy, security, and stability of energy sources, and consequently for customer supply security

  20. Assessment of the long-term risk of a meteorite impact on a hypothetical Canadian nuclear fuel waste disposal vault deep in plutonic rock

    International Nuclear Information System (INIS)

    Wuschke, D.M.; Whitaker, S.H.; Goodwin, B.W.; Rasmussen, L.R.

    1995-06-01

    This report describes an assessment of the long-term radiological risk to an individual of the critical group that would result from a meteorite impact on a hypothetical reference disposal vault for used fuel, located 500 m below the Earth's surface. The purpose of the assessment was to determine if this radiological risk could exceed or approach the AECB risk criterion. (author). 47 refs., 5 tabs., 6 figs

  1. Short and long term supply curves for crude oil and the consequences for the market; Kurz- und langfristige Angebotskurven fuer Rohoel und die Konsequenzen fuer den Markt

    Energy Technology Data Exchange (ETDEWEB)

    Schlothmann, Daniel

    2016-03-08

    In this work, supply curves for 22 major oil producing countries were identified and then aggregated into global supply curves. According to the identified supply curves, almost all oil-producing oil projects currently under development in the study countries are also profitable at the current oil price of $ 35 to $ 40 per barrel, taking short-term marginal costs into account. However, if the price of oil remains at this level in the coming years, a supply bottleneck on the global oil market will occur until 2024, as the development of cost-intensive, unconventional deposits and of deposits in deep and very deep waters is necessary to meet future demand. In order to avoid such a supply bottleneck by 2024, an oil price of at least US $ 80 per barrel is required, according to the long-term market equilibrium determined. [German] In dieser Arbeit wurden Angebotskurven fuer 22 bedeutende Oelfoerderlaender ermittelt und anschliessend zu globalen Angebotskurven aggregiert. Gemaess den ermittelten Angebotskurven sind nahezu alle gegenwaertig in der Foerderphase befindlichen Oelprojekte in den Untersuchungslaendern auch beim aktuellen Oelpreis von 35 bis 40 US-$ je Barrel unter Beruecksichtigung der kurzfristigen Grenzkosten rentabel. Sollte der Oelpreis jedoch in den kommenden Jahren auf diesem Niveau verharren, wird es bis zum Jahr 2024 zu einem Angebotsengpass auf dem globalen Oelmarkt kommen, da zur Deckung der zukuenftigen Nachfrage die Erschliessung kostenintensiver, unkonventioneller Lagerstaetten und von Lagerstaetten in tiefen und sehr tiefen Gewaessern notwendig ist. Damit es bis zum Jahr 2024 nicht zu einem solchen Angebotsengpass kommt, ist gemaess des ermittelten langfristigen Marktgleichgewichts ein Oelpreis von mindestens 80 (2014er) US-$ je Barrel notwendig.

  2. The challenge of long-term participatory repository governance. Lessons learned for high level radioactive waste and spent fuel

    International Nuclear Information System (INIS)

    Landstroem, Catharina

    2012-01-01

    Voluntaristic siting procedures for deep geological repositories are becoming increasingly common; they reconfigure the relationship of repositories and society in ways that have implications for the long-term governance of these facilities. This paper identifies three challenges emerging in relation to this question: principles of monitoring, repository content, and facility closure. This paper discusses them in a comparison with similar challenges being addressed in Belgian partnerships founded to facilitate the siting and design of a low- and intermediate level short lived waste repository. The empirical exploration confirms the importance of securing stakeholder engagement throughout the repository lifecycle, for which there is a need to develop knowledge about how to encourage long-term democratic governance systems.

  3. International symposium on MOX fuel cycle technologies for medium and long-term deployment. Book of extended synopses

    International Nuclear Information System (INIS)

    1999-05-01

    The purpose of the Symposium was to provide a forum to exchange information on MOX fuel cycle technologies with focus on how past experience is being or can be used to progress further, either for facing more demanding fabrication and utilization conditions or for extending into new processing or utilization domains. Presented papers covered the following topics: Current status and prospects concerning plutonium management and MOX fuel utilization; MOX fuel fabrication technology and quality control; Fuel design, performance and testing; In-core fuel management and advanced fuel cycle options; Safety analysis, licensing and safeguards; Transportation and management of irradiated MOX fuel

  4. Long-term trends in US gas supply and prices: 1993 edition of the GRI baseline projection of US energy supply and demand to 2010

    International Nuclear Information System (INIS)

    Woods, T.J.

    1993-03-01

    A Summary of the gas supply outlook in the 1993 Edition of the GRI Baseline Projection of U.S. Energy Supply and Demand, adopted as a major input to the planning cycle of the 1994 research and development program, is presented. Significant changes were made in developing the gas supply and price trends for the 1993 edition of the projection. The GRI Hydrocarbon Model was expanded to include the Canadian hydrocarbon resource base. Thus, Canadian and lower-48 gas production and prices were developed on a fully integrated basis in the 1993 projection. The lower-48 hydrocarbon resource estimate was increased, reflecting the results of the recent National Petroleum Council gas study and ongoing GRI resource work. The effects of new technology and practice on drilling costs and exploration efficiency were included for the first time. Appendices include comparisons of supply and price trends

  5. Evaluation of Thermal Creep and Hydride Re-orientation Properties of High Burnup Spent Fuel Cladding under Long Term Dry storage

    Energy Technology Data Exchange (ETDEWEB)

    Kamimura, K [JNES (Japan)

    2012-07-01

    In Japan, spent fuels will be reprocessed as recyclable energy source at a reprocessing plant. The first commercial plant is under-constructing and will start operation in 2008. It is necessary that spent fuels should be stored in the independent interim storage facilities (ISF) until reprocessing. Utilities plan the operation of the first ISF in 2010. JNES has a mission to support the safety body by researching the data of technical standard and regulation. Investigating of spent fuel integrity during long term dry storage is one of them. The objectives are: 1) Evaluation of the effects of material design changes on creep properties of high burnup spent fuel cladding; 2) Evaluation of the effects of alloy elements and texture of irradiated Zircaloy on hydride re-orientation properties and the effects of radial hydrides on cladding mechanical properties; 3) Evaluation of the effects of temperature on irradiation hardening recovery.

  6. Long-term effect of set potential on biocathodes in microbial fuel cells: electrochemical and phylogenetic characterization.

    Science.gov (United States)

    Xia, Xue; Sun, Yanmei; Liang, Peng; Huang, Xia

    2012-09-01

    The long-term effect of set potential on oxygen reducing biocathodes was investigated in terms of electrochemical and biological characteristics. Three biocathodes were poised at 200, 60 and -100 mV vs. saturated calomel electrode (SCE) for 110 days, including the first 17 days for startup. Electrochemical analyses showed that 60 mV was the optimum potential during long-term operation. The performance of all the biocathodes kept increasing after startup, suggesting a period longer than startup time needed to make potential regulation more effective. The inherent characteristics without oxygen transfer limitation were studied. Different from short-term regulation, the amounts of biomass were similar while the specific electrochemical activity was significantly influenced by potential. Moreover, potential showed a strong selection for cathode bacteria. Clones 98% similar with an uncultured Bacteroidetes bacterium clone CG84 accounted for 75% to 80% of the sequences on the biocathodes that showed higher electrochemical activity (60 and -100 mV). Copyright © 2012 Elsevier Ltd. All rights reserved.

  7. Supply Security in Future Nuclear Fuel Markets

    Energy Technology Data Exchange (ETDEWEB)

    Seward, Amy M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wood, Thomas W. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gitau, Ernest T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ford, Benjamin E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2013-11-18

    Previous PNNL work has shown the existing nuclear fuel markets to provide a high degree of supply security, including the ability to respond to supply disruptions that occur for technical and non-technical reasons. It is in the context of new reactor designs – that is, reactors likely to be licensed and market ready over the next several decades – that fuel supply security is most relevant. Whereas the fuel design and fabrication technology for existing reactors are well known, the construction of a new set of reactors could stress the ability of the existing market to provide adequate supply redundancy. This study shows this is unlikely to occur for at least thirty years, as most reactors likely to be built in the next three decades will be evolutions of current designs, with similar fuel designs to existing reactors.

  8. Supply Security in Future Nuclear Fuel Markets

    International Nuclear Information System (INIS)

    Seward, Amy M.; Wood, Thomas W.; Gitau, Ernest T.; Ford, Benjamin E.

    2013-01-01

    Previous PNNL work has shown the existing nuclear fuel markets to provide a high degree of supply security, including the ability to respond to supply disruptions that occur for technical and non-technical reasons. It is in the context of new reactor designs - that is, reactors likely to be licensed and market ready over the next several decades - that fuel supply security is most relevant. Whereas the fuel design and fabrication technology for existing reactors are well known, the construction of a new set of reactors could stress the ability of the existing market to provide adequate supply redundancy. This study shows this is unlikely to occur for at least thirty years, as most reactors likely to be built in the next three decades will be evolutions of current designs, with similar fuel designs to existing reactors.

  9. Fuel supply strategy for power projects in Asia

    International Nuclear Information System (INIS)

    Boyd, D.

    1997-01-01

    Electricity generation is forecast to grow in Asia over the next twenty years. This will bring with it a significant growth in demand for energy resources. Major Asian utility coal procurement strategy to date has aimed at securing a balance between two conflicting needs - security of supply and low cost of supply. Despite the oversupply of coal in the eighties, the two countries experiencing significant growth in demand, Japan and Korea, planned their fuel strategies to ensure security of supply. The supply shortage over the past two years has justified their forward thinking in keeping long term coal contracts in place. Changes are already happening. Recent developments are seeing a move towards the positive attributes of low ash/low sulphur coals appropriately focusing suppliers thoughts on the need in the future to develop and concentrate on environmentally attractive coals to achieve greater returns. Indeed, generally there is a trend in North Asia to demand coal with lower sulphur, and lower ash. The aim now should be to persuade consumers to amend the narrow benchmark view in favour of one that considers the value in use of a particular coal to the customer. The method of pricing thermal coals is also likely to be influenced by the liberalization of the electricity market itself. The introduction of competition amongst generators and the appearance and growth of the Independent Power Producers could well see further pressure on the current simplistic benchmark system. Those financing such projects will seek to reduce risk by every means possible and, in particular, will want to be confident of the long term security of coal supplies

  10. Possible effects of UO2 oxidation on light water reactor spent fuel performance in long-term geologic disposal

    International Nuclear Information System (INIS)

    Almassy, M.Y.; Woodley, R.E.

    1982-08-01

    Disposal of spent nuclear fuel in a conventionally mined geologic formation is the nearest-term option for permanently isolating radionuclides from the biosphere. Because irradiated uranium dioxide (UO 2 ) fuel pellets retain 95 to 99% of the radionuclides generated during normal light water reactor operation, they may represent a significant barrier to radionuclide release. This document presents a technical assessment of published literature representing the current level of understanding of spent fuel characteristics and conditions that may degrade pellet integrity during a geologic disposal sequence. A significant deterioration mechanism is spent UO 2 oxidation with possible consequences identified as fission gas release, rod diameter increases, cladding breach extension, and release of solid fuel particles containing radionuclides. Areas requiring further study to support development of a comprehensive spent fuel performance prediction model are highlighted. A program and preliminary schedule to obtain the information needed to develop model correlations are also presented

  11. Factors determining the long term back end nuclear fuel cycle strategy and future nuclear systems. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2002-05-01

    The Technical Committee Meeting (TCM) was held in Vienna on 8-10 November 1999; it was organized by the International Atomic Energy Agency and attended by 26 participants from 16 Member States. The purpose of the meeting was to exchange information among experts on the back end fuel cycle strategies adopted by Member States; to identify key factors determining the long-term back end fuel cycle strategies; and to assess the applicability of these factors to future nuclear systems. Issues associated with the back end fuel cycle supporting a country's nuclear power programme are technical, economic, institutional and political. This TCM provided an opportunity to address these issues and their impacts to the back end fuel cycles, as well as to identify and assess factors affecting the back end fuel cycle strategies. The discussion was organized ib the following topical sessions: the nuclear fuel cycle; spent fuel management; waste management and repository; plutonium management. This document contains a summary of the meeting and 22 individual papers presented by participants. Each of the papers was indexed separately

  12. Factors determining the long term back end nuclear fuel cycle strategy and future nuclear systems. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-05-01

    The Technical Committee Meeting (TCM) was held in Vienna on 8-10 November 1999; it was organized by the International Atomic Energy Agency and attended by 26 participants from 16 Member States. The purpose of the meeting was to exchange information among experts on the back end fuel cycle strategies adopted by Member States; to identify key factors determining the long-term back end fuel cycle strategies; and to assess the applicability of these factors to future nuclear systems. Issues associated with the back end fuel cycle supporting a country's nuclear power programme are technical, economic, institutional and political. This TCM provided an opportunity to address these issues and their impacts to the back end fuel cycles, as well as to identify and assess factors affecting the back end fuel cycle strategies. The discussion was organized ib the following topical sessions: the nuclear fuel cycle; spent fuel management; waste management and repository; plutonium management. This document contains a summary of the meeting and 22 individual papers presented by participants. Each of the papers was indexed separately.

  13. Long-term outlook for global natural uranium and uranium enrichment supply and demand situations after the impact of Fukushima Daiichi Nuclear Power Plant accident

    International Nuclear Information System (INIS)

    Matsuo, Yuhji; Murakami, Tomoko

    2012-01-01

    In this paper, the authors propose long-term projections of global nuclear power generation, uranium production, and uranium enrichment capacities by region, and estimate the trade flows of natural uranium and uranium enrichment activities in 2020 and 2035. In spite of the rapid nuclear power generation capacity growth expected especially in Asia, the natural uranium and uranium enrichment trade will not be tightened by 2020 due to the projected increase in both natural uranium production and uranium enrichment capacities, which may cause a drop in natural uranium and uranium enrichment prices. Thus, there is a great possibility that the current projects for capacity expansion will be delayed considerably. However, in the 'high-demand scenario', where nuclear expansion will be accelerated due to growing concerns about global warming and energy security issues, additional investments in uranium production and enrichment facilities will be needed by 2035. In Asia, the self-sufficiency ratio for both natural uranium supply and uranium enrichment activities will remain relatively low until 2035. However, the Herfindahl-Hirschman (HH) index of natural uranium and uranium enrichment activity trade to Asia will be lowered considerably up to 2035, indicating that nuclear capacity expansion can contribute to enhancing energy security in Asia. (author)

  14. A decision analysis framework to support long-term planning for nuclear fuel cycle technology research, development, demonstration and deployment

    International Nuclear Information System (INIS)

    Sowder, A.G.; Machiels, A.J.; Dykes, A.A.; Johnson, D.H.

    2013-01-01

    To address challenges and gaps in nuclear fuel cycle option assessment and to support research, develop and demonstration programs oriented toward commercial deployment, EPRI (Electric Power Research Institute) is seeking to develop and maintain an independent analysis and assessment capability by building a suite of assessment tools based on a platform of software, simplified relationships, and explicit decision-making and evaluation guidelines. As a demonstration of the decision-support framework, EPRI examines a relatively near-term fuel cycle option, i.e., use of reactor-grade mixed-oxide fuel (MOX) in U.S. light water reactors. The results appear as a list of significant concerns (like cooling of spent fuels, criticality risk...) that have to be taken into account for the final decision

  15. Review and evaluation of long-term integrity on metal casks and spent fuels stored in overseas countries

    International Nuclear Information System (INIS)

    Sasahara, Akihiro; Saegusa, Toshiari

    2009-01-01

    Inspection and experimental results on the metal cask and PWR-UO 2 spent fuels practically stored for fifteen years in Idaho National Laboratory (INL) are reviewed. Experimental results on PWR-UO 2 and BWR-MOX spent fuels stored for twenty years under wet or dry condition obtained by Central Research Institute of Electric Power Industry (CRIEPI) are also reviewed. These results show that the integrity of the metal cask and PWR-spent fuels are maintained at least during dry storage for fifteen years and that Japanese electric utilities may start their self-inspection on casks and spent fuels after fifteen-year storage. The gas sampling carrying out in INL can be applied to licensing for interim dry storage facilities in Japan. New program for the fuel integrity for high burn-up fuels (>45 GWd/MTU) at transportation after dry storage has been launched by Nuclear Regulation Commission (NRC), Department of Energy (DOE) and Electric Power Research Institute (EPRI) in USA. (author)

  16. Keys to fuel supply success

    International Nuclear Information System (INIS)

    Rostorfer, C.R.

    1991-01-01

    This article examines the changes to the fuel procurement process, some brought about by acid rain legislation, and provides a step-by-step guide to handling the changes. The topics include requirements planning, market research, developing a good procurement strategy, implementing the strategy, effective administration, and a checklist for contract review

  17. Hazard Classification for Fuel Supply Shutdown Facility

    International Nuclear Information System (INIS)

    BENECKE, M.W.

    2000-01-01

    Final hazard classification for the 300 Area N Reactor fuel storage facility resulted in the assignment of Nuclear Facility Hazard Category 3 for the uranium metal fuel and feed material storage buildings (303-A, 303-B, 303-G, 3712, and 3716). Radiological for the residual uranium and thorium oxide storage building and an empty former fuel storage building that may be used for limited radioactive material storage in the future (303-K/3707-G, and 303-E), and Industrial for the remainder of the Fuel Supply Shutdown buildings (303-F/311 Tank Farm, 303-M, 313-S, 333, 334 and Tank Farm, 334-A, and MO-052)

  18. 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

  19. Multilayer graphene for long-term corrosion protection of stainless steel bipolar plates for polymer electrolyte membrane fuel cell

    DEFF Research Database (Denmark)

    Stoot, Adam Carsten; Camilli, Luca; Spiegelhauer, Susie Ann

    2015-01-01

    Abstract Motivated by similar investigations recently published (Pu et al., 2015), we report a comparative corrosion study of three sets of samples relevant as bipolar plates for polymer electrolyte fuel cells: stainless steel, stainless steel with a nickel seed layer (Ni/SS) and stainless steel...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-10-01

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

  1. Long-term exposure to jet fuel. An investigation on occupationally exposed workers with special reference to the nervous system

    Energy Technology Data Exchange (ETDEWEB)

    Knave, B; Persson, H E; Goldberg, M; Westerholm, P

    1976-09-01

    Chronic solvent intoxication due to jet fuel vapor was diagnosed after tests on 29 aircraft factory workers. The exposed subjects were classified into (1) heavily exposed and (2) less heavily exposed groups. Tests included a clinical neurological examination, measurements of the peipheral nerve conduction velocities and threshold determination of vibratory sensations in the extremities. All 13 examined in the first group and 7 of 16 in the second group stated that, on repeated occasions, they had experienced acute effects (dizziness, dyspnoea, heart palpitations, chest striction, nausea, headaches) of the jet fuel vapors in the inhaled air. Air overrepresentation of symptoms of neurasthenia and physical disturbances, polyneuropathic symptoms and plyneuropathic findings were evident from the neurological status both in the heavily exposed group and in the two groups taken as a whole when comparison was made with reference groups. Moreover, relatively lower nerve conduction velocities and higher vibration thresholds were witnessed in both groups compared with a reference group from the heavy metal industry.

  2. Nuclear fuel supply view in Argentina

    International Nuclear Information System (INIS)

    Cirimello, R.O.

    1997-01-01

    The Argentine Atomic Energy Commission promoted and participated in a unique achievement in the R and D system in Argentina: the integration of science technology and production based on a central core of knowledge for the control and management of the nuclear fuel cycle technology. CONUAR SA, as a fuel manufacturer, FAE SA, the manufacturer of Zircaloy tubes, CNEA and now DIOXITEC SA producer of Uranium Dioxide, have been supply, in the last ten years, the amount of products required for about 1300 Tn of equivalent U content in fuels. The most promising changes for the fuel cycle economy is the Slight Enriched Uranium project which begun in Atucha I reactor. In 1997 seventy five fuel assemblies, equivalent to 900 Candu fuel bundles, will complete its irradiation. (author)

  3. Supply of fossil heating and motor fuels

    International Nuclear Information System (INIS)

    Kaegi, W.; Siegrist, S.; Schaefli, M.; Eichenberger, U.

    2003-01-01

    This comprehensive study made for the Swiss Federal Office of Energy (SFOE) within the framework of the Energy Economics Fundamentals research programme examines if it can be guaranteed that Swiss industry can be supplied with fossil fuels for heating and transport purposes over the next few decades. The results of a comprehensive survey of literature on the subject are presented, with a major focus being placed on oil. The study examines both pessimistic and optimistic views and also presents an overview of fossil energy carriers and the possibilities of substituting them. Scenarios and prognoses on the availability of fossil fuels and their reserves for the future are presented. Also, new technologies for exploration and the extraction of fossil fuels are discussed, as are international interdependencies that influence supply. Market and price scenarios are presented that take account of a possible increasing scarcity of fossil fuels. The implications for industry and investment planning are examined

  4. Nuclear fuel supply continues to be cheap and secure

    International Nuclear Information System (INIS)

    Braatz, U.; Dibbert, H.J.

    1985-01-01

    The fuel supply for German nuclear power stations has been secured in the long term in all the individual circuit stages. There are problems because of existing overcapacity worldwide on the suppliers' side. The worldwide throttling of natural uranium production has proved to be a possible way of supporting uranium prices. Because of the stagnant market for longterm contracts, there is still worry among uranium producer regarding further development of the market. The 1984 turnover on the spot market for natural uranium has nearly trebled compared with the previous year. The excess uranium conversion capacity in this sector caused low capacity utilisation and led to offers with considerable reductions. Turbulence with its epicentre in the USA has a feature of the separation work market. The centrifuge enrichers are better placed regarding production costs than the gas diffusion enrichers even with low capacity utilisation and use this advantage. The gas diffusion plants were only at half load, which led to new contract offers from DOE and to competitive prices with long term guaranteed discounts offered by COGEMA. The laser enrichment process was great interest to all energy producing countries. The use of recovered uranium and plutonium is still in the experimental stage. In view of the growing quantities of plutonium, the use of MOX in thermal reactors is growing in importance. (orig./HP) [de

  5. An assessment of the long-term impact of chemically toxic contaminants from the disposal of nuclear fuel waste

    International Nuclear Information System (INIS)

    Goodwin, B.W.; Garisto, N.C.; Barnard, J.W.

    1987-01-01

    This paper presents a study on the potential for impact on man of chemically toxic contaminants associated with the Canadian concept for the disposal of nuclear fuel waste. The elements of concern are determined through a series of screening criteria such as elemental abundances and solubilities. A systems variability analysis approach is then used to predict the possible concentrations of these elements that may arise in the biosphere. These concentrations are compared with environmental guidelines such as permissible levels in drinking water. Conclusions are made regarding the potential for the chemically toxic contaminants to have an impact on man. 54 refs

  6. Analytical approximations for the long-term decay behavior of spent fuel and high-level waste

    International Nuclear Information System (INIS)

    Malbrain, C.M.; Deutch, J.M.; Lester, R.K.

    1982-01-01

    Simple analytical approximations are presented that describe the radioactivity and radiogenic decay heat behavior of high-level wastes (HLWs) from various nuclear fuel cycles during the first 100,000 years of waste life. The correlations are based on detailed computations of HLW properties carried out with the isotope generation and depletion code ORIGEN 2. The ambiguities encountered in using simple comparisons of the hazards posed by HLWs and naturally occurring mineral deposits to establish the longevity requirements for geologic waste disposal schemes are discussed

  7. Long-term fuel retention and release in JET ITER-Like Wall at ITER-relevant baking temperatures

    Science.gov (United States)

    Heinola, K.; Likonen, J.; Ahlgren, T.; Brezinsek, S.; De Temmerman, G.; Jepu, I.; Matthews, G. F.; Pitts, R. A.; Widdowson, A.; Contributors, JET

    2017-08-01

    The fuel outgassing efficiency from plasma-facing components exposed in JET-ILW has been studied at ITER-relevant baking temperatures. Samples retrieved from the W divertor and Be main chamber were annealed at 350 and 240 °C, respectively. Annealing was performed with thermal desoprtion spectrometry (TDS) for 0, 5 and 15 h to study the deuterium removal effectiveness at the nominal baking temperatures. The remained fraction was determined by emptying the samples fully of deuterium by heating W and Be samples up to 1000 and 775 °C,respectively. Results showed the deposits in the divertor having an increasing effect to the remaining retention at temperatures above baking. Highest remaining fractions 54 and 87 % were observed with deposit thicknesses of 10 and 40 μm, respectively. Substantially high fractions were obtained in the main chamber samples from the deposit-free erosion zone of the limiter midplane, in which the dominant fuel retention mechanism is via implantation: 15 h annealing resulted in retained deuterium higher than 90 % . TDS results from the divertor were simulated with TMAP7 calculations. The spectra were modelled with three deuterium activation energies resulting in good agreement with the experiments.

  8. OPTIMIZATION OF THE CATHODE LONG-TERM STABILITY IN MOLTEN CARBONATE FUEL CELLS: EXPERIMENTAL STUDY AND MATHEMATICAL MODELING

    Energy Technology Data Exchange (ETDEWEB)

    Hector Colonmer; Prabhu Ganesan; Nalini Subramanian; Dr. Bala Haran; Dr. Ralph E. White; Dr. Branko N. Popov

    2002-09-01

    This project focused on addressing the two main problems associated with state of art Molten Carbonate Fuel Cells, namely loss of cathode active material and stainless steel current collector deterioration due to corrosion. We followed a dual approach where in the first case we developed novel materials to replace the cathode and current collector currently used in molten carbonate fuel cells. In the second case we improved the performance of conventional cathode and current collectors through surface modification. States of art NiO cathode in MCFC undergo dissolution in the cathode melt thereby limiting the lifetime of the cell. To prevent this we deposited cobalt using an electroless deposition process. We also coated perovskite (La{sub 0.8}Sr{sub 0.2}CoO{sub 3}) in NiO thorough a sol-gel process. The electrochemical oxidation behavior of Co and perovskites coated electrodes is similar to that of the bare NiO cathode. Co and perovskite coatings on the surface decrease the dissolution of Ni into the melt and thereby stabilize the cathode. Both, cobalt and provskites coated nickel oxide, show a higher polarization compared to that of nickel oxide, which could be due to the reduced surface area. Cobalt substituted lithium nickel oxide (LiNi{sub 0.8}Co{sub 0.2}O{sub 2}) and lithium cobalt oxide were also studied. LiNi{sub x}Co{sub 1-x}O{sub 2} was synthesized by solid-state reaction procedure using lithium nitrate, nickel hydroxide and cobalt oxalate precursor. LiNi{sub x}Co{sub 1-x}O{sub 2} showed smaller dissolution of nickel than state of art nickel oxide cathode. The performance was comparable to that of nickel oxide. The corrosion of the current collector in the cathode side was also studied. The corrosion characteristics of both SS304 and SS304 coated with Co-Ni alloy were studied. This study confirms that surface modification of SS304 leads to the formation of complex scales with better barrier properties and better electronic conductivity at 650 C. A three

  9. Legal aspects of nuclear fuel supply

    International Nuclear Information System (INIS)

    Sartorelli, C.

    1981-10-01

    This paper discusses the problems of nuclear fuel supply in the context of the types of purchase of uranium, the different technical operations involved (enrichment, reprocessing) and finally, the control exercised over such materials in the framework of IAEA Safeguards and the ''London Club'' agreement between the supplying countries. A description follows of the functions of the Euratom Supply Agency in application of the Euratom's Treaty's provisions on the principle of equal access to ores, source and special fissile materials for Community countries. (NEA) [fr

  10. International co-operation in the supply of nuclear fuel and fuel cycle services

    International Nuclear Information System (INIS)

    Sievering, N.F. Jr.

    1977-01-01

    Recent changes in the United States' nuclear policy, in recognition of the increased proliferation risk, have raised questions of US intentions in international nuclear fuel and fuel-cycle service co-operation. This paper details those intentions in relation to the key elements of the new policy. In the past, the USA has been a world leader in peaceful nuclear co-operation with other nations and, mindful of the relationships between civilian nuclear technology and nuclear weapon proliferation, remains strongly committed to the Non-Proliferation Treaty, IAEA safeguards and other elements concerned with international nuclear affairs. Now, in implementing President Carter's nuclear initiatives, the USA will continue its leading role in nuclear fuel and fuel-cycle co-operation in two ways, (1) by increasing its enrichment capacity for providing international LWR fuel supplies and (2) by taking the lead in solving the problems of near and long-term spent fuel storage and disposal. Beyond these specific steps, the USA feels that the international community's past efforts in controlling the proliferation risks of nuclear power are necessary but inadequate for the future. Accordingly, the USA urges other similarly concerned nations to pause with present developments and to join in a programme of international co-operation and participation in a re-assessment of future plans which would include: (1) Mutual assessments of fuel cycles alternative to the current uranium/plutonium cycle for LWRs and breeders, seeking to lessen proliferation risks; (2) co-operative mechanisms for ensuring the ''front-end'' fuel supply including uranium resource exploration, adequate enrichment capacity, and institutional arrangements; (3) means of dealing with short-, medium- and long-term spent fuel storage needs by means of technical co-operation and assistance and possibly establishment of international storage or repository facilities; and (4) for reprocessing plants, and related fuel

  11. Introduction: Long term prediction

    International Nuclear Information System (INIS)

    Beranger, G.

    2003-01-01

    Making a decision upon the right choice of a material appropriate to a given application should be based on taking into account several parameters as follows: cost, standards, regulations, safety, recycling, chemical properties, supplying, transformation, forming, assembly, mechanical and physical properties as well as the behaviour in practical conditions. Data taken from a private communication (J.H.Davidson) are reproduced presenting the life time range of materials from a couple of minutes to half a million hours corresponding to applications from missile technology up to high-temperature nuclear reactors or steam turbines. In the case of deep storage of nuclear waste the time required is completely different from these values since we have to ensure the integrity of the storage system for several thousand years. The vitrified nuclear wastes should be stored in metallic canisters made of iron and carbon steels, stainless steels, copper and copper alloys, nickel alloys or titanium alloys. Some of these materials are passivating metals, i.e. they develop a thin protective film, 2 or 3 nm thick - the so-called passive films. These films prevent general corrosion of the metal in a large range of chemical condition of the environment. In some specific condition, localized corrosion such as the phenomenon of pitting, occurs. Consequently, it is absolutely necessary to determine these chemical condition and their stability in time to understand the behavior of a given material. In other words the corrosion system is constituted by the complex material/surface/medium. For high level nuclear wastes the main features for resolving problem are concerned with: geological disposal; deep storage in clay; waste metallic canister; backfill mixture (clay-gypsum) or concrete; long term behavior; data needed for modelling and for predicting; choice of appropriate solution among several metallic candidates. The analysis of the complex material/surface/medium is of great importance

  12. SKI and SSI's recommendations to the government concerning long-term responsibility after closure of a repository for spent nuclear fuel

    International Nuclear Information System (INIS)

    Paeivioe Jonsson, Josefin

    2008-01-01

    Many activities will cease at the closure of a repository, but not responsibilities. The candidate municipalities in Sweden expressed concern about who will take over after the implementer is released from responsibility for the facility. The government thus commissioned SKI (Swedish Nuclear Power Inspectorate) and SSI (Swedish Radiation Protection Authority) to review the legal obligations of institutional players as laid out today in legislation in Sweden. After closure of the repository in about 100 years there will be post-closure monitoring, possibly for a few hundred years. This will be a part of the conditions on SKB (Swedish Nuclear Fuel and Waste Management Company) which will be set out at the time. Some activities will end at the closure of the facility but monitoring and safeguards obligations may continue. The exact nature of this monitoring and safeguard work needs to be discussed and agreed upon. With the proposed approach most of the liabilities rest with the state in the long term, the waste producers only have liabilities in the short term but their decisions could have big impacts on long term liabilities

  13. Spent fuel as a waste form: Data needs to allow long term performance assessment under repository disposal conditions

    International Nuclear Information System (INIS)

    Oversby, V.M.

    1986-12-01

    Performance assessment calculations are required for high level waste repositories for a period of 10,000 years. The Siting Guidelines require a comparison of sites following site characterization and prior to final site selection to be made over a 100,000 year period. To perform the required calculations, a detailed knowledge of the physical and chemical processes that affect waste form performance will be needed for each site. This paper will review the factors that affect the release of radionuclides from spent fuel under repository conditions, summarize our present state of knowledge, and suggest areas where more work is needed to support the performance assessment calculations. 17 refs., 5 figs., 3 tabs

  14. OPTIMIZATION OF THE CATHODE LONG-TERM STABILITY IN MOLTEN CARBONATE FUEL CELLS: EXPERIMENTAL STUDY AND MATHEMATICAL MODELING

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Ralph E. White; Dr. Branko N. Popov

    2002-04-01

    The dissolution of NiO cathodes during cell operation is a limiting factor to the successful commercialization of molten carbonate fuel cells (MCFCs). Lithium cobalt oxide coating onto the porous nickel electrode has been adopted to modify the conventional MCFC cathode which is believed to increase the stability of the cathodes in the carbonate melt. The material used for surface modification should possess thermodynamic stability in the molten carbonate and also should be electro catalytically active for MCFC reactions. Two approaches have been adopted to get a stable cathode material. First approach is the use of LiNi{sub 0.8}Co{sub 0.2}O{sub 2}, a commercially available lithium battery cathode material and the second is the use of tape cast electrodes prepared from cobalt coated nickel powders. The morphology and the structure of LiNi{sub 0.8}Co{sub 0.2}O{sub 2} and tape cast Co coated nickel powder electrodes were studied using scanning electron microscopy and X-Ray diffraction studies respectively. The electrochemical performance of the two materials was investigated by electrochemical impedance spectroscopy and polarization studies. A three phase homogeneous model was developed to simulate the performance of the molten carbonate fuel cell cathode. The homogeneous model is based on volume averaging of different variables in the three phases over a small volume element. The model gives a good fit to the experimental data. The model has been used to analyze MCFC cathode performance under a wide range of operating conditions.

  15. OPTIMIZATION OF THE CATHODE LONG-TERM STABILITY IN MOLTEN CARBONATE FUEL CELLS: EXPERIMENTAL STUDY AND MATHEMATICAL MODELING

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Ralph E. White; Dr. Branko N. Popov

    2001-10-01

    The dissolution of NiO cathodes during cell operation is a limiting factor to the successful commercialization of molten carbonate fuel cells (MCFCs). Lithium cobalt oxide coating onto the porous nickel electrode has been adopted to modify the conventional MCFC cathode which is believed to increase the stability of the cathodes in the carbonate melt. The material used for surface modification should possess thermodynamic stability in the molten carbonate and also should be electro catalytically active for MCFC reactions. Lithium Cobalt oxide was coated on Ni cathode by a sol-gel coating. The morphology and the LiCoO{sub 2} formation of LiCoO{sub 2} coated NiO was studied using scanning electron microscopy and X-Ray diffraction studies respectively. The electrochemical performance lithium cobalt oxide coated NiO cathodes were investigated with open circuit potential measurement and current-potential polarization studies. These results were compared to that of bare NiO. Dissolution of nickel into the molten carbonate melt was less in case of lithium cobalt oxide coated nickel cathodes. LiCoO{sub 2} coated on the surface prevents the dissolution of Ni in the melt and thereby stabilizes the cathode. Finally, lithium cobalt oxide coated nickel shows similar polarization characteristics as nickel oxide. Conventional theoretical models for the molten carbonate fuel cell cathode are based on the thin film agglomerate model. The principal deficiency of the agglomerate model, apart from the simplified pore structure assumed, is the lack of measured values for film thickness and agglomerate radius. Both these parameters cannot be estimated appropriately. Attempts to estimate the thickness of the film vary by two orders of magnitude. To avoid these problems a new three phase homogeneous model has been developed using the volume averaging technique. The model considers the potential and current variation in both liquid and solid phases. Using this approach, volume averaged

  16. A case study of the long-term retention of 137Cs after inhalation of high temperature reactor fuel element ash.

    Science.gov (United States)

    Froning, M; Kozielewski, T; Schläger, M; Hill, P

    2004-01-01

    In 1987, a worker was internally contaminated with 137Cs as a result of an accident during the handling of high temperature reactor fuel element ash. In the long-term follow-up monitoring an unusual retention behaviour was found. The observed time dependence of caesium retention does not agree with the standard models of ICRP Publication 30. The present case can be better explained by assuming an intake of a mixture of type F and type S compounds. However, experimental data can be best described by a four-exponential retention function with two long-lived components, which was used as an ad hoc model for dose calculation. The resulting dose is compared with doses calculated on the basis of ICRP Publication 66.

  17. 14 CFR 27.959 - Unusable fuel supply.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Unusable fuel supply. 27.959 Section 27.959... STANDARDS: NORMAL CATEGORY ROTORCRAFT Powerplant Fuel System § 27.959 Unusable fuel supply. The unusable fuel supply for each tank must be established as not less than the quantity at which the first evidence...

  18. 14 CFR 29.959 - Unusable fuel supply.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Unusable fuel supply. 29.959 Section 29.959... STANDARDS: TRANSPORT CATEGORY ROTORCRAFT Powerplant Fuel System § 29.959 Unusable fuel supply. The unusable fuel supply for each tank must be established as not less than the quantity at which the first evidence...

  19. Assessing the potential long-term increase of oceanic fossil fuel CO2 uptake due to CO2-calcification feedback

    Directory of Open Access Journals (Sweden)

    T. M. Lenton

    2007-07-01

    Full Text Available Plankton manipulation experiments exhibit a wide range of sensitivities of biogenic calcification to simulated anthropogenic acidification of the ocean, with the "lab rat" of planktic calcifiers, Emiliania huxleyi apparently not representative of calcification generally. We assess the implications of this observational uncertainty by creating an ensemble of realizations of an Earth system model that encapsulates a comparable range of uncertainty in calcification response to ocean acidification. We predict that a substantial reduction in marine carbonate production is possible in the future, with enhanced ocean CO2 sequestration across the model ensemble driving a 4–13% reduction in the year 3000 atmospheric fossil fuel CO2 burden. Concurrent changes in ocean circulation and surface temperatures in the model contribute about one third to the increase in CO2 uptake. We find that uncertainty in the predicted strength of CO2-calcification feedback seems to be dominated by the assumption as to which species of calcifier contribute most to carbonate production in the open ocean.

  20. Comparing the short and long term stability of biodegradable, ceramic and cation exchange membranes in microbial fuel cells.

    Science.gov (United States)

    Winfield, Jonathan; Chambers, Lily D; Rossiter, Jonathan; Ieropoulos, Ioannis

    2013-11-01

    The long and short-term stability of two porous dependent ion exchange materials; starch-based compostable bags (BioBag) and ceramic, were compared to commercially available cation exchange membrane (CEM) in microbial fuel cells. Using bi-directional polarisation methods, CEM exhibited power overshoot during the forward sweep followed by significant power decline over the reverse sweep (38%). The porous membranes displayed no power overshoot with comparably smaller drops in power during the reverse sweep (ceramic 8%, BioBag 5.5%). The total internal resistance at maximum power increased by 64% for CEM compared to 4% (ceramic) and 6% (BioBag). Under fixed external resistive loads, CEM exhibited steeper pH reductions than the porous membranes. Despite its limited lifetime, the BioBag proved an efficient material for a stable microbial environment until failing after 8 months, due to natural degradation. These findings highlight porous separators as ideal candidates for advancing MFC technology in terms of cost and operation stability. Copyright © 2013 Elsevier Ltd. All rights reserved.

  1. ARBRE monitoring - the fuel supply chain

    Energy Technology Data Exchange (ETDEWEB)

    Hilton, B.; Garstang, J.; Groves, S.; King, J.; Metcalfe, P.; Pepper, T.; McCrae, I.

    2005-07-01

    In this report the results of a study monitoring the fuel supply chain for the Arbre power plant from the growth of the crops is discussed as well as the handling, transport, and storage of the fuel, and monitoring the exhaust emissions and energy consumption of all the different stages of the process. The background to the study is traced and the objective of establishing confidence in the fuel supply is discussed. Details are given of the emissions to atmosphere from vehicles and machinery and of spores and dust. Energy and carbon requirements are examined along with the modelled water use of short rotation cultivation (SRC), water quality monitoring, the quality of runoff from wood stores, and soil carbon and fertility change. The performance of the SRC plantations is outlined and the practical lessons learnt are highlighted.

  2. ARBRE monitoring - the fuel supply chain

    International Nuclear Information System (INIS)

    Hilton, B.; Garstang, J.; Groves, S.; King, J.; Metcalfe, P.; Pepper, T.; McCrae, I.

    2005-01-01

    In this report the results of a study monitoring the fuel supply chain for the Arbre power plant from the growth of the crops is discussed as well as the handling, transport, and storage of the fuel, and monitoring the exhaust emissions and energy consumption of all the different stages of the process. The background to the study is traced and the objective of establishing confidence in the fuel supply is discussed. Details are given of the emissions to atmosphere from vehicles and machinery and of spores and dust. Energy and carbon requirements are examined along with the modelled water use of short rotation cultivation (SRC), water quality monitoring, the quality of runoff from wood stores, and soil carbon and fertility change. The performance of the SRC plantations is outlined and the practical lessons learnt are highlighted

  3. Japan's Long-term Energy Demand and Supply Scenario to 2050 - Estimation for the Potential of Massive CO2 Mitigation

    Energy Technology Data Exchange (ETDEWEB)

    Komiyama, Ryoichi; Marnay, Chris; Stadler, Michael; Lai, Judy; Borgeson, Sam; Coffey, Brian; Azevedo, Ines Lima

    2009-09-01

    In this analysis, the authors projected Japan's energy demand/supply and energy-related CO{sub 2} emissions to 2050. Their analysis of various scenarios indicated that Japan's CO{sub 2} emissions in 2050 could be potentially reduced by 26-58% from the current level (FY 2005). These results suggest that Japan could set a CO{sub 2} emission reduction target for 2050 at between 30% and 60%. In order to reduce CO{sub 2} emissions by 60% in 2050 from the present level, Japan will have to strongly promote energy conservation at the same pace as an annual rate of 1.9% after the oil crises (to cut primary energy demand per GDP (TPES/GDP) in 2050 by 60% from 2005) and expand the share of non-fossil energy sources in total primary energy supply in 2050 to 50% (to reduce CO{sub 2} emissions per primary energy demand (CO{sub 2}/TPES) in 2050 by 40% from 2005). Concerning power generation mix in 2050, nuclear power will account for 60%, solar and other renewable energy sources for 20%, hydro power for 10% and fossil-fired generation for 10%, indicating substantial shift away from fossil fuel in electric power supply. Among the mitigation measures in the case of reducing CO{sub 2} emissions by 60% in 2050, energy conservation will make the greatest contribution to the emission reduction, being followed by solar power, nuclear power and other renewable energy sources. In order to realize this massive CO{sub 2} abatement, however, Japan will have to overcome technological and economic challenges including the large-scale deployment of nuclear power and renewable technologies.

  4. Comparing long term energy scenarios

    International Nuclear Information System (INIS)

    Cumo, M.; Simbolotti, G.

    2001-01-01

    Major projection studies by international organizations and senior analysts have been compared with reference to individual key parameters (population, energy demand/supply, resources, technology, emissions and global warming) to understand trends and implications of the different scenarios. Then, looking at the long term (i.e., 2050 and beyond), parameters and trends have been compared together to understand and quantify whether and when possible crisis or market turbulence might occur due to shortage of resources or environmental problems [it

  5. Loads imposed on dual purpose casks in German on-site-storage facilities for long term intermediate storage of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Wetzel, N.; Rabe, O. [TUeV NORD EnSys Hannover GmbH und Co. KG, Hanover (Germany)

    2004-07-01

    In accordance with recent changes of the atomic energy act and in order to secure reliable removal of spent fuel from the nuclear power plants' fuel storage ponds the German utilities filed license applications for a total of 12 onsite- storage facilities for spent fuel assemblies. By the end of 2003 the last of these storage facilities were licensed and are currently under construction. The first on-site-storage facility of that line became operational in late 2002. There are several design lines of storage facilities with different handling procedures or possible accident conditions. Short term interim storage facilities for a few casks are characterized by individual concrete hoods shielding the casks in horizontal position whereas long term intermediate storage facilities currently erected for large numbers of casks typically feature a condensed pattern of casks stored in upright position and massive structures of reinforced concrete. TUeV Hannover/Sachsen-Anhalt e. V. (now TUeV NORD EnSys Hannover GmbH and Co. KG) has been contracted as a body of independent experts for the assessment of all related safety requirements on behalf of the national licensing authority, the federal office for radiation protection (BfS).

  6. Loads imposed on dual purpose casks in German on-site-storage facilities for long term intermediate storage of spent nuclear fuel

    International Nuclear Information System (INIS)

    Wetzel, N.; Rabe, O.

    2004-01-01

    In accordance with recent changes of the atomic energy act and in order to secure reliable removal of spent fuel from the nuclear power plants' fuel storage ponds the German utilities filed license applications for a total of 12 onsite- storage facilities for spent fuel assemblies. By the end of 2003 the last of these storage facilities were licensed and are currently under construction. The first on-site-storage facility of that line became operational in late 2002. There are several design lines of storage facilities with different handling procedures or possible accident conditions. Short term interim storage facilities for a few casks are characterized by individual concrete hoods shielding the casks in horizontal position whereas long term intermediate storage facilities currently erected for large numbers of casks typically feature a condensed pattern of casks stored in upright position and massive structures of reinforced concrete. TUeV Hannover/Sachsen-Anhalt e. V. (now TUeV NORD EnSys Hannover GmbH and Co. KG) has been contracted as a body of independent experts for the assessment of all related safety requirements on behalf of the national licensing authority, the federal office for radiation protection (BfS)

  7. The Supply of Medical Radioisotopes. Policy Options for Ensuring Long-term Supply Security of Molybdenum-99 and/or Technetium-99m Produced Without Highly Enriched Uranium Targets

    International Nuclear Information System (INIS)

    Westmacott, Chad; Cameron, Ron

    2012-01-01

    Following the shortages of the key medical radioisotopes, molybdenum-99 ( 99 Mo) and its daughter technetium-99m (' 99m Tc), the OECD-Nuclear Energy Agency (NEA) created the High-level Group on the Security of Supply of Medical Radioisotopes (HLG-MR). Since 2009, this group has identified the reasons for the isotope shortages and developed a policy approach to address the challenges to a long-term secure supply of these important medical isotopes. On top of the ongoing concerns related to long-term reliability, all current long-term major 99 Mo-producing nations have agreed to convert to using low-enriched uranium (LEU) targets for the production of 99 Mo. This decision was made based on important nonproliferation reasons; however, the conversion will have potential impacts on the global supply chain - both in terms of costs and available capacity. Recognising that conversion is important and will occur, and also recognising the need to ensure a long-term secure supply of 99 Mo/' 99m Tc, the NEA, along with stakeholders, examined potential policy options that could be used by to ensure a reliable supply of 99 Mo and/or ' 99m Tc produced without highly enriched uranium (HEU), consistent with the time frames and policies of the HLG-MR. This discussion paper provides the various policy options available to governments to encourage a reliable supply of 99 Mo and/or ' 99m Tc produced without HEU. The examination of these options was done through the lens of ensuring a reliable supply, consistent with the time frames and policies of the HLG-MR. The options described in this document are meant to meet this objective by taking one of three general actions: - Making the option of purchasing or producing non-HEU-based 99 Mo and/or ' 99m Tc more attractive. - Making the option of purchasing or producing HEU-based 99 Mo and/or ' 99m Tc less attractive. - Limiting access to HEU-based 99 Mo and/or ' 99m Tc. This paper presents the options in each category and provides some views

  8. Long-term maintenance of reducing conditions in a spent nuclear fuel repository. A re-examination of critical factors

    Energy Technology Data Exchange (ETDEWEB)

    Gascoyne, M. [Gascoyne GeoProjects Inc, Pinawa, MB (Canada)

    1999-04-01

    Penetration of oxidising groundwaters to depths of 500 m in a permeable bedrock, over a glacial/interglacial cycle, may compromise the stability of a spent nuclear fuel repository and cause the release and migration towards the surface of actinides and associated fission products. This report examines the potential for the penetration of oxygen (O{sub 2}) to depths of 500 m in a fractured crystalline rock environment, typical of the Fennoscandian Shield. Previous studies performed for the Swedish program of nuclear waste disposal (principally the SITE-94 safety assessment) have indicated that O{sub 2} might reach repository depths during a deglaciation when melt-water from the base of an ice sheet could enter the bedrock, driven by strong hydraulic gradients. This report re-examines aspects of this scenario and finds that: 1. The capacity of flow-path minerals to scavenge O{sub 2} from recharging groundwater may be lower than expected due to a previously unrecognised depletion of Fe(II)-bearing minerals in the active flow-paths in a fractured crystalline rock. 2. Assumptions in the SITE-94 assessment, such as the use of a continental-scale flow model, the lack of structural controls on groundwater flow, a preferred horizontal permeability, and the use of permeabilities to depths of 10 km that are up to two orders of magnitude greater than comparable environments, are disproportionately simplistic and represent an extremely conservative case. 3. Assumptions of a thin, discontinuous permafrost, a warm-based ice sheet, and high-O{sub 2} content melt-water at the repository site are unrealistic and overly conservative. A more realistic scenario, which includes a greater influence of permafrost, a cold based ice sheet, lower bedrock permeabilities and a more-limited, regional-scale flow path, is recommended as being more appropriate for use in the safety assessment. Under this revised scenario, it is believed that O{sub 2} will not penetrate to repository depths over

  9. Long-term maintenance of reducing conditions in a spent nuclear fuel repository. A re-examination of critical factors

    International Nuclear Information System (INIS)

    Gascoyne, M.

    1999-04-01

    Penetration of oxidising groundwaters to depths of 500 m in a permeable bedrock, over a glacial/interglacial cycle, may compromise the stability of a spent nuclear fuel repository and cause the release and migration towards the surface of actinides and associated fission products. This report examines the potential for the penetration of oxygen (O 2 ) to depths of 500 m in a fractured crystalline rock environment, typical of the Fennoscandian Shield. Previous studies performed for the Swedish program of nuclear waste disposal (principally the SITE-94 safety assessment) have indicated that O 2 might reach repository depths during a deglaciation when melt-water from the base of an ice sheet could enter the bedrock, driven by strong hydraulic gradients. This report re-examines aspects of this scenario and finds that: 1. The capacity of flow-path minerals to scavenge O 2 from recharging groundwater may be lower than expected due to a previously unrecognised depletion of Fe(II)-bearing minerals in the active flow-paths in a fractured crystalline rock. 2. Assumptions in the SITE-94 assessment, such as the use of a continental-scale flow model, the lack of structural controls on groundwater flow, a preferred horizontal permeability, and the use of permeabilities to depths of 10 km that are up to two orders of magnitude greater than comparable environments, are disproportionately simplistic and represent an extremely conservative case. 3. Assumptions of a thin, discontinuous permafrost, a warm-based ice sheet, and high-O 2 content melt-water at the repository site are unrealistic and overly conservative. A more realistic scenario, which includes a greater influence of permafrost, a cold based ice sheet, lower bedrock permeabilities and a more-limited, regional-scale flow path, is recommended as being more appropriate for use in the safety assessment. Under this revised scenario, it is believed that O 2 will not penetrate to repository depths over the next 100,000 years

  10. Characterization and supply of coal based fuels

    Energy Technology Data Exchange (ETDEWEB)

    1992-06-01

    Studies and data applicable for fuel markets and coal resource assessments were reviewed and evaluated to provide both guidelines and specifications for premium quality coal-based fuels. The fuels supplied under this contract were provided for testing of advanced combustors being developed under Pittsburgh Energy Technology Center (PETC) sponsorship for use in the residential, commercial and light industrial (RCLI) market sectors. The requirements of the combustor development contractors were surveyed and periodically updated to satisfy the evolving needs based on design and test experience. Available coals were screened and candidate coals were selected for further detailed characterization and preparation for delivery. A team of participants was assembled to provide fuels in both coal-water fuel (CWF) and dry ultrafine coal (DUC) forms. Information about major US coal fields was correlated with market needs analysis. Coal fields with major reserves of low sulfur coal that could be potentially amenable to premium coal-based fuels specifications were identified. The fuels requirements were focused in terms of market, equipment and resource constraints. With this basis, the coals selected for developmental testing satisfy the most stringent fuel requirements and utilize available current deep-cleaning capabilities.

  11. Worldwide supply of Framatome ANP Fuel

    International Nuclear Information System (INIS)

    Jouan, J.

    2002-01-01

    Framatome-ANP is organized according to a matrix structure with 4 business groups and 3 regional divisions. The fuel business group with a workforce of about 4600 people is active in all the trades needed to design and manufacture nuclear fuel. The activity ranges from the production of zirconium alloys to the production of finished fuel assemblies, facilities are located in France, Germany and Usa. Framatome-ANP is the foremost vendor of LWR fuel worldwide with 41 % of the PWR market share and 22 % of the BWR market share. The global operating experience built up is based on more than 150.000 fuel assemblies delivered to 169 reactors in 18 countries. This long history has allowed Framatome-ANP to develop an efficient quality-improvement program based on experience feedback, for instance fuel rod failures induced by debris have been almost completely eliminated with the introduction of anti-debris devices equipping bottom nozzles. Framatome-ANP has developed a large range of engineering services, for instance core design teams can provide the most cost-effective fuel management schemes for cycle lengths from 6 to 24 months. The first technology transfer between China entities and Framatome related to the AFA-2G technology started in 1991 and was completed successfully in 1994. Since this date the Chinese manufacturer has supplied fuel reload for the units of Daya-Bay. (A.C.)

  12. Fuel Supply Defaults for Regional Fuels and Fuel Wizard Tool in MOVES201X

    Science.gov (United States)

    The fuel supply report documents the data and methodology used to derive the default gasoline, diesel and fuel-blend fuel properties, and their respective fuel market share in MOVES. The default market share of the individual fuels varies by calendar year, seasons, and several do...

  13. Nuclear Fuel Supply Arrangements through the IAEA

    International Nuclear Information System (INIS)

    Phuong, Ha-Vinh

    1981-10-01

    By virtue of its statutory functions, the International Atomic Energy Agency may be the depositary and also the supplier of nuclear materials made available to it by Member States, and these may then be stored in facilities it has acquired or which it has established under its control. However, this possibility did not materialize, mainly because the supplying states -few in number- do not want an international organization to become directly involved in bilateral transactions in that field. This paper analyses in particular the provisions of supply agreements concluded with the United Kingdom, the USA and the USSR. The Annex contains a Table of Agreements on supply of nuclear fuel and equipment concluded between supplying and consumer states through the IAEA. (NEA) [fr

  14. The uranium industry: long term planning for short term competition

    International Nuclear Information System (INIS)

    Vottero, X.

    2000-01-01

    Today, uranium producers face new challenges in terms of both production (new regulatory, environmental and social constraints) and market conditions (new sources of uranium supply, very low prices and tough competition). In such a context, long-term planning is not just a prerequisite to survive in the nuclear fuel cycle industry. In fact, it also contributes to sustaining nuclear electricity generation facing fierce competition from other energy sources in increasingly deregulated markets. (authors)

  15. OPTIMIZATION OF THE CATHODE LONG TERM STABILITY IN MOLTEN CARBONATE FUEL CELLS: EXPERIMENTAL STUDY AND MATHEMATICAL MODELING

    Energy Technology Data Exchange (ETDEWEB)

    Anand Durairajan; Bala Haran; Branko N. Popov; Ralph E. White

    2000-05-01

    The cathode materials for molten carbonate fuel cells (MCFCs) must have low dissolution rate, high structural strength and good electrical conductivity. Currently available cathodes are made of lithiated NiO which have acceptable structural strength and conductivity. However a study carried out by Orfeld et al. and Shores et al. indicated that the nickel cathodes dissolved, then precipitated and reformed as dendrites across the electrolyte matrix. This results in a decrease in cell utilization and eventually leads to shorting of the cell. The solubility of NiO was found to depend upon the acidity/basicity of the melt (basicity is directly proportional to log P{sub CO2}), carbonate composition, H{sub 2}O partial pressure and temperature. Urushibata et al. found that the dissolution of the cathode is a primary life limiting constraint of MCFCs, particularly in pressurized operation. With currently available NiO cathodes, the goal of 40,000 hours for the lifetime of MCFC appears achievable with cell operation at atmospheric pressure. However, the cell life at 10 atm and higher cell pressures is in the range between 5,000 to 10,000 hours. The overall objective of this research is to develop a superior cathode for MCFC's with improved catalytic ability, enhanced corrosion resistance with low ohmic losses, improved electronic conductivity. We also plan to understand the corrosion processes occurring at the cathode/molten carbonate interface. The following cathode materials will be subjected to detailed electrochemical, performance, structural and corrosion studies. (i) Passivated NiO alloys using chemical treatment with yttrium ion implantation and anodic yttrium molybdate treatment; (ii) Novel composite materials based on NiO and nanosized Ce, Yt, Mo; (iii) Co doped LiNiO{sub 2} LiNiO{sub 2} doped with 10 to 20% Co (LiCo{sub 0.2}NiO{sub 2}) and NiO cathodes; and (iv) CoO as a replacement for NiO. Passivation treatments will inhibit corrosion and increase the

  16. Long-term collections

    CERN Multimedia

    Collectes à long terme

    2007-01-01

    The Committee of the Long Term Collections (CLT) asks for your attention for the following message from a young Peruvian scientist, following the earthquake which devastated part of her country a month ago.

  17. Characteristics of a direct methanol fuel cell system with the time shared fuel supplying approach

    International Nuclear Information System (INIS)

    Na, Youngseung; Kwon, Jungmin; Kim, Hyun; Cho, Hyejung; Song, Inseob

    2013-01-01

    DMFC (direct methanol fuel cell) systems usually employ two pumps for supplying the methanol solution. The conventional system configuration, however, may bring about free flow from the methanol reservoir and malfunctions in the self-priming of the pumps. When instruments such as check valves and pressure regulators are applied, they result in excessive weight and control system malfunctions. In this paper, a light and robust DMFC system is proposed. By using the time sharing approach to supply fuel with a 3-way valve, free flow does not occur because only one inlet is opened at one time which means that both the circulation flow from gas liquid separator and the fuel flow from the methanol cartridge are not allowed to be opened at same time. As a result, back flow and self-priming problems do not occur. This makes the system stable and robust due to the removal of both the check valves and the fluctuation from unstable back pressure. Stabilized system doesn't need excessive battery buffering and recycling water any more, which are responsible for the heavy system. The proposed system performs the same level of power and efficiency with the conventional system. Adaptability is also carried out in various environmental temperature conditions. - Highlights: ►A light and robust DMFC system is proposed. ► The circulation pump is able to self-prime by itself after long term storage. ► The time sharing approach to supply fuel enables to control the methanol concentration precisely. ► The methanol concentration is controlled without free flow and the back flow from the fuel feeding pump. ► The excessive buffer of the batteries and the recycling water level are reduced

  18. Nuclear Energy, Long Term Requirements

    International Nuclear Information System (INIS)

    Knapp, V.

    2006-01-01

    There are serious warnings about depletion of oil and gas and even more serious warnings about dangers of climate change caused by emission of carbon dioxide. Should developed countries be called to replace CO2 emitting energy sources as soon as possible, and the time available may not be longer then few decades, can nuclear energy answer the call and what are the requirements? Assuming optimistic contribution of renewable energy sources, can nuclear energy expand to several times present level in order to replace large part of fossil fuels use? Paper considers intermediate and long-term requirements. Future of nuclear power depends on satisfactory answers on several questions. First group of questions are those important for near and intermediate future. They deal with economics and safety of nuclear power stations in the first place. On the same time scale a generally accepted concept for radioactive waste disposal is also required. All these issues are in the focus of present research and development. Safer and more economical reactors are targets of international efforts in Generation IV and INPRO projects, but aiming further ahead these innovative projects are also addressing issues such as waste reduction and proliferation resistance. However, even assuming successful technical development of these projects, and there is no reason to doubt it, long term and large-scale nuclear power use is thereby not yet secured. If nuclear power is to play an essential role in the long-term future energy production and in reduction of CO2 emission, than several additional questions must be replied. These questions will deal with long-term nuclear fuel sufficiency, with necessary contribution of nuclear power in sectors of transport and industrial processes and with nuclear proliferation safety. This last issue is more political then technical, thus sometimes neglected by nuclear engineers, yet it will have essential role for the long-term prospects of nuclear power. The

  19. Investigation of a methanol reformer concept considering the particular impact of dynamics and long-term stability for use in a fuel-cell-powered passenger car

    Science.gov (United States)

    Peters, R.; Düsterwald, H. G.; Höhlein, B.

    A methanol reformer concept including a reformer, a catalytic burner, a gas cleaning unit, a PEMFC and an electric motor for use in fuel-cell-powered passenger cars was investigated. Special emphasis was placed on the dynamics and the long-term stability of the reformer. Experiments on a laboratory scale were performed in a methanol steam reformer consisting of four different reactor tubes, which were separately balanced. Due to the endothermy of the steam reforming reaction of methanol, a sharp drop in the reaction temperature of about 50 K occurs at the beginning of the catalyst bed. This agrees well with the high catalytic activity at the entrance of the catalyst bed. Forty-five percent of the methanol was converted within the first 10 cm of the catalyst bed where 12.6 g of the CuO/ZnO catalyst was located. Furthermore, CO formation during methanol steam reforming strongly depends on methanol conversion. Long-term measurements for more than 700 h show that the active reaction zone moved through the catalyst bed. Calculations, on the basis of these experiments, revealed that 63 g of reforming catalyst was necessary for mobile PEMFC applications, in this case for 400 W el at a system efficiency of 42% and a theoretical specific hydrogen production of 5.2 m 3n/(h kg Cat). This amount of catalyst was assumed to maintain a hydrogen production of at least 80% of the original amount over an operating range of 3864 h. Cycled start-up and shut-down processes of the methanol steam reformer under nitrogen and hydrogen atmospheres did not harm the catalytic activity. The simulation of the breakdown of the heating system, in which a liquid water/methanol mixture was in close contact with the catalyst, did not reveal any deactivation of the catalytic activity.

  20. The long-term effect of hydrogen on the UO2 spent fuel stability under anoxic conditions: Findings from the Cigar Lake Natural Analogue study

    International Nuclear Information System (INIS)

    Bruno, Jordi; Spahiu, Kastriot

    2014-01-01

    Highlights: • We have reviewed current information on the effect of hydrogen in UO 2 spent fuel. • We explored the radiolytic models generated in the Cigar Lake project. • The Cigar Lake data supports that H 2 reduces alpha radiolysis oxidants. • The results indicate the hydrogen effect is present after 100.000 years deposition. - Abstract: The present paradigm on UO 2 spent fuel stability under anoxic conditions assumes that the potential oxidative alteration of the matrix is suppressed in the presence of the hydrogen generated by the anoxic corrosion of iron by water. The observations from the Cigar Lake Natural Analogue project indicated the long-term stability of the uraninite ore under anoxic conditions and with substantial hydrogen generation. The radiolytic models developed in the analogue project have been used to test some of the hypothesis concerning the activation of hydrogen on the uranium(IV) oxide surface. Suggestions to pathways of radiolytic oxidant consumption by other processes than uranium dioxide or sulphide oxidation are presented. The stability of the ore body for billions of year indicates the presence of processes which neutralise radiolytic oxidants and one major factor may be the presence of dissolved hydrogen in the groundwaters contacting the ore body. The results from this test would indicate that hydrogen is activated on the surface of the Cigar Lake uraninites by alpha radiation consuming the generated radiolytic oxidants

  1. Long-Term Dry Storage of High Burn-Up Spent Pressurized Water Reactor (PWR) Fuel in TAD (Transportation, Aging, and Disposal) Containers

    International Nuclear Information System (INIS)

    Hwang, Yong Soo

    2008-12-01

    A TAD canister, in conjunction with specially-designed over-packs can accomplish the functions of transportation, aging, and disposal (TAD) in the management of spent nuclear fuel (SNF). Industrial dry cask systems currently available for SNF are licensed for storage-only or for dual-purpose (i.e., storage and transportation). By extending the function to include the indefinite storage and perhaps, eventual geologic disposal, the TAD canister would have to be designed to enhance, among others, corrosion resistance, thermal stability, and criticality-safety control. This investigative paper introduces the use of these advanced iron-based, corrosion-resistant materials for SNF transportation, aging, and disposal.The objective of this investigative project is to explore the interest that KAERI would research and develop its specific SAM coating materials for the TAD canisters to satisfy the requirements of corrosion-resistance, thermal stability, and criticality-controls for long-term dry storage of high burn-up spent PWR fuel

  2. Advanced Nuclear Fuel Cycle Effects on the Treatment of Uncertainty in the Long-Term Assessment of Geologic Disposal Systems - EBS Input

    International Nuclear Information System (INIS)

    Sutton, M.; Blink, J.A.; Greenberg, H.R.; Sharma, M.

    2012-01-01

    The Used Fuel Disposition (UFD) Campaign within the Department of Energy's Office of Nuclear Energy (DOE-NE) Fuel Cycle Technology (FCT) program has been tasked with investigating the disposal of the nation's spent nuclear fuel (SNF) and high-level nuclear waste (HLW) for a range of potential waste forms and geologic environments. The planning, construction, and operation of a nuclear disposal facility is a long-term process that involves engineered barriers that are tailored to both the geologic environment and the waste forms being emplaced. The UFD Campaign is considering a range of fuel cycles that in turn produce a range of waste forms. The UFD Campaign is also considering a range of geologic media. These ranges could be thought of as adding uncertainty to what the disposal facility design will ultimately be; however, it may be preferable to thinking about the ranges as adding flexibility to design of a disposal facility. For example, as the overall DOE-NE program and industrial actions result in the fuel cycles that will produce waste to be disposed, and the characteristics of those wastes become clear, the disposal program retains flexibility in both the choice of geologic environment and the specific repository design. Of course, other factors also play a major role, including local and State-level acceptance of the specific site that provides the geologic environment. In contrast, the Yucca Mountain Project (YMP) repository license application (LA) is based on waste forms from an open fuel cycle (PWR and BWR assemblies from an open fuel cycle). These waste forms were about 90% of the total waste, and they were the determining waste form in developing the engineered barrier system (EBS) design for the Yucca Mountain Repository design. About 10% of the repository capacity was reserved for waste from a full recycle fuel cycle in which some actinides were extracted for weapons use, and the remaining fission products and some minor actinides were encapsulated

  3. ADVANCED NUCLEAR FUEL CYCLE EFFECTS ON THE TREATMENT OF UNCERTAINTY IN THE LONG-TERM ASSESSMENT OF GEOLOGIC DISPOSAL SYSTEMS - EBS INPUT

    Energy Technology Data Exchange (ETDEWEB)

    Sutton, M; Blink, J A; Greenberg, H R; Sharma, M

    2012-04-25

    The Used Fuel Disposition (UFD) Campaign within the Department of Energy's Office of Nuclear Energy (DOE-NE) Fuel Cycle Technology (FCT) program has been tasked with investigating the disposal of the nation's spent nuclear fuel (SNF) and high-level nuclear waste (HLW) for a range of potential waste forms and geologic environments. The planning, construction, and operation of a nuclear disposal facility is a long-term process that involves engineered barriers that are tailored to both the geologic environment and the waste forms being emplaced. The UFD Campaign is considering a range of fuel cycles that in turn produce a range of waste forms. The UFD Campaign is also considering a range of geologic media. These ranges could be thought of as adding uncertainty to what the disposal facility design will ultimately be; however, it may be preferable to thinking about the ranges as adding flexibility to design of a disposal facility. For example, as the overall DOE-NE program and industrial actions result in the fuel cycles that will produce waste to be disposed, and the characteristics of those wastes become clear, the disposal program retains flexibility in both the choice of geologic environment and the specific repository design. Of course, other factors also play a major role, including local and State-level acceptance of the specific site that provides the geologic environment. In contrast, the Yucca Mountain Project (YMP) repository license application (LA) is based on waste forms from an open fuel cycle (PWR and BWR assemblies from an open fuel cycle). These waste forms were about 90% of the total waste, and they were the determining waste form in developing the engineered barrier system (EBS) design for the Yucca Mountain Repository design. About 10% of the repository capacity was reserved for waste from a full recycle fuel cycle in which some actinides were extracted for weapons use, and the remaining fission products and some minor actinides were

  4. Alternative transport fuels: supply, consumption and conservation

    International Nuclear Information System (INIS)

    Trindade, S.C.

    1990-01-01

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

  5. Managing aging effects on dry cask storage systems for extended long-term storage and transportation of used fuel - rev. 0

    Energy Technology Data Exchange (ETDEWEB)

    Chopra, O.K.; Diercks, D.; Fabian, R.; Ma, D.; Shah, V.; Tam, S.W.; Liu, Y. (Decision and Information Sciences); ( EVS); ( NE)

    2012-07-06

    The cancellation of the Yucca Mountain repository program in the United States raises the prospect of extended long-term storage (i.e., >120 years) and deferred transportation of used fuel at operating and decommissioned nuclear power plant sites. Under U.S. federal regulations contained in Title 10 of the Code of Federal Regulations (CFR) 72.42, the initial license term for an Independent Spent Fuel Storage Installation (ISFSI) must not exceed 40 years from the date of issuance. Licenses may be renewed by the U.S. Nuclear Regulatory Commission (NRC) at the expiration of the license term upon application by the licensee for a period not to exceed 40 years. Application for ISFSI license renewals must include the following: (1) Time-limited aging analyses (TLAAs) that demonstrate that structures, systems, and components (SSCs) important to safety will continue to perform their intended function for the requested period of extended operation; and (2) a description of the aging management program (AMP) for management of issues associated with aging that could adversely affect SSCs important to safety. In addition, the application must also include design bases information as documented in the most recent updated final safety analysis report as required by 10 CFR 72.70. Information contained in previous applications, statements, or reports filed with the Commission under the license may be incorporated by reference provided that those references are clear and specific. The NRC has recently issued the Standard Review Plan (SRP) for renewal of used-fuel dry cask storage system (DCSS) licenses and Certificates of Compliance (CoCs), NUREG-1927, under which NRC may renew a specific license or a CoC for a term not to exceed 40 years. Both the license and the CoC renewal applications must contain revised technical requirements and operating conditions (fuel storage, surveillance and maintenance, and other requirements) for the ISFSI and DCSS that address aging effects that

  6. 14 CFR 23.959 - Unusable fuel supply.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Unusable fuel supply. 23.959 Section 23.959 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION AIRCRAFT AIRWORTHINESS... Unusable fuel supply. (a) The unusable fuel supply for each tank must be established as not less than that...

  7. HLW Long-term Management Technology Development

    International Nuclear Information System (INIS)

    Choi, Jong Won; Kang, C. H.; Ko, Y. K.

    2010-02-01

    Permanent disposal of spent nuclear fuels from the power generation is considered to be the unique method for the conservation of human being and nature in the present and future. In spite of spent nuclear fuels produced from power generation, based on the recent trends on the gap between supply and demand of energy, the advance on energy price and reduction of carbon dioxide, nuclear energy is expected to play a role continuously in Korea. It means that a new concept of nuclear fuel cycle is needed to solve problems on spent nuclear fuels. The concept of the advanced nuclear fuel cycle including PYRO processing and SFR was presented at the 255th meeting of the Atomic Energy Commission. According to the concept of the advanced nuclear fuel cycle, actinides and long-term fissile nuclides may go out of existence in SFR. And then it is possible to dispose of short term decay wastes without a great risk bearing. Many efforts had been made to develop the KRS for the direct disposal of spent nuclear fuels in the representative geology of Korea. But in the case of the adoption of Advanced nuclear fuel cycle, the disposal of PYRO wastes should be considered. For this, we carried out the Safety Analysis on HLW Disposal Project with 5 sub-projects such as Development of HLW Disposal System, Radwaste Disposal Safety Analysis, Feasibility study on the deep repository condition, A study on the Nuclide Migration and Retardation Using Natural Barrier, and In-situ Study on the Performance of Engineered Barriers

  8. Studies of breakeven prices and electricity supply potentials of nuclear fusion by a long-term world energy and environment model

    International Nuclear Information System (INIS)

    Tokimatsu, K.; Asaoka, Y.; Okano, K.; Yoshida, T.; Hiwatari, R.; Konishi, S.; Nishio, S.; Fujino, J.; Ogawa, Y.; Yamaji, K.

    2002-01-01

    In response to social demand, this paper investigates the breakeven price (BP) and potential electricity supply of nuclear fusion energy in the 21st century by means of a world energy and environment model. We set the following objectives in this paper: (i) to reveal the economics of the introduction conditions of nuclear fusion; (ii) to know when tokamak-type nuclear fusion reactors are expected to be introduced cost-effectively into future energy systems; (iii) to estimate the share in 2100 of electricity produced by the presently designed reactors that could be economically selected in the year. The model can give in detail the energy and environment technologies and price-induced energy saving, and can illustrate optimal energy supply structures by minimizing the costs of total discounted energy systems at a discount rate of 5%. The following parameters of nuclear fusion were considered: cost of electricity (COE) in the nuclear fusion introduction year, annual COE reduction rates, regional introduction year, and regional nuclear fusion capacity projection. The investigations are carried out for three nuclear fusion projections one of which includes tritium breeding constraints, four future CO 2 concentration constraints, and technological assumptions on fossil fuels, nuclear fission, CO 2 sequestration, and anonymous innovative technologies. It is concluded that: (1) the BPs are from 65 to 125 mill kW -1 h -1 depending on the introduction year of nuclear fusion under the 550 ppmv CO 2 concentration constraints; those of a business-as-usual (BAU) case are from 51 to 68 mill kW -1 h -1 . Uncertainties resulting from the CO 2 concentration constraints and the technological options influenced the BPs by plus/minus some 10-30 mill kW -1 h -1 , (2) tokamak-type nuclear fusion reactors (as presently designed, with a COE range around 70-130 mill kW -1 h -1 ) would be favourably introduced into energy systems after 2060 based on the economic criteria under the 450 and

  9. Studies of breakeven prices and electricity supply potentials of nuclear fusion by a long-term world energy and environment model

    Science.gov (United States)

    Tokimatsu, K.; Asaoka, Y.; Konishi, S.; Fujino, J.; Ogawa, Y.; Okano, K.; Nishio, S.; Yoshida, T.; Hiwatari, R.; Yamaji, K.

    2002-11-01

    In response to social demand, this paper investigates the breakeven price (BP) and potential electricity supply of nuclear fusion energy in the 21st century by means of a world energy and environment model. We set the following objectives in this paper: (i) to reveal the economics of the introduction conditions of nuclear fusion; (ii) to know when tokamak-type nuclear fusion reactors are expected to be introduced cost-effectively into future energy systems; (iii) to estimate the share in 2100 of electricity produced by the presently designed reactors that could be economically selected in the year. The model can give in detail the energy and environment technologies and price-induced energy saving, and can illustrate optimal energy supply structures by minimizing the costs of total discounted energy systems at a discount rate of 5%. The following parameters of nuclear fusion were considered: cost of electricity (COE) in the nuclear fusion introduction year, annual COE reduction rates, regional introduction year, and regional nuclear fusion capacity projection. The investigations are carried out for three nuclear fusion projections one of which includes tritium breeding constraints, four future CO2 concentration constraints, and technological assumptions on fossil fuels, nuclear fission, CO2 sequestration, and anonymous innovative technologies. It is concluded that: (1) the BPs are from 65 to 125 mill kW-1 h-1 depending on the introduction year of nuclear fusion under the 550 ppmv CO2 concentration constraints; those of a business-as-usual (BAU) case are from 51 to 68 mill kW-1h-1. Uncertainties resulting from the CO2 concentration constraints and the technological options influenced the BPs by plus/minus some 10 30 mill kW-1h-1, (2) tokamak-type nuclear fusion reactors (as presently designed, with a COE range around 70 130 mill kW-1h-1) would be favourably introduced into energy systems after 2060 based on the economic criteria under the 450 and 550 ppmv CO2

  10. Long-term experiences in the use of rapeseed oil fuel in tractors of the emissions levels I and II; Langzeiterfahrungen zum Einsatz von Rapsoelkraftstoff in Traktoren der Abgasstufe I und II

    Energy Technology Data Exchange (ETDEWEB)

    Emberger, Peter; Thuneke, Klaus; Remmele, Edgar

    2013-06-01

    The operational behavior as well as the emission behavior should be clarified in long-term use by means of tractors which are powered by rapeseed oil fuel. This is based on the following measures: review of the quality of rapeseed oil fuel used; testing of the quality of the engine oil on a random basis; documentation of failures, maintenance and repair work; measurement of performance and fuel economy; measurement of exhaust emissions; diagnosis of engines.

  11. 30 CFR 36.27 - Fuel-supply system.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Fuel-supply system. 36.27 Section 36.27 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR TESTING, EVALUATION, AND APPROVAL OF... Construction and Design Requirements § 36.27 Fuel-supply system. (a) Fuel tank. (1) The fuel tank shall not...

  12. Long-Term Collections

    CERN Multimedia

    Comité des collectes à long terme

    2011-01-01

    It is the time of the year when our fireman colleagues go around the laboratory for their traditional calendars sale. A part of the money of the sales will be donated in favour of the long-term collections. We hope that you will welcome them warmly.

  13. Burn-up credit criticality safety benchmark phase VII - UO2 fuel: study of spent fuel compositions for long-term disposal

    International Nuclear Information System (INIS)

    2012-01-01

    After spent nuclear fuel (SNF) is discharged from a nuclear reactor, fuel composition and reactivity continue to vary as a function of time due to the decay of unstable nuclides. Accurate predictions of the concentrations of long-lived radionuclides in SNF, which represent a significant potential hazard to human beings and to the environment over a very long period, are particularly necessary for radiological dose assessments. This report assesses the ability of existing computer codes and associated nuclear data to predict isotopic compositions and their corresponding neutron multiplication factor (k eff ) values for pressurised-water-reactor (PWR) UO 2 fuel at 50 GWd/MTU burn-up in a generic spent fuel cask configuration. Fuel decay compositions and k eff values have been calculated for 30 post-irradiation time steps out to one million years

  14. Supply chain modeling of forest fuel

    Energy Technology Data Exchange (ETDEWEB)

    Gunnarsson, Helene; Lundgren, Jan T.; Roennqvist, Mikael

    2001-04-01

    We study the problem of deciding when and where forest residues are to be converted into forest fuel, and how the residues are to be transported and stored in order to satisfy demand at heating plants. Decisions also include whether or not additional harvest areas and saw-mills are to be contracted. In addition, we consider the flow of products from saw-mills and import harbors, and address the question about which terminals to use. The planning horizon is one year and monthly time periods are considered. The supply chain problem is formulated as a large mixed integer linear programming model. In order to obtain solutions within reasonable time we have developed a heuristic solution approach. Computational results from a large Swedish supplying entrepreneur are reported.

  15. Supply chain modeling of forest fuel

    International Nuclear Information System (INIS)

    Gunnarsson, Helene; Lundgren, Jan T.; Roennqvist, Mikael

    2001-04-01

    We study the problem of deciding when and where forest residues are to be converted into forest fuel, and how the residues are to be transported and stored in order to satisfy demand at heating plants. Decisions also include whether or not additional harvest areas and saw-mills are to be contracted. In addition, we consider the flow of products from saw-mills and import harbors, and address the question about which terminals to use. The planning horizon is one year and monthly time periods are considered. The supply chain problem is formulated as a large mixed integer linear programming model. In order to obtain solutions within reasonable time we have developed a heuristic solution approach. Computational results from a large Swedish supplying entrepreneur are reported

  16. Identification and understanding the factors affecting the public and political acceptance of long term storage of spent fuel and high-level radioactive wastes

    International Nuclear Information System (INIS)

    Gorea, Valica

    2006-01-01

    In the end of 2004, according to the information available to the IAEA, there were 440 nuclear reactors operating worldwide, with a total net capacity of 366.3 GW(e), 6 of them being connected to the grid in 2004 ( 2 in Ukraine, one each in China, Japan and the Russian Federation and a reconnection in Canada) by comparison with 2 connections and 2 re-connections in 2003. Also, in the end of 2004, 26 nuclear power plants were under construction with a total net capacity of 20.8 GW(e). The conclusion accepted by common consent is that the nuclear power is still in progress and represents one of the options for power security on long and middle term. If we refer to the nuclear fusion which will produce commercial electric power, over 30 - 40 years, in practically unlimited quantities, the above underlining becomes even more evident. Fortunately, besides the beneficent characteristics, such as: clean, stable as engendering and price, has also a negative characteristic, which generally breathes fear into the people: radioactive waste. A classification of the radioactive waste is not the target of this presentation. I just want to point that a nuclear power plant produces during the time spent fuel - long life high radioactive, generating heat. Another high radioactive waste have similar characteristics (HLW = High Level Waste) for which reason these two categories of wastes are treated together. The spent fuel and the High Level Waste are interim stored for cooling, for around 50 years, afterwards it is transferred to the final repository where it will be kept for hundreds of years, in the case of an open fuel cycle and this is also the case of Cernavoda NPP. Taking into consideration that the Cernavoda Unit 1 reaches the age of 10 years of commercial running during December 2006, it results that the issue of the final disposal is not such urgent as it looks. The objectives of long term management of radioactive waste are public health and protection of the environment

  17. 14 CFR 25.959 - Unusable fuel supply.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Unusable fuel supply. 25.959 Section 25.959 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION AIRCRAFT AIRWORTHINESS STANDARDS: TRANSPORT CATEGORY AIRPLANES Powerplant Fuel System § 25.959 Unusable fuel supply. The unusable...

  18. 10 CFR 503.21 - Lack of alternate fuel supply.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 4 2010-01-01 2010-01-01 false Lack of alternate fuel supply. 503.21 Section 503.21 Energy DEPARTMENT OF ENERGY (CONTINUED) ALTERNATE FUELS NEW FACILITIES Temporary Exemptions for New Facilities § 503.21 Lack of alternate fuel supply. (a) Eligibility. Section 211(a)(1) of the Act provides for...

  19. Long-term trends in supply and sustainability of the health workforce in remote Aboriginal communities in the Northern Territory of Australia.

    Science.gov (United States)

    Zhao, Yuejen; Russell, Deborah J; Guthridge, Steven; Ramjan, Mark; Jones, Michael P; Humphreys, John S; Carey, Timothy A; Wakerman, John

    2017-12-19

    International evidence suggests that a key to improving health and attaining more equitable health outcomes for disadvantaged populations is a health system with a strong primary care sector. Longstanding problems with health workforce supply and turnover in remote Aboriginal communities in the Northern Territory (NT), Australia, jeopardise primary care delivery and the effort to overcome the substantial gaps in health outcomes for this population. This research describes temporal changes in workforce supply in government-operated clinics in remote NT communities through a period in which there has been a substantial increase in health funding. Descriptive and Markov-switching dynamic regression analysis of NT Government Department of Health payroll and financial data for the resident health workforce in 54 remote clinics, 2004-2015. The workforce included registered Remote Area Nurses and Midwives (nurses), Aboriginal Health Practitioners (AHPs) and staff in administrative and logistic roles. total number of unique employees per year; average annual headcounts; average full-time equivalent (FTE) positions; agency employed nurse FTE estimates; high and low supply state estimates. Overall increases in workforce supply occurred between 2004 and 2015, especially for administrative and logistic positions. Supply of nurses and AHPs increased from an average 2.6 to 3.2 FTE per clinic, although supply of AHPs has declined since 2010. Each year almost twice as many individual NT government-employed nurses or AHPs are required for each FTE position. Following funding increases, some clinics doubled their nursing and AHP workforce and achieved relative stability in supply. However, most clinics increased staffing to a much smaller extent or not at all, typically experiencing a "fading" of supply following an initial increase associated with greater funding, and frequently cycling periods of higher and lower staffing levels. Overall increases in workforce supply in remote NT

  20. Money demand elasticity, effective money supply and money market disequilibrium: ¡°China¡¯s Puzzle¡± and long-term excessive liquidity

    OpenAIRE

    LI Zhiguo

    2008-01-01

    Chinese excessive liquidity problems are more serious than other main countries. The upgrading industrial structure and the increasing opening degree lead to the excessive money demand and higher money demand elasticity. Bad credits weaken money supply effectiveness and lead to illusive increasing money. We set up the money market disequilibrium model under the condition of the excessive liquidity. The imbalance between money demand and money supply is the key of Chinese excessive liquidity p...

  1. Assessment of the long-term risks of inadvertent human intrusion into a proposed Canadian nuclear fuel waste disposal vault in deep plutonic rock -revision 1

    International Nuclear Information System (INIS)

    Wuschke, D.M.

    1996-04-01

    Canada has conducted an extensive research program on a concept of safe disposal of nuclear fuel wastes deep In plutonic rock of the Canadian Shield. An essential goal of this program has been to develop and demonstrate a methodology to evaluate the performance of the facility against safety criteria established by Canada's regulatory agency, the Atomic Energy Control Board. These criteria are expressed in terms of risk, where risk is defined as the sum, over all significant scenarios, of the product of the probability of the scenario, the magnitude of the resultant dose, and the probability of a health effect per unit dose. This report describes the methodology developed to assess the long-term risk from inadvertent human intrusion into such a facility, and the results of its application to the proposed facility. Four intrusion scenarios were analysed, all initiated by a drilling operation. These scenarios are exposure of a member of the drilling crew, of a technologist conducting a core examination, of a construction worker and of a resident. The consequence of each scenario was estimated using standard computer codes for environmental pathways analysis and radiation dosimetry. For comparison with the risk criterion, an estimate of the probability of each scenario is also required. An event-tree methodology was used to estimate these probabilities. The estimated risks from these intrusion scenarios are several orders of magnitude below the established risk criterion. The event-tree methodology has the advantages of explicity displaying the assumptions made, of permitting easy testing of the sensitivity of the risk estimates to assumptions, and of combining technical and sociological information. (author). 53 refs., 8 tabs., 2 figs

  2. Assessment of the long-term risks of inadvertent human intrusion into a proposed Canadian nuclear fuel waste disposal vault in deep plutonic rock -revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Wuschke, D M

    1996-04-01

    Canada has conducted an extensive research program on a concept of safe disposal of nuclear fuel wastes deep In plutonic rock of the Canadian Shield. An essential goal of this program has been to develop and demonstrate a methodology to evaluate the performance of the facility against safety criteria established by Canada`s regulatory agency, the Atomic Energy Control Board. These criteria are expressed in terms of risk, where risk is defined as the sum, over all significant scenarios, of the product of the probability of the scenario, the magnitude of the resultant dose, and the probability of a health effect per unit dose. This report describes the methodology developed to assess the long-term risk from inadvertent human intrusion into such a facility, and the results of its application to the proposed facility. Four intrusion scenarios were analysed, all initiated by a drilling operation. These scenarios are exposure of a member of the drilling crew, of a technologist conducting a core examination, of a construction worker and of a resident. The consequence of each scenario was estimated using standard computer codes for environmental pathways analysis and radiation dosimetry. For comparison with the risk criterion, an estimate of the probability of each scenario is also required. An event-tree methodology was used to estimate these probabilities. The estimated risks from these intrusion scenarios are several orders of magnitude below the established risk criterion. The event-tree methodology has the advantages of explicity displaying the assumptions made, of permitting easy testing of the sensitivity of the risk estimates to assumptions, and of combining technical and sociological information. (author). 53 refs., 8 tabs., 2 figs.

  3. Multiple fuel supply system for an internal combustion engine

    Science.gov (United States)

    Crothers, William T.

    1977-01-01

    A multiple fuel supply or an internal combustion engine wherein phase separation of components is deliberately induced. The resulting separation permits the use of a single fuel tank to supply components of either or both phases to the engine. Specifically, phase separation of a gasoline/methanol blend is induced by the addition of a minor amount of water sufficient to guarantee separation into an upper gasoline phase and a lower methanol/water phase. A single fuel tank holds the two-phase liquid with separate fuel pickups and separate level indicators for each phase. Either gasoline or methanol, or both, can be supplied to the engine as required by predetermined parameters. A fuel supply system for a phase-separated multiple fuel supply contained in a single fuel tank is described.

  4. Long-Term Collections

    CERN Multimedia

    Staff Association

    2016-01-01

    45 years helping in developing countries! CERN personnel have been helping the least fortunate people on the planet since 1971. How? With the Long-Term Collections! Dear Colleagues, The Staff Association’s Long-Term Collections (LTC) Committee is delighted to share this important milestone in the life of our Laboratory with you. Indeed, whilst the name of CERN is known worldwide for scientific discoveries, it also shines in the many humanitarian projects which have been supported by the LTC since 1971. Several schools and clinics, far and wide, carry its logo... Over the past 45 years, 74 projects have been supported (9 of which are still ongoing). This all came from a group of colleagues who wanted to share a little of what life offered them here at CERN, in this haven of mutual understanding, peace and security, with those who were less fortunate elsewhere. Thus, the LTC were born... Since then, we have worked as a team to maintain the dream of these visionaries, with the help of regular donat...

  5. Long-Term Collection

    CERN Multimedia

    Staff Association

    2016-01-01

    Dear Colleagues, As previously announced in Echo (No. 254), your delegates took action to draw attention to the projects of the Long-Term Collections (LTC), the humanitarian body of the CERN Staff Association. On Tuesday, 11 October, at noon, small Z-Cards were widely distributed at the entrances of CERN restaurants and we thank you all for your interest. We hope to have achieved an important part of our goal, which was to inform you, convince you and find new supporters among you. We will find out in the next few days! An exhibition of the LTC was also set up in the Main Building for the entire week. The Staff Association wants to celebrate the occasion of the Long-Term Collection’s 45th anniversary at CERN because, ever since 1971, CERN personnel have showed great support in helping the least fortunate people on the planet in a variety of ways according to their needs. On a regular basis, joint fundraising appeals are made with the Directorate to help the victims of natural disasters around th...

  6. Collectes à long terme

    CERN Multimedia

    Collectes à long terme

    2014-01-01

    En cette fin d’année 2014 qui approche à grands pas, le Comité des Collectes à Long Terme remercie chaleureusement ses fidèles donatrices et donateurs réguliers pour leurs contributions à nos actions en faveur des plus démunis de notre planète. C’est très important, pour notre Comité, de pouvoir compter sur l’appui assidu que vous nous apportez. Depuis plus de 40 ans maintenant, le modèle des CLT est basé principalement sur des actions à long terme (soit une aide pendant 4-5 ans par projet, mais plus parfois selon les circonstances), et sa planification demande une grande régularité de ses soutiens financiers. Grand MERCI à vous ! D’autres dons nous parviennent au cours de l’année, et ils sont aussi les bienvenus. En particulier, nous tenons à remercier...

  7. Accounting for Unliquidated Obligations for the Defense Fuel Supply Center

    National Research Council Canada - National Science Library

    1996-01-01

    .... The Defense Finance and Accounting Service (DFAS) Columbus Center, Columbus, Ohio, and the Defense Fuel Supply Center share responsibility for accurate accounting information and financial reporting...

  8. INTERACTION OF AIR TRANSPORTATION AND FUEL-SUPPLY COMPANIES

    Directory of Open Access Journals (Sweden)

    I. P. Zheleznaya

    2014-01-01

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

  9. The current and perspective problems of nuclear power fuel supply

    International Nuclear Information System (INIS)

    Solonin, M.I.; Konovalov, I.I.

    2003-01-01

    Conception of fuel supply is comprised of supplying of natural uranium resources, nuclear fuel production including engineering stages of refining, enriching, production, use of secondary uranium and plutonium raw materials. The structure of nuclear fuel cycle is considered. Enterprises of the Russian nuclear fuel cycle, world recourses and fundamental producers of uranium are performed, demands in natural uranium of Russian and frontier NPP to 2010 are demonstrated. Dynamics of the development of separate methods - diffusion and centrifugal is presented as well as parameters of fuel supply at Russian and frontier NPP are compared [ru

  10. Methanol supply issues for alternative fuels demonstration programs

    International Nuclear Information System (INIS)

    Teague, J.M.; Koyama, K.K.

    1995-01-01

    This paper surveys issues affecting the supply of fuel-grade methanol for the California Energy Commission's alternative fuels demonstration programs and operations by other public agencies such as transit and school districts. Establishing stable and reasonably priced sources of methanol (in particular) and of alternative fuels generally is essential to their demonstration and commercialization. Development both of vehicle technologies and of fuel supply and distribution are complementary and must proceed in parallel. However, the sequence of scaling up supply and distribution is not necessarily smooth; achievement of volume thresholds in demand and through-put of alternative fuels are marked by different kinds of challenges. Four basic conditions should be met in establishing a fuel supply: (1) it must be price competitive with petroleum-based fuels, at least when accounting for environmental and performance benefits; (2) bulk supply must meet volumes required at each phase; necessitating resilience among suppliers and a means of designating priority for high value users; (3) distribution systems must be reliable, comporting with end users' operational schedules; (4) volatility in prices to the end user for the fuel must be minimal. Current and projected fuel volumes appear to be insufficient to induce necessary economies of scale in production and distribution for fuel use. Despite their benefits, existing programs will suffer absent measures to secure economical fuel supplies. One solution is to develop sources that are dedicated to fuel markets and located within the end-use region

  11. A risk-based framework to assess long-term effects of policy and water supply changes on water resources systems

    Science.gov (United States)

    Hassanzadeh, Elmira; Elshorbagy, Amin; Wheater, Howard; Gober, Patricia

    2015-04-01

    Climate uncertainty can affect water resources availability and management decisions. Sustainable water resources management therefore requires evaluation of policy and management decisions under a wide range of possible future water supply conditions. This study proposes a risk-based framework to integrate water supply uncertainty into a forward-looking decision making context. To apply this framework, a stochastic reconstruction scheme is used to generate a large ensemble of flow series. For the Rocky Mountain basins considered here, two key characteristics of the annual hydrograph are its annual flow volume and the timing of the seasonal flood peak. These are perturbed to represent natural randomness and potential changes due to future climate. 30-year series of perturbed flows are used as input to the SWAMP model - an integrated water resources model that simulates regional water supply-demand system and estimates economic productivity of water and other sustainability indicators, including system vulnerability and resilience. The simulation results are used to construct 2D-maps of net revenue of a particular water sector; e.g., hydropower, or for all sectors combined. Each map cell represents a risk scenario of net revenue based on a particular annual flow volume, timing of the peak flow, and 200 stochastic realizations of flow series. This framework is demonstrated for a water resources system in the Saskatchewan River Basin (SaskRB) in Saskatchewan, Canada. Critical historical drought sequences, derived from tree-ring reconstructions of several hundred years of annual river flows, are used to evaluate the system's performance (net revenue risk) under extremely low flow conditions and also to locate them on the previously produced 2D risk maps. This simulation and analysis framework is repeated under various reservoir operation strategies (e.g., maximizing flood protection or maximizing water supply security); development proposals, such as irrigation

  12. Report on the long-term interim storage of spent fuels and vitrified wastes; Gutachten zur Langzeitzwischenlagerung abgebrannter Brennelemente und verglaster Abfaelle

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-12-03

    Long-term interim storage for several hundred years is an option on the management of high-level radioactive wastes. The decision on final disposal is postponed. Worldwide the long-term interim storage is not part of the disposal concept - a geologic final repository is the ultimate aim. Using today's technology the interim storage over several hundred years is supposed to be uncritical. Aging management is the most important challenge - the renewal of the facilities would have to be expected. Possible social change and their impact on the interim storage problem has not been considered.

  13. Salinization may attack you from behind: upconing and related long-term downstream salinization in the Amsterdam Water Supply Dunes (Invited)

    Science.gov (United States)

    Olsthoorn, T.

    2010-12-01

    Groundwater from the Amsterdam Water Supply Dunes (GE: 52.35°N 4.55°E) has been used for the drinking water supply of Amsterdam since 1853. During the first half of the 20th century, severe intrusion and upconing occurred, with many of the wells turning brackish or saline. Already in 1903, the hydrologist/director of the Amsterdam Water Supply, Pennink, predicted this, based on his unique sand-box modeling, which he published in 1915 in the form of a large-size hard-bound book in four languages showing detailed black and white photographs of his tests. This book is now on the web: http://www.citg.tudelft.nl/live/pagina.jsp?id=68e12562-a4d2-489a-b82e-deca5dd32c42&lang=en Pennink devoted much of his work on saltwater upconing below wells, which he so feared. He simulated simultaneous flow of fresh and salt water, using milk to represent the saltwater having about the same density. With our current modeling tools, we can simulate his experiments, allowing to better understand his setup and even to verify our code. Pennink took interest in the way these cones form and in the point at which the salt water enters the screen. Surprizing, at least to many, is that this entry point is not necessarily the screen bottom. Measurements of the salinity distribution in salinized wells in the Amsterdam Water Supply Dune area confirmed this thirty years later when salinzation was severely occurring. The curved cone shape under ambient flow conditions provides part of the explanation why a short-term shut down of a well almost immediately diminishes salt concentrations, but salinization downstream of the wells in case with substantial lateral groundwater flow is not affected. Downstream salinization due to extraction was clearly shown in Pennink's experiments. However, the phenomenon seems still largely unknown or ignored. Downstream salinization also affects downstream heads for years after extraction has stopped. The presentation demonstrates and explains these local and more

  14. DOCUMENTATION OF NATIONAL WEATHER CONDITIONS AFFECTING LONG-TERM DEGRADATION OF COMMERCIAL SPENT NUCLEAR FUEL AND DOE SPENT NUCLEAR FUEL AND HIGH-LEVEL WASTE

    International Nuclear Information System (INIS)

    W. L. Poe, Jr.; P.F. Wise

    1998-01-01

    The U.S. Department of Energy (DOE) is preparing a proposal to construct, operate 2nd monitor, and eventually close a repository at Yucca Mountain in Nye County, Nevada, for the geologic disposal of spent nuclear fuel (SNF) and high-level radioactive waste (HLW). As part of this effort, DOE has prepared a viability assessment and an assessment of potential consequences that may exist if the repository is not constructed. The assessment of potential consequences if the repository is not constructed assumes that all SNF and HLW would be left at the generator sites. These include 72 commercial generator sites (three commercial facility pairs--Salem and Hope Creek, Fitzpatrick and Nine Mile Point, and Dresden and Morris--would share common storage due to their close proximity to each other) and five DOE sites across the country. DOE analyzed the environmental consequences of the effects of the continued storage of these materials at these sites in a report titled Continued Storage Analysis Report (CSAR; Reference 1 ) . The CSAR analysis includes a discussion of the degradation of these materials when exposed to the environment. This document describes the environmental parameters that influence the degradation analyzed in the CSAR. These include temperature, relative humidity, precipitation chemistry (pH and chemical composition), annual precipitation rates, annual number of rain-days, and annual freeze/thaw cycles. The document also tabulates weather conditions for each storage site, evaluates the degradation of concrete storage modules and vaults in different regions of the country, and provides a thermal analysis of commercial SNF in storage

  15. The Present, Mid-Term, and Long-Term Supply Curves for Tellurium; and Updates in the Results from NREL's CdTe PV Module Manufacturing Cost Model (Presentation)

    Energy Technology Data Exchange (ETDEWEB)

    Woodhouse, M.; Goodrich, A.; Redlinger, M.; Lokanc, M.; Eggert, R.

    2013-09-01

    For those PV technologies that rely upon Te, In, and Ga, first-order observations and calculations hint that there may be resource constraints that could inhibit their successful deployment at a SunShot level. These are only first-order approximations, however, and the possibility for an expansion in global Te, In, and Ga supplies needs to be considered in the event that there are upward revisions in their demand and prices.In this study, we examine the current, mid-term, and long-term prospects of Tellurium (Te) for use in PV. We find that the current global supply base of Te would support <10 GW of annual traditional CdTe PV manufacturing production. But as for the possibility that the supply base for Te might be expanded, after compiling several preliminary cumulative availability curves we find that there may be significant upside potential in the supply base for this element - principally vis a vis increasing demand and higher prices. Primarily by reducing the Tellurium intensity in manufacturing and by increasing the recovery efficiency of Te in Cu refining processes, we calculate that it may prove affordable to PV manufacturers to expand the supply base for Te such that 100 GW, or greater, of annual CdTe PV production is possible in the 2030 - 2050 timeframe.

  16. U.S. contribution of section A.3. The significance of long-term supply and energy sufficiency prospects offered by fast breeders

    International Nuclear Information System (INIS)

    1978-10-01

    Costs involved in breeder deployment are identified and analyzed, i.e., high breeder capital costs, fuel cycle costs, research and development costs and discount rates. It is pointed out that while there are potential benefits to be derived from future application of fast breeders, there are also significant costs and other factors requiring consideration. Careful country-specific analyses are needed. Such analyses may conclude for example that although breeders could become economical in less highly industrialized nations, such nations may find it more economical and practical to purchase reprocessing services from existing large commercial size plants rather than deploy their own small scale reprocessing plants

  17. A long-term survivor of Bland-White-Garland syndrome with systemic collateral supply: A case report and review of the literature

    Directory of Open Access Journals (Sweden)

    Papagiannopoulou P

    2005-12-01

    Full Text Available Abstract Background land-White-Garland syndrome (anomalous origin of the left coronary artery from the pulmonary artery is a rare disease which may result in myocardial infarction, congestive heart failure and sometimes death during the early infantile period. Case presentation: A succesfully treated case of a 45-year-old mother of 2 children with Bland-White-Garland syndrome and concomitant severe mitral regurgitation is presented. Subsequent therapy consisted of ligation of the anomalous origin of the left coronary artery, anastomosis of the left internal mammary artery to the left anterior descending branch and mitral valve replacement. Continuous blood flow from the left coronary artery ostium during extracorporeal circulation and aorta clamping suggested systemic collateral supply. Conclusions: Recognition and diagnosis of Bland-White-Garland syndrome is important due to its potentially life-threatening complications.

  18. Long-Term Symbolic Learning

    National Research Council Canada - National Science Library

    Kennedy, William G; Trafton, J. G

    2007-01-01

    What are the characteristics of long-term learning? We investigated the characteristics of long-term, symbolic learning using the Soar and ACT-R cognitive architectures running cognitive models of two simple tasks...

  19. LONG TERM COLLECTIONS

    CERN Multimedia

    STAFF ASSOCIATION

    2010-01-01

    ACKNOWLEDGMENTS The Long-Term Collections (CLT) committee would like to warmly thank its faithful donors who, year after year, support our actions all over the world. Without you, all this would not be possible. We would like to thank, in particular, the CERN Firemen’s Association who donated 5000 CHF in the spring thanks to the sale of their traditional calendar, and the generosity of the CERN community. A huge thank you to the firemen for their devotion to our cause. And thank you to all those who have opened their door, their heart, and their purses! Similarly, we warmly thank the CERN Yoga Club once again for its wonderful donation of 2000 CHF we recently received. We would also like to tell you that all our projects are running well. Just to remind you, we are currently supporting the activities of the «Réflexe-Partage» Association in Mali; the training centre of «Education et Développement» in Abomey, Benin; and the orphanage and ...

  20. Long term radiotoxicity

    International Nuclear Information System (INIS)

    Slessarev, I.

    2001-01-01

    A major issue to secure the development of nuclear energy in future is the radioactive waste minimization, both inside the fuel cycle and in a deep geological storage. The aim of this paper is to establish the physical principles which provide an inherent minimization of the radioactive wastes. A new concept is introduced to characterize the radiotoxicity associated to various nuclei families in equilibrium state. The analysis shows the potential of evolutionary nuclear systems, mostly based on known technologies and the potential of more futuristic systems, like accelerator-driven systems and Th-fuel cycle. Several groups of the toxicity sources are object of the studies: Actinides as a part of the nuclear fuel which is remaining unusable after irradiation in nuclear power plants; long-lived fission products as the inevitable result of nuclear energy production; Lanthanides as an important part of fission products which separation from Actinides is technologically difficult because of similar chemical properties

  1. Study of long-term loss of all AC power supply sources for VVER-1000/V320 in connection with application of new engineering safety features for SAMG

    International Nuclear Information System (INIS)

    Borisov, Evgeni; Grigorov, Dobrin; Mancheva, Kaliopa

    2013-01-01

    Highlights: • In this study we presented analysis for a new SAMG approach. • The approach is applicable for all PWR reactors from 2nd generation. • We investigated two scenarios with total black out. • The RELAP/MOD 3.2 computer code is used in performing the analyses. - Abstract: This paper presents the results of analysis for application of a new Severe Accident Management Guideline (SAMG) approach which is specifically applied for VVER-1000/B320 reactor installations. In general, this innovative approach is fully applicable for all the pressurized water reactors from second generation. The purposes of the analysis for the new SAMG approach application are as follows: • To represent suggestions for new engineering safety features application for SAMG strategies. • To assess the applicability of the new engineering safety features and means for SAMG strategies in case of loss of all off-site power supply sources for VVER-1000/B320 reactor installations. • To represent important operator actions and to analyse the effectiveness of these actions for accidents management in compliance with the new approach. • The RELAP5/MOD3.3 computer code has been used in performing the analyses in a VVER-1000 Nuclear Power Plant (NPP) model. The input data deck for the analysis is optimized, verified and validated

  2. Evaluating long term forecasts

    Energy Technology Data Exchange (ETDEWEB)

    Lady, George M. [Department of Economics, College of Liberal Arts, Temple University, Philadelphia, PA 19122 (United States)

    2010-03-15

    The U.S. Department of Energy's Energy Information Administration (EIA), and its predecessor organizations, has published projections of U.S. energy production, consumption, distribution and prices annually for over 30 years. A natural issue to raise in evaluating the projections is an assessment of their accuracy compared to eventual outcomes. A related issue is the determination of the sources of 'error' in the projections that are due to differences between the actual versus realized values of the associated assumptions. One way to do this would be to run the computer-based model from which the projections are derived at the time the projected values are realized, using actual rather than assumed values for model assumptions; and, compare these results to the original projections. For long term forecasts, this approach would require that the model's software and hardware configuration be archived and available for many years, possibly decades, into the future. Such archival creates many practical problems; and, in general, it is not being done. This paper reports on an alternative approach for evaluating the projections. In the alternative approach, the model is run many times for cases in which important assumptions are changed individually and in combinations. A database is assembled from the solutions and a regression analysis is conducted for each important projected variable with the associated assumptions chosen as exogenous variables. When actual data are eventually available, the regression results are then used to estimate the sources of the differences in the projections of the endogenous variables compared to their eventual outcomes. The results presented here are for residential and commercial sector natural gas and electricity consumption. (author)

  3. Uranium ... long-term confidence

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    Half way through 1983 the outlook for the world's uranium producers was far from bright if one takes a short term view. The readily accessible facts present a gloomy picture. The spot prices of uranium over the past few years decreased from a high of $42-$43/lb to a low of $17 in 1982. It now hovers between $23 and $24. the contract prices negotiated between producers and consumers are not so accessible but they do not reflect the spot price. The reasons why contractual uranium prices do not follow the usual dictates of supply and demand are related to the position in which uranium and associated power industries find themselves. There is public reaction with strong emotional overtones as well as much reduced expectations about the electric power needs of the world. Furthermore the supply of uranium is not guaranteed despite present over production. However the people in the industry, taking the medium- and long-term view, are not despondent

  4. PSA modeling of long-term accident sequences

    International Nuclear Information System (INIS)

    Georgescu, Gabriel; Corenwinder, Francois; Lanore, Jeanne-Marie

    2014-01-01

    In the context of the extension of PSA scope to include external hazards, in France, both operator (EDF) and IRSN work for the improvement of methods to better take into account in the PSA the accident sequences induced by initiators which affect a whole site containing several nuclear units (reactors, fuel pools,...). These methodological improvements represent an essential prerequisite for the development of external hazards PSA. However, it has to be noted that in French PSA, even before Fukushima, long term accident sequences were taken into account: many insight were therefore used, as complementary information, to enhance the safety level of the plants. IRSN proposed an external events PSA development program. One of the first steps of the program is the development of methods to model in the PSA the long term accident sequences, based on the experience gained. At short term IRSN intends to enhance the modeling of the 'long term' accident sequences induced by the loss of the heat sink or/and the loss of external power supply. The experience gained by IRSN and EDF from the development of several probabilistic studies treating long term accident sequences shows that the simple extension of the mission time of the mitigation systems from 24 hours to longer times is not sufficient to realistically quantify the risk and to obtain a correct ranking of the risk contributions and that treatment of recoveries is also necessary. IRSN intends to develop a generic study which can be used as a general methodology for the assessment of the long term accident sequences, mainly generated by external hazards and their combinations. This first attempt to develop this generic study allowed identifying some aspects, which may be hazard (or combinations of hazards) or related to initial boundary conditions, which should be taken into account for further developments. (authors)

  5. Long-term safety for the final repository for spent nuclear fuel at Forsmark. Main report of the SR-Site project

    Energy Technology Data Exchange (ETDEWEB)

    2011-03-15

    The central conclusion of the safety assessment SR-Site is that a KBS-3 repository that fulfils long-term safety requirements can be built at the Forsmark site. This conclusion is reached because the favourable properties of the Forsmark site ensure the required long-term durability of the barriers of the KBS-3 repository. In particular, the copper canisters with their cast iron inserts have been demonstrated to provide a sufficient resistance to the mechanical and chemical loads to which they may be subjected in the repository environment. The conclusion is underpinned by: - The reliance of the KBS-3 repository on i) a geological environment that exhibits long-term stability with respect to properties of importance for long-term safety, i.e. mechanical stability, low groundwater flow rates at repository depth and the absence of high concentrations of detrimental components in the groundwater, and ii) the choice of naturally occurring materials (copper and bentonite clay) for the engineered barriers that are sufficiently durable in the repository environment to provide the barrier longevity required for safety. - The understanding, through decades of research at SKB and in international collaboration, of the phenomena that affect long-term safety, resulting in a mature knowledge base for the safety assessment. - The understanding of the characteristics of the site through several years of surface-based investigations of the conditions at depth and of scientific interpretation of the data emerging from the investigations, resulting in a mature model of the site, adequate for use in the safety assessment. - The detailed specifications of the engineered parts of the repository and the demonstration of how components fulfilling the specifications are to be produced in a quality assured manner, thereby providing a quality assured initial state for the safety assessment. The detailed analyses demonstrate that canister failures in a one million year perspective are rare

  6. Long-term safety for the final repository for spent nuclear fuel at Forsmark. Main report of the SR-Site project

    International Nuclear Information System (INIS)

    2011-03-01

    The central conclusion of the safety assessment SR-Site is that a KBS-3 repository that fulfils long-term safety requirements can be built at the Forsmark site. This conclusion is reached because the favourable properties of the Forsmark site ensure the required long-term durability of the barriers of the KBS-3 repository. In particular, the copper canisters with their cast iron inserts have been demonstrated to provide a sufficient resistance to the mechanical and chemical loads to which they may be subjected in the repository environment. The conclusion is underpinned by: - The reliance of the KBS-3 repository on i) a geological environment that exhibits long-term stability with respect to properties of importance for long-term safety, i.e. mechanical stability, low groundwater flow rates at repository depth and the absence of high concentrations of detrimental components in the groundwater, and ii) the choice of naturally occurring materials (copper and bentonite clay) for the engineered barriers that are sufficiently durable in the repository environment to provide the barrier longevity required for safety. - The understanding, through decades of research at SKB and in international collaboration, of the phenomena that affect long-term safety, resulting in a mature knowledge base for the safety assessment. - The understanding of the characteristics of the site through several years of surface-based investigations of the conditions at depth and of scientific interpretation of the data emerging from the investigations, resulting in a mature model of the site, adequate for use in the safety assessment. - The detailed specifications of the engineered parts of the repository and the demonstration of how components fulfilling the specifications are to be produced in a quality assured manner, thereby providing a quality assured initial state for the safety assessment. The detailed analyses demonstrate that canister failures in a one million year perspective are rare

  7. Long term storage techniques for 85Kr

    International Nuclear Information System (INIS)

    Foster, B.A.; Pence, D.T.; Staples, B.A.

    1975-01-01

    As new nuclear fuel reprocessing plants go on stream, the collection of fission product 85 Kr will be required to avoid potential local release problems and long-term atmospheric buildup. Storage of the collected 85 Kr for a period of at least 100 years will be necessary to allow approximately 99.9 percent decay before it is released. A program designed to develop and evaluate proposed methods for long-term storage of 85 Kr is discussed, and the results of a preliminary evaluation of three methods, high pressure steel cylinders, zeolite encapsulation, and clathrate inclusion are presented. (U.S.)

  8. Approach to securing of stable nuclear fuel supplies

    International Nuclear Information System (INIS)

    Koike, Kunihisa; Imamura, Isao; Noda, Tetsuya

    2010-01-01

    With the dual objectives of not only ensuring stable electric power supplies but also preventing global warming, the construction of new nuclear power plants is being planned in many countries throughout the world. Toshiba and Westinghouse Electric Company (WEC), a member of the Toshiba Group, are capable of supplying both boiling water reactor (BWR) and pressurized water reactor (PWR) plants to satisfy a broad range of customer requirements. Furthermore, to meet the growing demand for the securing of nuclear fuel supplies, Toshiba and WEC have been promoting the strengthening and further expansion of supply chains in the fields of uranium production, uranium hexafluoride (UF 6 ) conversion, uranium enrichment, and fuel fabrication. (author)

  9. Design Optimization of a Low Pressure LNG Fuel Supply System

    OpenAIRE

    Nguyen, Kim

    2015-01-01

    In 2014 there were 50 liquefied natural gas (LNG) fuelled ships in operation and around 70 on order worldwide. LNG proves to emit less pollution and considering the present and future emission regulations and optimistic gas fuel prices, LNG would be a preferable option as a marine fuel. The number of LNG fuelled ships is therefore likely to increase significantly the next five to ten years. There are many ways to configure the fuel supply system. The fuel supply system consists of a tank,...

  10. Long Term Financing of Infrastructure

    OpenAIRE

    Sinha, Sidharth

    2014-01-01

    Infrastructure projects, given their long life, require long term financing. The main sources of long term financings are insurance and pension funds who seek long term investments with low credit risk. However, in India household financial savings are mainly invested in bank deposits. Insurance and pension funds account for only a small percentage of household financial savings. In addition most infrastructure projects do not qualify for investment by insurance and pension funds because of t...

  11. Long-term trends in U.S. gas supply and prices: 1991 edition of the GRI baseline projection of U.S. energy supply and demand to 2010, April 1991. Gas research insights

    International Nuclear Information System (INIS)

    Woods, T.J.

    1991-04-01

    The report summarizes the gas supply and price outlook in the 1991 Edition of the GRI Baseline Projection of U.S. Energy Supply and Demand. Projected U.S. gas production, gas imports, and other sources of gas supply are discussed along with the sensitivity of the outlook to changes in price expectations. The critical uncertainties and issues affecting the gas supply and price outlook are discussed. Appendixes include a comparison of the 1991 and the 1989 projections of gas supply and price trends; and a description of the GRI Hydrocarbon Model

  12. Fuel Supply Shutdown Facility Interim Operational Safety Requirements

    International Nuclear Information System (INIS)

    BENECKE, M.W.

    2000-01-01

    The Interim Operational Safety Requirements for the Fuel Supply Shutdown (FSS) Facility define acceptable conditions, safe boundaries, bases thereof, and management of administrative controls to ensure safe operation of the facility

  13. 300 Area fuel supply facilities deactivation function analysis report

    International Nuclear Information System (INIS)

    Lund, D.P.

    1995-09-01

    The document contains the functions, function definitions, function interfaces, function interface definitions, Input Computer Automated Manufacturing Definition (IDEFO) diagrams, and a function hierarchy chart that describe what needs to be performed to deactivate the 300 Area Fuel Supply Facilities

  14. The uranium industry: long-term planning for short-term competition

    International Nuclear Information System (INIS)

    Vottero, X.; Georges Capus, G.

    2001-01-01

    Long term planning for short term competition Today, uranium producers face new challenges in terms of both production (new regulatory, environmental and social constraints) and market conditions (new sources of uranium supply, very low prices and tough competition). In such a context, long-term planning is not just a prerequisite to survive in the nuclear fuel cycle industry. In fact, it also contributes to sustaining nuclear electricity generation facing fierce competition from other energy sources in increasingly deregulated markets. Firstly, the risk of investing in new mining projects in western countries is growing because, on the one hand, of very erratic market conditions and, on the other hand, of increasingly lengthy, complex and unpredictable regulatory conditions. Secondly, the supply of other sources of uranium (uranium derived from nuclear weapons, uranium produced in CIS countries, ...) involve other risks, mainly related to politics and commercial restrictions. Consequently, competitive uranium supply requires not only technical competence but also financial strength and good marketing capabilities in order to anticipate long-term market trends, in terms of both demand and supply. It also requires taking into account new parameters such as politics, environment, regulations, etc. Today, a supplier dedicated to the sustainable production of nuclear electricity must manage a broad range of long-term risks inherent to the procurement of uranium. Taking into account all these parameters in a context of short-term, fast-changing market is a great challenge for the future generation. World Uranium Civilian Supply and Demand. (authors)

  15. Nuclear fuel cycles : description, demand and supply estimates

    International Nuclear Information System (INIS)

    Gadallah, A.A.; Abou Zahra, A.A.; Hammad, F.H.

    1985-01-01

    This report deals with various nuclear fuel cycles description as well as the world demand and supply estimates of materials and services. Estimates of world nuclear fuel cycle requirements: nuclear fuel, heavy water and other fuel cycle services as well as the availability and production capabilities of these requirements, are discussed for several reactor fuel cycle strategies, different operating and under construction fuel cycle facilities in some industrialized and developed countries are surveyed. Various uncertainties and bottlenecks which are recently facing the development of some fuel cycle components are also discussed, as well as various proposals concerning fuel cycle back-end concepts. finally, the nuclear fuel cycles activities in some developing countries are reviewed with emphasis on the egyptian plans to introduce nuclear power in the country. 11 fig., 16 tab

  16. Safety relevant aspects of the long-term intermediate storage of spent fuel elements and vitrified high-level radioactive wastes; Sicherheitstechnische Aspekte der langfristigen Zwischenlagerung von bestrahlten Brennelementen und verglastem HAW

    Energy Technology Data Exchange (ETDEWEB)

    Ellinger, A.; Geupel, S.; Gewehr, K.; Gmal, B.; Hannstein, V.; Hummelsheim, K.; Kilger, R.; Wagner, M. [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), Koeln (Germany); Schmidt, G.; Spieth-Achtnich, A. [Oeko-Institut e.V. - Institut fuer angewandte Oekolgie (Germany)

    2010-04-15

    The currently in Germany pursued concept for management of spent fuel from nuclear power plants provides intermediate dry cask storage at the NPP sites until direct disposal in a deep geologic repository. In addition the earlier commissioned centralized dry storage facilities are being used for storage of high level radioactive waste returned from foreign reprocessing of German spent fuel performed so far. The dry interim storage facilities are licensed for 40 years of operation time. According to the German regulations a full scope periodic safety review is not required so far, neither practical experience on dry storage for this period of time is available. With regard to this background the report at hand is dealing with long term effects, which may affect safety of the interim storage during the 40 years period or beyond if appropriate, and with the question, whether additional analyses or monitoring measures may be required. Therefore relevant publications have been evaluated, calculations have been performed as well as a systematic screening with regard to loads and possible ageing effects has been applied to structures and components important for safety of the storage, in order to identify relevant long term effects, which may not have been considered sufficiently so far and to provide proposals for an improved ageing management. The report firstly provides an overview on the current state of technology describing shortly the national and international practice and experience. In the following chapters safety aspects of interim storage with regard to time dependent effects and variations are being analyzed and discussed. Among this not only technical aspects like the long term behavior of fuel elements, canisters and storage systems are addressed, but also operational long term aspects regarding personnel planning, know how conservation, documentation and quality management are taken into account. A separate chapter is dedicated to developing and describing

  17. Preliminary evaluation of supply decentralization of fuels

    International Nuclear Information System (INIS)

    Trindade, C.O.C. da.

    1990-03-01

    Energy policy in Brazil has been made in a centralized way. The total transportation costs for liquid fuel were calculated the local production of an alternative fuel was examined. It was concluded that locally produced alcohol, although is not competitive with diesel, can substitute, at this moment, the alcohol imported from other regions and approaches competitiveness with gasoline. (author)

  18. Long-term urethral catheterisation.

    Science.gov (United States)

    Turner, Bruce; Dickens, Nicola

    This article discusses long-term urethral catheterisation, focusing on the relevant anatomy and physiology, indications for the procedure, catheter selection and catheter care. It is important that nurses have a good working knowledge of long-term catheterisation as the need for this intervention will increase with the rise in chronic health conditions and the ageing population.

  19. Criticality evaluation of long term for spent fuel, using Scale; Evaluacion de criticidad a largo plazo para combustible gastado, utilizando SCALE

    Energy Technology Data Exchange (ETDEWEB)

    Esquivel E, J.; Vargas E, S.; Ramirez S, J. R., E-mail: jaime.esquivel@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    Once carried out the spent fuel discharge, of the reactor core, this continues generating decay heat and diverse fission products, reason why is important to store this fuel inside containers able to dissipate the heat generated by the isotopes decay of the fuel and to maintain the fuels arrangement in subcritical condition. This means that: is necessary to assure the sub-criticality of those fuel assemblies in the time. This work, presents a criticality evaluation of fuel assemblies type PWR in a storage generic container. For this purpose have been used two codes: GeeWiz, to carry out the geometric model of the container with the fuel assemblies, and Keno, with which, the criticality of the full container with fuel is determined until a 10{sup 6} years period. These codes are part of the package Scale. The specifications for each one of the analyzed components are based on a Benchmark document of the Nea/OECD, of where, the results that reports are compared with the obtained results by the realized analysis. (Author)

  20. Financing long term liabilities

    International Nuclear Information System (INIS)

    Noviello, Luigi

    2003-01-01

    In the '80 even if there were no precise law disposition in this specific matter, Enel has created a fund for the plants decommissioning and a fund for the irradiated fuel management. A setting aside pluri-annual plan has been defined. Cumulated funds transferred to the Sogin at the date of its constitution amount to about 1500 MLD ITL (750 M Euro). This amount was adequate to complete decommissioning activities within the Safe Store strategy. Following the separation of Sogin from Enel, a funding mechanism has been defined to provide resources for additional costs deriving from the different economic conditions (new discount rate and taxes), from the management costs for the new company, and from the change in strategy (from Safe Store to DECON). A Decree of the Ministry of the Industry, issued on 26 January 2000, states that the above mentioned extra costs for Sogin shall be financed on a levy on the price of the sold kWh. Every year Sogin shall present the program of future activities, with associated costs: on this basis, the national Authority for Electric energy and Gas (the national body which defines tariff policy) shall re-evaluate the global amount to be granted to Sogin and the levy on the price of the kWh due to Sogin for next three years. The re-evaluation will take into account economic efficiency criteria. For the period 2002- 2004 the Authority has defined a global amount of about 362 M euros to be granted to Sogin, corresponding to ∼0,04 cents of Euro per kWh. The same procedure is foreseen by the Decree in order to finance Sogin for additional costs related to the dismantling of nuclear installations now property of ENEA. In this context, a Consortium between ENEA and Sogin has been established. The Authority for the period 2002-2004 has defined a global amount of about 106 M euros to be granted to the Consortium, corresponding to ∼0,015 cents of Euro per kWh. (author)

  1. Fuel supply shutdown facility interim operational safety requirements

    International Nuclear Information System (INIS)

    Besser, R.L.; Brehm, J.R.; Benecke, M.W.; Remaize, J.A.

    1995-01-01

    These Interim Operational Safety Requirements (IOSR) for the Fuel Supply Shutdown (FSS) facility define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls to ensure safe operation. The IOSRs apply to the fuel material storage buildings in various modes (operation, storage, surveillance)

  2. 300 Area fuel supply facilities deactivation mission analysis report

    International Nuclear Information System (INIS)

    Lund, D.P.

    1995-01-01

    This report presents the results of the 300 Area fuel supply facilities (formerly call ''N reactor fuel fabrication facilities'') Deactivation Project mission analysis. Hanford systems engineering (SE) procedures call for a mission analysis. The mission analysis is an important first step in the SE process

  3. A valuation study of fuel supply stability of nuclear energy

    International Nuclear Information System (INIS)

    Nagano, Koji; Nagata, Yutaka; Hitomi, Kazumi; Hamagata, Sumio; Asaoka, Yoshiyuki

    2008-01-01

    In order to assess potential benefits of nuclear power with regard to its characteristics of fuel supply stability, the following three aspects are valuated under the Japanese energy and electricity mix: a) economic stability; i.e. nuclear power's contribution to the whole energy and electricity mix in terms of resistance to fluctuation and/or fuel price hikes, b) procurement stability; i.e. natural uranium, the raw fuel material for nuclear power generation, is being imported from more reliable sources through adequately diverse markets than in the cases of oil and natural gas, and, c) passive reserve effect; i.e. fuel materials as running stocks at power stations and fuel service facilities could maintain nuclear power generation running for a certain duration under unexpected disruption of fuel supply. (author)

  4. Resumption of transport of KUR spent fuel from Japan to USA - Very long-term storage and public acceptance for transport

    International Nuclear Information System (INIS)

    Nakagome, Yoshihiro; Nishimaki, Kenzo; Kanda, Keiji

    1999-01-01

    The Research Reactor Institute, Kyoto University (KURRI) has more than 250 MTR-type HEU spent fuel elements. They have been stored in water pools after irradiation in the Kyoto University Research Reactor (KUR) core. The longest pool residence time is 25 years. In accordance with the Foreign Research Reactor Spent Nuclear Fuel Receipt Program of the United States, sixty KUR spent fuel elements were shipped from KURRI to the Savannah River Site of the USDOE in August, 1999. This shipment was done successfully through a public port in Osaka Prefecture, Japan. This is the first shipment in the past twenty-six years after the last shipment through the Yokohama Port. Concerning the use of a public port, we had to solve many issues for public acceptance. In this paper, we describe how we have stored the spent fuels for a long time with high integrity and how we have obtained public acceptance for the transport. (author)

  5. Long-term trends in U.S. gas supply and prices: 1992 edition of the GRI baseline projection of U.S. energy supply and demand to 2010

    International Nuclear Information System (INIS)

    Woods, T.J.

    1991-12-01

    The paper summarizes the gas supply outlook in the 1992 Edition of the GRI Baseline Projection of U.S. Energy Supply and Demand, which has been adopted as a major input to the planning cycle leading to the development of the Gas Research Institute (GRI) 1993 research and development program. The 1992 projection presents the GRI planning outlook for the economic and the energy supply and demand situation to the year 2010. It was prepared independently by GRI using publicly available data and a framework of commercially available models that GRI has developed over several years. It is not derived from the views of GRI member companies. The 1992 Edition of the GRI Baseline Projection presents an optimistic outlook for the U.S. gas industry in which increased gas supply can be obtained at competitive prices. The gas prices in the 1992 projection support growth in all major U.S. gas supply sources: lower-48, Alaska, Canada, Mexico, and LNG. By about 2005, U.S. gas supply is at its highest level ever. By 2010, U.S. gas supply has grown to almost 25 quads. U.S. gas production increases 2.6 quads between 1990 and 2010; imports increase 2.2 quads. Although imports do not increase as much as U.S. gas production, they account for an increased share of U.S. gas supply. The import share grows from 7 percent to 12 percent over the projection period. Supplemental gas sources provide about 1 percent of U.S. gas supply

  6. Development of a Code for the Long Term Radiological Safety Assessment of Radioactive Wastes from Advanced Nuclear Fuel Cycle Facilities in Republic of Korea

    International Nuclear Information System (INIS)

    Hwang, Yong Soo

    2010-01-01

    For the purpose of evaluating annual individual doses from a potential repository disposing of radioactive wastes from the operation of the prospective advanced nuclear fuel cycle facilities in Korea, the new safety assessment code based on the Goldsim has been developed. It was designed to compare the environmental impacts from many fuel cycle options such as direct disposal, wet and dry recycling. The code based on the compartment theory can be applied to assess both normal and what if scenarios

  7. Inflation Hedging for Long-Term Investors

    OpenAIRE

    Shaun K. Roache; Alexander P. Attie

    2009-01-01

    Long-term investors face a common problem-how to maintain the purchasing power of their assets over time and achieve a level of real returns consistent with their investment objectives. While inflation-linked bonds and derivatives have been developed to hedge the effects of inflation, their limited supply and liquidity lead many investors to continue to rely on the indirect hedging properties of traditional asset classes. In this paper, we assess these properties over different time horizons,...

  8. Long term adequacy of uranium resources

    International Nuclear Information System (INIS)

    Steyn, J.

    1990-01-01

    This paper examines the adequacy of world economic uranium resources to meet requirements in the very long term, that is until at least 2025 and beyond. It does so by analysing current requirements forecasts, existing and potential production centre supply capability schedules and national resource estimates. It takes into account lead times from resource discovery to production and production rate limitations. The institutional and political issues surrounding the question of adequacy are reviewed. (author)

  9. Distillate Fuel Trends: International Supply Variations and Alternate Fuel Properties

    Science.gov (United States)

    2013-01-31

    fuel in NATO countries will have some amount of FAME present. There is some work being done on hydrocarbon alternatives but the regulatory structure ... synthesis or hydrotreatment – Requirements and test methods.” According to the specification, paraffinic diesel fuel does not meet the current requirements...or international specification for triglyceride based fuel oils (straight vegetable oil / raw vegetable oil). The same holds true for alcohol-based

  10. Assessment of the long-term risks of inadvertent human intrusion into a proposed Canadian nuclear fuel waste disposal vault in deep plutonic rock

    International Nuclear Information System (INIS)

    Wuschke, D.M.

    1992-05-01

    This report describes the methodology developed to assess the long-term risk from inadvertent human intrusion into such a facility, and the results of its application to the proposed facility. Four intrusion scenarios were analysed, all initiated by a drilling operation. These scenarios are exposure of a member of the drilling crew, of a technologist conducting a core examination, of a construction worker and of a resident. The consequence of each scenario was estimated using standard computer codes for environmental pathways analysis and radiation dosimetry. For comparison with the risk criterion, an estimate of the probability of each scenario is also required. An event-tree methodology was used to estimate these probabilities. The estimated risks from these intrusion scenarios are several orders of magnitude below the established risk criterion. The event-tree methodology has the advantages of explicitly displaying the assumptions made, of permitting easy testing of the sensitivity of the risk estimates to assumptions, and of combining technical and sociological information

  11. Long-term safety of radioactive waste disposal: Chemical reaction of fabricated and high burnup spent UO2 fuel with saline brines. Final report

    International Nuclear Information System (INIS)

    Grambow, B.; Casas, I.; Pablo, J. de; Gimenez, J.; Torrero, M.E.

    1996-03-01

    This is the final report of a large EU-research project on spent fuel stability in saline repository environments. Static dissolution experiments with high burnup spent fuel samples and unirradiated UO 2 were performed for about two years in anaerobic NaCl solutions and deionized water with and without container material (iron) being present. Experiments performed at 25 and 150 C gave similar results. Dissolution rates were similar to those measured in the Swedish, or Canadian program for granite media. Rates are strongly influenced by the specific sample surface area, probably related to the mass balance of consumption and production of radiolytic oxidants. In the competition between the oxidizing effect of radiolysis and the reducing effect of iron, the metal corrosion process dominates. Processes controlling radionuclide release are matrix dissolution, solubility, coprecipitation sorption phenomena and colloid formation. In the absence of iron release rates of Sr90, Tc99, Np237, Sb125 and at low reaction progress Ru106 were controlled by matrix dissolution whereas concentrations of tetra-, hexa-, and trivalent actinides (U, Pu, Am, Cm) were controlled by solubility or coprecipitation. The presence of iron did effectively reduce the rates of fuel dissolution and the concentration of many, though not all radionuclides. Solubilities of U were similar for uniradiated UO 2 and for spent fuel both in the case of oxidizing and reducing conditions. In contrast, due to the effect of radiolysis, reaction rates of spent fuel were higher than UO 2 dissolution rates. (orig.) [de

  12. Fuel price and supply projections, 1980 to 2000

    International Nuclear Information System (INIS)

    1980-06-01

    In 1978, over 95% of California's energy was derived from conventional fuels - oil, natural gas, coal, and uranium. Approximately one-third of these conventional fuels was produced within the state, the remaining two-thirds coming from other states and foreign countries. Dependence on these fuels is not likely to diminish rapidly in the near future, therefore the factors that contribute to the future supplies and prices of these fuels will have a major influence on the state's energy future. This report serves as a basis for Commission analysis and is also intended as a tool to be used by others who must make decisions involving the future cost and availability of fuels. This report documents the staff's projections on future supply, price, and availability of these fuels and presents information on historical fuel use and price for background and perspective. Analyses of commercially developable derived fuels and of recent Federal statutory restrictions on the use of oil and gas are also presented. These analyses include economic, logistic, environmental, geologic, and social and institutional considerations. This report does not focus on the costs included in fuel production and preparation; nor does the report go into detail on the transportation, disposal, and downstream costs of the various fuels

  13. Influence of the Scientific and Technical Progress upon the Fuel and Energy Complex of Ukraine until 2050: Methodology of Assessment of Long-term Forecasts

    Directory of Open Access Journals (Sweden)

    Antonenko Leonid A.

    2013-12-01

    Full Text Available The article makes an attempt, using new methodological initial grounds by the works of leading foreign authors, to present an aggregate of qualitatively different conditions of development of the fuel and energy complex of Ukraine until 2050 in the context of forecasts of development of USA until 2100. The authors justify factors that significantly differentiate trajectories of future development of the Ukrainian energy sector and USA energy sector, which envisages development of own methodology and realisation of forecasts officially already developed by Ukrainian scientists. On the basis of this the article presents the authors’ comparative analysis of fuel and energy complexes of Ukraine and China.

  14. Long term complications of diabetes

    Science.gov (United States)

    ... medlineplus.gov/ency/patientinstructions/000327.htm Long-term complications of diabetes To use the sharing features on this page, ... other tests. All these may help you keep complications of diabetes away. You will need to check your blood ...

  15. Risk Analysis of Reservoir Operations Considering Short-Term Flood Control and Long-Term Water Supply: A Case Study for the Da-Han Creek Basin in Taiwan

    Directory of Open Access Journals (Sweden)

    Wen-Ming Cheng

    2017-06-01

    Full Text Available This study applies an integrated methodology to assess short-term over-levee risk and long-term water shortage risk in the Da-Han Creek basin, which is the most important flood control and water storage system in northern Taiwan. An optimization model for reservoir flood control and water supply is adopted, to determine reservoir releases based on synthetic inflow hydrographs during typhoons, which are generated by Monte Carlo simulations. The release is then used to calculate the water level at a downstream control point using a novel developed back-propagation neural network-based model, to reduce computational complexity and achieve automatic-efficient risk evaluation. The calculated downstream water levels and final reservoir water levels after a typhoon event are used to evaluate the mapped over-levee risk and water shortage risk, respectively. The results showed that the different upper limit settings for the reservoir have a significant influence on the variation of 1.19 × 10−5% to 75.6% of the water shortage risk. This occurs because of the insufficient inflow and narrow storage capacity of the Shih-Men Reservoir during drought periods. However, the upper limit settings have a minor influence (with a variation of only 0.149% to 0.157% on the over-levee risk in typhoon periods, because of the high protection standards for the downstream embankment.

  16. Short- and long-term effects on fuels, forest structure, and wildfire potential from prescribed fire and resource benefit fire in southwestern forests, USA

    Science.gov (United States)

    Molly E. Hunter; Jose M. Iniguez; Leigh B. Lentile

    2011-01-01

    Prescribed and resource benefit fires are used to manage fuels in fire-prone landscapes in the Southwest. These practices, however, typically occur under different conditions, potentially leading to differences in fire behavior and effects. The objectives of this study were to investigate the effects of recent prescribed fires, resource benefit fires, and repeated...

  17. Long-Term Hydrocarbon Trade Options for the Maghreb Region and Europe—Renewable Energy Based Synthetic Fuels for a Net Zero Emissions World

    Directory of Open Access Journals (Sweden)

    Mahdi Fasihi

    2017-02-01

    Full Text Available Concerns about climate change and increasing emission costs are drivers for new sources of fuels for Europe. Sustainable hydrocarbons can be produced synthetically by power-to-gas (PtG and power-to-liquids (PtL facilities, for sectors with low direct electrification such as aviation, heavy transportation and chemical industry. Hybrid PV–Wind power plants can harvest high solar and wind potentials of the Maghreb region to power these systems. This paper calculates the cost of these fuels for Europe, and presents a respective business case for the Maghreb region. Calculations are hourly resolved to find the least cost combination of technologies in a 0.45° × 0.45° spatial resolution. Results show that, for 7% weighted average cost of capital (WACC, renewable energy based synthetic natural gas (RE-SNG and RE-diesel can be produced in 2030 for a minimum cost of 76 €/MWhHHV (0.78 €/m3SNG and 88 €/MWhHHV (0.85 €/L, respectively. While in 2040, these production costs can drop to 66 €/MWhHHV (0.68 €/m3SNG and 83 €/MWhHHV (0.80 €/L, respectively. Considering access to a WACC of 5% in a de-risking project, oxygen sales and CO2 emissions costs, RE-diesel can reach fuel-parity at crude oil prices of 101 and 83 USD/bbl in 2030 and 2040, respectively. Thus, RE-synthetic fuels could be produced to answer fuel demand and remove environmental concerns in Europe at an affordable cost.

  18. Compact Fuel Cell Power Supplies with Safe Fuel Storage

    National Research Council Canada - National Science Library

    Powell, M. R; Chellappa, A. S; Vencill, T. R

    2004-01-01

    .... Despite its energy-density advantage, this ammonia-based power supply will not likely be deployed in military or commercial markets unless safety concerns related to the possible rapid release of ammonia are resolved...

  19. [Long-term psychiatric hospitalizations].

    Science.gov (United States)

    Plancke, L; Amariei, A

    2017-02-01

    Long-term hospitalizations in psychiatry raise the question of desocialisation of the patients and the inherent costs. Individual indicators were extracted from a medical administrative database containing full-time psychiatric hospitalizations for the period 2011-2013 of people over 16 years old living in the French region of Nord-Pas-de-Calais. We calculated the proportion of people who had experienced a hospitalization with a duration of 292 days or more during the study period. A bivariate analysis was conducted, then ecological data (level of health-care offer, the deprivation index and the size of the municipalities of residence) were included into a multilevel regression model in order to identify the factors significantly related to variability of long-term hospitalization rates. Among hospitalized individuals in psychiatry, 2.6% had had at least one hospitalization of 292 days or more during the observation period; the number of days in long-term hospitalization represented 22.5% of the total of days of full-time hospitalization in psychiatry. The bivariate analysis revealed that seniority in the psychiatric system was strongly correlated with long hospitalization rates. In the multivariate analysis, the individual indicators the most related to an increased risk of long-term hospitalization were: total lack of autonomy (OR=9.0; 95% CI: 6.7-12.2; P<001); diagnoses of psychological development disorders (OR=9.7; CI95%: 4.5-20.6; P<.001); mental retardation (OR=4.5; CI95%: 2.5-8.2; P<.001): schizophrenia (OR=3.0; CI95%: 1.7-5.2; P<.001); compulsory hospitalization (OR=1.7; CI95%: 1.4-2.1; P<.001); having experienced therapeutic isolation (OR=1.8; CI95%: 1.5-2.1; P<.001). Variations of long-term hospitalization rates depending on the type of establishment were very high, but the density of hospital beds or intensity of ambulatory activity services were not significantly linked to long-term hospitalization. The inhabitants of small urban units had

  20. French Approach for Long Term Storage Safety

    International Nuclear Information System (INIS)

    Marciano, Jacob; Carreton, Jean-Pierre; Lizot, Marie Therese; Lhomme, Veronique

    2014-01-01

    IRSN presents its statement regarding long-term storage facilities; in France, the regulatory documents do not define the long term duration. The storage facility lifetime can only be appreciated according to the needs and materials stored therein. However, the magnitude of the long-term can be estimated at a few hundred years compared to a few decades for current storage. Usually, in France, construction of storage facilities is driven from the necessity various necessities, linked to the management of radioactive material (eg spent fuel) and to the management of radioactive waste. Because of the variety of 'stored materials and objects' (fission product solutions, plutonium oxide powders, activated solids, drums containing technological waste, spent fuel...), a great number of storage facility design solutions have been developed (surface, subsurface areas, dry or wet conditions...) in the World. After describing the main functions of a storage facility, IRSN displays the safety principles and the associated design principles. The specific design principles applied to particular storage (dry or wet spent fuel storage, depleted uranium or reprocessed uranium storage, plutonium storage, waste containing tritium storage, HLW and ILLW storage...) are also presented. Finally, the concerns due to the long-term duration storage and related safety assessment are developed. After discussing these issues, IRSN displays its statement. The authorization procedures governing the facility lifetime are similar to those of any basic nuclear installation, the continuation of the facility operation remaining subject to periodic safety reviews (in France, every 10 years). The applicant safety cases have to show, that the safety requirements are always met; this requires, at minimum, to take into account at the design stage, comfortable design margins. (author)

  1. Alternative fossil-based transportation fuels

    Science.gov (United States)

    2008-01-01

    "Alternative fuels derived from oil sands and from coal liquefaction can cost-effectively diversify fuel supplies, but neither type significantly reduces U.S. carbon-dioxide emissions enough to arrest long-term climate change".

  2. Security of supply of uranium as nuclear fuel

    International Nuclear Information System (INIS)

    Guzman Gomez-Selles, L.

    2011-01-01

    When we talk about Sustainability related to nuclear fuel, the first concern that comes to our mind is about the possibility of having guarantees on the uranium supply for a sufficient period of time. In this paper we are going to analyze the last Reserves data published by the OCD's Red Book and also how the Reserve concept in fully linked to the uranium price. Additionally, it is demonstrated how the uranium Security of supply is guaranteed for, at least, the next 100 years. finally, some comments are made regarding other sources of nuclear fuel as it is the uranium coming from the phosphates or the thorium. (Author)

  3. Quality assurance in nuclear fuel element component supply

    International Nuclear Information System (INIS)

    Jenkins, B.P.

    1987-01-01

    The paper describes the application of Quality Assurance to nuclear fuel element component supply. The Quality Assurance programme includes integrated procurement, purchasing, surveillance and receipt inspection functions. Purchasing policy is based on a consistent preference for competitive tendering. Multiple sourcing is used to encourage competitive pricing and increase security of supply. A receipt inspection facility is maintained to ensure the high product quality levels demanded by the nuclear industry. (U.K.)

  4. Is Yucca Mountain a long-term solution for disposing of US spent nuclear fuel and high-level radioactive waste?

    Science.gov (United States)

    Thorne, M C

    2012-06-01

    On 26 January 2012, the Blue Ribbon Commission on America's Nuclear Future released a report addressing, amongst other matters, options for the managing and disposal of high-level waste and spent fuel. The Blue Ribbon Commission was not chartered as a siting commission. Accordingly, it did not evaluate Yucca Mountain or any other location as a potential site for the storage or disposal of spent nuclear fuel and high-level waste. Nevertheless, if the Commission's recommendations are followed, it is clear that any future proposals to develop a repository at Yucca Mountain would require an extended period of consultation with local communities, tribes and the State of Nevada. Furthermore, there would be a need to develop generally applicable regulations for disposal of spent fuel and high-level radioactive waste, so that the Yucca Mountain site could be properly compared with alternative sites that would be expected to be identified in the initial phase of the site-selection process. Based on what is now known of the conditions existing at Yucca Mountain and the large number of safety, environmental and legal issues that have been raised in relation to the DOE Licence Application, it is suggested that it would be imprudent to include Yucca Mountain in a list of candidate sites for future evaluation in a consent-based process for site selection. Even if there were a desire at the local, tribal and state levels to act as hosts for such a repository, there would be enormous difficulties in attempting to develop an adequate post-closure safety case for such a facility, and in showing why this unsaturated environment should be preferred over other geological contexts that exist in the USA and that are more akin to those being studied and developed in other countries.

  5. High-level radioactive wastes storage characterization and behaviour of spent fuels in long-term; Almacenamiento definitivo de residuos de radiactividad alta. Caracterizacion y comportamiento a largo plazo de los combustibles nucleares irradisos (II)

    Energy Technology Data Exchange (ETDEWEB)

    Diaz Arocas, P; Cobos, J; Quinones, J.; Rodriguez Almazan, J L; Serrano, J [CIEMAT, Madrid (Spain)

    2001-07-01

    In order to understand the long term spent fuel dissolution under repository this report shows the study performed by considering spent fuel as a part of the multi barriers containment system. The study takes into account that the oxidative alteration/dissolution of spent fuel matrix is influenced by the intrinsic spent fuel physicochemical characteristics and the repository environmental parameters. Experimental and modelling results for granite and saline repositories are reported. Parameters considered in this work were pH, pCO{sub 2}, S/V ratio, redox conditions and the influence of the container material in the redox conditions. The influence of alpha, beta and gamma radiation and the resulting radiolytic products formed remains as one of the main uncertainties to quantify the spent fuel behaviour under repository conditions. It was studied in a first approach through dose calculations, modelling of radiolytic products formation and leaching experiments in the presence of external gamma irradiation source and leaching experiments of alpha doped UO{sub 2} pellets. Materials considered are LWR spent fuel (UO{sub 2} and MOX fuel) and their chemical analogues non irradiated UO{sub 2}, SIMFUEL and alpha doped UO{sub 2}. Lea chants were granite groundwater, synthetic granite groundwater, synthetic granite groundwater saturated in bentonite, and high concentrated saline solutions. The matrix dissolution rate and release rate of key radionuclides (i. e. actinides and fission products) obtained through the several experimental techniques and methodologies (dissolution, co-dissolution, precipitation and co-precipitation) together with modelling studies supported in geochemical codes are proposed. Moreover, secondary phases formed that could control release and retention of key nuclides are identified. Maximum concentration values for these radionuclides are reported. The data provided by this study were used in ENRESA-2000 performance assessment. (Author)

  6. Nuclear Waste Management Organization: moving forward together - program update: Canada's plan for the long-term management of used nuclear fuel

    International Nuclear Information System (INIS)

    Nash, K.

    2011-01-01

    In June 2007, the Government of Canada selected Adaptive Phased Management as Canada's plan for safeguarding the public and environment over the very long time in which used nuclear fuel must be managed. The plan requires that Canada's used nuclear fuel be safely and securely contained and isolated from people and the environment in a deep geological repository in a suitable rock formation. In May 2010, the NWMO published a process for identifying an informed and willing community to host the project and currently a number of communities in northwestern Ontario and Saskatchewan have expressed interest in learning about the project. The NWMO anticipates that it will take between seven and ten years to decide on where to locate the deep geological repository and associated facilities. By international standards, this is an ambitious timeline. Ultimately, there will have to be a compelling demonstration of willingness expressed by the citizens of any interested community after a long period of site assessment, and learning about the project, before it is selected to host the project. The presentation will cover the history leading to the 2007 government decision and the full range of activities being undertaken to implement that decision.

  7. Voltage balancing: Long-term experience with the 250 V supercapacitor module of the hybrid fuel cell vehicle HY-LIGHT

    Energy Technology Data Exchange (ETDEWEB)

    Koetz, R.; Sauter, J.-C.; Ruch, P.; Dietrich, P.; Buechi, F.N. [Paul Scherrer Institut, Electrochemistry Laboratory, CH-5232 Villigen PSI (Switzerland); Magne, P.A.; Varenne, P. [Conception et Developpement Michelin SA, CH-1762 Givisiez (Switzerland)

    2007-11-22

    On the occasion of the ''Challenge Bibendum'' 2004 in Shanghai, the hybrid fuel cell - supercapacitor vehicle HY-LIGHT, a joint project of Conception et Developpement Michelin and the Paul Scherrer Institut, was presented to the public. The drive train of this vehicle comprises a 30 kW polymer electrolyte fuel cell (PEFC) and a 250 V supercapacitor (SC) module for energy recuperation and boost power during short acceleration and start-up processes. The supercapacitor module was deliberately constructed without continuous voltage balancing units. The performance of the supercapacitor module was monitored over the 2 years of operation particularly with respect to voltage balancing of the large number of SC cells connected in series. During the investigated period of 19 months and about 7000 km driving, the voltage imbalance within the supercapacitor module proved negligible. The maximum deviation between best and worst SC was always below 120 mV and the capacitor with the highest voltage never exceeded the nominal voltage by more than 40 mV. (author)

  8. The future role of thorium in assuring CANDU fuel supplies

    International Nuclear Information System (INIS)

    Slater, J.B.

    1985-01-01

    Atomic Energy of Canada Limited (AECL), in partnership with Canadian industry and power utilities, has developed the CANDU reactor as a safe, reliable and economic means of transforming nuclear fuel into useable power. The use of thorium/uranium-233 recycle gives the possibility of a many-fold increase in energy yield over that which can be obtained from the use of uranium in once-through cycles. The neutronic properties of uranium-233 combine with the inherent neutron economy of the CANDU reactor to offer the possibility of near-breeder cycles in which there is no net consumption of fissile material under equilibrium fuelling conditions. Use of thorium cycles in CANDU will limit the impact of higher uranium prices. When combined with the potential for significant reductions in CANDU capital costs, then the long-term prospect is for generating costs near to current levels. Development of thorium cycles in CANDU will safeguard against possible uranium shortages in the next century, and will maintain and continue the commercial viability of CANDU as a long-term energy technology. (author)

  9. Security of supply: a neglected fossil fuel externality

    International Nuclear Information System (INIS)

    Cavallo, A.J.

    1995-01-01

    Various groups have attempted to set a monetary value on the externalities of fossil fuel usage based on damages caused by emissions of particulates, sulfur dioxide, and oxides of nitrogen and carbon. One externality that has been neglected in this type of analysis, however, is the cost of maintaining a secure supply of fossil fuels. Military expenditures for this purpose are relatively easy to quantify based on US Department of Defense and Office of Management and Budget figures, and amount to between $1 and more than $3 per million Btu, based on total fossil fuel consumption in the US. Open acknowledgment of such expenses would, at the very least, have a profound effect on the perceived competitiveness of all non-fossil fuel technologies. It should also provide a simple and easily comprehended rationale for an energy content (Btu) charge on all fossil fuels. (Author)

  10. 14 CFR 121.639 - Fuel supply: All domestic operations.

    Science.gov (United States)

    2010-01-01

    ... nontransport category airplanes type certificated after December 31, 1964, to fly for 30 minutes at normal... § 121.639 Fuel supply: All domestic operations. No person may dispatch or take off an airplane unless it has enough fuel— (a) To fly to the airport to which it is dispatched; (b) Thereafter, to fly to and...

  11. 300 Area fuel supply shutdown facility hazards assessment

    International Nuclear Information System (INIS)

    Campbell, L.R.

    1998-01-01

    This document establishes the technical basis in support of Emergency Planning activities for the 300 Area Fuel Supply Shutdown Facilities on the Hanford Site. Through this document, the technical basis for the development of facility specific Emergency Action Levels and Emergency Planning Zone, is demonstrated

  12. Demand and supply of wood fuels in the emission trade

    International Nuclear Information System (INIS)

    Ranta, T.; Lahtinen, P.; Laitila, J.

    2005-01-01

    The emission trade according to the EU directive on greenhouse gas emission allowance started at the beginning of the year 2005. This will boost the demand for wood fuels because of the addition-al value of CO 2 neutrality compared to fossil fuels. This bulletin covers the development of the demand and supply of wood fuels from 2002 to 2010 both at a national and a provincial level. The demand and supply balance of wood fuels will be evaluated both without the effect of emission trade and when the emission trade price level is 20 euro/ton- CO 2 for emission rights in 2010. The evaluations of fuel consumption for individual boilers were made with the help of the databases of Electrowatt-Ekono Ltd. The demand for wood fuels was estimated to double by the year 2010, being almost 50 TWh. The share of forest chips of the demand was one third, i.e. 17 TWh. The supply potential was divided into forest chips and solid by-products from forest industry. Forest chip sources included small diameter wood from young forests and logging residues and stumps from re-generation felling sites. The supply potential calculations of logging residues and stump biomass were based on databases of regeneration felling stands. The biomass potential from small diamreter wood was evaluated on the basis of field measurements of NFI 8 and 9 at a provincial level and multi-source data at a municipal level. In 2010, the supply potential of by-products was estimated to be 28 TWh of which 11 TWh was marketable out-side of the internal use of forest industry. Correspondingly, the theoretical potential of forest chips was estimated to be 51 TWh and the techno-economical potential 24 TWh. As a result of the regional optimization model, the energy use of wood fuels was 29 TWh, which was 59 % of the potential demand. In emission trade the demand was 33 TWh, which was 68 % of the potential demand. Regionally, the potential demand for wood fuels for energy use was higher than the supply in all provinces

  13. Fuel ethanol production from granular corn starch using Saccharomyces cerevisiae in a long term repeated SSF process with full stillage recycling.

    Science.gov (United States)

    Białas, Wojciech; Szymanowska, Daria; Grajek, Włodzimierz

    2010-05-01

    A major problem with fermentative ethanol production is the formation of large amounts of numerous organic pollutants. In an industrial distillery, stillage, fermenter and condenser cooling water are the main sources of wastewater. However, the selection of a proper technology makes it possible to almost completely avoid emissions of such kind of wastewater to the environment. This study examines the effect of stillage recirculation on fuel ethanol production. It is based on the use of Saccharomyces cerevisiae and a granular starch hydrolyzing enzyme in a simultaneous saccharification and fermentation process using a native starch obtained from corn flour. It was shown that the yield of the ethanol production was not influenced by the recycled stillage, a mean yield being 83.38% of the theoretical value. No significant trend for change in the ethanol concentration or in the residual starch was observed during any particular run, even after the 75% of fresh water was replaced with stillage. Thus, by applying this new clean technology it is possible to significantly reduce the rate of water consumption and in this way the production of by-products such as stillage. Copyright 2009 Elsevier Ltd. All rights reserved.

  14. Financing long term liabilities (Germany)

    International Nuclear Information System (INIS)

    2003-01-01

    charges and fees levied from the waste producers. Altogether, financial resources for decommissioning are needed for the following steps: the post-operational phase in which the facility is prepared for dismantling after its final shut-down, dismantling of the radioactive part of the facility, management, storage and disposal of the radioactive waste, restoration of the site, licensing and regulatory supervision of all these steps. Additional means are necessary for the management, storage and disposal of the spent fuel. The way in which the availability of financial resources is secured differs between public owned installations and installations of the private power utilities. In Germany, past practices has resulted in singular contaminated sites of limited extent, mainly during the first half of the 20. century. Those contaminated sites have been or are being cleaned up and redeveloped. In large areas of Saxony and Thuringia, the geological formations permitted the surface and underground mining of Uranium ore. Facilities of the former Soviet-German WISMUT Ltd. where ore was mined and processed from 1946 until the early 1990's can be found at numerous sites. In the course of the re-unification of Germany, the soviet shares of the WISMUT were taken over by the Federal Republic of Germany and the closure of the WISMUT facilities was initiated. In that phase the extent of the damages to the environment and of the necessary remediation work became clear. All mining and milling sites are now closed and are under decommissioning. A comprehensive remediation concept covers all WISMUT sites. Heaps and mill-tailing ponds are transferred into a long-term stable condition. The area of the facilities to be remediated amounts to more than 30 km 2 . Heaps cover a total area of ca. 15,5 km 2 , tailing ponds in which the tailings resulting from the Uranium production are stored as sludges cover 6,3 km 2 ). In total, the remediation issues are very complex and without precedent. The

  15. 'When you use the term 'long term', how long is that term'. Risk, Exclusion, and the Politics of Knowledge Production in Canadian Nuclear Fuel Waste Management Policy Making

    International Nuclear Information System (INIS)

    Stanley, Anna

    2006-01-01

    Risk operates within Canadian Nuclear Fuel Waste (NFW) management policy making as a heuristic for knowledge production about its effects which reconciles the knowledge of the nuclear industry with the outcomes of the NFW management process. In so doing it marginalizes the present and historical experiences of Aboriginal peoples with the nuclear industry, and removes from view the ways in which they have been implicated in the geography and political economy of the nuclear industry. Risk is a discursive form that protects a particular group's claims about the effects of NFW by providing it a universalizing epistemological structure with which to obscure its connection to context. Further risk discourse provides the nuclear industry with a conceptual vocabulary that deliberately casts all competing knowledge as perceptions, values, or as an object of inquiry. The arguments of Aboriginal peoples about the residual effects of radiation in their lands which hosted nuclear activities, such as uranium mining and disposal, have no representation in how the discourse of risk defines and represents knowledge, and thus no purchase in the policy debate. As a result the challenge they present to the nuclear industry's claims are contained. The arrangements which permit the unloading of the negative effects of nuclear power generation onto Aboriginal peoples are thus reproduced (both materially and conceptually), but not shown, by the policy making process and likely, its outcome. In order to raise critical questions about the democratic abilities of risk, this paper has examined the role of 'risk' in Canadian NFW policy making. I have shown how when the politics of knowledge production within the philosophy of risk is analyzed, and the use and role of the notion of risk are interrogated, difficult questions are posed for the democratic potential of risk. I have suggested, through an analysis of the NWMO's representations of Aboriginal content in their process, that in this

  16. Modelling renewable supply chain for electricity generation with forest, fossil, and wood-waste fuels

    International Nuclear Information System (INIS)

    Palander, Teijo

    2011-01-01

    In this paper, a multiple objective model to large-scale and long-term industrial energy supply chain scheduling problems is considered. The problems include the allocation of a number of fossil, peat, and wood-waste fuel procurement chains to an energy plant during different periods. This decision environment is further complicated by sequence-dependent procurement chains for forest fuels. A dynamic linear programming model can be efficiently used for modelling energy flows in fuel procurement planning. However, due to the complex nature of the problem, the resulting model cannot be directly used to solve the combined heat and electricity production problem in a manner that is relevant to the energy industry. Therefore, this approach was used with a multiple objective programming model to better describe the combinatorial complexity of the scheduling task. The properties of this methodology are discussed and four examples of how the model works based on real-world data and optional peat fuel tax, feed-in tariff of electricity and energy efficiency constraints are presented. The energy industry as a whole is subject to policy decisions regarding renewable energy production and energy efficiency regulation. These decisions should be made on the basis of comprehensive techno-economic analysis using local energy supply chain models. -- Highlights: → The energy policy decisions are made using comprehensive techno-economic analysis. → Peat tax, feed-in tariff and energy efficiency increases renewable energy production. → The potential of peat procurement deviates from the current assumptions of managers. → The dynamic MOLP model could easily be adapted to a changing decision environment.

  17. Domestic nuclear fuels supply: possibility of an independent technology

    International Nuclear Information System (INIS)

    Cirimello, R.O.

    1982-01-01

    After considering the different energy sources, their consumption and their respective periods of exploitation, technological considerations in the nuclear fuel field are made. The main subject is the Domestic Supply Project of Embalse Fuel (CANDU type). The different aspects which had to be developed during the realization of this project still under progress, and which are fundamental for the command of the technology, are described: 1) Qualification of the produced fuel elements: fuel elements' characteristics; the reactors' operating parameters, and the prototype fuel elements' characteristics; 2) Development of materials and/or suppliers: the obtainment of UO 2 and its physical properties are considered, as well as those of Zircaloy-4, the development of suppliers and the respective developments for the obtainment of materials such as beryllium, helium and colloidal graphite; 3) Processes development; the following processes are studied and defined: UO 2 pellets fabrication with UO 2 granulated powder; beryllium coating under vaccum; and induction brazing of bearing pads and spacers, end cap and end plate resistance welding and stamping of Zircaloy components, graphite-coating of cladding's internal face; 4) Development of special production equipments; automatic equipment for end cap-to-cladding resistance welding among others. The need for a specific program of quality assurance for nuclear fuels supply is emphasized and the basic criteria are established. The IAEA's quality asssurance requirements are also analyzed. (M.E.L.) [es

  18. Global prospects for nuclear power development in the long term

    International Nuclear Information System (INIS)

    Semenov, Boris A.

    1994-01-01

    Population growth, economic development and improvement of quality of life will lead to significant increase of electricity consumption worldwide with more rapid growth in developing and newly industrialised countries. At the same time, concerns for environmental protection and security of supply will call for the development of alternatives to fossil fuels for electricity generation. Sustain ability will be a major driving factor for the choice of electricity generation options and strategies. Costs, and macro-economic and social impacts, will also influence future strategies in the electricity sector. Since renewable sources require significant development efforts to reach competitiveness, nuclear power is the most likely non-fossil source to be deployed on a large scale for base load electricity generation. Nuclear power is already a proven technology providing a significant share of electricity supply worldwide. In several countries, including the Republic of Korea, nuclear generated electricity is a major contributor to secure and competitive electricity supply. Technological progress aiming towards enhancing safety as well as technical and economic performance of nuclear power plants will enlarge the potential market share of nuclear generated electricity. The purpose of the paper is to give an overview of the prospects for nuclear power development in the world in the medium and long term. For the short term, up to 2005, projections of nuclear power installed capacities are rather straightforward to establish. The Agency publishes such projections every years, based upon a review of nuclear programmes in Member States. For the medium term, up to 2015, two illustrative cases have been developed by the IAEA reflecting contrasted, but not extreme, assumptions on the different parameters influencing nuclear power deployment worldwide. The paper gives estimations of the installed nuclear capacity, and of the share of nuclear power in total electricity and energy

  19. Nuclear fuel cycle and its supply industrial system

    Energy Technology Data Exchange (ETDEWEB)

    Takei, M [Japan Energy Economic Research Inst., Tokyo

    1976-04-01

    This paper discusses problems about the supply and costs of nuclear fuel cycle referring to the discussions of IAEA's Advisory Group Meeting. As for natural uranium resources, prospect is given to the demand, supply, and cost trend up to 2000. As for uranium enrichment, the increasing capacity is compared with the projected demand. The comparison of cost characteristics between diffusion and centrifuge plants is presented with respect to plant scale, investment cost, electric power cost, and operation and maintenance cost. The fabrication cost for fuel is analyzed, and it is suggested that some cost down can be expected for the future. As for the mixed oxide fuel fabrication, the capacity in each country and the estimated fabrication costs for PWR, prototype fast breeder reactor and commercial fast breeder reactor are presented. As for reprocessing, the shortage of supply capacity and the needs for more storage capacity are emphasized. The estimated reprocessing cost for a new plant is also presented. Finally, the present status and future trend of fuel storage in each major country are reviewed.

  20. Analysing long term discursive processes

    DEFF Research Database (Denmark)

    Horsbøl, Anders

    which extend beyond the single interaction, for instance negotiations or planning processes, seems to have played a less important role, with studies such as Iedema 2001 and Wodak 2000 as exceptions. These long term processes, however, are central to the constitution and workings of organizations......What do timescales - the notion that processes take place or can be viewed within a shorter or longer temporal range (Lemke 2005) - mean for the analysis of discourse? What are the methodological consequences of analyzing discourse at different timescales? It may be argued that discourse analysis...... in general has favored either the analysis of short term processes such as interviews, discussions, and lessons, or the analysis of non-processual entities such as (multimodal) texts, arguments, discursive repertoires, and discourses (in a Foucaultian sense). In contrast, analysis of long term processes...

  1. Hydrogen in a global long-term perspective

    International Nuclear Information System (INIS)

    Quakernaat, J.

    1994-01-01

    For many countries, the hydrogen economy offers an operational objective for their long-term energy structure. At the end of the next century, the world will depend on the predominate use of carbon-free and carbon-neutral sources of energy, such as flow energy, energy from modern biomass, and safe nuclear energy. The direct and indirect costs involved in the use of traditional energy supplies will increase sharply in the process of time, so that the economic feasibility of a less intensive use of energy and the introduction of alternative energy supply systems will no longer be insurmountable problems. The supply and demand structures of energy will be optimally blended by the use of hydrogen and electricity, an almost ideal combination of secondary energy carriers. With these carriers, practically every centralized or decentralized, environmentally sound energy supply can be permanently maintained, both within and outside of industrialized, metropolitan areas. The economic development of developing countries will depend on the predominate use of relatively 'cheap' fossil energy carriers (coal, petroleum and natural gas), as well as on the accompanying energy supplies structures. Yet those countries as well, similar to the wealthy industrial countries, will have to start using the highly capital intensive and very energy efficient energy supply systems and energy consumption technologies. This requires innovative strategies that are aimed at compensating developing countries (temporarily) for their lack of purchasing power and knowledge infrastructure. The costs involved in the hydrogen chain are still too high, and the world energy prices are still too low for such a transfer to take place. The attention, however, will focus on drastic energy saving, decarbonization of fossil fuels, substitution to natural gas, the opening up of flow energy, biomass production, and the development of inherent, safe nuclear energy. 49 refs

  2. Long term radioactive waste management

    International Nuclear Information System (INIS)

    Lavie, J.M.

    1984-01-01

    In France, waste management, a sensitive issue in term of public opinion, is developing quickly, and due to twenty years of experience, is now reaching maturity. With the launching of the French nuclear programme, the use of radioactive sources in radiotherapy and industry, waste management has become an industrial activity. Waste management is an integrated system dealing with the wastes from their production to the long term disposal, including their identification, sortage, treatment, packaging, collection and transport. This system aims at guaranteing the protection of present and future populations with an available technology. In regard to their long term management, and the design of disposals, radioactive wastes are divided in three categories. This classification takes into account the different radioisotopes contained, their half life and their total activity. Presently short-lived wastes are stored in the shallowland disposal of the ''Centre de la Manche''. Set up within the French Atomic Energy Commission (CEA), the National Agency for waste management (ANDRA) is responsible within the framework of legislative and regulatory provisions for long term waste management in France [fr

  3. Modeling long-term dynamics of electricity markets

    International Nuclear Information System (INIS)

    Olsina, Fernando; Garces, Francisco; Haubrich, H.-J.

    2006-01-01

    In the last decade, many countries have restructured their electricity industries by introducing competition in their power generation sectors. Although some restructuring has been regarded as successful, the short experience accumulated with liberalized power markets does not allow making any founded assertion about their long-term behavior. Long-term prices and long-term supply reliability are now center of interest. This concerns firms considering investments in generation capacity and regulatory authorities interested in assuring the long-term supply adequacy and the stability of power markets. In order to gain significant insight into the long-term behavior of liberalized power markets, in this paper, a simulation model based on system dynamics is proposed and the underlying mathematical formulations extensively discussed. Unlike classical market models based on the assumption that market outcomes replicate the results of a centrally made optimization, the approach presented here focuses on replicating the system structure of power markets and the logic of relationships among system components in order to derive its dynamical response. The simulations suggest that there might be serious problems to adjust early enough the generation capacity necessary to maintain stable reserve margins, and consequently, stable long-term price levels. Because of feedback loops embedded in the structure of power markets and the existence of some time lags, the long-term market development might exhibit a quite volatile behavior. By varying some exogenous inputs, a sensitivity analysis is carried out to assess the influence of these factors on the long-run market dynamics

  4. Long term testing of PSI-membranes

    Energy Technology Data Exchange (ETDEWEB)

    Huslage, J; Brack, H P; Geiger, F; Buechi, F N; Tsukada, A; Scherer, G G [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1999-08-01

    Long term tests of PSI membranes based on radiation-grafted FEP and ETFE films were carried out and FEP-based membranes were evaluated by monitoring the in-situ membrane area resistance measured by a current pulse method. By modifying our irradiation procedure and using the double crosslinking concept we obtain reproducible membrane cell lifetimes (in term of in-situ membrane resistance) of greater than 5000 hours at 60-65{sup o}C. Preliminary tests at 80-85{sup o}C with lifetimes of greater than 2500 demonstrate the potential long term stability of PSI proton exchange membranes based on FEP over the whole operating temperature range of low-temperature polymer electrolyte fuel cells. Radiation grafted PSI membranes based on ETFE have better mechanical properties than those of the FEP membranes. Mechanical properties are particularly important in large area cells and fuel cell stacks. ETFE membranes have been tested successfully for approximately 1000 h in a 2-cell stack (100 cm{sup 2} active area each cell). (author) 4 figs., 4 refs.

  5. Research on assurance system of nuclear fuel supply (Contract research)

    International Nuclear Information System (INIS)

    Kobayashi, Naoki; Naoi, Yosuke; Wakabayashi, Shuji; Tazaki, Makiko; Senzaki, Masao

    2010-03-01

    Assurance of supply (AOS) of nuclear fuel is a special arrangement in case of nuclear fuel supply disruption caused by political reasons other than nonproliferation. It aims to support a stable supply of nuclear fuel while avoiding unnecessary spread of sensitive enrichment technology. Current discussions on AOS have been initiated by the IAEA Director-General's article published in The Economist entitled 'Towards a Safer World' Oct. 2003. Since then, various proposals on AOS have been presented. In order to facilitate international discussions on AOS, authors have conducted studies of AOS system based on Japanese Government's proposal 'IAEA Standby Arrangement System (INFCIRC/683)'. In this paper, we gave an overview of discussions on AOS since World War II, and elaborated on some of current proposals. We have been able to discuss feasibility of AOS system more specifically by including additional costs and period required for AOS, and to present a system which could work as a practical system. Issues we have tried to tackle here include definitions of AOS, and roles of consumer states, supplier states, IAEA and nuclear industries. We present some solutions including broadening coverage of AOS, declaration by supplier states on AOS, establishing advisory committee in the IAEA on the actual application of AOS, and setting up an IAEA fund for AOS. (author)

  6. Research on assurance system of nuclear fuel supply (Contract research)

    International Nuclear Information System (INIS)

    Kobayashi, Naoki; Naoi, Yosuke; Wakabayashi, Shuji; Tazaki, Makiko; Senzaki, Masao

    2010-08-01

    Assurance of supply (AOS) of nuclear fuel is a special arrangement in case of nuclear fuel supply disruption caused by political reasons other than nonproliferation. It aims to support a stable supply of nuclear fuel while avoiding spread of sensitive enrichment technology. Current discussions on AOS have been initiated by the IAEA Director-General's article published in The Economist entitled 'Towards a Safer World' Oct. 2003. Since then, various proposals on AOS have been presented. In order to facilitate international discussions on AOS, authors have conducted studies of AOS system based on Japanese Government's proposal 'IAEA Standby Arrangement System (INFCIRC/683)'. In this paper, we have been able to discuss feasibility of AOS system more specifically by including additional costs and period required for AOS, and to present a system which could work as a practical system. Issues we have tried to tackle here include definitions of AOS, and roles of consumer States, supplier States, IAEA and nuclear industries. We present some solutions including broadening coverage of AOS, declaration by supplier States on AOS, establishing advisory committee in the IAEA on the actual application of AOS, and setting up an IAEA fund for AOS. (author)

  7. The long-term power purchase: Recovery of capacity costs

    International Nuclear Information System (INIS)

    Cross, P.S.

    1990-01-01

    As electric utilities increase their reliance on the long-term power purchase as an alternative to utility-owned generation, the appropriate rate treatment of the costs established in the purchase agreement assumes growing importance. In the November 9, 1989, issue, the authors examined the recent trend among state regulators to treat the long-term purchase in a manner similar to the addition by a utility of a new plant, including a full-scale prudence review. This installment will review recent rulings on the related issue of rate recovery of long-term capacity costs through the fuel cost adjustment clause

  8. Introduction of long term cycle of reactor operation

    International Nuclear Information System (INIS)

    Aoyati, M.; Tanaka, T.

    2004-01-01

    Introduction of long term cycle of LWR reactor operation at NPP in Japan is considered, and problems of technical, legislative and economical character, increase of power coefficient are discussed. More long term operation period provides decreasing frequency of periodic inspections and reduction of personnel radiation doses. Reliability of fuel, energetic equipment, mechanisms and devices must be taken into account for the decision of technical problems. Consumptions for electric power generation are studied [ru

  9. Architecture Study for a Fuel Depot Supplied from Lunar Assets

    Science.gov (United States)

    Perrin, Thomas M.; Casler, James G.

    2016-01-01

    This architecture study sought to determine the optimum architecture for a fuel depot supplied from lunar assets. Four factors - the location of propellant processing (on the Moon or on the depot), the depot location (on the Moon, L1, GEO, or LEO), the propellant transfer location (L1, GEO, or LEO), and the propellant transfer method (bulk fuel or canister exchange) were combined to identify 18 candidate architectures. Two design reference missions (DRMs) - a commercial satellite servicing mission and a Government cargo mission to Mars - created demand for propellants, while a propellant delivery DRM examined supply issues. The study concluded Earth-Moon L1 is the best location for an orbiting depot. For all architectures, propellant boiloff was less than anticipated, and was far overshadowed by delta-v requirements and resulting fuel consumption. Bulk transfer is the most flexible for both the supplier and customer. However, since canister exchange bypasses the transfer of bulk cryogens and necessary chilldown losses, canister exchange shows promise and merits further investigation. Overall, this work indicates propellant consumption and loss is an essential factor in assessing fuel depot architectures.

  10. Long-term biodosimetry Redux

    International Nuclear Information System (INIS)

    Simon, Steven L.; Bouville, Andre

    2016-01-01

    This paper revisits and reiterates the needs, purposes and requirements of bio-dosimetric assays for long-term dose and health risk assessments. While the most crucial need for bio-dosimetric assays is to guide medical response for radiation accidents, the value of such techniques for improving our understanding of radiation health risk by supporting epidemiological (long-term health risk) studies is significant. As new cohorts of exposed persons are identified and new health risk studies are undertaken with the hopes that studying the exposed will result in a deeper understanding of radiation risk, the value of reliable dose reconstruction is underscored. The ultimate application of biodosimetry in long-term health risk studies would be to completely replace model-based dose reconstruction-a complex suite of methods for retrospectively estimating dose that is commonly fraught with large uncertainties due to the absence of important exposure-related information, as well as imperfect models. While biodosimetry could potentially supplant model-based doses, there are numerous limitations of presently available techniques that constrain their widespread application in health risk research, including limited ability to assess doses received far in the past, high cost, great inter-individual variability, invasiveness, higher than preferred detection limits and the inability to assess internal dose (for the most part). These limitations prevent the extensive application of biodosimetry to large cohorts and should be considered a challenge to researchers to develop new and more flexible techniques that meet the demands of long-term health risk research. Events in recent years, e.g. the Fukushima reactor accident and the increased threat of nuclear terrorism, underscore that any event that results in significant radiation exposures of a group of people will also produce a much larger population, exposed at lower levels, but that likewise needs (or demands) an exposure

  11. Long term stability of power systems

    Energy Technology Data Exchange (ETDEWEB)

    Kundur, P; Gao, B [Powertech Labs. Inc., Surrey, BC (Canada)

    1994-12-31

    Power system long term stability is still a developing subject. In this paper we provide our perspectives and experiences related to long term stability. The paper begins with the description of the nature of the long term stability problem, followed by the discussion of issues related to the modeling and solution techniques of tools for long term stability analysis. Cases studies are presented to illustrate the voltage stability aspect and plant dynamics aspect of long term stability. (author) 20 refs., 11 figs.

  12. ComfortPower - System improvements and long-term evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Silversand, Fredrik [Catator AB, Lund (Sweden)

    2011-11-15

    Catator has previously developed a novel heating system abbreviated ComfortPower in a RandD-programme supported by Catator, Swedish Gas Centre (SGC), Swedish Defence Materiel Administration (FMV), Skanska, Nibe and Alfa Laval. The ComfortPower unit comprises a multi fuel reformer system tied to a high-temperature polymer electrolyte fuel cell (HT-PEM) and a heat pump system. Since the residual heat from the fuel cell system can be utilized in a very effective way, it is possible to reach high thermal efficiencies. Indeed, the thermal efficiency in the unit has previously been shown to reach values as high as 175 - 200 % based on the lower heating value of the fuel. In addition to heat, ComfortPower can supply comfort cooling and surplus electricity. This project phase has focused on the following elements: 1. System improvements to further enhance the efficiency with existing fuel cell (HT-PEM). 2. System simplifications (e.g. DC-compressor system) to manage issues with start-up currents. 3. Tests with biogas qualities (various levels of CO{sub 2}) and biogas/air. 4. Long-term test with biogas quality (upgraded biogas). 5. Additional tests with liquid fuels (alcohols and diesel). 6. Map the need for cooling and heating in various applications. 7. Investigate how ComfortPower can reduce the primary energy consumption and reduce the environmental impact. 8. Study the possibility with a SOFC-based system with internal reforming. It was found that the Optiformer technology can be used to derive a suitable reformate gas for the HT-PEM unit from a wide range of fuels. Even if operation with fuel gases is the natural choice in most cases, it is possible also to use alcohols and other liquid fuels (e.g. in Campus applications). The heat pump system was equipped with a 24 V DC-compressor provided by Nibe. The compressor could be directly powered by the accumulator system and start-up currents, harmful to the inverter, could be avoided. Some improvements were made on the

  13. Navigating Long-Term Care

    Directory of Open Access Journals (Sweden)

    James D. Holt MD

    2017-03-01

    Full Text Available Americans over age 65 constitute a larger percentage of the population each year: from 14% in 2010 (40 million elderly to possibly 20% in 2030 (70 million elderly. In 2015, an estimated 66 million people provided care to the ill, disabled, and elderly in the United States. In 2000, according to the Centers for Disease Control and Prevention (CDC, 15 million Americans used some form of long-term care: adult day care, home health, nursing home, or hospice. In all, 13% of people over 85 years old, compared with 1% of those ages 65 to 74, live in nursing homes in the United States. Transitions of care, among these various levels of care, are common: Nursing home to hospital transfer, one of the best-studied transitions, occurs in more than 25% of nursing home residents per year. This article follows one patient through several levels of care.

  14. Quality assurance program plan fuel supply shutdown project

    International Nuclear Information System (INIS)

    Metcalf, I.L.

    1998-01-01

    This Quality Assurance Program plan (QAPP) describes how the Fuel Supply Shutdown (FSS) project organization implements the quality assurance requirements of HNF-MP-599, Project Hanford Quality Assurance Program Description (QAPD) and the B and W Hanford Company Quality Assurance Program Plan (QAPP), FSP-MP-004. The QAPP applies to facility structures, systems, and components and to activities (e.g., design, procurement, testing, operations, maintenance, etc.) that could affect structures, systems, and components. This QAPP also provides a roadmap of applicable Project Hanford Policies and Procedures (PHPP) which may be utilized by the FSS project organization to implement the requirements of this QAPP

  15. 500 Watt Diesel Fueled TPV Portable Power Supply

    Science.gov (United States)

    Horne, W. E.; Morgan, M. D.; Sundaram, V. S.; Butcher, T.

    2003-01-01

    A test-bed 500 watt diesel fueled thermophotovoltaic (TPV) portable power supply is described. The goal of the design is a compact, rugged field portable unit weighing less than 15 pounds without fuel. The conversion efficiency goal is set at 15% fuel energy to electric energy delivered to an external load at 24 volts. A burner/recuperator system has been developed to meet the objectives of high combustion air preheat temperatures with a compact heat exchanger, low excess air operation, and high convective heat transfer rates to the silicon carbide emitter surface. The burner incorporates a air blast atomizer with 100% of the combustion air passing through the nozzle. Designed firing rate of 2900 watts at 0.07 gallons of oil per hour. This incorporates a single air supply dc motor/fan set and avoids the need for a system air compressor. The recuperator consists of three annular, concentric laminar flow passages. Heat from the combustion of the diesel fuel is both radiantly and convectively coupled to the inside wall of a cylindrical silicon carbide emitter. The outer wall of the emitter then radiates blackbody energy at the design temperature of 1400°C. The cylindrical emitter is enclosed in a quartz envelope that separates it from the photovoltaic (PV) cells. Spectral control is accomplished by a resonant mesh IR band-pass filter placed between the emitter and the PV array. The narrow band of energy transmitted by the filter is intercepted and converted to electricity by an array of GaSb PV cells. The array consists of 216 1-cm × 1-cm GaSb cells arranged into series and parallel arrays. An array of heat pipes couple the PV cell arrays to a heat exchanger which is cooled by forced air convection. A brief status of the key TPV technologies is presented followed by data characterizing the performance of the 500 watt TPV system.

  16. Long term prospects for world gas trade

    International Nuclear Information System (INIS)

    Linder, P.T.

    1991-01-01

    Results are presented from a world gas trade model used to forecast long term gas markets. Assumptions that went into the model are described, including the extent of current proven gas reserves, production ratios, total energy and gas demand, gas supply cost curves for each producing country, available gas liquefaction and transportation facilities, and liquefied natural gas (LNG) shipping costs. The results indicate that even with generally very low supply costs for most gas producing basins, gas trade will continue to be restricted by the relatively high cost of transportation, whether by pipeline or tanker. As a consequence, future gas trade will tend to be regionally oriented. United States gas imports will come mostly from Canada, Venezuela, and Mexico; Western Europe will largely be supplied by the Soviet Union and Africa, and Japan's requirements will generally be met by Pacific Rim producers. Although the Middle East has vast quantities of gas reserves, its export growth will continue to be hampered by its remote location from major markets. 16 figs

  17. Laboratory Testing of Solar Combi System with Compact Long Term PCM Heat Storage

    DEFF Research Database (Denmark)

    Johansen, Jakob Berg; Englmair, Gerald; Dannemand, Mark

    2016-01-01

    To enable the transition from fossil fuels as a primary heat source for domestic hot water preparation and space heating solar thermal energy has great potential. The heat from the sun has the disadvantage that it is not always available when there is a demand. To solve this mismatch a thermal...... seasonal storage can be used to store excess heat from the summer to the winter when the demand is higher than the supply. Installing a long term thermal storage in a one family house it needs to be compact and sensible heat storages are not suitable. A latent heat storage with a phase change material (PCM...

  18. Air/fuel supply system for use in a gas turbine engine

    Science.gov (United States)

    Fox, Timothy A; Schilp, Reinhard; Gambacorta, Domenico

    2014-06-17

    A fuel injector for use in a gas turbine engine combustor assembly. The fuel injector includes a main body and a fuel supply structure. The main body has an inlet end and an outlet end and defines a longitudinal axis extending between the outlet and inlet ends. The main body comprises a plurality of air/fuel passages extending therethrough, each air/fuel passage including an inlet that receives air from a source of air and an outlet. The fuel supply structure communicates with and supplies fuel to the air/fuel passages for providing an air/fuel mixture within each air/fuel passage. The air/fuel mixtures exit the main body through respective air/fuel passage outlets.

  19. Supplying the six. [Supplies of nuclear fuels and ores to the European Community

    Energy Technology Data Exchange (ETDEWEB)

    Oboussier, F

    1975-07-01

    Under the Euratom Treaty, the European Community must ensure that all users in the Community receive a regular and equitable supply of ores and nuclear fuels. Supply to users in the Community of ores, source materials, and special fissile materials is based on the principle of equal access of the users to the supply sources. To ensure such equal access, the Treaty prohibits all practices designed to secure a privileged position for certain users. In addition, an agency has been set up with two essential rights--that of an option on all ores, source materials, and special fissile materials produced in the territories of the Member States; and the exclusive right to conclude all contracts relating to the supply of ores, source materials, and special fissile materials coming from inside the Community or from outside. Dealings of the Agency with outside agencies, especially the former US AEC, are described. The uranium market and its economics and the availability of special fissile materials are summarized. (MCW)

  20. Performance of fuel cell for energy supply of passive house

    Energy Technology Data Exchange (ETDEWEB)

    Badea, G.; Felseghi, R. A., E-mail: Raluca.FELSEGHI@insta.utcluj.ro; Mureşan, D.; Naghiu, G. [Technical University of Cluj-Napoca, Building Services Engineering Department, Bd. December 21, no. 128-130, 400600, Cluj-Napoca (Romania); Răboacă, S. M. [National R& D Institute for Cryogenic and Isotopic Technologies, str. Uzinei, no. 4, Rm. Vălcea, 240050 (Romania); Aşchilean, I. [SC ACI Cluj SA, Avenue Dorobanţilor, no. 70, 400609, Cluj-Napoca (Romania)

    2015-12-23

    Hydrogen technology and passive house represent two concepts with a remarkable role for the efficiency and decarbonisation of energy systems in the residential buildings area. Through design and functionality, the passive house can make maximum use of all available energy resources. One of the solutions to supply energy of these types of buildings is the fuel cell, using this technology integrated into a system for generating electricity from renewable primary sources, which take the function of backup power (energy reserve) to cover peak load and meteorological intermittents. In this paper is presented the results of the case study that provide an analysis of the energy, environmental and financial performances regarding energy supply of passive house by power generation systems with fuel cell fed with electrolytic hydrogen produced by harnessing renewable energy sources available. Hybrid systems have been configured and operate in various conditions of use for five differentiated locations according to the main areas of solar irradiation from the Romanian map. Global performance of hybrid systems is directly influenced by the availability of renewable primary energy sources - particular geo-climatic characteristics of the building emplacement.

  1. Long term study of mechanical

    Directory of Open Access Journals (Sweden)

    Ahmed M. Diab

    2016-06-01

    Full Text Available In this study, properties of limestone cement concrete containing different replacement levels of limestone powder were examined. It includes 0%, 5%, 10%, 15%, 20% and 25% of limestone powder as a partial replacement of cement. Silica fume was added incorporated with limestone powder in some mixes to enhance the concrete properties. Compressive strength, splitting tensile strength and modulus of elasticity were determined. Also, durability of limestone cement concrete with different C3A contents was examined. The weight loss, length change and cube compressive strength loss were measured for concrete attacked by 5% sodium sulfate using an accelerated test up to 525 days age. The corrosion resistance was measured through accelerated corrosion test using first crack time, cracking width and steel reinforcement weight loss. Consequently, for short and long term, the use of limestone up to 10% had not a significant reduction in concrete properties. It is not recommended to use blended limestone cement in case of sulfate attack. The use of limestone cement containing up to 25% limestone has insignificant effect on corrosion resistance before cracking.

  2. Long-term competence restoration.

    Science.gov (United States)

    Morris, Douglas R; DeYoung, Nathaniel J

    2014-01-01

    While the United States Supreme Court's Jackson v. Indiana decision and most state statutes mandate determinations of incompetent defendants' restoration probabilities, courts and forensic clinicians continue to lack empirical evidence to guide these determinations and do not yet have a consensus regarding whether and under what circumstances incompetent defendants are restorable. The evidence base concerning the restoration likelihood of those defendants who fail initial restoration efforts is even further diminished and has largely gone unstudied. In this study, we examined the disposition of a cohort of defendants who underwent long-term competence restoration efforts (greater than six months) and identified factors related to whether these defendants were able to attain restoration and adjudicative success. Approximately two-thirds (n = 52) of the 81 individuals undergoing extended restoration efforts were eventually deemed restored to competence. Lengths of hospitalization until successful restoration are presented with implications for the reasonable length of time that restoration efforts should persist. Older individuals were less likely to be restored and successfully adjudicated, and individuals with more severe charges and greater factual legal understanding were more likely to be restored and adjudicated. The significance of these findings for courts and forensic clinicians is discussed.

  3. Long-term corrosion studies

    International Nuclear Information System (INIS)

    Gdowski, G.

    1998-01-01

    The scope of this activity is to assess the long-term corrosion properties of metallic materials under consideration for fabricating waste package containers. Three classes of metals are to be assessed: corrosion resistant, intermediate corrosion resistant, and corrosion allowance. Corrosion properties to be evaluated are general, pitting and crevice corrosion, stress-corrosion cracking, and galvanic corrosion. The performance of these materials will be investigated under conditions that are considered relevant to the potential emplacement site. Testing in four aqueous solutions, and vapor phases above them, and at two temperatures are planned for this activity. (The environmental conditions, test metals, and matrix are described in detail in Section 3.0.) The purpose and objective of this activity is to obtain the kinetic and mechanistic information on degradation of metallic alloys currently being considered for waste package containers. This information will be used to provide assistance to (1) waste package design (metal barrier selection) (E-20-90 to E-20-92), (2) waste package performance assessment activities (SIP-PA-2), (3) model development (E-20-75 to E-20-89). and (4) repository license application

  4. Long-Term Stability of Anode-Supported Solid Oxide Fuel Cells with a Co-Sintered Cathode Backbone and Infiltrated La0.95Co0.4Ni0.6O3 (LCN) Electro-Catalyst

    DEFF Research Database (Denmark)

    Küngas, Rainer; Veltzé, Sune; Ovtar, Simona

    2016-01-01

    Infiltration is a fabrication method that is offering potentially significant improvements in cell performance at reduced materials and fabrication costs, especially when combined with co-sintering. However, important questions regarding the long-term performance and microstructural stability of ...

  5. Impact of Multilateral Approaches for Assurances of Nuclear Fuel Supply

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Han Myung; Lee, B. W.; Ko, H. S.; Ryu, J. S.; Yang, M. H.; Oh, K. B.; Lee, K. S

    2007-12-15

    This study consists of 3 parts : analysis of the characteristics of the recent proposals for a nuclear fuel supply and the progress of them, responses from various sectors in the world, and measures for them. In response to recent proposals, majority of countries possessing sensitive nuclear fuel facilities are supportive in general. In contrast, many countries not possessing such facilities are reluctant about the proposals. To satisfy both parties, an ideal proposal could suggest measures to assure a non-proliferation as well as measures to acquire confidence from the so-called user nations. To get strong support from all countries concerned, the proposal should contain some critical elements such as clear attractiveness for a participation, equal opportunities for the participating countries, voluntarily in decision on a participation, and a gradual approach to remove any future obstacles encountered. The criteria to judge a legitimate need of a country for the introduction of nuclear fuel facilities should be prepared by a consensus. Compliance of a nonproliferation obligation, scale of an economy, and an energy security can be proposed as such criteria.

  6. Impact of Multilateral Approaches for Assurances of Nuclear Fuel Supply

    International Nuclear Information System (INIS)

    Lee, Han Myung; Lee, B. W.; Ko, H. S.; Ryu, J. S.; Yang, M. H.; Oh, K. B.; Lee, K. S.

    2007-12-01

    This study consists of 3 parts : analysis of the characteristics of the recent proposals for a nuclear fuel supply and the progress of them, responses from various sectors in the world, and measures for them. In response to recent proposals, majority of countries possessing sensitive nuclear fuel facilities are supportive in general. In contrast, many countries not possessing such facilities are reluctant about the proposals. To satisfy both parties, an ideal proposal could suggest measures to assure a non-proliferation as well as measures to acquire confidence from the so-called user nations. To get strong support from all countries concerned, the proposal should contain some critical elements such as clear attractiveness for a participation, equal opportunities for the participating countries, voluntarily in decision on a participation, and a gradual approach to remove any future obstacles encountered. The criteria to judge a legitimate need of a country for the introduction of nuclear fuel facilities should be prepared by a consensus. Compliance of a nonproliferation obligation, scale of an economy, and an energy security can be proposed as such criteria

  7. North American long-term soil productivity research program

    Science.gov (United States)

    Allan E. Tiarks; Robert F. Powers; Jerry F. Ragus; Deborah S. Page-Dumroese; Felix Ponder; Douglas M. Stone

    1997-01-01

    The National Long-term Soil Productivity research program was chartered to address National Forest Management Act concerns over possible losses n soil productivity on national forest lands. The program supports validation of soil quality monitoring standards and process-level productivity research. Summarized results are supplied to forests as collected. National...

  8. The long term agroecosystem research network - shared research strategy

    Science.gov (United States)

    Jean L. Steiner; Timothy Strickland; Peter J.A. Kleinman; Kris Havstad; Thomas B. Moorman; M.Susan Moran; Phil Hellman; Ray B. Bryant; David Huggins; Greg McCarty

    2016-01-01

    While current weather patterns and rapidly accelerated changes in technology often focus attention on short-term trends in agriculture, the fundamental demands on modern agriculture to meet society food, feed, fuel and fiber production while providing the foundation for a healthy environment requires long-term perspective. The Long- Term Agroecoystem Research Network...

  9. Strategies for fuel cell product development. Developing fuel cell products in the technology supply chain

    International Nuclear Information System (INIS)

    Hellman, H.L.

    2004-01-01

    Due to the high cost of research and development and the broad spectrum of knowledge and competences required to develop fuel cell products, many product-developing firms outsource fuel cell technology, either partly or completely. This article addresses the inter-firm process of fuel cell product development from an Industrial Design Engineering perspective. The fuel cell product development can currently be characterised by a high degree of economic and technical uncertainty. Regarding the technology uncertainty: product-developing firms are more often then not unfamiliar with fuel cell technology technology. Yet there is a high interface complexity between the technology supplied and the product in which it is to be incorporated. In this paper the information exchange in three current fuel cell product development projects is analysed to determine the information required by a product designer to develop a fuel cell product. Technology transfer literature suggests that transfer effectiveness is greatest when the type of technology (technology uncertainty) and the type of relationship between the technology supplier and the recipient are carefully matched. In this line of thinking this paper proposes that the information required by a designer, determined by the design strategy and product/system volume, should be met by an appropriate level of communication interactivity with a technology specialist. (author)

  10. Long term radiological impact of thorium extraction

    International Nuclear Information System (INIS)

    Menard, S.; Schapira, J.P.

    1995-01-01

    Thorium extraction produces a certain amount of radioactive wastes. Potential long term radiological impact of these residues has been calculated using the recent ICRP-68 ingestion dose factors in connection with the computing code DECAY, developed at Orsay and described in this work. This code solves the well known Bateman's equations which govern the time dependence of a set of coupled radioactive nuclei. Monazites will be very likely the minerals to be exploited first, in case of an extensive use of thorium as nuclear fuel. Because monazites contain uranium as well, mining residues will contain not only the descendants of 232 Th and a certain proportion of non-extracted thorium (taken here to be 5%), but also this uranium, if left in the wastes for economical reasons. If no uranium would be present at all in the mineral, the potential radiotoxicity would strongly decrease in approximately 60 years, at the pace of the 5.8 years period of 228 Ra, which becomes the longest-lived radionuclide of the 4n radioactive family in the residues. Moreover, there is no risk due to radon exhalation, because of the very short period of 220 Rn. These significant differences between uranium and thorium mining have to be considered in view of some estimated long term real radiological impacts due to uranium residues, which could reach a value of the order of 1 mSv/year, the dose limit recommended for the public by the recent ICRP-60. (authors). 15 refs., 4 figs., 3 tabs., 43 appendices

  11. Options: the value of flexibilities in long term uranium contracts

    International Nuclear Information System (INIS)

    Major-Sosias, M.A.

    1996-01-01

    It has been commonplace for uranium suppliers to offer utilities long-term contracts with significant quantity flexibilities. These are attractive to the utility for which the consumption of fuel is dependent on variable reactor performance and have given the suppliers an additional competitive tool. The return to a uranium market in which near-term supply is likely to be tight is a disincentive to suppliers to offer new contracts with flexibilities. Typical recent flexibility offers have been significantly less generous than in the past. A methodology is outlined which can be used to give a theoretical estimate of the value of the flexibility provision to the supplier and buyer. It is based on the similarity between flexibility provision and option contracts in the securities and commodity markets. By regarding flexibilities as ''embedded options'' it is possible to apply to them the Black-Scholes option pricing formula as long as the necessary inputs, such as the price of uranium, the loan rate and the volatility, are available. The formula does have its shortfalls, however; in particular, it cannot incorporate the political perturbations that are continually taking place in the uranium industry. (13 figures, 15 references). (UK)

  12. Long-term scenarios for sustainable energy use in Germany

    International Nuclear Information System (INIS)

    Fischedick, M.; Nitsch, J.; Lechtenboehmer, S.; Hanke, T.; Barthel, C.; Jungbluth, C.; Assmann, D.; Brueggen, T. vor der; Trieb, F.; Nast, M.; Langniss, O.; Brischke, L.A.

    2002-01-01

    The study was able to show, and explain vividly through scenarios describing change processes, that a sustainable use of energy (aimed, among other things, at reducing CO 2 emissions by 80% by 2050 compared with 1990 levels) is technically feasible, economically viable, compatible with farther-reaching objectives of energy policy (e.g. supply security), and does not, in spite of the substantial need for change, present the players involved with any insurmountable problems but, rather, constitutes both a challenge and an opportunity. Such a development is possible only if the efforts launched to give momentum to the increased use of renewable energy sources are continued consistently, the impending need for replacement and renewal within the generation system is consistently utilised for increasing efficiency and a reorientation mainly towards combined heat and power production, and energy saving is made a new focal point of energy policy. Furthermore, with regard to long-term infrastructure requirements (decentralisation, new fuels), the necessary decisions must be prepared at an early stage and sufficiently robust lines of development must be identified and followed. (orig.) [de

  13. Long-term trends in U.S. gas transportation: 1992 edition of the GRI baseline projection of U.S. energy supply and demand to 2010, June 1992. Gas Research Insights

    International Nuclear Information System (INIS)

    Lihn, M.L.; Woods, T.J.

    1992-06-01

    The paper summarizes the trends in lower-48 gas transportation in the 1992 Edition of the GRI Baseline Projection of U.S. Energy Supply and Demand to 2010, which has been adopted as a major input to the planning cycle leading to the development of the Gas Research Institute (GRI) 1993 research and development program. The 1992 projection presents an optimistic outlook for the U.S. gas industry in which increased gas supply can be obtained at competitive prices

  14. Possibility of hydrogen supply by shared residential fuel cell systems for fuel cell vehicles

    Directory of Open Access Journals (Sweden)

    Ono Yusuke

    2017-01-01

    Full Text Available Residential polymer electrolyte fuel cells cogeneration systems (residential PEFC systems produce hydrogen from city gas by internal gas-reformer, and generate electricity, the hot water at the same time. From the viewpoint of the operation, it is known that residential PEFC systems do not continuously work but stop for long time, because the systems generate enough hot water for short operation time. In other words, currently residential PEFC systems are dominated by the amount of hot water demand. This study focuses on the idle time of residential PEFC systems. Since their gas-reformers are free, the systems have potential to produce hydrogen during the partial load operations. The authors expect that residential PEFC systems can take a role to supply hydrogen for fuel cell vehicles (FCVs before hydrogen fueling stations are distributed enough. From this perspective, the objective of this study is to evaluate the hydrogen production potential of residential PEFC systems. A residential PEFC system was modeled by the mixed integer linear programming to optimize the operation including hydrogen supply for FCV. The objective function represents annual system cost to be minimized with the constraints of energy balance. It should be noted that the partial load characteristics of the gas-reformer and the fuel cell stack are taken into account to derive the optimal operation. The model was employed to estimate the possible amount of hydrogen supply by a residential PEFC system. The results indicated that the system could satisfy at least hydrogen demand for transportation of 8000 km which is as far as the average annual mileage of a passenger car in Japan. Furthermore, hydrogen production by sharing a residential PEFC system with two households is more effective to reduce primary energy consumption with hydrogen supply for FCV than the case of introducing PEFC in each household.

  15. Long-term scenarios and strategies for the deployment of renewable energies in Germany

    International Nuclear Information System (INIS)

    Pregger, Thomas; Nitsch, Joachim; Naegler, Tobias

    2013-01-01

    The transformation of the energy supply in Germany (the “Energiewende”) as described in the German Federal government’s ‘Energy Concept’ (Energiekonzept, 2010) is based on a political consensus about long-term targets for energy efficiency and renewable energies. The aim of this article is to present a consistent scenario for this transformation process reflecting the long-term implementation of renewable energies and the possible future structure of the German energy system as a whole. Structural and economic effects of this development are derived and discussed. It summarizes results of scenario analyses done by the department of Systems Analysis and Technology Assessment of the German Aerospace Center as part of a three-year research project for the German Federal Ministry for the Environment. The underlying study provides a detailed data base reflecting a long-term roadmap for the energy system transformation in Germany. The scenarios show that the policy targets are consistent and can be achieved, if appropriate policy measures are to be implemented. The economic analysis shows the amount of investments and the strong market dynamics required for new generation technologies but also the huge economic benefits that can result from this development path in terms of fuel cost savings and lower fuel imports. - Highlights: • Long-term scenario for the German energy system according to the political targets. • Comparison of three variants with differing developments of the fleets of vehicles. • Analysis of economic effects: investments, generation and differential costs. • Importance of strategies in the sectors electricity, heat, and transportation. • Recommended measures for the successful implementation of the CO 2 reductions

  16. Opening remarks for a panel discussion on short-term vs long-term procurement

    International Nuclear Information System (INIS)

    Courtenay, R.H.

    1990-01-01

    Long-term contracting in the late 1970's and early 1980's is blamed for some of the inequities that plague the uranium industry today. Utilities are obliged to pay prices far above prevailing levels and relatively low cost producers are forced to shut down while watching less efficient suppliers stay in business thanks to their long term supply agreements. Furthermore, it is argued that long-term contracts have contributed to supply instability by forcing the buildup of surplus inventories and by supporting excess incremental production by suppliers who have a baseload of long-term contracts. The depressed prices resulting from this oversupply are in turn jeopardizing future resource development and damaging supply reliability. In summary, the author's argument is that supply reliability will be greatly enhanced by the assurance of adequate primary supply from traditional sources such as Canada. This will not happen without long-term contracts. This conclusion may not be expected coming from a representative of Canada's largest uranium producer. But the final comment is less self serving. Many of the critics of long term contracts apparently expect a continuing and plentiful supply of East Bloc uranium to the spot market. A further question is to what extent East Bloc suppliers will eventually require long-term contracts in order to maintain production facilitates in economies that are no longer centrally planned, and where there is open competition for capital. Ultimately, reliability of supply from the non-traditional suppliers may also depend on long-term contracts

  17. The long-term outlook for nuclear capacity in Ontario

    International Nuclear Information System (INIS)

    Archinoff, G.H.

    1979-04-01

    This report derives three estimates of long-term nuclear growth in Ontario for use in strategy studies of alternate nuclear fuel cycles. The low and high estimates encompass the full range of possible long-term nuclear growth rates. The middle, or base growth, estimate represents the nuclear growth pattern which seems at the present time most likely to occur. For the base growth estimate, nuclear capacity in Ontario reaches 31 GWe in 2000, grows to 175 GWe by 2060, and then remains constant. For the high growth estimate, the capacity in 2000 is 33 GWe, and climbs continuously to 833 GWe by the year 2100. (auth)

  18. The long-term nuclear explosives predicament

    International Nuclear Information System (INIS)

    Swahn, J.

    1992-01-01

    A scenario is described, where the production of new military fissile materials is halted and where civil nuclear power is phased out in a 'no-new orders' case. It is found that approximately 1100 tonnes of weapons-grade uranium, 233 tonnes of weapons-grade plutonium and 3795 tonnes of reactor-grade plutonium have to be finally disposed of as nuclear waste. This material could be used for the construction of over 1 million nuclear explosives. Reactor-grade plutonium is found to be easier to extract from spent nuclear fuel with time and some physical characteristics important for the construction of nuclear explosives are improved. Alternative methods for disposal of the fissile material that will avoid the long-term nuclear explosives predicament are examined. Among these methods are dilution, denaturing or transmutation of the fissile material and options for practicably irrecoverable disposal in deep boreholes, on the sea-bed, and in space. It is found that the deep boreholes method for disposal should be the primary alternative to be examined further. This method can be combined with an effort to 'forget' where the material was put. Included in the thesis is also an evaluation of the possibilities of controlling the limited civil nuclear activities in a post-nuclear world. Some surveillance technologies for a post-nuclear world are described, including satellite surveillance. In a review part of the thesis, methods for the production of fissile material for nuclear explosives are described, the technological basis for the construction of nuclear weapons is examined, including use of reactor-grade plutonium for such purposes; also plans for the disposal of spent fuel from civil nuclear power reactors and for the handling of the fissile material from dismantled warheads is described. The Swedish plan for the handling and disposal of spent nuclear fuel is described in detail. (490 refs., 66 figs., 27 tabs.)

  19. Basis for Interim Operation for Fuel Supply Shutdown Facility

    International Nuclear Information System (INIS)

    BENECKE, M.W.

    2003-01-01

    This document establishes the Basis for Interim Operation (BIO) for the Fuel Supply Shutdown Facility (FSS) as managed by the 300 Area Deactivation Project (300 ADP) organization in accordance with the requirements of the Project Hanford Management Contract procedure (PHMC) HNF-PRO-700, ''Safety Analysis and Technical Safety Requirements''. A hazard classification (Benecke 2003a) has been prepared for the facility in accordance with DOE-STD-1027-92 resulting in the assignment of Hazard Category 3 for FSS Facility buildings that store N Reactor fuel materials (303-B, 3712, and 3716). All others are designated Industrial buildings. It is concluded that the risks associated with the current and planned operational mode of the FSS Facility (uranium storage, uranium repackaging and shipment, cleanup, and transition activities, etc.) are acceptable. The potential radiological dose and toxicological consequences for a range of credible uranium storage building have been analyzed using Hanford accepted methods. Risk Class designations are summarized for representative events in Table 1.6-1. Mitigation was not considered for any event except the random fire event that exceeds predicted consequences based on existing source and combustible loading because of an inadvertent increase in combustible loading. For that event, a housekeeping program to manage transient combustibles is credited to reduce the probability. An additional administrative control is established to protect assumptions regarding source term by limiting inventories of fuel and combustible materials. Another is established to maintain the criticality safety program. Additional defense-in-depth controls are established to perform fire protection system testing, inspection, and maintenance to ensure predicted availability of those systems, and to maintain the radiological control program. It is also concluded that because an accidental nuclear criticality is not credible based on the low uranium enrichment

  20. Long-term plutonium storage: Design concepts

    International Nuclear Information System (INIS)

    Wilkey, D.D.; Wood, W.T.; Guenther, C.D.

    1994-01-01

    An important part of the Department of Energy (DOE) Weapons Complex Reconfiguration (WCR) Program is the development of facilities for long-term storage of plutonium. The WCR design goals are to provide storage for metals, oxides, pits, and fuel-grade plutonium, including material being held as part of the Strategic Reserve and excess material. Major activities associated with plutonium storage are sorting the plutonium inventory, material handling and storage support, shipping and receiving, and surveillance of material in storage for both safety evaluations and safeguards and security. A variety of methods for plutonium storage have been used, both within the DOE weapons complex and by external organizations. This paper discusses the advantages and disadvantages of proposed storage concepts based upon functional criteria. The concepts discussed include floor wells, vertical and horizontal sleeves, warehouse storage on vertical racks, and modular storage units. Issues/factors considered in determining a preferred design include operational efficiency, maintenance and repair, environmental impact, radiation and criticality safety, safeguards and security, heat removal, waste minimization, international inspection requirements, and construction and operational costs

  1. Moisture management, energy density and fuel quality in forest fuel supply chains

    Energy Technology Data Exchange (ETDEWEB)

    Tahvanainen, T. [Joensuu Science Park Ltd., Joensuu (Finland); Sikanen, L. [Joensuu Univ. (Finland); Roser, D. [Finnish Forest Research Inst., Joensuu (Finland)

    2009-07-01

    This presentation provided tools for reducing the moisture content (MC) in wood chips, as moisture is one of the main quality factors for woody biomass, along with energy density and cleanness. The amount of water in solid wood fuels has a considerable effect on transportation efficiency, combustion efficiency and emissions. Under favourable storage conditions, MC can be decreased from typical fresh cut 50-55 per cent to 20-30 per cent in relatively short periods of storing by natural or artificial drying. Minor modifications can boost natural drying in fuel wood supply chains. This natural drying effect can have significant effects on the total energy efficiency and emissions of supply chains. The effect of improved packing density on transportation phase was discussed along with the need to control chip purity and size distribution. A procedure developed at the University of Joensuu and in the Finnish Forest Research Institute was used to estimate transportation costs and emissions according to transportation fleet and MC of the transported fuel. tabs., figs.

  2. A Long-term Plan for Kalk

    DEFF Research Database (Denmark)

    2017-01-01

    In this case, the author demonstrates together with the owner-manager of KALK A/S, Mr Rasmus Jorgensen, how to use the Family Business Map to frame a constructive discussion about long-term planning. The Family Business Map is a tool for long-term planning in family firms developed by Professor...

  3. Virtual Models of Long-Term Care

    Science.gov (United States)

    Phenice, Lillian A.; Griffore, Robert J.

    2012-01-01

    Nursing homes, assisted living facilities and home-care organizations, use web sites to describe their services to potential consumers. This virtual ethnographic study developed models representing how potential consumers may understand this information using data from web sites of 69 long-term-care providers. The content of long-term-care web…

  4. Medium and Long Term Natural Gas Outlook - February 2015

    International Nuclear Information System (INIS)

    Lecarpentier, Armelle

    2015-02-01

    World natural gas demand is expected to grow by 1.8%/year over 2013- 2035. Asia-Oceania explains 42% of the incremental demand (China: 28%), followed by the Middle East (24%). Natural gas share in world primary energy supply is projected to increase from an estimated 21.3% in 2013 to 23.6% in 2035 to the detriment of other fossil fuels. Although the expansion of gas demand is spread across all of the main consuming sectors, gas-fired power generation remains the largest contributor to growth. Natural gas production is growing everywhere, with the exception of Europe (-2.1%/year). The largest regional production gains are expected in Asia Oceania, the Middle East and North America. Shale gas will provide one third of the incremental natural gas supply by 2035. In the US, shale gas production will account for 56% of national output by 2035, versus 44% in 2013. Net inter-regional trade is forecast to grow by 3.1%/year to 821 bcm by 2035. The CIS will record the largest volumetric growth in net exports (+ 191 bcm). The share of LNG in net inter-regional flows will increase from 46% in 2013 to 50% in 2035. The international LNG market is expected to tighten after 2020. The price differentials between the US, Europe and Japan will narrow in a context of globalization of gas markets via a strong expansion of the LNG trade (flexible LNG). A number of powerful factors argue in favour of a growing contribution of natural gas to meet the economic, environmental and security challenges of the world energy system. In terms of supply, costly investments must be made to meet future demand, limit tensions on international markets and favour supply security, flexibility and diversification. Despite a growing component of spot indexing in pricing formulas, oil indexing (Asia) and long term contracts will remain necessary to meet the massive investment requirements in new and capital-intensive projects. The competitiveness of natural gas remains a major challenge. The orientation of

  5. Long term plan of atomic energy development and utilization

    International Nuclear Information System (INIS)

    1982-01-01

    The atomic energy utilization and development in Japan have progressed remarkably, and already nuclear power generation has borne an important part in electric power supply, while radiation has been utilized in the fields of industry, agriculture, medicine and so on. Now, atomic energy is indispensable for national life and industrial activity. The former long term plan was decided in September, 1978, and the new long term plan should be established since the situation has changed largely. The energy substituting for petroleum has been demanded, and the expectation to nuclear power generation has heightened because it enables stable and economical power supply. The independently developed technology related to atomic energy must be put in practical use. The peaceful utilization of atomic energy must be promoted, while contributing to the nuclear non-proliferation policy. The Atomic Energy Commission of Japan decided the new long term plan to clearly show the outline of the important measures related to atomic energy development and utilization in 10 years hereafter, and the method of its promotion. The basic concept of atomic energy development and utilization, the long term prospect and the concept on the promotion, the method of promoting the development and utilization, and the problems of funds, engineers and location are described. (kako, I.)

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

    International Nuclear Information System (INIS)

    2005-01-01

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

  7. Japan’s Long-term Energy Demand and Supply Scenario to 2050 – Estimation for the Potential of Massive CO2 Mitigation

    OpenAIRE

    Ryoichi Komiyama; Chris Marnay; Michael Stadler; Judy Lai; Sam Borgeson; Brian Coffey; Inês Lima Azevedo

    2009-01-01

    In this analysis, we projected Japans energy demand/supply and energy-related CO2 emissions to 2050. Our analysis of various scenarios indicated that Japans CO2 emissions in 2050 could be potentially reduced by 26-58% from the current level (FY 2005) (Figure 1). These results suggest that Japan could set a CO2 emission reduction target for 2050 at between 30% and 60%. In order to reduce CO2 emissions by 60% in 2050 from the present level, Japan will have to strongly promote energy conservatio...

  8. FUEL SUPPLY IN ACCUMULATOR DIESEL SYSTEMS WITH ELECTRONIC CONTROL AT STARTING REGIME

    Directory of Open Access Journals (Sweden)

    G. M. Kuharenok

    2009-01-01

    Full Text Available The paper contains review and analysis of fuel supply process in accumulator diesel systems with electronic control at starting regime. The necessity has been shown to  develop and use programs of mathematic simulation pertaining to fuel supply processes with the purpose to decrease number of bench tests and time period required for a fuel system adaptation. The paper cites results of practical investigations on starting engines  equipped with the mentioned-above systems.

  9. Fuel supply investment cost: coal and nuclear. Commercial electric power cost studies (6)

    International Nuclear Information System (INIS)

    1979-04-01

    This study presents an accounting model for calculating the capital investment requirements for coal and nuclear fuel supply facilities. The study addresses mining, processing, fabrication, and transportation of coal and nuclear fuels. A generic example is provided, for coal from different sources, and for nuclear fuel. The relationship of capital investment requirements to delivered prices is included in each example

  10. Integrated scheme of long-term for spent fuel management of power nuclear reactors; Esquema integrado de largo plazo para la administracion de combustible gastado de reactores nucleares de potencia

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez S, J. R.; Palacios H, J. C.; Martinez C, E., E-mail: ramon-ramirez@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2015-09-15

    After of irradiation of the nuclear fuel in the reactor core, is necessary to store it for their cooling in the fuel pools of the reactor. This is the first step in a processes series before the fuel can reach its final destination. Until now there are two options that are most commonly accepted for the end of the nuclear fuel cycle, one is the open nuclear fuel cycle, requiring a deep geological repository for the fuel final disposal. The other option is the fuel reprocessing to extract the plutonium and uranium as valuable materials that remaining in the spent fuel. In this study the alternatives for the final part of the fuel cycle, which involves the recycling of plutonium and the minor actinides in the same reactor that generated them are shown. The results shown that this is possible in a thermal reactor and that there are significant reductions in actinides if they are recycled into reactor fuel. (Author)

  11. Evaluation of nuclear power development scenarios in romania envisaging the long-term national energy sustainability

    International Nuclear Information System (INIS)

    Margeanu, C.; Apostol, M.; Visan, I.; Prodea, I.

    2015-01-01

    The paper summarizes the results of RATEN ICN Pitesti experts' activities in the IAEA's Collaborative Project INPRO-SYNERGIES. Romanian study proposes to evaluate and analyze development of the nuclear capacity and increasing of its share in national energy sector, envisaging the long term national and regional energy sustainability by keeping options open for the future while bringing solutions to short/medium-term challenges. The study focused on the modelling of national NES (Nuclear Energy System) development on short and medium-term (time horizon 2050), considering the existing NFC (Nuclear Fuel Cycle) infrastructure and legislation, provisions of strategic documents in force and including also the possibility of regional collaboration regarding U/fresh fuel supply and SF (Spent Fuel) storage, as services provided at international market prices. The energy system modelling was realized by using the IAEA's MESSAGE program. The study results offer a clear image and also the possible answer to several key questions regarding: potential of nuclear energy to participate with an important share in national energy mix, in conditions of cost competitiveness, safety and security of supply; impact on national energy mix portfolio of capacities and electricity production; impact on Uranium domestic resources; economic projection/investments needed for new nuclear capacities addition; fresh fuel requirements for nuclear capacities; SF annually discharged and transferred to interim wet storage for cooling; SF volume in interim dry storage, etc. (authors)

  12. A basic strategy for financing long term care.

    Science.gov (United States)

    Greenberg, J A; Leutz, W N

    1984-02-01

    As pressure mounts to contain Medicaid long term care spending, short-range "quick fixes" must be avoided. Three such false solutions in particular have shortcomings that may actually exacerbate long term care's financial dilemma because they are based on inadequate definitions of the problem. Two of these proposals--legislation to broaden family responsibility toward institutionalized elders on Medicaid and expanded state power to put liens on such elders' real property--err by trying to mandate "caring" and are predicated on a misunderstanding of the "spend-down" problem. The other proposal--to provide tax incentives to family members who care for elders--requires a large administrative apparatus, assumes an elasticity of supply that may not exist, and could disrupt the "gift relationship" on which family exchanges are often based. What is needed is a strategy with short term, intermediate, and long term objectives that move toward an insurance approach. The short term plan should lay the groundwork for intermediate strategy and control costs by changing rate-setting methods and putting limits on facility construction. The intermediate plan should change the problem's definition from one of merely controlling Medicaid long term care expenditures to one of efficiently managing state resources for the elderly through the development of state financing and local delivery systems that target older persons in greatest need. An effective means of doing this is through the creation of social/HMOs, which have five key features: integration of service responsibility and authority; flexibility in organizational design; balanced clientele; pooled prepaid funding; and financial risk for the provider organization. Finally, the long term strategy should transfer much of the long term care financial burden from individuals and state Medicaid agencies to insurance mechanisms. Many individuals would thus avoid impoverishment caused by health care spending and Medicaid would

  13. Long-term development of the Swedish market of energy wood

    Energy Technology Data Exchange (ETDEWEB)

    Dickens, C H

    1980-03-01

    The aim of the report is to elucidate the long-term development. The sort of wood for industrial purposes also seems to be best suited for the introduction in fuel supply. This might change the conditions precedent for the manufacturing - refining industry. The appraisement should thus cover the total wood market. The report considers three time spans namely the historical development, the description of the actual situation and an estimate of the future. The actual situation presents large regional differences which must be observed for times to come. The potential of the wood industry is its proximity to the European market, its character of long-term productivity, the technical qualifications and its unexploited opportunities as to the markets and the raw materials. The problems of the industry are the following: economy, the energy situation and the limited supply of raw products. The essential parts of the strategy of means are as follows - marketing, product development, the utilization of the qualities of the raw products, improvement of process techniques and the development of a market for energy wood and peat. The study presents recommendations of continued analysis of the market based upon regions of the size of administrative districts.

  14. Global long-term cost dynamics of offshore wind electricity generation

    NARCIS (Netherlands)

    Gernaat, David E H J; Van Vuuren, Detlef P.; Van Vliet, Jasper; Sullivan, Patrick; Arent, Douglas J.

    2014-01-01

    Using the IMAGE/TIMER (The Targets IMage Energy Regional) long-term integrated assessment model, this paper explores the regional and global potential of offshore wind to contribute to global electricity production. We develop long-term cost supply curve for offshore wind, a representation of the

  15. Safety of Long-term Interim Storage Facilities - Workshop Proceedings

    International Nuclear Information System (INIS)

    2014-01-01

    The objective of this workshop was to discuss and review current national activities, plans and regulatory approaches for the safety of long term interim storage facilities dedicated to spent nuclear fuel (SF), high level waste (HLW) and other radioactive materials with prolonged storage regimes. It was also intended to discuss results of experiments and to identify necessary R and D to confirm safety of fuel and cask during the long-term storage. Safety authorities and their Technical Support Organisation (TSO), Fuel Cycle Facilities (FCF) operating organisations and international organisations were invited to share information on their approaches, practices and current developments. The workshop was organised in an opening session, three technical sessions, and a conclusion session. The technical sessions were focused on: - National approaches for long term interim storage facilities; - Safety requirements, regulatory framework and implementation issues; - Technical issues and operational experience, needs for R and D. Each session consisted of a number of presentations followed by a panel discussion moderated by the session Chairs. A summary of each session and subsequent discussion that ensued are provided as well as a summary of the results of the workshop with the text of the papers given and presentations made