WorldWideScience

Sample records for fuel managment issue

  1. Potential Interface Issues in Spent Fuel Management

    International Nuclear Information System (INIS)

    2015-10-01

    This publication is an output of a series of meetings to identify and evaluate issues and opportunities associated with interfaces in the back end of the fuel cycle (BEFC) and to describe effective management approaches based on the experience of Member States. During the meetings, participants from Member States and other international organizations shared and evaluated the main interfaces and potential interface issues among the spent fuel storage, transport, reprocessing and disposal of the BEFC, and also reviewed the national approaches to addressing these issues. The aim of this publication is to provide an approach to identify the interfaces in the BEFC as well as the potential issues that should be addressed. It also aims at responding to the solutions Member States most often find to be effective and, in some cases, were adjusted or revisited to reach the fixed target. Most of the interfaces and issues are country specific, as evidenced by the variety and diversity of examples provided in this publication

  2. International trade and waste and fuel managment issue, 2006

    Energy Technology Data Exchange (ETDEWEB)

    Agnihotri, Newal (ed.)

    2006-01-15

    The focus of the January-February issue is on international trade and waste and fuel managment. Major articles/reports in this issue include: HLW management in France, by Michel Debes, EDF, France; Breakthroughs from future reactors, by Jacques Bouchard, CEA, France; 'MOX for peace' a reality, by Jean-Pierre Bariteau, AREVA Group, France; Swedish spent fuel and radwaste, by Per H. Grahn and Marie Skogsberg, SKB, Sweden; ENC2005 concluding remarks, by Larry Foulke, 'Nuclear Technology Matters'; Fuel crud formation and behavior, by Charles Turk, Entergy; and, Plant profile: major vote of confidence for NP, by Martti Katka, TVO, Finland.

  3. Issues related to EM management of DOE spent nuclear fuel

    International Nuclear Information System (INIS)

    Abbott, D.G.; Abashian, M.S.; Chakraborti, S.; Roberson, K.; Meloin, J.M.

    1993-07-01

    This document is a summary of the important issues involved in managing spent nuclear fuel (SNF) owned by the Department of Energy (DOE). Issues related to civilian SNF activities are not discussed. DOE-owned SNF is stored primarily at the Hanford Site, Idaho National Engineering Laboratory (INEL), Savannah River Site (SRS), Oak Ridge National Laboratory (ORNL), and West Valley Demonstration Project. Smaller quantities of SNF are stored at Brookhaven National Laboratory, Sandia National Laboratories, and Los Alamos National Laboratory (LANL). There is a wide variety of fuel types, including both low and high enrichment fuels from weapons production, DOE reactors, research and development programs, naval programs, and universities. Most fuel is stored in pools associated with reactor or reprocessing facilities. Smaller quantities are in dry storage. Physical conditions of the fuel range from excellent to poor or severely damaged. An issue is defined as an important question that must be answered or decision that must be made on a topic or subject relevant to achieving the complimentary objectives of (a) storing SNF in compliance with applicable regulations and orders until it can be disposed, and (b) safely disposing of DOE's SNF. The purpose of this document is to define the issues; no recommendations are made on resolutions. As DOE's national SNF management program is implemented, a system of issues identification, documentation, tracking, and resolution will be implemented. This document is an initial effort at issues identification. The first section of this document is an overview of issues that are common to several or all DOE facilities that manage SNF. The common issues are organized according to specific aspects of spent fuel management. This is followed by discussions of management issues that apply specifically to individual DOE facilities. The last section provides literature references

  4. International trade and waste and fuel managment issue, 2007

    Energy Technology Data Exchange (ETDEWEB)

    Agnihotri, Newal (ed.)

    2007-01-15

    The focus of the January-February issue is on international trade and waste and fuel managment. Major articles/reports in this issue include: New plants with high safety and availability, by Bill Poirier, Westinghouse Electric Company; Increased reliability and competitiveness, by Russell E. Stachowski, GE Energy, Nuclear; Fuel for long-term supply of nuclear power, by Kumiaki Moriya, Hitachi, Ltd., Japan; Super high burnup fuel, By Noboru Itagaki and Tamotsu Murata, Nuclear Fuel Industries LTD., Japan; Zero fuel failures by 2010, by Tom Patten, AREVA NP Inc.; Decommissioning opportunities in the UK, by David Brown and William Thorn, US Department of Commerce; Industry's three challenges, by Dale E. Klein, US Nuclear Regulatory Commission; and, A step ahead of the current ABWR's, compiled by Claire Zurek, GE Energy.

  5. International trade and waste and fuel managment issue, 2008

    Energy Technology Data Exchange (ETDEWEB)

    Agnihotri, Newal (ed.)

    2008-01-15

    The focus of the January-February issue is on international trade and waste and fuel managment. Major articles/reports in this issue include: A global solution for clients, by Yves Linz, AREVA NP; A safer, secure and economical plant, by Andy White, GE Hitachi Nuclear; Robust global prospects, by Ken Petrunik, Atomic Energy of Canada Limited; Development of NPPs in China, by Chen Changbing and Li Huiqiang, Huazhong University of Science and Technology; Yucca Mountain update; and, A class of its own, by Tyler Lamberts, Entergy Nuclear. The Industry Innovation articles in this issue are: Fuel assembly inspection program, by Jim Lemons, Tennessee Valley Authority; and, Improved in-core fuel shuffle for reduced refueling duration, by James Tusar, Exelon Nuclear.

  6. International trade and waste and fuel management issue, 2009

    Energy Technology Data Exchange (ETDEWEB)

    Agnihotri, Newal (ed.)

    2009-01-15

    The focus of the January-February issue is on international trade and waste and fuel managment. Major articles/reports in this issue include: Innovative financing and workforce planning, by Donna Jacobs, Entergy Nuclear; Nuclear power - a long-term need, by John C. Devine, Gerald Goldsmith and Michael DeLallo, WorleyParsons; Importance of loan guarantee program, by Donald Hintz; EPC contracts for new plants, by Dave Barry, Shaw Power Group; GNEP and fuel recycling, by Alan Hanson, AREVA NC Inc.; Safe and reliable reactor, by Kiyoshi Yamauchi, Mitsubishi Heavy Industries, Ltd.; Safe, small and simple reactors, by Yoshi Sakashita, Toshiba Corporation; Nuclear power in Thailand, by Tatchai Sumitra, Thailand Institute of Nuclear Technology; and, Nuclear power in Vietnam, by Tran Huu Phat, Vietnam Atomic Energy Commission. The Industry Innovation article this issue is Rectifying axial-offset-anomaly problems, by Don Adams, Tennessee Valley Authority. The Plant Profile article is Star of Stars Excellence, by Tyler Lamberts, Entergy Nuclear Operations, Inc.

  7. 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)

  8. Issues and decisions for nuclear power plant management after fuel damage events

    International Nuclear Information System (INIS)

    1997-04-01

    Experience has shown that the on-site activities following an incident that results in severely damaged fuel at a nuclear power plant required extraordinary effort. Even in cases that are not extreme but in which fuel damage is greater than mentioned in the specifications for operation, the recovery will require extensive work. This publication includes information from several projects at the IAEA since 1989 that have resulted in a Technical Report, a TECDOC and a Workshop. While the initial purpose of the projects was focused on providing technical information transfer to the experts engaged in recovery work at the damaged unit of Chernobyl NPP, the results have led to a general approach to managing events in which there is substantial fuel damage. This TECDOC summarizes the work to focus on management issues that may be encountered in any such event whether small or large. 11 refs, 2 figs, 5 tabs

  9. Fuels planning: science synthesis and integration; social issues fact sheet 13: Strategies for managing fuels and visual quality

    Science.gov (United States)

    Christine Esposito

    2006-01-01

    The public's acceptance of forest management practices, including fuels reduction, is heavily based on how forests look. Fuels managers can improve their chances of success by considering aesthetics when making management decisions. This fact sheet reviews a three-part general strategy for managing fuels and visual quality: planning, implementation, and monitoring...

  10. Korean interim storage issues and R and D activities on spent fuel management

    International Nuclear Information System (INIS)

    Ji Sup Yoon; Seung-Gy Ro; Hyun-Soo Park

    1999-01-01

    Korea has witnessed over a decade of vicissitudes in the issue of radioactive waste management due mainly to the problem of site acquisition. As the major mission of the nation at radioactive waste management programme was to provide a center for disposal of low-level radwaste and for interim storage of spent nuclear fuel from nuclear power plants, the question of site securing has had a big impact on the implement action of overall programme. The site problem has resulted in, as an aftermath, restructuring of the overall programme for radioactive waste management. Missions of NEMAC (Nuclear Environment Management Center), originally established as a subsidiary of Korea Atomic Energy Research Institute (KAERI), for the national programme was dissolved as of the end of last year. Beginning of this year, a new entity NETEC (Nuclear Environment Technology Center) as a subsidiary of KEPCO (Korea Electric Power Co.) has taken over major tasks of the past NEMAC, while the R and D work associated with the past task of NEMAC is transferred back to KAERI. This paper gives a review on the past background which has driven the radioactive waste management in Korea to the current state of the affairs, with special emphasis on R and D activities associated with spent nuclear fuel transportation, handling, and storage. (author)

  11. Fuel Behaviour in Transport after Dry Storage: a Key Issue for the Management of used Nuclear Fuel

    International Nuclear Information System (INIS)

    Issard, Herve

    2014-01-01

    Interim used fuel dry storage has been developed in many countries providing an intermediate solution while waiting for evaluation and decisions concerning future use (such as recycling) or disposal sites. There is an important industrial experience feedback and excellent safety records. It appears that the duration of interim storage may become longer than initially expected. At the start of storage operations 40 years was considered sufficiently long to make a decision on either recycling or direct disposal of used nuclear fuel. Now it is said that storage time may have to be extended. Whatever the choice for the management of used fuel, it will finally have to be transported from the storage facility to another location, for recycling or final disposal. Bearing in mind the important principle that radioactive waste shall be managed in such a way that undue burdens will not be imposed on future generations, there is no guarantee that the fuel characteristics can be maintained in perpetuity. On the other hand, transport accident conditions from applicable regulation (IAEA SSR-6) are very severe for irradiated materials. Therefore, in compliance with transport regulations, the safety analysis of the fuel in transport after storage is mandatory. This paper will give an overview of the current situation related to the used fuel behaviour in transport after dry storage. On this matter there are some elements of information already available as well as some gaps of knowledge. Several national R and D programs and international teams are presently addressing these gaps. A lot of R and D work has already been done. An objective of these R and D projects is to aid decision makers. It is important to fix a limit and not to multiply intermediate operations because it means higher costs and more uncertainties. The identified gaps concern the following issues especially for high burn-up (HBU) fuels: thermal model for casks, degradation process of fuel material, cladding creep

  12. The Western Energy Corridor Initiative: Unconventional Fuel Development Issues, Impacts, and Management Assessment

    Science.gov (United States)

    Wolfsberg, A.; Hagood, M.; Pasqualini, D.; Wood, T.; Wilson, C.; Witkowski, M.; Levitt, D.; Pawar, R.; Keating, G.; Ziock, H.

    2008-12-01

    The United States is increasingly dependent on imported oil and gas; commodities for which other nations are competing and for which future supply may be inadequate to support our transportation fuel needs. Therefore, a renewed interest in 'harder-to-get' unconventional fuels has emerged in both industry and government with directed focus on world class hydrocarbon resources within a corridor extending from Canada southward through the Rocky Mountain States. Within this Western Energy Corridor, co-located with significant conventional hydrocarbon and renewable energy resources, lie some of the world's richest unconventional hydrocarbon resources in oil shales, oil sands and coal for coal-to-liquid conversion. However, development of these resources poses substantial environmental concerns as well as increasing competition for limited resources of water and habitat. With large-scale energy development in the predominantly rural region, local communities, infrastructures, and economies will face increasing demands for roads, electricity, law enforcement, labor, and other support services. The Western Energy Corridor Initiative (WECI) seeks to develop an integrated assessment of the impacts of unconventional fuel development, the interrelationships of planned energy developments in different basins, and the resultant demands placed on the region. This initial WECI study focuses on two of the most important current issues for industry, regulators, and stakeholders -- the assessment of carbon and water resources issues, impacts, and management strategies. Through scenario analyses using coupled systems and process level models, this study investigates the viability of integrated development of multiple energy resources in a carbon neutral and environmentally acceptable manner, and the interrelationships of various energy resource development plans. The modeling framework is designed to extend to include infrastructure, employment, training, fiscal and economic demands

  13. Management of waste from french nuclear fuel cycle: what are the key issues?

    International Nuclear Information System (INIS)

    Londres, V.; Do Quang, R.; Fournier, P.

    2000-01-01

    Like any other industry, the nuclear industry generates waste. This waste arises in the different successive stages of the fuel cycle, including nuclear power plants, and its physical and chemical properties vary greatly. What is special about it is the radioactivity it contains. Management of waste generated by spent fuel conditioning in nuclear reprocessing facilities, and which cannot be stored in surface repositories, according to current French regulations (ILW and HLW), is specifically discussed in this paper. (authors)

  14. Experimental analysis and management issues of a hydrogen fuel cell system for stationary and mobile application

    Energy Technology Data Exchange (ETDEWEB)

    Corbo, Pasquale; Migliardini, Fortunato; Veneri, Ottorino [Istituto Motori of Italian National Research Council, Via Marconi 8, 80125 Napoli (Italy)

    2007-08-15

    A laboratory fuel cell system based on a 20 kW H{sub 2}/air proton exchange membrane stack was designed, realized and characterized with the aim to elucidate specific concerns to be considered for both hydrogen stationary power systems and automotive applications. The overall system characterization permitted the effect of the main operative variables (temperature, pressure and stoichiometric ratio) on stack power and efficiency to be evaluated. Reactant feeding, humidification and cooling problems are discussed, evidencing in particular the roles of air compressor, fuel purge, stack temperature and humidification strategy in system management. The characterization results are analyzed in terms of H{sub 2} consumption and available power, evidencing the energy losses of the individual fuel cell system components. In particular, the data obtained on key components (stack, reactants, heat and water management devices) are used for a critical discussion about their specifications and operation characteristics as demanded by both stationary and mobile applications. (author)

  15. Experimental analysis and management issues of a hydrogen fuel cell system for stationary and mobile application

    International Nuclear Information System (INIS)

    Corbo, Pasquale; Migliardini, Fortunato; Veneri, Ottorino

    2007-01-01

    A laboratory fuel cell system based on a 20 kW H 2 /air proton exchange membrane stack was designed, realized and characterized with the aim to elucidate specific concerns to be considered for both hydrogen stationary power systems and automotive applications. The overall system characterization permitted the effect of the main operative variables (temperature, pressure and stoichiometric ratio) on stack power and efficiency to be evaluated. Reactant feeding, humidification and cooling problems are discussed, evidencing in particular the roles of air compressor, fuel purge, stack temperature and humidification strategy in system management. The characterization results are analyzed in terms of H 2 consumption and available power, evidencing the energy losses of the individual fuel cell system components. In particular, the data obtained on key components (stack, reactants, heat and water management devices) are used for a critical discussion about their specifications and operation characteristics as demanded by both stationary and mobile applications

  16. German Spent Nuclear Fuel Legacy: Characteristics and High-Level Waste Management Issues

    Directory of Open Access Journals (Sweden)

    A. Schwenk-Ferrero

    2013-01-01

    Full Text Available Germany is phasing-out the utilization of nuclear energy until 2022. Currently, nine light water reactors of originally nineteen are still connected to the grid. All power plants generate high-level nuclear waste like spent uranium or mixed uranium-plutonium dioxide fuel which has to be properly managed. Moreover, vitrified high-level waste containing minor actinides, fission products, and traces of plutonium reprocessing loses produced by reprocessing facilities has to be disposed of. In the paper, the assessments of German spent fuel legacy (heavy metal content and the nuclide composition of this inventory have been done. The methodology used applies advanced nuclear fuel cycle simulation techniques in order to reproduce the operation of the German nuclear power plants from 1969 till 2022. NFCSim code developed by LANL was adopted for this purpose. It was estimated that ~10,300 tonnes of unreprocessed nuclear spent fuel will be generated until the shut-down of the ultimate German reactor. This inventory will contain ~131 tonnes of plutonium, ~21 tonnes of minor actinides, and 440 tonnes of fission products. Apart from this, ca.215 tonnes of vitrified HLW will be present. As fission products and transuranium elements remain radioactive from 104 to 106 years, the characteristics of spent fuel legacy over this period are estimated, and their impacts on decay storage and final repository are discussed.

  17. Status of native fishes in the western United States and issues for fire and fuels management

    Science.gov (United States)

    Rieman, B.; Lee, D.; Burns, D.; Gresswell, Robert E.; Young, M.; Stowell, R.; Rinne, J.; Howell, P.

    2003-01-01

    Conservation of native fishes and changing patterns in wildfire and fuels are defining challenges for managers of forested landscapes in the western United States. Many species and populations of native fishes have declined in recorded history and some now occur as isolated remnants of what once were larger more complex systems. Land management activities have been viewed as one cause of this problem. Fires also can have substantial effects on streams and riparian systems and may threaten the persistence of some populations of fish, particularly those that are small and isolated. Despite that, major new efforts to actively manage fires and fuels in forests throughout the region may be perceived as a threat rather than a benefit to conservation of native fishes and their habitats. The management of terrestrial and aquatic resources has often been contentious, divided among a variety of agencies with different goals and mandates. Management of forests, for example, has generally been viewed as an impact on aquatic systems. Implementation of the management-regulatory process has reinforced a uniform approach to mitigate the threats to aquatic species and habitats that may be influenced by management activities. The problems and opportunities, however, are not the same across the landscapes of interest. Attempts to streamline the regulatory process often search for generalized solutions that may oversimplify the complexity of natural systems. Significant questions regarding the influence of fire on aquatic ecosystems, changing fire regimes, and the effects of fire-related management remain unresolved and contribute to the uncertainty. We argue that management of forests and fishes can be viewed as part of the same problem, that of conservation and restoration of the natural processes that create diverse and productive ecosystems. We suggest that progress toward more integrated management of forests and native fishes will require at least three steps: (1) better

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  19. Near surface spent fuel storage: environmental issues

    International Nuclear Information System (INIS)

    Nelson, I.C.; Shipler, D.B.; McKee, R.W.; Glenn, R.D.

    1979-01-01

    Interim storage of spent fuel appears inevitable because of the lack of reprocessing plants and spent fuel repositories. This paper examines the environmental issues potentially associated with management of spent fuel before disposal or reprocessing in a reference scenario. The radiological impacts of spent fuel storage are limited to low-level releases of noble gases and iodine. Water needed for water basin storage of spent fuel and transportation accidents are considered; the need to minimize the distance travelled is pointed out. Resource commitments for construction of the storage facilities are analyzed

  20. Human factors issues in fuel handling

    International Nuclear Information System (INIS)

    Beattie, J.D.; Iwasa-Madge, K.M.; Tucker, D.A.

    1994-01-01

    The staff of the Atomic Energy Control Board wish to further their understanding of human factors issues of potential concern associated with fuel handling in CANDU nuclear power stations. This study contributes to that objective by analysing the role of human performance in the overall fuel handling process at Ontario Hydro's Darlington Nuclear Generating Station, and reporting findings in several areas. A number of issues are identified in the areas of design, operating and maintenance practices, and the organizational and management environment

  1. Fuel management

    International Nuclear Information System (INIS)

    Schwarz, E.R.

    1975-01-01

    Description of the operation of power plants and the respective procurement of fuel to fulfil the needs of the grid. The operation of the plants shall be optimised with respect to the fuel cost. (orig./RW) [de

  2. Waste management issues and their potential impact on technical specifications of CANDU fuel materials

    Energy Technology Data Exchange (ETDEWEB)

    Tait, J.C.; Johnson, L.H. [Atomic Energy of Canada Limited, Pinawa, Manitoba (Canada)

    1997-07-01

    The technical specifications for the composition of nuclear fuels and materials used in Canada's CANDU reactors have been developed by AECL and materials manufacturers, taking into account considerations specific to their manufacture and the effect of minor impurities on fuel behaviour in reactor. Nitrogen and chlorine are examples of UO{sub 2} impurities, however, where there is no technical specification limit. These impurities are present in the source materials or introduced in the fabrication process and are neutron activated to {sup 14}C and {sup 36}C1, which after {sup 129}I , are the two most significant contributors to dose in safety assessments for the disposal of used fuel. For certain impurities, environmental factors, particularly the safety of the disposal of used fuels, should be taken into consideration when deriving 'allowable' impurity limits for nuclear fuel materials. (author)

  3. Waste management issues and their potential impact on technical specifications of CANDU fuel materials

    International Nuclear Information System (INIS)

    Tait, J.C.; Johnson, L.H.

    1997-01-01

    The technical specifications for the composition of nuclear fuels and materials used in Canada's CANDU reactors have been developed by AECL and materials manufacturers, taking into account considerations specific to their manufacture and the effect of minor impurities on fuel behaviour in reactor. Nitrogen and chlorine are examples of UO 2 impurities, however, where there is no technical specification limit. These impurities are present in the source materials or introduced in the fabrication process and are neutron activated to 14 C and 36 C1, which after 129 I , are the two most significant contributors to dose in safety assessments for the disposal of used fuel. For certain impurities, environmental factors, particularly the safety of the disposal of used fuels, should be taken into consideration when deriving 'allowable' impurity limits for nuclear fuel materials. (author)

  4. Spent fuel management

    International Nuclear Information System (INIS)

    2005-01-01

    The production of nuclear electricity results in the generation of spent fuel that requires safe, secure and efficient management. Appropriate management of the resulting spent fuel is a key issue for the steady and sustainable growth of nuclear energy. Currently about 10,000 tonnes heavy metal (HM) of spent fuel are unloaded every year from nuclear power reactors worldwide, of which 8,500 t HM need to be stored (after accounting for reprocessed fuel). This is the largest continuous source of civil radioactive material generated, and needs to be managed appropriately. Member States have referred to storage periods of 100 years and even beyond, and as storage quantities and durations extend, new challenges arise in the institutional as well as in the technical area. The IAEA gives high priority to safe and effective spent fuel management. As an example of continuing efforts, the 2003 International Conference on Storage of Spent Fuel from Power Reactors gathered 125 participants from 35 member states to exchange information on this important subject. With its large number of Member States, the IAEA is well-positioned to gather and share information useful in addressing Member State priorities. IAEA activities on this topic include plans to produce technical documents as resources for a range of priority topics: spent fuel performance assessment and research, burnup credit applications, cask maintenance, cask loading optimization, long term storage requirements including records maintenance, economics, spent fuel treatment, remote technology, and influence of fuel design on spent fuel storage. In addition to broader topics, the IAEA supports coordinated research projects and technical cooperation projects focused on specific needs

  5. Thorium fuel cycle management

    International Nuclear Information System (INIS)

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

    2010-01-01

    In this presentation author deals with the thorium fuel cycle management. Description of the thorium fuels and thorium fuel cycle benefits and challenges as well as thorium fuel calculations performed by the computer code HELIOS are presented.

  6. Scientific issues in fuel behaviour

    International Nuclear Information System (INIS)

    1995-01-01

    The current limits on discharge burnup in today's nuclear power stations have proven the fuel to be very reliable in its performance, with a negligibly small rate of failure. However, for reasons of economy, there are moves to increase the fuel enrichment in order to extend both the cycle time and the discharge burnup. But, longer periods of irradiation cause increased microstructural changes in the fuel and cladding, implying a larger degradation of physical and mechanical properties. This degradation may well limit the plant life, hence the NSC concluded that it is of importance to develop a predictive capability of fuel behaviour at extended burnup. This can only be achieved through an improved understanding of the basic underlying phenomena of fuel behaviour. The Task Force on Scientific Issues Related to Fuel Behaviour of the NEA Nuclear Science Committee has identified the most important scientific issues on the subject and has assigned priorities. Modelling aspects are listed in Appendix A and discussed in Part II. In addition, quality assurance process for performing and evaluating new integral experiments is considered of special importance. Main activities on fuel behaviour modelling, as carried out in OECD Member countries and international organisations, are listed in Part III. The aim is to identify common interests, to establish current coverage of selected issues, and to avoid any duplication of efforts between international agencies. (author). refs., figs., tabs

  7. Safety issues on advanced fuel

    International Nuclear Information System (INIS)

    Gross, H.; Krebs, W.D.

    1998-01-01

    In the recent years a general discussion has started whether unsolved safety issues are related to advanced fuel. Advanced fuel is in this context a summary of features like high burnup, improved clad materials, low leakage loading pattern with high peaking factors etc. The design basis accidents RIA and Loca are of special interest for this discussion. From the Siemens point of view RIA is not a safety issue. There are sufficient margins between the enthalpy rise calculated by modern 3D methods and the fuel failures which occurred in RIA simulation tests when the effect of pulse width is taken into account. The evaluation of possible uncertainties for the established Loca criteria (17% equivalent corrosion, 1200 C clad temperature) for high burnup makes sense. But fuel with high burnup has significantly lower peaking factors than fuel with lower burnup. This gives sufficient margin counterbalancing possible uncertainties. In contrast to the above incomplete control rod insertion at higher burnup is potentially a real safety issue. Although Siemens fuel was not affected by the reported incidents they addressed the problem and checked that they have sufficient design margin for their fuel. (orig.) [de

  8. Environmental issues: New techniques for managing and using wood fuel ash

    Energy Technology Data Exchange (ETDEWEB)

    Fehrs, J.E.; Donovan, C.T. [C.T. Donovan Associates, Inc., Burlington, VT (United States)

    1993-12-31

    Continued research and development of environmentally-acceptable and cost-effective end uses for wood ash is having a significant affect on the ability to use wood and wood waste for fuel. This is particularly true for ash resulting from treated wood combustion. Concerns about the contents of ash from wood containing paint, stain, preservatives, or other chemicals is one of the largest regulatory barriers to its use as fuel. The purpose of this paper is to: (1) Identify the physical and chemical characteristics of ashes produced from the combustion of untreated and treated wood; (2) Explain the types of {open_quotes}clean, untreated{close_quotes} and {open_quotes}treated{close_quotes} wood that are likely to produce ash that can beneficially used; (3) Describe existing and potential products and end uses for untreated and treated wood ash.

  9. Alternative transportation fuels: Financing issues

    International Nuclear Information System (INIS)

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

    1992-06-01

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

  10. Management of waste from French nuclear fuel cycle: what are the key issues?

    International Nuclear Information System (INIS)

    Londres, V.; Do Quang, R.; FOURNIER, P.

    2001-01-01

    The publication on 2 CD-ROMs and includes 145 presentations delivered at the congress. In the work of the International Youth Nuclear Congress 2000 participated 288 young scientific works from over 30 countries. The address discusses the following sessions: Young Generation Session Nuclear Education and Transfer of Know-How; Nuclear Technology I; Political Aspects; Nuclear Technology II; Environment and Safety; Communication and Public Perception I; Communication and Public Perception II; Nuclear Programs and Technical Cooperation; Economics; Fuel Cycle Challenges. Each paper has been indexed separately. Before of full papers the first CD contains next chapters: Introduction (in 19 languages); General Information; Day by Day; Y-Notes Session Results; Sponsors; Media Album, and Conclusions. The second CD-ROM contains 28 minutes of video-film about programme of International Youth Nuclear Congress 2000. (authors)

  11. Human factors issues in fuel handling

    Energy Technology Data Exchange (ETDEWEB)

    Beattie, J D; Iwasa-Madge, K M; Tucker, D A [Humansystems Inc., Milton, ON (Canada)

    1994-12-31

    The staff of the Atomic Energy Control Board wish to further their understanding of human factors issues of potential concern associated with fuel handling in CANDU nuclear power stations. This study contributes to that objective by analysing the role of human performance in the overall fuel handling process at Ontario Hydro`s Darlington Nuclear Generating Station, and reporting findings in several areas. A number of issues are identified in the areas of design, operating and maintenance practices, and the organizational and management environment. 1 fig., 4 tabs., 19 refs.

  12. Safety issues on advanced fuel

    Energy Technology Data Exchange (ETDEWEB)

    Gross, H.; Krebs, W.D. [Siemens AG, Bereich Energieerzeugug (KWU), Erlangen (Germany). Geschaeftsgebiet Nukleare Energieerzeugung

    1998-05-01

    In the recent years a general discussion has started whether unsolved safety issues are related to advanced fuel. Advanced fuel is in this context a summary of features like high burnup, improved clad materials, low leakage loading pattern with high peaking factors etc. The design basis accidents RIA and Loca are of special interest for this discussion. From the Siemens point of view RIA is not a safety issue. There are sufficient margins between the enthalpy rise calculated by modern 3D methods and the fuel failures which occurred in RIA simulation tests when the effect of pulse width is taken into account. The evaluation of possible uncertainties for the established Loca criteria (17% equivalent corrosion, 1200 C clad temperature) for high burnup makes sense. But fuel with high burnup has significantly lower peaking factors than fuel with lower burnup. This gives sufficient margin counterbalancing possible uncertainties. In contrast to the above incomplete control rod insertion at higher burnup is potentially a real safety issue. Although Siemens fuel was not affected by the reported incidents they addressed the problem and checked that they have sufficient design margin for their fuel. (orig.) [Deutsch] In den letzten Jahren hat eine allgemeine Diskussion begonnen, ob mit fortgeschrittenen Brennelementen (BE) ungeklaerte Sicherheitsprobleme verbunden sind. Dabei ist `Fortgeschrittene Brennelemente` ein Sammelbegriff fuer hohe Abbraende, verbesserte Huellrohrmaterialien, Low-leakage-Einsatzplanungen mit hohen Heissstellenfaktoren usw. Die Auslegungsstoerfaelle RIA und Loca sind in dieser Diskussion von besonderer Bedeutung. Aus der Sicht von Siemens ist der RIA kein Sicherheitsproblem. Zwischen den mit modernen 3D-Methoden berechneten Enthalpieerhoehungen und den in RIA-Experimenten aufgetretenen Brennstabdefekten bestehen ausreichende Abstaende, wenn der Einfluss der Pulsbreite beruecksichtigt wird. Die Untersuchung eventueller Unsicherheiten bei hohen

  13. Fuel management of HTR-10

    International Nuclear Information System (INIS)

    Wu Zongxin; Jing Xingqing

    2001-01-01

    The 10 MW high temperature cooled reactor (HTR-10) built in Tsinghua University is a pebble bed type of HTGR. The continuous recharge and multiple-pass of spherical fuel elements are used for fuel management. The initiative stage of core is composed of the mix of spherical fuel elements and graphite elements. The equilibrium stage of core is composed of identical spherical fuel elements. The fuel management during the transition from the initiative stage to the equilibrium stage is a key issue for HTR-10 physical design. A fuel management strategy is proposed based on self-adjustment of core reactivity. The neutron physical code is used to simulate the process of fuel management. The results show that the graphite elements, the recharging fuel elements below the burn-up allowance, and the discharging fuel elements over the burn-up allowance could be identified by burn-up measurement. The maximum of burn-up fuel elements could be controlled below the burn-up limit

  14. Product Category Management Issues

    OpenAIRE

    Żukowska, Joanna

    2011-01-01

    The purpose of the paper is to present the issues related to category management. It includes the overview of category management definitions and the correct process of exercising it. Moreover, attention is paid to the advantages of brand management, the benefits the supplier and retailer may obtain in this way. The risk element related to this topics is also presented herein. Joanna Żukowska

  15. Fuel management and economics

    Energy Technology Data Exchange (ETDEWEB)

    Vendryes, G

    1972-11-01

    From international conference on nuclear solutions to world energy problems; Washington, District of Columbia, USA (12 Nov The low cost of the fuel cycle is the most attractive feature of the fast neutron breeder reactor. In order to achieve it a good fuel management is essential, with well balanced fixed investment and renewal fuel costs. In addition the designer can optimize the power station as a whole (fuel cycle and thermal characteristics). (auth)

  16. Spent fuel management in Canada

    International Nuclear Information System (INIS)

    Pattantyus, P.

    1998-01-01

    The current status of the Canadian Spent Fuel Management is described. This includes wet and dry interim storage, transportation issues and future plans regarding final disposal based on deep underground emplacement in stable granite rock. Extension of wet interim storage facilities is not planned, as dry storage technologies have found wide acceptance. (author)

  17. Space reactor fuels performance and development issues

    International Nuclear Information System (INIS)

    Wewerka, E.M.

    1984-01-01

    Three compact reactor concepts are now under consideration by the US Space Nuclear Power Program (the SP-100 Program) as candidates for the first 100-kWe-class space reactor. Each of these reactor designs puts unique constraints and requirements on the fuels system, and raises issues of fuel systems feasibility and performance. This paper presents a brief overview of the fuel requirements for the proposed space reactor designs, a delineation of the technical feasibility issues that each raises, and a description of the fuel systems development and testing program that has been established to address key technical issues

  18. Special Issue: Aviation Alternative Fuels

    Directory of Open Access Journals (Sweden)

    Yang Zhang

    2014-12-01

    Full Text Available The investigation of aviation alternative fuels has increased significantly in recent years in an effort to reduce the environment and climate impact by aviation industry. Special requirements have to be met for qualifying as a suitable aviation fuel. The fuel has to be high in energy content per unit of mass and volume, thermally stable and avoiding freezing at low temperatures. There are also many other special requirements on viscosity, ignition properties and compatibility with the typical aviation materials. There are quite a few contending alternative fuels which can be derived from coal, natural gas and biomass.[...

  19. Fuel cycle management

    International Nuclear Information System (INIS)

    Herbin, H.C.

    1977-01-01

    The fuel cycle management is more and more dependent on the management of the generation means among the power plants tied to the grid. This is due mainly because of the importance taken by the nuclear power plants within the power system. The main task of the fuel cycle management is to define the refuelling pattern of the new and irradiated fuel assemblies to load in the core as a function of: 1) the differences which exist between the actual conditions of the core and what was expected for the present cycle, 2) the operating constraints and the reactor availability, 3) the technical requirements in safety and the technological limits of the fuel, 4) the economics. Three levels of fuel cycle management can be considered: 1) a long term management: determination of enrichments and expected cycle lengths, 2) a mid term management whose aim corresponds to the evaluation of the batch to load within the core as a function of both: the next cycle length to achieve and the integrated power history of all the cycles up to the present one, 3) a short term management which deals with the updating of the loaded fuel utilisations to take into account the operation perturbations, or with the alteration of the loading pattern of the next batch to respect unexpected conditions. (orig.) [de

  20. Overview of spent fuel management and problems

    International Nuclear Information System (INIS)

    Ritchie, I.G.; Ernst, P.C.

    1998-01-01

    Results compiled in the research reactor spent fuel database are used to assess the status of research reactor spent fuel worldwide. Fuel assemblies, their types, enrichment, origin of enrichment and geological distribution among the industrialized and developed countries of the world are discussed. Fuel management practices in wet and dry storage facilities and the concerns of reactor operators about long-term storage of their spent fuel are presented and some of the activities carried out by the International Atomic Energy Agency to address the issues associated with research reactor spent fuel are outlined. Some projections of spent fuel inventories to the year 2006 are presented and discussed. (author)

  1. Federal Republic of Germany R and D programme: A special issue of the journal radioactive waste management and the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Merz, E.R.

    1986-01-01

    This book examines the issues of radioactive waste management and the nuclear fuel cycle in the Federal Republic of Germany. Topics considered include the challenges of waste handling and disposal, the borosilicate glass for Pamela, the treatment and conditioning of transuranelement bearing wastes in the Federal Republic of Germany, conditioning of low and intermediate level wastes, volume reduction of low level solid radioactive waste by incineration and compaction in the Federal Republic of Germany, MAW test emplacement in boreholes, treatment and disposal of special radioactive wastes comprising tritium, carbon 14, krypton 85 and iodine 129, and the German Project: ''Safety Studies for Nuclear Waste Management: Development of Safety Assessment Methodology for Final Disposal of Nuclear Waste in a Salt Dome

  2. Analysis of high burnup fuel safety issues

    International Nuclear Information System (INIS)

    Lee, Chan Bock; Kim, D. H.; Bang, J. G.; Kim, Y. M.; Yang, Y. S.; Jung, Y. H.; Jeong, Y. H.; Nam, C.; Baik, J. H.; Song, K. W.; Kim, K. S

    2000-12-01

    Safety issues in steady state and transient behavior of high burnup LWR fuel above 50 - 60 MWD/kgU were analyzed. Effects of burnup extension upon fuel performance parameters was reviewed, and validity of both the fuel safety criteria and the performance analysis models which were based upon the lower burnup fuel test results was analyzed. It was found that further tests would be necessary in such areas as fuel failure and dispersion for RIA, and high temperature cladding corrosion and mechanical deformation for LOCA. Since domestic fuels have been irradiated in PWR up to burnup higher than 55 MWD/kgU-rod. avg., it can be said that Korea is in the same situation as the other countries in the high burnup fuel safety issues. Therefore, necessary research areas to be performed in Korea were derived. Considering that post-irradiation examination(PIE) for the domestic fuel of burnup higher than 30 MWD/kgU has not been done so far at all, it is primarily necessary to perform PIE for high burnup fuel, and then simulation tests for RIA and LOCA could be performed by using high burnup fuel specimens. For the areas which can not be performed in Korea, international cooperation will be helpful to obtain the test results. With those data base, safety of high burnup domestic fuels will be confirmed, current fuel safety criteria will be re-evaluated, and finally transient high burnup fuel behavior analysis technology will be developed through the fuel performance analysis code development

  3. Analysis of high burnup fuel safety issues

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chan Bock; Kim, D. H.; Bang, J. G.; Kim, Y. M.; Yang, Y. S.; Jung, Y. H.; Jeong, Y. H.; Nam, C.; Baik, J. H.; Song, K. W.; Kim, K. S

    2000-12-01

    Safety issues in steady state and transient behavior of high burnup LWR fuel above 50 - 60 MWD/kgU were analyzed. Effects of burnup extension upon fuel performance parameters was reviewed, and validity of both the fuel safety criteria and the performance analysis models which were based upon the lower burnup fuel test results was analyzed. It was found that further tests would be necessary in such areas as fuel failure and dispersion for RIA, and high temperature cladding corrosion and mechanical deformation for LOCA. Since domestic fuels have been irradiated in PWR up to burnup higher than 55 MWD/kgU-rod. avg., it can be said that Korea is in the same situation as the other countries in the high burnup fuel safety issues. Therefore, necessary research areas to be performed in Korea were derived. Considering that post-irradiation examination(PIE) for the domestic fuel of burnup higher than 30 MWD/kgU has not been done so far at all, it is primarily necessary to perform PIE for high burnup fuel, and then simulation tests for RIA and LOCA could be performed by using high burnup fuel specimens. For the areas which can not be performed in Korea, international cooperation will be helpful to obtain the test results. With those data base, safety of high burnup domestic fuels will be confirmed, current fuel safety criteria will be re-evaluated, and finally transient high burnup fuel behavior analysis technology will be developed through the fuel performance analysis code development.

  4. Spent fuel management newsletter. No. 2

    International Nuclear Information System (INIS)

    1993-04-01

    This issue of the newsletter consists of two parts. The first part describes the IAEA Secretariat activities - work and programme of the Nuclear Materials and Fuel Cycle Technology Section of the Division of Nuclear Fuel Cycle and Waste Management, recent and planned meetings and publications, Technical Co-operation projects, Co-ordinated Research programmes. The second part contains country reports - national programmes on spent fuel management: current and planned storage and reprocessing capacities, spent fuel arisings, safety, transportation, storage and treatment of spent fuel

  5. Spent fuel management newsletter. No. 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-04-01

    This issue of the newsletter consists of two parts. The first part describes the IAEA Secretariat activities - work and programme of the Nuclear Materials and Fuel Cycle Technology Section of the Division of Nuclear Fuel Cycle and Waste Management, recent and planned meetings and publications, Technical Co-operation projects, Co-ordinated Research programmes. The second part contains country reports - national programmes on spent fuel management: current and planned storage and reprocessing capacities, spent fuel arisings, safety, transportation, storage and treatment of spent fuel.

  6. FERC perspectives on nuclear fuel accounting issues

    International Nuclear Information System (INIS)

    McDanal, M.W.

    1986-01-01

    The purpose of the presentation is to discuss the treatment of nuclear fuel and problems that have evolved in industry practices in accounting for fuel. For some time, revisions to the Uniform System of Accounts have been considered with regard to the nuclear fuel accounts. A number of controversial issues have been encountered on audits, including treatment of nuclear fuel enrichment charges, costs associated with delays in enrichment services, the treatment and recognition of fuel inventories in excess of current or projected needs, and investments in and advances to mining and milling companies for future deliveries of nuclear fuel materials. In an effort to remedy the problems and to adapt the Federal Energy Regulatory Commission's accounting to more easily provide for or point out classifications for each problem area, staff is reevaluating the need for contemplated amendments to the Uniform System of Accounts

  7. Strategy of fuel management

    International Nuclear Information System (INIS)

    Guesdon, B.; Le Bars, M.; Mathonniere, G.

    1996-01-01

    The management of nuclear fuels in PWR type reactors has been adapted to improve the safety and the competitiveness of brackets. The economic optimum, at the park level, depends on many parameters, variable with time and in function of them, we favour the annual campaigns and the economy won on the cost of cycle, or long campaigns with benefit on availability. The reduction of the number of stopping improves the availability, limits the doses integrated by the personnel of intervention and reduces the number of incidents during the stopping. An other determining factor is connected to the policy of closed cycle with the the principle of equality between the reprocessing flux and the valorization of reprocessed fuels: plutonium and reprocessed uranium. The progress of fuel have allowed significant improvements in the managements of cores. With the safety, the aim is also to keep if not improve the competitiveness of the Nuclear park by valorizing the matter coming from reprocessing. (N.C.)

  8. Global Energy Issues and Alternate Fueling

    Science.gov (United States)

    Hendricks, Robert C.

    2007-01-01

    This viewgraph presentation describes world energy issues and alternate fueling effects on aircraft design. The contents include: 1) US Uses about 100 Quad/year (1 Q = 10(exp 15) Btu) World Energy Use: about 433 Q/yr; 2) US Renewable Energy about 6%; 3) Nuclear Could Grow: Has Legacy Problems; 4) Energy Sources Primarily NonRenewable Hydrocarbon; 5) Notes; 6) Alternate Fuels Effect Aircraft Design; 7) Conventional-Biomass Issue - Food or Fuel; 8) Alternate fuels must be environmentally benign; 9) World Carbon (CO2) Emissions Problem; 10) Jim Hansen s Global Warming Warnings; 11) Gas Hydrates (Clathrates), Solar & Biomass Locations; 12) Global Energy Sector Response; 13) Alternative Renewables; 14) Stratospheric Sulfur Injection Global Cooling Switch; 15) Potential Global Energy Sector Response; and 16) New Sealing and Fluid Flow Challenges.

  9. Fuel System Compatibility Issues for Prometheus-1

    International Nuclear Information System (INIS)

    DC-- Noe; KB Gibbard; MH Krohn

    2006-01-01

    Compatibility issues for the Prometheus-1 fuel system have been reviewed based upon the selection of UO 2 as the reference fuel material. In particular, the potential for limiting effects due to fuel- or fission product-component (cladding, liner, spring, etc) chemical interactions and clad-liner interactions have been evaluated. For UO 2 -based fuels, fuel-component interactions are not expected to significantly limit performance. However, based upon the selection of component materials, there is a potential for degradation due to fission products. In particular, a chemical liner may be necessary for niobium, tantalum, zirconium, or silicon carbide-based systems. Multiple choices exist for the configuration of a chemical liner within the cladding; there is no clear solution that eliminates all concerns over the mechanical performance of a clad/liner system. A series of tests to evaluate the performance of candidate materials in contact with real and simulated fission products is outlined

  10. International issue: the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    In this special issue a serie of short articles of informations are presented on the following topics: the EEC's medium term policy regarding the reprocessing and storage of spent fuel, France's natural uranium supply, the Pechiney Group in the nuclear field, zircaloy cladding for nuclear fuel elements, USSI: a major French nuclear engineering firm, gaseous diffusion: the only commercial enrichment process, the transport of nuclear materials in the fuel cycle, Cogema and spent fuel reprocessing, SGN: a leader in the fuel cycle, quality control of mechanical, thermal and termodynamic design in nuclear engineering, Sulzer's new pump testing station in Mantes, the new look of the Ateliers et Chantiers de Bretagne, tubes and piping in nuclear power plants, piping in pressurized water reactor. All these articles are written in English and in French [fr

  11. Criticality safety issues associated with the introduction of low void reactivity fuel in the Bruce reactors - a management and technical overview

    International Nuclear Information System (INIS)

    Thompson, J.W.; Austman, G.; Iglesias, F.; Schmeing, H.; Elliott, C.; Archinoff, G.

    2004-01-01

    The concept of criticality for operating reactor staff, particularly in a natural uranium-fuelled reactor, is relatively benign - the reactor is controlled at the critical condition by the regulating system. That is, issues related to criticality exist only within the reactor, in a set of carefully managed circumstances. With the introduction of enriched Low Void Reactivity Fuel (LVRF) into this operating environment comes a new 'concept of criticality', one which, although physically the same, cannot be treated in the same fashion. It may be the case that criticality can be achieved outside the reactor, albeit with a set of very pessimistic assumptions. Such 'inadvertent criticality' outside the reactor, should it occur, cannot be controlled. The consequences of such an inadvertent criticality could have far-reaching effects, not only in terms of severe health effects to those nearby, but also in terms of the negative impact on Bruce Power, and the Canadian nuclear industry in general. Thus the introduction of LVRF in the Bruce B reactors, and therefore the introduction of this new hazard, inadvertent criticality, warrants the development of a governance structure for its management. Such a program will consist of various elements, including the establishment of a framework to administer the criticality safety program, analytical assessment to support the process design, the development of operational procedures, the development of enhanced emergency procedures if necessary, and the implementation of a criticality safety training program. The entire package must be sufficient to demonstrate to station management, and the regulator, that the criticality safety risks associated with the implementation of enriched fuel have been properly evaluated, and that all necessary steps have been taken to effectively manage these risks. A well-founded Criticality Safety Program will offer such assurance. In this paper, we describe the establishment of a Criticality Safety

  12. Past and future IAEA spent fuel management activities

    International Nuclear Information System (INIS)

    Grigoriev, A.

    1993-01-01

    The main objectives and strategies of the Agency's activities in the area of spent fuel management are to promote the exchange of information between Member States on technical, safety, environmental and economic aspects of spent fuel management technology, including storage, transport and treatment of spent fuel, and to provide assistance to Member States in the planning, implementation and operation of nuclear fuel cycle facilities. This paper give a list of the meetings held since the last issue of the Spent Fuel Management Newsletter

  13. SAT project introduction: management issues

    International Nuclear Information System (INIS)

    Kazennov, A.Yu.

    1998-01-01

    Management issues of introducing SAT Project include main objectives and expectations; SAT goal and management; major phases of SAT implementation; project quality assurance; SAT based training system and procedures; role of the project team qualifications

  14. Fuel quality issues in stationary fuel cell systems.

    Energy Technology Data Exchange (ETDEWEB)

    Papadias, D.; Ahmed, S.; Kumar, R. (Chemical Sciences and Engineering Division)

    2012-02-07

    Fuel cell systems are being deployed in stationary applications for the generation of electricity, heat, and hydrogen. These systems use a variety of fuel cell types, ranging from the low temperature polymer electrolyte fuel cell (PEFC) to the high temperature solid oxide fuel cell (SOFC). Depending on the application and location, these systems are being designed to operate on reformate or syngas produced from various fuels that include natural gas, biogas, coal gas, etc. All of these fuels contain species that can potentially damage the fuel cell anode or other unit operations and processes that precede the fuel cell stack. These detrimental effects include loss in performance or durability, and attenuating these effects requires additional components to reduce the impurity concentrations to tolerable levels, if not eliminate the impurity entirely. These impurity management components increase the complexity of the fuel cell system, and they add to the system's capital and operating costs (such as regeneration, replacement and disposal of spent material and maintenance). This project reviewed the public domain information available on the impurities encountered in stationary fuel cell systems, and the effects of the impurities on the fuel cells. A database has been set up that classifies the impurities, especially in renewable fuels, such as landfill gas and anaerobic digester gas. It documents the known deleterious effects on fuel cells, and the maximum allowable concentrations of select impurities suggested by manufacturers and researchers. The literature review helped to identify the impurity removal strategies that are available, and their effectiveness, capacity, and cost. A generic model of a stationary fuel-cell based power plant operating on digester and landfill gas has been developed; it includes a gas processing unit, followed by a fuel cell system. The model includes the key impurity removal steps to enable predictions of impurity breakthrough

  15. Automated and interactive fuel management tools: Past, present and future

    International Nuclear Information System (INIS)

    Cook, A.G.; Casadei, A.L.

    1986-01-01

    The past, present and future status of automated and interactive fuel management tools are reviewed. Issues such as who are the customers for these products and what are their needs are addressed. The nature of the fuel management problem is reviewed. The Westinghouse fuel management tools and methods are presented as an example of how the technology has evolved

  16. Software management issues

    International Nuclear Information System (INIS)

    Kunz, P.F.

    1990-06-01

    The difficulty of managing the software in large HEP collaborations appears to becoming progressively worst with each new generation of detector. If one were to extrapolate to the SSC, it will become a major problem. This paper explores the possible causes of the difficulty and makes suggestions on what corrective actions should be taken

  17. Fuel Behavior Modeling Issues Associated with Future Fast Reactor Systems

    International Nuclear Information System (INIS)

    Yacout, A.M.; Hofman, G.L.; Lambert, J.D.B.; Kim, Y.S.

    2007-01-01

    Major issues of concern related to advanced fast reactor fuel behavior are discussed here with focus on phenomena that are encountered during irradiation of metallic fuel elements. Identification of those issues is part of an advanced fuel simulation effort that aims at improving fuel design and reducing reliance on conventional approach of design by experiment which is both time and resource consuming. (authors)

  18. Remote technology applications in spent fuel management

    International Nuclear Information System (INIS)

    2005-03-01

    Spent fuel management has become a prospective area for application of remote technology in recent years with a steadily growing inventory of spent fuel arising from nuclear power production. A remark that could be made from the review of technical information collected from the IAEA meetings was that remote technology in spent fuel management has matured well through the past decades of industrial experiences. Various remote technologies have been developed and applied in the past for facility operation and maintenance work in spent fuel examination, storage, transportation, reprocessing and radioactive waste treatment, among others, with significant accomplishments in dose reduction to workers, enhancement of reliability, etc. While some developmental activities are continuing for more advanced applications, industrial practices have made use of simple and robust designs for most of the remote systems technology applications to spent fuel management. In the current state of affairs, equipment and services in remote technology are available in the market for applications to most of the projects in spent fuel management. It can be concluded that the issue of critical importance in remote systems engineering is to make an optimal selection of technology and equipment that would best satisfy the as low as reasonably achievable (ALARA) requirements in terms of relevant criteria like dose reduction, reliability, costs, etc. In fact, good selection methodology is the key to efficient implementation of remote systems applications in the modern globalized market. This TECDOC gives a review of the current status of remote technology applications for spent fuel management, based on country reports from some Member States presented at the consultancy meetings, of which updated reports are attached in the annex. The scope of the review covers the series of spent fuel handling operations involved in spent fuel management, from discharge from reactor to reprocessing or

  19. Issues in Coastal Zone Management.

    Science.gov (United States)

    Davis, Derrin

    1992-01-01

    Addresses the following issues relevant to coastal zone management: overcrowding, resource exploitation, pollution, agriculture, fisheries, industrial, and other uses. Describes conflicts and trade-offs in management typified by fragmented agency decision making. Discusses implications of the greenhouse effect, sustainable development, and the…

  20. Accelerators and alternative nuclear fuel management options

    International Nuclear Information System (INIS)

    Harms, A.A.

    1983-01-01

    The development of special accelerators suggests the po tential for new directions in nuclear energy systems evolution. Such directions point towards a more acceptable form of nuclear energy by reason of the consequent accessibility of enhanced fuel management choices. Essential and specifically directed research and development activity needs to be under taken in order to clarify and resolve a number of technical issues

  1. Waste management issues, a set of technologies

    International Nuclear Information System (INIS)

    Gautrot, J.J.

    2000-01-01

    As any other industry, nuclear fuel cycle back-end raises the major issue of waste management. In France, spent fuel is considered as valuable materials and only the ultimate waste are considered as actual waste. Accordingly, waste issue is as follows: a sorting out has to be done, in order to separate valuable materials from actual wastes, put any outlet flow under a stable form and condition them appropriately to their respective recycling or disposal routes. This implies the implementation of a comprehensive set of technologies. Actually, it is an industrial reality, as the COGEMA Group has for a long time set up a reprocessing and conditioning strategy in its plants. Waste management issues are common to many activities. European as well as French regulators already introduced the twofold necessity to reduce waste volumes, and to dispose of only ''ultimate waste'' as concerns industrial and household waste mainly. In this objective, French nuclear reprocessing and recycling industry may be seen as a breeding ground of well-proven technologies and management options. Actually, processes used can also give an answer to such different issues as excess plutonium immobilization, sites cleaning up (including for instance treatment of the liquid HLW legacy), dismantling wastes management. There are a number of operations to be dealt with worldwide that will find a solution in any of the technologies implemented and optimized in COGEMA facilities. Based on the COGEMA Group know-how, the present paper will describe those technologies and explain how they can solve the other stringent waste management issues worldwide. (author)

  2. Issues Management Process Course # 38401

    Energy Technology Data Exchange (ETDEWEB)

    Binion, Ula Marie [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2018-02-01

    The purpose of this training it to advise Issues Management Coordinators (IMCs) on the revised Contractor Assurance System (CAS) Issues Management (IM) process. Terminal Objectives: Understand the Laboratory’s IM process; Understand your role in the Laboratory’s IM process. Learning Objectives: Describe the IM process within the context of the CAS; Describe the importance of implementing an institutional IM process at LANL; Describe the process flow for the Laboratory’s IM process; Apply the definition of an issue; Use available resources to determine initial screening risk levels for issues; Describe the required major process steps for each risk level; Describe the personnel responsibilities for IM process implementation; Access available resources to support IM process implementation.

  3. Quality management of nuclear fuel

    International Nuclear Information System (INIS)

    2006-01-01

    The Guide presents the quality management requirements to be complied with in the procurement, design, manufacture, transport, receipt, storage, handling and operation of nuclear fuel. The Guide also applies to control rods and shield elements to be placed in the reactor. The Guide is mainly aimed for the licensee responsible for the procurement and operation of fuel, for the fuel designer and manufacturer and for other organisations, whose activities affect fuel quality and the safety of fuel transport, storage and operation. General requirements for nuclear fuel are presented in Section 114 of the Finnish Nuclear Energy Decree and in Section 15 of the Government Decision (395/1991). Regulatory control of the safety of fuel is described in Guides YVL6.1, YVL6.2 and YVL6.3. An overview of the regulatory control of nuclear power plants carried out by STUK (Radiation and Nuclear Safety Authority, Finland) is clarified in Guide YVL1.1

  4. Strategic Issues in University Management

    NARCIS (Netherlands)

    Roosendaal, Hans E.

    2005-01-01

    In this paper we will discuss developments in the field of scientific information with the aim to determine and analyse some of the pertinent strategic issues related to higher education (HE) as seen from the stakeholder perspective of the university and its management.

  5. AGR fuel management using PANTHER

    International Nuclear Information System (INIS)

    Haddock, S.A.; Parks, G.T.

    1995-01-01

    This paper describes recent improvements in the AGR fuel management methodology implemented within PANTHER and the use of the code both for stand-alone calculations and within an automatic optimisation procedure. (author)

  6. Spent fuel management in Spain

    International Nuclear Information System (INIS)

    Gonzalez, J.L.

    2002-01-01

    The spent fuel management strategy in Spain is presented. The strategy includes temporary solutions and plans for final disposal. The need for R and D including partitioning and transmutation, as well as the financial constraints are also addressed. (author)

  7. Technical Issues in the development of high burnup and long cycle fuel pellets

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Dong Joo; Yang, Jae Ho; Oh, Jang Soo; Kim, Keon Sik; Rhee, Young Woo; Kim, Jong Hun; Nam, Ik Hui [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-10-15

    Over the last half century, a nuclear fuel cycle, a fuel discharged burnup and a uranium enrichment of the LWR (Light Water Reactor) fuel have continuously increased. It was the efforts to reduce the LWR fuel cycle cost, and to make reactor operation more efficiently. Improved fuel and reactor performance contribute further to the reduction and management efficiency of spent fuels. The primary incentive for operating nuclear reactor fuel to higher burnup and longer cycle is the economic benefits. The fuel cycle costs could be reduced by extending fuel discharged burnup and fuel cycle length. The higher discharged burnup can increase the energy production per unit fuel mass or fuel assembly. The longer fuel cycle can increase reactor operation flexibility and reduce the fuel changing operation and the spent fuel management burden. The margin to storage capacity limits would be also increased because high burnup and long cycle fuel reduces the mass of spent fuels. However, increment of fuel burnup and cycle length might result in the acceleration of material aging consisting fuel assembly. Then, the safety and integrity of nuclear fuel will be degraded. Therefore, to simultaneously enhance the safety and economics of the LWR fuel through the fuel burnup and cycle extension, it is indispensable to develop the innovative nuclear fuel material concepts and technologies which can overcome degradation of fuel safety. New fuel research project to extend fuel discharged burnup and cycle length has been launched in KAERI. Main subject is to develop innovative LWR fuel pellets which can provide required fuel performance and safety at extended fuel burnup and cycle length. In order to achieve the mission, we need to know that what the impediments are and how to break through current limit of fuel pellet properties. In this study, the technical issues related to fuel pellets at high burnup were surveyed and summarized. We have collected the technical issues in the literatures

  8. Technical Issues in the development of high burnup and long cycle fuel pellets

    International Nuclear Information System (INIS)

    Kim, Dong Joo; Yang, Jae Ho; Oh, Jang Soo; Kim, Keon Sik; Rhee, Young Woo; Kim, Jong Hun; Nam, Ik Hui

    2012-01-01

    Over the last half century, a nuclear fuel cycle, a fuel discharged burnup and a uranium enrichment of the LWR (Light Water Reactor) fuel have continuously increased. It was the efforts to reduce the LWR fuel cycle cost, and to make reactor operation more efficiently. Improved fuel and reactor performance contribute further to the reduction and management efficiency of spent fuels. The primary incentive for operating nuclear reactor fuel to higher burnup and longer cycle is the economic benefits. The fuel cycle costs could be reduced by extending fuel discharged burnup and fuel cycle length. The higher discharged burnup can increase the energy production per unit fuel mass or fuel assembly. The longer fuel cycle can increase reactor operation flexibility and reduce the fuel changing operation and the spent fuel management burden. The margin to storage capacity limits would be also increased because high burnup and long cycle fuel reduces the mass of spent fuels. However, increment of fuel burnup and cycle length might result in the acceleration of material aging consisting fuel assembly. Then, the safety and integrity of nuclear fuel will be degraded. Therefore, to simultaneously enhance the safety and economics of the LWR fuel through the fuel burnup and cycle extension, it is indispensable to develop the innovative nuclear fuel material concepts and technologies which can overcome degradation of fuel safety. New fuel research project to extend fuel discharged burnup and cycle length has been launched in KAERI. Main subject is to develop innovative LWR fuel pellets which can provide required fuel performance and safety at extended fuel burnup and cycle length. In order to achieve the mission, we need to know that what the impediments are and how to break through current limit of fuel pellet properties. In this study, the technical issues related to fuel pellets at high burnup were surveyed and summarized. We have collected the technical issues in the literatures

  9. Clearing and vegetation management issues

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    Clearing and continued management of incompatible plant species is critical to maintaining safe and reliable transmission and distribution lines at British Columbia Hydro. As part of a general review of policies regarding rights-of-way, the clearing of BC Hydro rights-of-way was studied by a task team in order to formulate a set of recommended policies and procedures to guide employees in all rights-of-way decisions, and to provide clear direction for resolution of all rights-of-way issues in a cost-effective manner. Issues reviewed were: clearing standards and line security standardization for transmission circuits; clearing rights for removal of trees or management of vegetation beyond the statutory right-of-way; clearing and vegetation management procedures; tree replacement; arboricultural techniques; periodic reviewing of clearing practices; compensation for tree removal; herbicide use; and heritage and wildlife trees. Justification for the recommendation is provided along with alternate options and costs of compliance

  10. Managing mixed wastes: technical issues

    International Nuclear Information System (INIS)

    Lytle, J.E.; Eyman, L.D.; Burton, D.W.; McBrayer, J.F.

    1986-01-01

    The US Department of Energy manages wastes that are both chemically hazardous and radioactive. These mixed wastes are often unique and many have national security implications. Management practices have evolved over the more than forty years that the Department and its predecessor agencies have been managing these wastes, both in response to better understanding of the hazards involved and in response to external, regulatory influences. The Department has recently standarized its waste management practices and has initited an R and D program to address priority issues identified by its operating contractor organizations. The R and D program is guided by waste management strategy that emphasizes reduction of human exposure to hazardous wastes in the environment, reduction of the amount and toxicity of wastes generated, treatment of wastes that are generated to reduce volumes and toxicities, and identification of alternatives to land disposal of wastes that remain hazardous following maximum practicable treatment

  11. Fuel cycle management in Finland

    International Nuclear Information System (INIS)

    Vaeyrynen, H.; Mikkola, I.

    1987-01-01

    Both Finnish utilities producing nuclear power - Imatran Voima Oy (IVO) and Teollisuuden Voima Oy (Industrial Power Co. Ltd, TVO) - have created efficient fuel cycle management systems. The systems however differ in almost all respects. The reason is that the principal supplier for IVO is the Soviet Union and for TVO is Sweden. A common feature of both systems at the front end of the cycle is the building of stockpiles in order to provide for interruptions in fuel deliveries. Quality assurance supervision at the fuel factory for IVO is regulated by the Soviet Chamber of Commerce and Industry and a final control is made in Finland. The in-core fuel management is done by IVO using codes developed in Finland. The whole IVO fuel cycle is basically a leasing arrangement. The spent fuel is returned to the USSR after five years cooling. TVO carries out the in-core fuel management using a computer code system supplied by Asea-Atom. TVO is responsable for the back end of the cycle and makes preparations for the final disposal of the spent fuel in Finland. 6 refs., 2 figs

  12. Spent fuel management in Japan

    International Nuclear Information System (INIS)

    Mineo, H.; Nomura, Y.; Sakamoto, K.

    1998-01-01

    In Japan 52 commercial nuclear power units are now operated, and the total power generation capacity is about 45 GWe. The cumulative amount of spent fuel arising is about 13,500 tU as of March 1997. Spent fuel is reprocessed, and recovered nuclear materials are to be recycled in LWRs and FBRs. In February 1997 short-term policy measures were announced by the Atomic Energy Commission, which addressed promotion of reprocessing programme in Rokkasho, plutonium utilization in LWRs, spent fuel management, backend measures and FBR development. With regard to the spent fuel management, the policy measures included expansion of spent fuel storage capacity at reactor sites and a study on spent fuel storage away from reactor sites, considering the increasing amount of spent fuel arising. Research and development on spent fuel storage has been carried out, particularly on dry storage technology. Fundamental studies are also conducted to implement the burnup credit into the criticality safety design of storage and transportation casks. Rokkasho reprocessing plant is being constructed towards its commencement in 2003, and Pu utilization in LWRs will be started in 1999. Research and development of future recycling technology are also continued for the establishment of nuclear fuel cycle based on FBRs and LWRs. (author)

  13. Fuel reprocessing and waste management

    International Nuclear Information System (INIS)

    Philippone, R.L.; Kaiser, R.A.

    1989-01-01

    Because of different economic, social and political factors, there has been a tendency to compartmentalize the commercial nuclear power industry into separate power and fuel cycle operations to a greater degree in some countries compared to other countries. The purpose of this paper is to describe how actions in one part of the industry can affect the other parts and recommend an overall systems engineering approach which incorporates more cooperation and coordination between individual parts of the fuel cycle. Descriptions are given of the fuel cycle segments and examples are presented of how a systems engineering approach has benefitted the fuel cycle. Descriptions of fuel reprocessing methods and the waste forms generated are given. Illustrations are presented describing how reprocessing options affect waste management operations and how waste management decisions affect reprocessing

  14. Spent fuel management overview: a global perspective

    International Nuclear Information System (INIS)

    Bonne, A.; Crijns, M.J.; Dyck, P.H.; Fukuda, K.; Mourogov, V.M.

    1999-01-01

    The paper defines the main spent fuel management strategies and options, highlights the challenges for spent fuel storage and gives an overview of the regional balances of spent fuel storage capacity and spent fuel arising. The relevant IAEA activities in the area of spent fuel management are summarised. (author)

  15. Spent fuel management in Japan

    International Nuclear Information System (INIS)

    Shirahashi, K.; Maeda, M.; Nakai, T.

    1996-01-01

    Japan has scarce energy resources and depends on foreign resources for 84% of its energy needs. Therefore, Japan has made efforts to utilize nuclear power as a key energy source since mid-1950's. Today, the nuclear energy produced from 49 nuclear power plants is responsible for about 31% of Japan's total electricity supply. The cumulative amount of spent fuel generated as of March 1995 was about 11,600 Mg U. Japan's policy of spent fuel management is to reprocess spent nuclear fuel and recycle recovered plutonium and uranium as nuclear fuel. The Tokai reprocessing plant continues stable operation keeping the annual treatment capacity or around 90 Mg U. A commercial reprocessing plant is under construction at Rokkasho, northern part of Japan. Although FBR is the principal reactor to use plutonium, LWR will be a major power source for some time and recycling of the fuel in LWRs will be prompted. (author). 3 figs

  16. Spent fuel management in Canada

    International Nuclear Information System (INIS)

    Khan, A.; Pattantyus, P.

    1999-01-01

    The current status of the Canadian spent fuel storage is presented. This includes wet and dry interim storage. Extension of wet interim storage facilities is nor planned, as dry technologies have found wide acceptance. The Canadian nuclear program is sustained by commercial Ontario Hydro CANDU type reactors, since 1971, representing 13600 MW(e) of installed capacity, able to produce 9200 spent fuel bundles (1800 tU) every year, and Hydro Quebec and New Brunswick CANDU reactors each producing 685 MW(e) and about 100 tU of spent fuel annually. The implementation of various interim (wt and dry) storage technologies resulted in simple, dense and low cost systems. Economical factors determined that the open cycle option be adopted for the CANDU type reactors rather that recycling the spent fuel. Research and development activities for immobilization and final disposal of nuclear waste are being undertaken in the Canadian Nuclear Fuel Waste Management Program

  17. Commercializing fuel cells: managing risks

    Science.gov (United States)

    Bos, Peter B.

    Commercialization of fuel cells, like any other product, entails both financial and technical risks. Most of the fuel cell literature has focussed upon technical risks, however, the most significant risks during commercialization may well be associated with the financial funding requirements of this process. Successful commercialization requires an integrated management of these risks. Like any developing technology, fuel cells face the typical 'Catch-22' of commercialization: "to enter the market, the production costs must come down, however, to lower these costs, the cumulative production must be greatly increased, i.e. significant market penetration must occur". Unless explicit steps are taken to address this dilemma, fuel cell commercialization will remain slow and require large subsidies for market entry. To successfully address this commercialization dilemma, it is necessary to follow a market-driven commercialization strategy that identifies high-value entry markets while minimizing the financial and technical risks of market entry. The financial and technical risks of fuel cell commercialization are minimized, both for vendors and end-users, with the initial market entry of small-scale systems into high-value stationary applications. Small-scale systems, in the order of 1-40 kW, benefit from economies of production — as opposed to economies to scale — to attain rapid cost reductions from production learning and continuous technological innovation. These capital costs reductions will accelerate their commercialization through market pull as the fuel cell systems become progressively more viable, starting with various high-value stationary and, eventually, for high-volume mobile applications. To facilitate market penetration via market pull, fuel cell systems must meet market-derived economic and technical specifications and be compatible with existing market and fuels infrastructures. Compatibility with the fuels infrastructure is facilitated by a

  18. Spent Nuclear Fuel project, project management plan

    International Nuclear Information System (INIS)

    Fuquay, B.J.

    1995-01-01

    The Hanford Spent Nuclear Fuel Project has been established to safely store spent nuclear fuel at the Hanford Site. This Project Management Plan sets forth the management basis for the Spent Nuclear Fuel Project. The plan applies to all fabrication and construction projects, operation of the Spent Nuclear Fuel Project facilities, and necessary engineering and management functions within the scope of the project

  19. CANDU-PHW fuel management

    International Nuclear Information System (INIS)

    Frescura, G.M.; Wight, A.L.

    1982-01-01

    This report covers the material presented in a series of six lectures at the Winter College on Nuclear Physics and Reactors held at the International Centre for Theoretical Physics in Trieste, Italy, Jan 22 - March 28, 1980. The report deals with fuel management in natural uranium fuelled CANDU-PHW reactors. Assuming that the reader has a basic knowledge of CANDU core physics, some of the reactor systems which are more closely related to fuelling are described. This is followed by a discussion of the methods used to calculate the power distribution and perform fuel management analyses for the equilibrium core. A brief description of some computer codes used in fuel management is given, together with an overview of the calculations required to provide parameters for core design and support the accident analysis. Fuel scheduling during approach to equilibrium and equilibrium is discussed. Fuel management during actual reactor operation is discussed with a review of the operating experience for some of the Ontario Hydro CANDU reactors. (author)

  20. Spent fuel management and closed nuclear fuel cycle

    International Nuclear Information System (INIS)

    Kudryavtsev, E.G.

    2012-01-01

    Strategic objectives set by Rosatom Corporation in the field of spent fuel management are given. By 2030, Russia is to create technological infrastructure for innovative nuclear energy development, including complete closure of the nuclear fuel cycle. A target model of the spent NPP nuclear fuel management system until 2030 is analyzed. The schedule for key stages of putting in place the infrastructure for spent NPP fuel management is given. The financial aspect of the problem is also discussed [ru

  1. Reactor core fuel management

    International Nuclear Information System (INIS)

    Silvennoinen, P.

    1976-01-01

    The subject is covered in chapters, entitled: concepts of reactor physics; neutron diffusion; core heat transfer; reactivity; reactor operation; variables of core management; computer code modules; alternative reactor concepts; methods of optimization; general system aspects. (U.K.)

  2. HFIR spent fuel management alternatives

    International Nuclear Information System (INIS)

    Begovich, J.M.; Green, V.M.; Shappert, L.B.; Lotts, A.L.

    1992-01-01

    The High Flux Isotope Reactor (HFIR) at Martin Marietta Energy Systems' Oak Ridge National Laboratory (ORNL) has been unable to ship its spent fuel to Savannah River Site (SRS) for reprocessing since 1985. The HFIR storage pools are expected to fill up in the February 1994 to February 1995 time frame. If a management altemative to existing HFIR pool storage is not identified and implemented before the HFIR pools are full, the HFIR will be forced to shut down. This study investigated several alternatives for managing the HFIR spent fuel, attempting to identify options that could be implemented before the HFIR pools are full. The options investigated were: installing a dedicated dry cask storage facility at ORNL, increasing HFIR pool storage capacity by clearing the HFIR pools of debris and either close-packing or stacking the spent fuel elements, storing the spent fuel at another ORNL pool, storing the spent fuel in one or more hot cells at ORNL, and shipping the spent fuel offsite for reprocessing or storage elsewhere

  3. Report of the international workshop on safety measures to address the year 2000 issue at radioactive waste management and nuclear fuel cycle facilities. (Supplement to IAEA-TECDOC-1073 and IAEA-TECDOC-1087)

    International Nuclear Information System (INIS)

    1999-08-01

    In resolution GC(42)/RES/11 on 'Measures to address the Year 2000 (Y2K) issue', adopted on 25 September 1998, the General Conference of the International Atomic Energy Agency (IAEA) - inter alia - urged Member States 'to share information with the Secretariat regarding diagnostic and corrective actions being planned or implemented by operating and regulatory organizations at ... fuel cycle facilities ... to make those facilities Year 2000 ready', encouraged the Secretariat, 'within existing resources, to act as a clearinghouse and central point of contact for Member States to exchange information regarding diagnostic and remediation actions being taken at ... fuel cycle facilities ... to make these facilities Year 2000 ready', urged the Secretariat 'to handle the information provided by Member States carefully' and requested the Director General to report to it at its next (1999) regular session on the implementation of that resolution. In response to resolution GC(42)/RES/11, the Secretariat convened: a group of consultants who met in Vienna from 20 to 22 January 1999 and produced a technical document (IAEA-TECDOC-1073) entitled Safety Measures to Address the Year 2000 Issue at Radioactive Waste Management Facilities; and a specialists meeting in Vienna from 24 to 26 March 1999, which produced a technical document (IAEA-TECDOC-1087) entitled Potential Vulnerabilities of Nuclear Fuel Cycle Facilities to the Year 2000 (Y2K) Issue and Measures to Address Them. To foster information exchange and share existing experience the IAEA held an International Workshop on Safety Measures to Address the Year 2000 Issue at Radioactive Waste Management and Nuclear Fuel Cycle Facilities in Vienna on 1-2 July 1999. Whereas the focus of TECDOC-1073 and TECDOC-1087 had been on identifying relevant safety issues in relation to Y2K computer problems and on proposing methods to address them, the focus of the International Workshop was on sharing experience, setting priorities

  4. Using Online Databases in Corporate Issues Management.

    Science.gov (United States)

    Thomsen, Steven R.

    1995-01-01

    Finds that corporate public relations practitioners felt they were able, using online database and information services, to intercept issues earlier in the "issue cycle" and thus enable their organizations to develop more "proactionary" or "catalytic" issues management repose strategies. (SR)

  5. Energy management in fuel cell power trains

    International Nuclear Information System (INIS)

    Corbo, P.; Corcione, F.E.; Migliardini, F.; Veneri, O.

    2006-01-01

    In this paper, experimental results obtained on a small size fuel cell power train (1.8 kW) based on a 500 W proton exchange membrane (PEM) stack are reported and discussed with specific regard to energy management issues to be faced for attainment of the maximum propulsion system efficiency. The fuel cell system (FCS) was realized and characterized via investigating the effects of the main operative variables on efficiency. This resulted in an efficiency higher than 30% in a wide power range with a maximum of 38% at medium load. The efficiency of the overall fuel cell power train measured during both steady state and dynamic conditions (European R40 driving cycle) was about 30%. A discussion about the control strategy to direct the power flows is reported with reference to two different test procedures used in dynamic experiments, i.e., load levelled and load following

  6. PWR fuel management optimization

    International Nuclear Information System (INIS)

    Dumas, Michel.

    1981-10-01

    This report is aimed to the optimization of the refueling pattern of a nuclear reactor. At the beginning of a reactor cycle a batch of fuel assemblies is available: the physical properties of the assemblies are known: the mathematical problem is to determine the refueling pattern which maximizes the reactivity or which provides the flattest possible power distribution. The state of the core is mathematically characterized by a system of partial derivative equations, its smallest eigenvalue and the associated eigenvector. After a study of the convexity properties of the problem, two algorithms are proposed. The first one exhanges assemblies to improve the starting configurations. The enumeration of the exchanges is limited to the 2 by 2, 3 by 3, 4 by 4 permutations. The second one builds a solution in two steps: in the first step the discrete variables are replaced by continuous variables. The non linear optimization problem obtained is solved by ''the Method of Approximation Programming'' and in the second step, the refuelling pattern which provides the best approximation of the optimal power distribution is searched by a Branch an d Bound Method [fr

  7. Management of irradiated CANDU fuel

    International Nuclear Information System (INIS)

    Lupien, Mario

    1985-01-01

    The nuclear industry, like any other industrial activity, generates waste and, since these radioactive products are known to be hazardous both to man and his natural environment, they are subject to stringent controls. The irradiated fuel is also highly radioactive and remains so for thousands of years. It is estimated that by the year 2000, nuclear reactors in Canada alone will have produced some 50 Gg of radioactive fuel which is stored at the nuclear plant site itself. The nuclear industry plays a leading role in the research and development effort to find suitable waste-management methods. Its R and D programs cover many scientific fields, including chemistry, and therefore demand a considerable amount of coordination. The knowledge acquired in this multidisciplinary context should form a basis for solving many of today's industrial-waste problems. This paper describes the various stages in the long management process. In the medium term, the irradiated fuel will be stored in surface installations but the long-term solution proposed is to emplace the used fuel or the fuel recycle waste deep underground in a stable geologic formation

  8. Critical Issues for Particle-Bed Reactor Fuels

    Science.gov (United States)

    Evans, Robert S.; Husser, Dewayne L.; Jensen, Russell R.; Kerr, John M.

    1994-07-01

    Particle-Bed Reactors (PBRs) potentially offer performance advantages for nuclear thermal propulsion, including very high power densities, thrust-to-weight ratios, and specific impulses. A key factor in achieving all of these is the development of a very-high-temperature fuel. The critical issues for all such PBR fuels are uranium loading, thermomechanical and thermochemical stability, compatibility with contacting materials, fission product retention, manufacturability, and operational tolerance for particle failures. Each issue is discussed with respect to its importance to PBR operation, its status among current fuels, and additional development needs. Mixed-carbide-based fuels are recommended for further development to support high-performance PBRs.

  9. Spent fuel management in Spain

    International Nuclear Information System (INIS)

    Gago, J.A.; Gravalos, J.M.

    1996-01-01

    There are presently nine Light Water Reactors in operation, representing around a 34% of the overall electricity production. In the early years, a small amount of spent fuel was sent to be reprocessed, although this policy was cancelled in favor of the open cycle option. A state owned company, ENRESA, was created in 1984, which was given the mandate to manage all kinds of radioactive wastes generated in the country. Under the present scenario, a rough overall amount of 7000 tU of spent fuel will be produced during the lifetime of the plants, which will go into final disposal. (author)

  10. Nuclear fuel assurance: origins, trends, and policy issues

    International Nuclear Information System (INIS)

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

    1979-02-01

    The economic, technical and political issues which bear on the security of nuclear fuel supply internationally are addressed. The structure of international markets for nuclear fuel is delineated; this includes an analysis of the political constraints on fuel availability, especially the connection to supplier nonproliferation policies. The historical development of nuclear fuel assurance problems is explored and an assessment is made of future trends in supply and demand and in the political context in which fuel trade will take place in the future. Finally, key events and policies which will affect future assurance are identified

  11. Environmental issues in operations management

    Science.gov (United States)

    Muthulingam, Suresh

    Adoption of sustainable operating practices is becoming an increasingly important issue for many organizations in the world today. In this dissertation, I use empirical methods to investigate factors that influence the adoption of sustainable practices and also identify issues that may hinder the adoption of such practices. I explore these issues in two diverse settings. In Chapter 1, I investigate the adoption and non-adoption of energy efficiency initiatives using a database of over 100,000 recommendations provided to more than 13,000 small and medium sized manufacturing firms. Even though the average payback across all recommendations is just over one year, many of these profitable opportunities are not implemented. Using a probit instrumental variable model, I identify four biases in the adoption of these recommendations. First, managers are myopic as they miss out on many profitable opportunities. Second, managers are more influenced by upfront costs than by net benefits when evaluating such initiatives. Third, adoption of a recommendation depends not only on its characteristics but also on the sequence in which the recommendations are presented. Adoption rates are higher for initiatives appearing early in a list of recommendations. Finally, adoption is not influenced by the number of options provided to decision makers. This contributes to the debate about whether or not choice overload occurs. We highlight decision biases previously unobserved in the Operations Management literature using field data rather than experimental data. We draw implications for enhancing adoption of energy efficiency initiatives and for other decision contexts where a collection of process improvement recommendations are made to firms. In Chapter 2, I examine the depth of adoption of the voluntary LEED (Leadership in Energy and Environmental Design) standards for green buildings. Depth of adoption refers to the extent to which the buildings adopt practices related to the standard

  12. Issues affecting the acceptance of hydrogen fuel

    International Nuclear Information System (INIS)

    Schulte, I.; Hart, D.; Vorst, R. van der

    2004-01-01

    While the topic of hydrogen as an alternative vehicle fuel is gaining increasing attention internationally, one significant aspect of its introduction has been given less attention than others: the public acceptance of such a new technology and fuel. After reviewing the existing literature on acceptance, risk perception and customer satisfaction, this paper describes the development of a model that illustrates important aspects in influencing a person's attitude towards a new product. 'Values', 'wants' and 'perception' are the three components found to influence acceptance, they themselves are affected by 'social background' and 'experience'. Suggestions are then given on how to use marketing methods, education projects and product exposure in order to maximise the likelihood of a successful introduction of hydrogen as an alternative fuel. (author)

  13. User requirements for innovative nuclear reactors and fuel cycle technologies in the area of economics, environment, safety, waste management, proliferation resistance and cross cutting issues, and methodology for innovative technologies assessment

    International Nuclear Information System (INIS)

    Kupitz, Juergen; Depisch, Frank; Allan, Colin

    2003-01-01

    The IAEA General Conference in 2000 has invited ''all interested Member States to combine their efforts under the aegis of the Agency in considering the issues of the nuclear fuel cycle, in particular by examining innovative and proliferation-resistant nuclear technology''. In response to this invitation, the IAEA initiated an ''International Project on Innovative Nuclear Reactors and Fuel Cycles'', INPRO. The overall objectives of INPRO is to help to ensure that nuclear energy is available to contribute in fulfilling in a sustainable manner energy needs in the 21st century, and to bring together all interested Member States, both technology holders and technology users, to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles that use sound and economically competitive technology. Phase-I of INPRO was initiated in May 2001. During Phase-I, work was subdivided in two sub phase: Phase 1A (finished in June 2003) and Phase 1B (started in June 2003). Phase 1A dealt with the definition of Basic Principles, User Requirements and Criteria, and the development of a methodology for the evaluation of innovative nuclear technologies. In Phase 1A, task groups for several areas were established: (a) Prospects and Potentials of Nuclear Power, (b) Economics; (c) Sustainability and Environment, (d) Safety of Nuclear Installations, (e) Waste Management, (f) Proliferation Resistance, (g) Crosscutting issues and (h) for the Methodology for Assessment. In Phase-IB evaluations of innovative nuclear energy technologies will be performed by Member States against the INPRO Basic Principles, User Requirements and Criteria. This paper summarizes the results achieved in the Phase 1A of INPRO and is a cooperative effort of the INPRO team, consisting of all INPRO cost free experts and task managers. (author)

  14. The transportation issue management system: A tool for issue resolution

    International Nuclear Information System (INIS)

    Branch, K.M.; Boryczka, M.K.

    1987-01-01

    During the last decade, issue management programs have been developed and used by a number of large corporations in the United States. These systems have generally been designed to help senior program managers identify issues, develop strategic plans, and resolve issues. These systems involve scanning and abstracting literature to create a database that is then used for 1) issue identification, 2) issue analysis, 3) priority assessment, 4) development of corporate position/strategic options, and 5) action planning and implementation. Most of the existing systems rely on staff to identify trends in the computerized output, analyze the importance of the issue to the company, and assist in developing corporate responses. The Department of Energy has recently developed an issue management system for the Office of Civilian Radioactive Waste Management's (OCRWM) transportation program. This system is designed to help DOE identify institutional issues related to radioactive waste transportation, analyze the issues, and resolve them in a manner that is responsive to interested parties. The system will contain pertinent information from DOE technical reports, other federal documents, correspondence, professional journals, popular literature, newsclips, legislation and testimony. The program is designed around a number of institutional issues including: prenotification, physical protection procedures; highway, rail, and barge routing; inspections and enforcement of shipments; emergency response; liability, cask design and testing; overweight trucks; rail service; modal mix; infrastructure improvements; training standards, and operational procedures

  15. Control issues in oxy-fuel combustion

    Energy Technology Data Exchange (ETDEWEB)

    Snarheim, Dagfinn

    2009-08-15

    Combustion of fossil fuels is the major energy source in todays society. While the use of fossil fuels is a necessity for our society to function, there has been an increasing concern on the emissions of CO{sub 2} resulting from human activities. Emissions of CO{sub 2} are considered to be the main cause for the global warming and climate changes we have experienced in recent years. To fight the climate changes, the emissions of CO{sub 2} must be reduced in a timely fashion. Strategies to achieve this include switching to less carbon intensive fuels, renewable energy sources, nuclear energy and combustion with CO{sub 2} capture. The use of oxy-fuel combustion is among the alternative post- and pre combustion capture concepts, a strategy to achieve power production from fossil fuels with CO{sub 2} capture. In an oxy-fuel process, the fuel is burned in a mixture of oxygen and CO{sub 2} (or steam), leaving the exhaust consisting mainly of CO{sub 2} and steam. The steam can be removed by use of a condenser, leaving (almost) pure CO{sub 2} ready to be captured. The downside to CO{sub 2} capture is that it is expensive, both in capital cost of extra equipment, and in operation as it costs energy to capture the CO{sub 2}. Thus it is important to maximize the efficiency in such plants. One attractive concept to achieve CO{sub 2} capture by use of oxy-fuel, is a semi-closed oxy-fuel gas turbine cycle. The dynamics of such a plant are highly integrated, involving energy and mass recycle, and optimizing efficiency might lead to operational (control) challenges. In these thesis we investigate how such a power cycle should be controlled. By looking at control at such an early stage in the design phase, it is possible to find control solutions otherwise not feasible, that leads to better overall performance. Optimization is used on a nonlinear model based on first principles, to compare different control structures. Then, closed loop simulations using MPC, are used to validate

  16. Review: Durability and degradation issues of PEM fuel cell components

    NARCIS (Netherlands)

    Bruijn, de F.A.; Dam, V.A.T.; Janssen, G.J.M.

    2008-01-01

    Besides cost reduction, durability is the most important issue to be solved before commercialisation of PEM Fuel Cells can be successful. For a fuel cell operating under constant load conditions, at a relative humidity close to 100% and at a temperature of maximum 75 °C, using optimal stack and flow

  17. 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

  18. PEM fuel cells thermal and water management fundamentals

    CERN Document Server

    Wang, Yun; Cho, Sung Chan

    2014-01-01

    Polymer Electrolyte Membrane (PEM) fuel cells convert chemical energy in hydrogen into electrical energy with water as the only by-product. Thus, PEM fuel cells hold great promise to reduce both pollutant emissions and dependency on fossil fuels, especially for transportation-passenger cars, utility vehicles, and buses-and small-scale stationary and portable power generators. But one of the greatest challenges to realizing the high efficiency and zero emissions potential of PEM fuel cells technology is heat and water management. This book provides an introduction to the essential concepts for effective thermal and water management in PEM fuel cells and an assessment on the current status of fundamental research in this field. The book offers you: An overview of current energy and environmental challenges and their imperatives for the development of renewable energy resources, including discussion of the role of PEM fuel cells in addressing these issues; Reviews of basic principles pertaining to PEM fuel cel...

  19. Spent fuel transportation regulatory and institutional issues

    International Nuclear Information System (INIS)

    Lippek, H.E.

    1978-01-01

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

  20. Safety and Regulatory Issues of the Thorium Fuel Cycle

    Energy Technology Data Exchange (ETDEWEB)

    Ade, Brian [ORNL; Worrall, Andrew [ORNL; Powers, Jeffrey [ORNL; Bowman, Steve [ORNL; Flanagan, George [ORNL; Gehin, Jess [ORNL

    2014-02-01

    Thorium has been widely considered an alternative to uranium fuel because of its relatively large natural abundance and its ability to breed fissile fuel (233U) from natural thorium (232Th). Possible scenarios for using thorium in the nuclear fuel cycle include use in different nuclear reactor types (light water, high temperature gas cooled, fast spectrum sodium, molten salt, etc.), advanced accelerator-driven systems, or even fission-fusion hybrid systems. The most likely near-term application of thorium in the United States is in currently operating light water reactors (LWRs). This use is primarily based on concepts that mix thorium with uranium (UO2 + ThO2), add fertile thorium (ThO2) fuel pins to LWR fuel assemblies, or use mixed plutonium and thorium (PuO2 + ThO2) fuel assemblies. The addition of thorium to currently operating LWRs would result in a number of different phenomenological impacts on the nuclear fuel. Thorium and its irradiation products have nuclear characteristics that are different from those of uranium. In addition, ThO2, alone or mixed with UO2 fuel, leads to different chemical and physical properties of the fuel. These aspects are key to reactor safety-related issues. The primary objectives of this report are to summarize historical, current, and proposed uses of thorium in nuclear reactors; provide some important properties of thorium fuel; perform qualitative and quantitative evaluations of both in-reactor and out-of-reactor safety issues and requirements specific to a thorium-based fuel cycle for current LWR reactor designs; and identify key knowledge gaps and technical issues that need to be addressed for the licensing of thorium LWR fuel in the United States.

  1. Biodiesel fuel costs and environmental issues when powering railway locomotives

    Energy Technology Data Exchange (ETDEWEB)

    Mirza, Abdul; Ziemer, Norbert; Tatara, Robert; Moraga, Reinaldo; Mirman, Clifford; Vohra, Promod

    2010-09-15

    Issues for adopting biodiesel fuel, instead of petrodiesel, to power railroad locomotives are engine performance and emissions, fuel infrastructure, and fuel cost. These are evaluated for B2 through B100 blends. Biodiesel's solvent action on fuel systems is addressed. With biodiesel, hydrocarbon, carbon monoxide, and particulate emissions are unchanged or reduced. Nitrogen oxides are elevated but it is believed that engine alterations can minimize these emissions. A Transportation Model, using data from a major railway, has demonstrated that refueling depots can be fully supplied with biodiesel at a pricing premium of 1% to 26%, depending on blend and geographical location.

  2. Nuclear fuel management via fuel quality factor averaging

    International Nuclear Information System (INIS)

    Mingle, J.O.

    1978-01-01

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

  3. Safety of fuel cycle facilities. Topical issues paper no. 3

    International Nuclear Information System (INIS)

    Ranguelova, V.; Niehaus, F.; Delattre, D.

    2001-01-01

    that the relative hazards vary from facility to facility depending upon the processes employed. However, all installations should be designed and operated so as to keep all sources of radiation exposure under strict technical and administrative control. The design management should ensure that the structures, systems and components important to safety have the appropriate characteristics, specifications and material composition to perform the required safety functions. Emphasis should be placed on the use of proven engineered safety features in the implementation of the defence in depth concept in the facility design and operation. The development of nuclear safety standards is one of the tasks given by the Statute of the IAEA. Over a number of years, the IAEA has developed a comprehensive set of publications which address, in a structured manner, the safety of nuclear installations. The Safety Fundamentals publication entitled 'The Safety of Nuclear Installations' presents an international consensus on the basic concepts underlying the principles for the regulation, design and operation of nuclear installations, including fuel cycle facilities. Detailed requirements and guides for activities relating to siting, design, construction, operation, decommissioning and regulation of nuclear installations are addressed by lower hierarchy safety standards, which cover nuclear power plants (NPPs) and research reactors. Although some of the IAEA NPP standards can be adapted and applied to fuel cycle facilities and some standards on criticality safety are published by the International Organization for Standardization (ISO), in general there is a lack of international safety standards to cover the safety of such facilities. With a view to establishing a plan for the development of safety standards for fuel cycle facilities, the IAEA began to compile information on the status of national regulations and safety issues concerning such facilities. It also held a Technical Committee

  4. 96 Globalization and Management: Issues and Concepts

    African Journals Online (AJOL)

    User

    2010-10-17

    Oct 17, 2010 ... Oseyomon, Ehi Patrick - Department of Business, Admiistration, Faculty of. Management ... attention of scholars apart from economic issues such as trade, labour practices, the ..... Moral Issues in Business. 6th Edition. In C.

  5. Public policy issues in nuclear waste management

    International Nuclear Information System (INIS)

    Nealey, S.M.; Radford, L.M.

    1978-10-01

    This document aims to raise issues and to analyze them, not resolve them. The issues were: temporal equity, geographic and socioeconomic equity, implementation of a nuclear waste management system, and public involvement

  6. Strategies of management of the nuclear fuel

    International Nuclear Information System (INIS)

    Leon, J.R.; Perez, A.; Filella, J.M.

    1996-01-01

    The management of nuclear fuel is depending on several factors: - Regulatory commission. The enterprises owner of the NPPs.The enterprise owner of the energy distribution. These factors are considered for the management of nuclear fuel. The design of fuel elements, the planning of cycles, the design of core reactors and the costs are analyzed. (Author)

  7. Current status of IAEA activities in spent fuel management

    International Nuclear Information System (INIS)

    Danker, W.J.

    2003-01-01

    Spent fuel storage is a common issue in all IAEA Member States with nuclear reactors. Whatever strategy is selected for the back-end of the nuclear fuel cycle, the storage of spent fuel will be an increasingly significant consideration. Notwithstanding considerable efforts to increase the efficient use of nuclear fuel and to optimize storage capacity, delays in plans for geological repositories or in implementing reprocessing result in increased spent fuel storage capacity needs in combination with longer storage durations over the foreseeable future. As storage inventories and durations increase, issues associated with long term storage compel more attention...monitoring for potential degradation mechanisms, records retention, maintenance, efficiencies through burnup credit. Since the IAEA contribution to ICNC'99 focused exclusively on IAEA burnup credit activities including requirements and methods, this paper provides a broader perspective on IAEA activities in response to the above trends in spent fuel management, while also describing efforts to disseminate information regarding burnup credit applications. (author)

  8. Spent Nuclear Fuel Project Safety Management Plan

    International Nuclear Information System (INIS)

    Garvin, L.J.

    1996-02-01

    The Spent Nuclear Fuel Project Safety Management Plan describes the new nuclear facility regulatory requirements basis for the Spemt Nuclear Fuel (SNF) Project and establishes the plan to achieve compliance with this basis at the new SNF Project facilities

  9. Investigation of Burnup Credit Issues in BWR Fuel

    International Nuclear Information System (INIS)

    Broadhead, B.L.; DeHart, M.D.

    1999-01-01

    Calculations for long-term-disposal criticality safety of spent nuclear fuel requires the application of burnup credit because of 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, followed by criticality calculations to assess the value of keff for 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 used to characterize spent fuel. Most effort in the United States this decade has focused on burnup issues related to pressurized-water reactors. However, requirements for the permanent disposal of fuel from boiling-water reactors has necessitated development of methods for prediction of spent fuel contents for such fuels. Concomitant with such analyses, validation is also necessary. This paper provides a summary of initial efforts at the Oak Ridge National Laboratory to better understand and validate spent fuel analyses for boiling-water-reactor fuel

  10. An overview of economic and technical issues related to LWR MOX fuel usage

    International Nuclear Information System (INIS)

    Malone, J.P.; Varley, G.; Goldstein, L.

    1999-01-01

    This paper will present comparisons of the economics of MOX versus UO 2 fuels. In addition to the economics of the front end, the scope of the comparison will include the back end of the fuel cycle. Management of spent MOX fuel assemblies presents utilities with some technical issues that can complicate spent fuel pool operation. Alternative spent fuel management methods, such as dry storage of spent MOX fuel assemblies, will also be discussed. Differences in decay heat loads versus time for spent MOX and UO 2 fuel assemblies will be presented. This difference is one of the main problems confronting spent fuel managers relative to MOX. The difference in decay heat loads will serve as the basis for a performance overview of the various spent fuel technologies available today. The economics of the front end of MOX will be presented relative to UO 2 fuel. Availability of MOX manufacturing capability will also be discussed, along with a discussion of its impact on future MOX fabrication prices. The in-core performance of MOX will be compared to that of UO 2 fuel with similar performance characteristics. The information will include highlights of nuclear design and related operational considerations such as: Reactivity reduction with burnup is slower for MOX fuel than for UO 2 fuel; Spectral hardening resulting in lower control rod worths and a lower soluble boron worth; and more negative moderator, void and fuel temperature coefficients. A comparison of Westinghouse and ABB-CE core designs for use on disposition of weapons MOX in 12- and 18-month cycles will be presented. (author)

  11. Spent nuclear fuel management. Moving toward a century of spent fuel management: A view from the halfway mark

    International Nuclear Information System (INIS)

    Shephard, L.

    2004-01-01

    Full text: A half-century ago, President Eisenhower in his 1953 'Atoms for Peace' speech, offered nuclear technology to other nations as part of a broad nuclear arms control initiative. In the years that followed, the nuclear power generation capabilities of many nations has helped economic development and contributed to the prosperity of the modern world. The growth of nuclear power, while providing many benefits, has also contributed to an increasing global challenge over safe and secure spent fuel management. Over 40 countries have invested in nuclear energy, developing over 400 nuclear power reactors. Nuclear power supplies approximately 16% of the global electricity needs. With the finite resources and challenges of fossil fuels, nuclear power will undoubtedly become more prevalent in the future, both in the U.S. and abroad. We must address this inevitability with new paradigms for managing a global nuclear future. Over the past fifty years, the world has come to better understand the strong interplay between all elements of the nuclear fuel cycle, global economics, and global security. In the modern world, the nuclear fuel cycle can no longer be managed as a simple sequence of technological, economic and political challenges. Rather it must be seen, and managed, as a system of strongly interrelated challenges. Spent fuel management, as one element of the nuclear fuel system, cannot be relegated to the back-end of the fuel cycle as only a disposal or storage issue. There exists a wealth of success and experience with spent fuel management over the past fifty years. We must forge this experience with a global systems perspective, to reshape the governing of all aspects of the nuclear fuel cycle, including spent fuel management. This session will examine the collective experience of spent fuel management enterprises, seeking to shape the development of new management paradigms for the next fifty years. (author)

  12. CANFLEX-NU fuel licensing status and issues in Korea

    International Nuclear Information System (INIS)

    Geun-Sun Auh; Jun-Sang Park; Sweng-Woong Woo; Yong-Ho Ryu

    1999-01-01

    The CANFLEX-NU Fuel Design Report (FDR) for Wolsung 1,2,3,4 was submitted for licensing review in July 1996. The FDR contains sections of fuel rod design, fuel bundle design, nuclear design and thermal-hydraulic design. Each section describes the design bases, design methodology and design evaluation results showing that the design bases are met. The CANFLEX-NU fuel design is not finalized yet in Korean licensing point of view. For example, among others, new Xc-BL correlation is needed to be developed, fuel rod gap reduction effect is to be considered in the Critical Heat Flux, more information for power ramp defect of fuel rod especially in the end-cap weld region is needed in the fuel rod design, and enough data are not available in irradiated conditions in the fuel rod and bundle designs. The specific detailed technical licensing issues and their backgrounds are explained for the CANFLEX-NU FDR in Korea. The Korean nuclear regulation environment is changing due to the Korean government policy of overall regulation reduction. The contents and timetables of Korean nuclear regulation changes are also explained for new fuel licensing. (author)

  13. Incentive Issues in Information Security Management

    Science.gov (United States)

    Lee, Chul Ho

    2012-01-01

    This dissertation studies three incentive issues in information security management. The first essay studies contract issues between a firm that outsources security functions and a managed security service provider (MSSP) that provides security functions to the firm. Since MSSP and firms cannot observe each other's actions, both can suffer…

  14. Spent fuel management in India

    International Nuclear Information System (INIS)

    Balu, K.

    1998-01-01

    From Indian point of view, the spent fuel management by the reprocessing and plutonium recycle option is considered to be a superior and an inevitable option. The nuclear energy programme in Indian envisages three stages of implementation involving installation of thermal reactors in the first phase followed by recycling of plutonium from reprocessed fuel in fast breeder reactors and in the third phase utilization of its large thorium reserves in reactor system based on U-233-Th cycle. The Indian programme for Waste Management envisages disposal of low and intermediate level radioactive waste in near surface disposal facilities and deep geological disposal for high level and alpha bearing wastes. A Waste Immobilization Plant (WHIP), employing metallic melter for HLW vitrification is operational at Tarapur. Two more WIPs are being set up at Kalpakkam and Tarapur. A Solid waste Storage Surveillance Facility (SSSF) is also set up for interim storage of vitrified HLW. Site investigations are in progress for selecting site for ultimate disposal in igneous rock formations. R and D works is taken up on partitioning of HLW. Solvent extraction and extraction chromatographic studies are in progress. Presently emphasis is on separation of heat generating short lived nuclides like strontium and alpha emitters. (author)

  15. Areva solutions for management of defective fuel

    International Nuclear Information System (INIS)

    Morlaes, I.; Vo Van, V.

    2014-01-01

    Defective fuel management is a major challenge for nuclear operators when all fuel must be long-term managed. This paper describes AREVA solutions for managing defective fuel. Transport AREVA performs shipments of defective fuel in Europe and proposes casks that are licensed for that purpose in Europe and in the USA. The paper presents the transport experience and the new European licensing approach of defective fuel transport. Dry Interim Storage AREVA is implementing the defective fuel storage in the USA, compliant with the Safety Authority's requirements. In Europe, AREVA is developing a new, more long-term oriented storage solution for defective fuel, the best available technology regarding safety requirements. The paper describes these storage solutions. Treatment Various types of defective fuel coming from around the world have been treated in the AREVA La Hague plant. Specific treatment procedures were developed when needed. The paper presents operational elements related to this experience. (authors)

  16. Conceptual development of a test facility for spent fuel management

    Energy Technology Data Exchange (ETDEWEB)

    Park, S.W.; Lee, H.H.; Lee, J.Y.; Lee, J.S.; Ro, S.G. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    Spent fuel management is an important issue for nuclear power program, requiring careful planning and implementation. With the wait-and-see policy on spent fuel management in Korea, research efforts are directed at KAERI to develop advanced technologies for safer and more efficient management of the accumulating spent fuels. In support of these research perspectives, a test facility of pilot scale is being developed with provisions for integral demonstration of a multitude of technical functions required for spent fuel management. The facility, baptized SMART (Spent fuel MAnagement technology Research and Test facility), is to be capable of handling full size assembly of spent PWR fuel (as well as CANDU fuel) with a maximum capacity of 10 MTU/y (about 24 assemblies of PWR type). Major functions of the facility are consolidation of spent PWR fuel assembly into a half-volume package and optionally transformation of the fuel rod into a fuel of CANDU type (called DUPIC). Objectives of these functions are to demonstrate volume reduction of spent fuel (for either longer-term dry storage or direct disposal ) in the former case and direct refabrication of the spent PWR fuel into CANDU-type DUPIC fuel for reuse in CANDU reactors in the latter case, respectively. In addition to these major functions, there are other associated technologies to be demonstrated : such as waste treatment, remote maintenance, safeguards, etc. As the facility is to demonstrate not only the functional processes but also the safety and efficiency of the test operations, engineering criteria equivalent to industrial standards are incorporated in the design concept. The hot cell structure enclosing the radioactive materials is configured in such way to maximize costs within the given functional and operational requirements. (author). 3 tabs., 4 figs.

  17. Conceptual development of a test facility for spent fuel management

    International Nuclear Information System (INIS)

    Park, S.W.; Lee, H.H.; Lee, J.Y.; Lee, J.S.; Ro, S.G.

    1997-01-01

    Spent fuel management is an important issue for nuclear power program, requiring careful planning and implementation. With the wait-and-see policy on spent fuel management in Korea, research efforts are directed at KAERI to develop advanced technologies for safer and more efficient management of the accumulating spent fuels. In support of these research perspectives, a test facility of pilot scale is being developed with provisions for integral demonstration of a multitude of technical functions required for spent fuel management. The facility, baptized SMART (Spent fuel MAnagement technology Research and Test facility), is to be capable of handling full size assembly of spent PWR fuel (as well as CANDU fuel) with a maximum capacity of 10 MTU/y (about 24 assemblies of PWR type). Major functions of the facility are consolidation of spent PWR fuel assembly into a half-volume package and optionally transformation of the fuel rod into a fuel of CANDU type (called DUPIC). Objectives of these functions are to demonstrate volume reduction of spent fuel (for either longer-term dry storage or direct disposal ) in the former case and direct refabrication of the spent PWR fuel into CANDU-type DUPIC fuel for reuse in CANDU reactors in the latter case, respectively. In addition to these major functions, there are other associated technologies to be demonstrated : such as waste treatment, remote maintenance, safeguards, etc. As the facility is to demonstrate not only the functional processes but also the safety and efficiency of the test operations, engineering criteria equivalent to industrial standards are incorporated in the design concept. The hot cell structure enclosing the radioactive materials is configured in such way to maximize costs within the given functional and operational requirements. (author). 3 tabs., 4 figs

  18. Sustainability issues for resource managers.

    Science.gov (United States)

    Daniel L. Bottom; Gordon H. Reeves; Martha H. Brookes

    1996-01-01

    Throughout their history, conservation science and sustainable-yield management have failed to maintain the productivity of living resources. Repeated overexploitation of economic species, loss of biological diversity, and degradation of regional environments now call into question the economic ideas and values that have formed the foundation of scientific management...

  19. Plutonium recycle. In-core fuel management

    International Nuclear Information System (INIS)

    Vincent, F.; Berthet, A.; Le Bars, M.

    1985-01-01

    Plutonium recycle in France will concern a dozen of PWR 900 MWe controlled in gray mode till 1995. This paper presents the main characteristics of fuel management with plutonium recycle. The organization of management studies will be copied from this developed for classical management studies. Up these studies, a ''feasibility report'' aims at establishing at each stage of the fuel cycle, the impact of the utilization of fuel containing plutonium [fr

  20. Safety issues of dry fuel storage at RSWF

    International Nuclear Information System (INIS)

    Clarksean, R.L.; Zahn, T.P.

    1995-01-01

    Safety issues associated with the dry storage of EBR-II spent fuel are presented and discussed. The containers for the fuel have been designed to prevent a leak of fission gases to the environment. The storage system has four barriers for the fission gases. These barriers are the fuel cladding, an inner container, an outer container, and the liner at the RSWF. Analysis has shown that the probability of a leak to the environment is much less than 10 -6 per year, indicating that such an event is not considered credible. A drop accident, excessive thermal loads, criticality, and possible failure modes of the containers are also addressed

  1. Issues in Canadian LLRW management

    International Nuclear Information System (INIS)

    Charlesworth, D.H.

    1988-01-01

    Some of the issues which are of concern in Canada are similar to those being discussed in the US because Canadian low-level radioactive waste (LLRW) production is similar in quantity and characteristics to that which will be handled by some state compacts. This paper gives a Canadian viewpoint of: the choice between interim storage and permanent disposal; the importance of considering inadvertent intrusion; the role of waste categorization and stability; and the concerns in assessing disposal performance. The discussion is related to Atomic Energy of Canada Limited's LLRW disposal program, and its approach to resolving these issues

  2. MANAGEMENT OF EXAMINATIONS: ETHICAL ISSUES.

    African Journals Online (AJOL)

    Elizabeth

    Abstract. Examinations occupy a strategic position in our lives and society today.. In a .... Test Development and Research Office (TEDRO), as an arm of WAEC. ..... classroom management as proposed by Queen, Blackwelder & Mallen. (1997):.

  3. Review of spent fuel related issues in SKB's SR 97

    International Nuclear Information System (INIS)

    Grambow, B.

    2000-01-01

    The solid waste form 'spent fuel' constitutes both the dominant radionuclide source as well as a first radionuclide retention barrier of a planned future high level nuclear waste isolation systems in deep granite formations. In order to evaluate the performance of spent fuel as part of the multibarrier containment system in a deep repository, the radionuclide release properties in groundwater must be predicted over very long time periods. Radionuclide release is not an inherent materials property of the fuel but depends, besides fuel specific parameters, mainly on time but as well on the geochemical and hydraulic environment of the disposal location. The study SR 97 documents the large effort of SKB to assess the long-term performance of a repository containing spent nuclear fuel. Scenario and consequence analyses are clearly described, considering major physical and chemical interactions of the various components of the multi-barrier isolation system. The approach attempts to assess both a realistic and a pessimistic evolution scenario. The present report attempts to evaluate whether this approach is thoroughly carried through to assess the performance of spent nuclear fuel in a repository. Main issues are radionuclide inventories and inventory distribution between structural parts of the fuel assembly and the fuel matrix, potential fuel alteration prior to water access, as well as models for fuel matrix dissolution and instant release fractions. Uncertainties in radionuclide inventories are discussed and were found for many radionuclides to be higher than assumed in SR 97. This is particularly true for Cl-36. This nuclide is a potential key biosphere dose contributor in various international safety assessments. Of particular importance are uncertainties related to the partition of radionuclides between metallic parts of the fuel assembly and the fuel matrix, since inventories of metallic parts are considered to be released instantaneously. Using C-14 as an

  4. The Canadian fuel waste management program

    International Nuclear Information System (INIS)

    McConnell, D.B.

    1986-04-01

    This report is the sixth in the series of annual reports on the research and development program for the safe management and disposal of Canada's nuclear fuel waste. The report summarizes progress in 1984 for the following activities: storage and transportation of used fuel, immobilization of nuclear fuel waste, geotechnical research, environmental research, and environmental and safety assessment. 186 refs

  5. Management issues in automated audit analysis

    Energy Technology Data Exchange (ETDEWEB)

    Jackson, K.A.; Hochberg, J.G.; Wilhelmy, S.K.; McClary, J.F.; Christoph, G.G.

    1994-03-01

    This paper discusses management issues associated with the design and implementation of an automated audit analysis system that we use to detect security events. It gives the viewpoint of a team directly responsible for developing and managing such a system. We use Los Alamos National Laboratory`s Network Anomaly Detection and Intrusion Reporter (NADIR) as a case in point. We examine issues encountered at Los Alamos, detail our solutions to them, and where appropriate suggest general solutions. After providing an introduction to NADIR, we explore four general management issues: cost-benefit questions, privacy considerations, legal issues, and system integrity. Our experiences are of general interest both to security professionals and to anyone who may wish to implement a similar system. While NADIR investigates security events, the methods used and the management issues are potentially applicable to a broad range of complex systems. These include those used to audit credit card transactions, medical care payments, and procurement systems.

  6. Management and disposal of spent nuclear fuel

    International Nuclear Information System (INIS)

    1987-05-01

    The National Board for Spent Nuclear Fuel, in submitting its statement of comment to the Government on the Swedish Nuclear Fuel and Waste Management Company's (Svensk Kaernbraenslehantering AB, SKB) research programme, R and D Programme 86, has also put forward recommendations on the decision-making procedure and on the question of public information during the site selection process. In summary the Board proposes: * that the Government instruct the National Board for Spent Nuclear Fuel to issue certain directives concerning additions to and changes in R and D Programme 86, * that the Board's views on the decision-making procedure in the site selection process be taken into account in the Government's review of the so-called municipal veto in accordance with Chapter 4, Section 3 of the Act (1987:12) on the conservation of natural resources etc., NRL, * that the Board's views on the decision-making procedure and information questions during the site selection process serve as a basis for the continued work. Three appendices are added to the report: 1. Swedish review statements (SV), 2. International Reviews, 3. Report from the site selection group (SV)

  7. Spent fuel management in France: Programme status

    International Nuclear Information System (INIS)

    Chaudat, J.P.

    1990-01-01

    France's programme is best characterized as a closed fuel cycle including reprocessing, Plutonium recycling in PWR and use of breeder reactors. The current installed nuclear capacity is 52.5 GWe from 55 units. The spent fuel management scheme chosen is reprocessing. This paper describes the national programme, spent nuclear fuel storage, reprocessing and contracts for reprocessing of spent fuel from various countries. (author). 5 figs, 2 tabs

  8. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Dixon, R.S.; Rosinger, E.L.J.

    1984-04-01

    This report, the fifth of a series of annual reports, reviews the progress that has been made in the research and development program for the safe management and disposal of Canada's nuclear fuel waste. The report summarizes activities over the past year in the following areas: public interaction; used fuel storage and transportation; immobilization of used fuel and fuel recycle waste; geoscience research related to deep underground disposal; environmental research; and environmental and safety assessment

  9. Spent Nuclear Fuel Project dose management plan

    International Nuclear Information System (INIS)

    Bergsman, K.H.

    1996-03-01

    This dose management plan facilitates meeting the dose management and ALARA requirements applicable to the design activities of the Spent Nuclear Fuel Project, and establishes consistency of information used by multiple subprojects in ALARA evaluations. The method for meeting the ALARA requirements applicable to facility designs involves two components. The first is each Spent Nuclear Fuel Project subproject incorporating ALARA principles, ALARA design optimizations, and ALARA design reviews throughout the design of facilities and equipment. The second component is the Spent Nuclear Fuel Project management providing overall dose management guidance to the subprojects and oversight of the subproject dose management efforts

  10. Durability Issues and Status of PBI-Based Fuel Cells

    DEFF Research Database (Denmark)

    Jakobsen, Mark Tonny Dalsgaard; Jensen, Jens Oluf; Cleemann, Lars Nilausen

    2016-01-01

    This chapter briefly reviews durability and stability issues with key materials and components for HT-PEMFCs, including the polymer membrane, the doping acid, the electrocatalyst, the catalyst support and bipolar plates. Degradation mechanisms and their dependence on fuel cell operating condition...

  11. Research and development issues for molten carbonate fuel cells

    Energy Technology Data Exchange (ETDEWEB)

    Krumpelt, M.

    1996-04-01

    This paper describes issues pertaining to the development of molten carbonate fuel cells. In particular, the corrosion resistance and service life of nickel oxide cathodes is described. The resistivity of lithium oxide/iron oxides and improvement with doping is addressed.

  12. Fuels planning: science synthesis and integration; social issues fact sheet 18: Issues affecting social acceptability of fuels treatments

    Science.gov (United States)

    Christine Esposito

    2006-01-01

    Researchers have tried to understand how information about forest management can influence a person's landscape preferences and aesthetic appreciation. These findings are relevant for fuels management projects, since these projects are often characterized by conflicts between aesthetic and ecological objectives. This fact sheet discusses different aspects and ways...

  13. Fuel management approach in IRIS Reactor

    International Nuclear Information System (INIS)

    Petrovic, B.; Franceschini, F.

    2004-01-01

    This paper provides an overview of fuel management approach employed in IRIS (International Reactor Innovative and Secure). It introduces the initial, rather ambitious, fuel management goals and discusses their evolution that reflected the fast pace of progress of the overall project. The updated objectives rely on using currently licensed fuel technology, thus enabling near-term deployment of IRIS, while still providing improved fuel utilization. The paper focuses on the reference core design and fuel management strategy that is considered in pre-application licensing, which enables extended cycle of three to four years. The extended cycle reduces maintenance outage time and increases capacity factor, thus reducing the cost of electricity. Approaches to achieving this goal are discussed, including use of different reloading strategies. Additional fuel management options, which are not part of the licensing process, but are pursued as long-term research for possible future implementation, are presented as well. (Author)

  14. In-core fuel management and perspectives

    International Nuclear Information System (INIS)

    Waeckel, N.

    2009-01-01

    The management of nuclear fuel inside the core has to take into account the necessity to stop the reactor periodically to renew the fuel partially and to perform maintenance operations. The fuel management strategy determines the cost of the fuel (through the number of assemblies that have been changed and their enrichment rate) and the duration of the campaign till next stop. Fuel management strategies have to conciliate different objectives: -) the safety of the reactor, -) the reliability of the fuel assemblies, -) the optimization of the fuel cost by increasing the discharge burnup. The necessity of spent fuel processing implies a maximal discharge burnup. During the 1990-2000 period, the discharge burnups have been progressively increased through the following fuel management strategies: Garance, Cyclades and Gemmes. During the years 2000-2009, the progressive absorption of the nuclear over-equipment, the opening of the European electricity markets favored power production through the MOX-parity, Alcade and Galice fuel management strategies. The perspective for next decade is to favor production to the prejudice of higher burnups. (A.C.)

  15. Past, present and emerging toxicity issues for jet fuel

    International Nuclear Information System (INIS)

    Mattie, David R.; Sterner, Teresa R.

    2011-01-01

    The US Air Force wrote the specification for the first official hydrocarbon-based jet fuel, JP-4, in 1951. This paper will briefly review the toxicity of the current fuel, JP-8, as compared to JP-4. JP-8 has been found to have low acute toxicity with the adverse effects being slight dermal irritation and weak dermal sensitization in animals. JP-4 also has low acute toxicity with slight dermal irritation as the adverse effect. Respiratory tract sensory irritation was greater in JP-8 than in JP-4. Recent data suggest exposure to jet fuel may contribute to hearing loss. Subchronic studies for 90 days with JP-8 and JP-4 showed little toxicity with the primary effect being male rat specific hydrocarbon nephropathy. A 1-year study was conducted for JP-4. The only tumors seen were associated with the male rat specific hydrocarbon nephropathy. A number of immunosuppressive effects have been seen after exposure to JP-8. Limited neurobehavioral effects have been associated with JP-8. JP-8 is not a developmental toxicant and has little reproductive toxicity. JP-4 has not been tested for immune, neurobehavioral or reproductive endpoints. JP-8 and JP-4 were negative in mutagenicity tests but JP-4 showed an increase in unscheduled DNA synthesis. Currently, JP-8 is being used as the standard for comparison of future fuels, including alternative fuels. Emerging issues of concern with jet fuels include naphthalene content, immunotoxicity and inhalation exposure characterization and modeling of complex mixtures such as jet fuels.

  16. Policy issues of transporting spent nuclear fuel by rail

    International Nuclear Information System (INIS)

    Spraggins, H.B.

    1994-01-01

    The topic of this paper is safe and economical transportation of spent nuclear fuel by rail. The cost of safe movement given the liability consequences in the event of a rail accident involving such material is the core issue. Underlying this issue is the ability to access the risk probability of such an accident. The paper delineates how the rail industry and certain governmental agencies perceive and assess such important operational, safety, and economic issues. It also covers benefits and drawbacks of dedicated and regular train movement of such materials

  17. Recent BWR fuel management reactor physics advances

    International Nuclear Information System (INIS)

    Crowther, R.L.; Congdon, S.P.; Crawford, B.W.; Kang, C.M.; Martin, C.L.; Reese, A.P.; Savoia, P.J.; Specker, S.R.; Welchly, R.

    1982-01-01

    Improvements in BWR fuel management have been under development to reduce uranium and separative work (SWU) requirements and reduce fuel cycle costs, while also maintaining maximal capacity factors and high fuel reliability. Improved reactor physics methods are playing an increasingly important role in making such advances feasible. The improved design, process computer and analysis methods both increase knowledge of the thermal margins which are available to implement fuel management advance, and improve the capability to reliably and efficiently analyze and design for fuel management advances. Gamma scan measurements of the power distributions of advanced fuel assembly and advanced reactor core designs, and improved in-core instruments also are important contributors to improving 3-d predictive methods and to increasing thermal margins. This paper is an overview of the recent advances in BWR reactor physics fuel management methods, coupled with fuel management and core design advances. The reactor physics measurements which are required to confirm the predictions of performance fo fuel management advances also are summarized

  18. Nuclear fuel cycle issues and challenges. Scientific forum during the 48th Regular Session of the IAEA General Conference. Session summaries and reports

    International Nuclear Information System (INIS)

    2004-01-01

    The three sessions of the forum focused on: Advanced Fuel Cycles and Reactor Concepts; Waste and Spent Fuel Management Issues; and Research Reactor Fuel Cycle and Related Issues. Twelve detailed presentations were made by leading experts, followed by panellists' comments and discussion with participants

  19. Intelligence Community Programs, Management, and Enduring Issues

    Science.gov (United States)

    2016-11-08

    books, journal papers, conference presentations, working papers, and other electronic and print publications. Intelligence Community Programs... Intelligence Community Programs, Management, and Enduring Issues Anne Daugherty Miles Analyst in Intelligence and National Security Policy...

  20. An economic analysis of spent fuel management and storage

    International Nuclear Information System (INIS)

    Nagano, Koji

    1998-01-01

    Spent fuel management is becoming a key issue not only in the countries that have already experienced years of nuclear operation but also in the Asian countries that started nuclear utilization rather lately. This paper summarizes the key aspects that essentially determine optimal conditions for desired spent fuel management strategies from the engineering-economic point of view, in both national and regional perspectives. The term 'desired' is intended to highlight positive and beneficial aspects of such strategies, namely mobile and timely exploitation of spent fuel storage. Among all, the economy of scale, the economy of scope, the learning-by-doing effect, and benefits of R and D are reviewed theoretically and empirically, and the paper overviews to what extent these factors are implemented in solving spent fuel management strategy optimization problem. (author)

  1. Information technology: management issues in outsource contracts.

    OpenAIRE

    2008-01-01

    This study concerns the investigation of management issues within information technology outsourcing contracts. The information technology outsourcing life cycle is used as the flow structure for the investigation. The associated user expectations that occur in each of the phases of the information technology outsourcing life cycle are identified. Following the identification of the management and user expectation issues in each phase of the outsource life cycle, the “Coetzee solution framewo...

  2. Spent Fuel Management Newsletter. No. 1

    International Nuclear Information System (INIS)

    1990-03-01

    This Newsletter has been prepared in accordance with the recommendations of the International Regular Advisory Group on Spent Fuel Management and the Agency's programme (GC XXXII/837, Table 76, item 14). The main purpose of the Newsletter is to provide Member States with new information about the state-of-the-art in one of the most important parts of the nuclear fuel cycle - Spent Fuel Management. The contents of this publication consists of two parts: (1) IAEA Secretariat contribution -work and programme of the Nuclear Materials and Fuel Cycle Technology Section of the Division of Nuclear Fuel Cycle and Waste Management, recent and planned meetings and publications, Technical Co-operation projects, Co-ordinated Research programmes, etc. (2) Country reports - national programmes on spent fuel management: current and planned storage and reprocessing capacities, spent fuel arisings, safety, transportation, storage, treatment of spent fuel, some aspects of uranium and plutonium recycling, etc. The IAEA expects to publish the Newsletter once every two years between the publications of the Regular Advisory Group on Spent Fuel Management. Figs and tabs

  3. Special topics of inner fuel management

    International Nuclear Information System (INIS)

    Wuenschmann, A.

    1977-01-01

    Burnable Poison Rod Assemblies (BPRA) are currently used as lumped burnable poison only in the first cycles of many power reactors to insure a negative moderator coefficient at beginning of life and to help shape core power distribution (out-in shuffle scheme). BPRA's are also a valuable tool in later cycles where they can be used as an additional design parameter to improve fuel performance and fuel cycle economics, to shape fuel assembly power, and to increase fuel management flexibility (in-out shuffle scheme). This paper describes the two fuel shuffle schemes and compares the two shuffle strategies concerning economic and flexibility aspects. (orig.) [de

  4. Spent fuel management: Current status and prospects 1993

    International Nuclear Information System (INIS)

    1994-02-01

    Spent fuel management has always been one of the most important stages in the nuclear fuel cycle and it is still one of the most vital problems common to all countries with nuclear reactors. It begins with the discharge of spent fuel from a power or a research reactor and ends with its ultimate disposition, either by direct disposal or by reprocessing of the spent fuel. Two options exist at present - an open, once-through cycle with direct disposal of the spent fuel and a closed cycle with reprocessing of the spent fuel and recycling of plutonium and uranium in new mixed oxide fuels. The selection of a spent fuel strategy is a complex procedure in which many factors have to be weighed, including political, economic and safeguards issues as well as protection of the environment. Continuous attention is being given by the IAEA to the collection, analysis and exchange of information on spent fuel management. Its role in this area is to provide a forum for the exchange of information and to co-ordinate and to encourage closer co-operation among Member States in certain research an development activities that are of common interest. Refs, figs and tabs

  5. Social science to improve fuels management: a synthesis of research on aesthetics and fuels management

    Science.gov (United States)

    Robert L. Ryan

    2005-01-01

    A series of syntheses were commissioned by the USDA Forest Service to aid in fuels mitigation project planning. This synthesis focuses on research addressing aesthetic considerations of fuels management. A general finding is that fuels management activities can contribute to the visual quality of a landscape. Topics covered in the synthesis include research findings on...

  6. Nuclear fuel management in JMTR

    International Nuclear Information System (INIS)

    Naka, Michihiro; Miyazawa, Masataka; Sato, Hiroshi; Nakayama, Fusao; Ito, Haruhiko

    1999-01-01

    The Japan Materials Testing Reactor (JMTR) is the largest scale materials (author)ted the fission gas release compared with the steady state opkW/l in Japan. JMTR as a multi-purpose reactor has been contributing to research and development on nuclear field with a wide variety of irradiation for performing engineering tests and safety research on fuel and component for light water reactor as well as fast breeder reactor, high temperature gas-cooled reactor etc., for research and development on blanket material for fusion reactor, for fundamental research, and for radio-isotope (RI) production. The driver nuclear fuel used in JMTR is aluminum based MTR type fuel. According to the Reduced Enrichment for Research and Test Reactors (RERTR) Program, the JMTR fuel elements had been converted from 93% high enriched uranium (HEU) fuel to 45% medium enriched uranium (MEU) fuel in 1986, and then to 20% low enriched uranium (LEU) fuel in 1994. The cumulative operation cycles until March 1999 reached to 127 cycles since the first criticality in 1968. JMTR has used 1,628 HEU, 688 MEU and 308 LEU fuel elements for these operation cycles. After these spent fuel elements were cooled in the JMTR water canal more than one year after discharged from the JMTR core, they had been transported to reprocessing plants in Europe, and then to plants in USA in order to extract the uranium remaining in the spent fuel. The JMTR spent fuel transportation for reprocessing had been continued until the end of 1988. However, USA had ceased spent fuel reprocessing in 1989, while USDOE committed to prepare an environmental review of the impacts of accepting spent fuels from foreign research reactors. After that, USDOE decided to implement a new acceptance policy in 1996, the spent fuel transportation from JMTR to Savannah River Site was commenced in 1997. It was the first transportation not only in Japan but in Asia also. Until resuming the transportation, the spent fuel elements stored in JMTR

  7. Safeguards aspects for future fuel management alternatives

    International Nuclear Information System (INIS)

    Richter, B.; Stein, G.; Gerstler, R.

    1987-01-01

    In the future, more flexible fuel management strategies will be realized in light-water reactor power stations. The incentives for this development are based on considerations related to safe and economic plant operation, e.g. improved fuel strategies can save fuel resources and waste management efforts. A further important aspect of the nuclear fuel cycle deals with recycling strategies. At the back-end of the fuel cycle, the direct final disposal of spent fuel will have to be assessed as an alternative to recycling strategies. These major development fields will also have consequences for international safeguards. In particular, reactor fuel strategies may involve higher burn-up, conditioning of spent fuel directly in the power plant, gadolinium-poisoned fuel and different levels of enrichment. These strategies will have an impact on inspection activities, especially on the applicability of NDA techniques. The inspection frequency could also be affected in recycling strategies using MOX fuel. There may be problems with NDA methods if reprocessed feed is used in enrichment plants. On the other hand, the direct final disposal of spent fuel will raise safeguards problems regarding design verification, long-term safeguarding and the very feasibility of inaccessible nuclear material

  8. Issues for small businesses with waste management.

    Science.gov (United States)

    Redmond, Janice; Walker, Elizabeth; Wang, Calvin

    2008-07-01

    Participation by small and medium enterprise (SME) in corporate social responsibility issues has been found to be lacking. This is a critical issue, as individually SMEs may have little impact on the environment but their collective footprint is significant. The management style and ethical stance of the owner-manager affects business decision making and therefore has a direct impact on the environmental actions of the business. Although adoption of environmental practices to create competitive advantage has been advocated, many businesses see implementation as a cost which cannot be transferred to their customers. After a brief review of pertinent literature this paper reports on an exploratory investigation into the issue. Results show that whereas owner-managers of small enterprises express concern regarding the environment, this does not then translate into better waste management practices.

  9. Impact of fuel fabrication and fuel management technologies on uranium management

    International Nuclear Information System (INIS)

    Arnsberger, P.L.; Stucker, D.L.

    1994-01-01

    Uranium utilization in commercial pressurized water reactors is a complex function of original NSSS design, utility energy requirements, fuel assembly design, fuel fabrication materials and fuel fabrication materials and fuel management optimization. Fuel design and fabrication technologies have reacted to the resulting market forcing functions with a combination of design and material changes. The technologies employed have included ever-increasing fuel discharge burnup, non-parasitic structural materials, burnable absorbers, and fissile material core zoning schemes (both in the axial and radial direction). The result of these technological advances has improved uranium utilization by roughly sixty percent from the infancy days of nuclear power to present fuel management. Fuel management optimization technologies have also been developed in recent years which provide fuel utilization improvements due to core loading pattern optimization. This paper describes the development and impact of technology advances upon uranium utilization in modern pressurized water reactors. 10 refs., 3 tabs., 10 figs

  10. Waste management in IFR [Integral Fast Reactor] fuel cycle

    International Nuclear Information System (INIS)

    Johnson, T.R.; Battles, J.E.

    1991-01-01

    The fuel cycle of the Integral Fast Reactor (IFR) has important potential advantage for the management of high-level wastes. This sodium-cooled, fast reactor will use metal fuels that are reprocessed by pyrochemical methods to recover uranium, plutonium, and the minor actinides from spent core and blanket fuel. More than 99% of all transuranic (TRU) elements will be recovered and returned to the reactor, where they are efficiently burned. The pyrochemical processes being developed to treat the high-level process wastes are capable of producing waste forms with low TRU contents, which should be easier to dispose of. However, the IFR waste forms present new licensing issues because they will contain chloride salts and metal alloys rather than glass or ceramic. These fuel processing and waste treatment methods can also handle TRU-rich materials recovered from light-water reactors and offer the possibility of efficiently and productively consuming these fuel materials in future power reactors

  11. Overview on spent fuel management strategies

    International Nuclear Information System (INIS)

    Dyck, P.

    2002-01-01

    This paper presents an overview on spent fuel management strategies which range from reprocessing to interim storage in a centralised facility followed by final disposal in a repository. In either case, more spent fuel storage capacity (wet or dry, at-reactor or away-from-reactor, national or regional) is required as spent fuel is continuously accumulated while most countries prefer to defer their decision to choose between these two strategies. (author)

  12. Nuclear spent fuel management. Experience and options

    International Nuclear Information System (INIS)

    1986-01-01

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

  13. General considerations in fuel management for thermal reactors

    International Nuclear Information System (INIS)

    Tyror, J.G.; Fayers, F.J.

    1971-07-01

    By fuel management we mean the strategy for fuelling and refuelling a reactor together with any associated absorber movements. It incorporates (a) decisions made about the timing of fuel loading operations; (b) choice of enrichments to be loaded; (c) selection of sites at which reloading occurs; (d) programming of control rods and any other reactivity control facilities such as soluble or burnable poisons; and (e) evaluation of the resulting fuel element performance consequences. The topic of fuel management is thus a vast and vital one. It embraces most of the various aspects of core performance and determines many of a reactor's design characteristics. In this paper we review what to us appear to be some of the important issues in this important field

  14. Past, present and emerging toxicity issues for jet fuel.

    Science.gov (United States)

    Mattie, David R; Sterner, Teresa R

    2011-07-15

    The US Air Force wrote the specification for the first official hydrocarbon-based jet fuel, JP-4, in 1951. This paper will briefly review the toxicity of the current fuel, JP-8, as compared to JP-4. JP-8 has been found to have low acute toxicity with the adverse effects being slight dermal irritation and weak dermal sensitization in animals. JP-4 also has low acute toxicity with slight dermal irritation as the adverse effect. Respiratory tract sensory irritation was greater in JP-8 than in JP-4. Recent data suggest exposure to jet fuel may contribute to hearing loss. Subchronic studies for 90 days with JP-8 and JP-4 showed little toxicity with the primary effect being male rat specific hydrocarbon nephropathy. A 1-year study was conducted for JP-4. The only tumors seen were associated with the male rat specific hydrocarbon nephropathy. A number of immunosuppressive effects have been seen after exposure to JP-8. Limited neurobehavioral effects have been associated with JP-8. JP-8 is not a developmental toxicant and has little reproductive toxicity. JP-4 has not been tested for immune, neurobehavioral or reproductive endpoints. JP-8 and JP-4 were negative in mutagenicity tests but JP-4 showed an increase in unscheduled DNA synthesis. Currently, JP-8 is being used as the standard for comparison of future fuels, including alternative fuels. Emerging issues of concern with jet fuels include naphthalene content, immunotoxicity and inhalation exposure characterization and modeling of complex mixtures such as jet fuels. Copyright © 2011 Elsevier Inc. All rights reserved.

  15. Fuel design and operational experience in Loviisa NPP, future trends in fuel issues

    International Nuclear Information System (INIS)

    Terasvirta, R.

    2001-01-01

    This paper summarizes the past operational experience of nuclear fuel with reference to most significant design changes during the years. In general, the fuel behaviour in Loviisa NPP in terms of leaking fuel assemblies has been good. The major improvements by fuel design changes in Lovissa NPP, including rod elongation margin, change in the pellet design and manufacturing process, upper grid modifications, change of material in the spacer grids and reduction of the shroud tube thickness are discussed and related to the number of failed fuel assemblies. The detailed investigation of fuel failure rates as function of different fuel and operation characteristics allows to classify the leaking fuel assemblies according to the cause of failure. In a brief discussion concerning new changes in the safety guide for nuclear design limits, re-issued by the Finnish Safety Authority (STUK), the frequencies for class 1 and class 2 accidents are determined. Another change in this guide is the introduction of design limits for the number of fuel rods experiencing DNB in class 1 accidents and number of failed rods in class 2 accidents. It is concluded that as far as normal operation is concerned, there seems to be sufficiently large margin between present operational limits in Loviisa and the design limits. The real limits do not come from fuel behaviour in the normal operation or operational occurrences but from the accident behaviour. At the moment, fuel assembly burnup extension beyond 45 MWd/kgU is clearly out of the question before further information and positive results are obtained on high burnup fuel behaviour in accident conditions

  16. Radwaste management and spent fuel management in JAVYS

    International Nuclear Information System (INIS)

    Bozik, M.; Strazovec, R.

    2010-01-01

    In this work authors present radwaste management and spent fuel management in JAVYS, a.s. Processing of radioactive wastes (RAW) in the Bohunice Radioactive Waste Processing Center and surface storage of RAW in National RAW Repository as well as Interim Spent fuel storage in Jaslovske Bohunice are presented.

  17. Challenges and Issues in Knowledge Management

    DEFF Research Database (Denmark)

    "Challenges and Issues in Knowledge Management" - the fifth volume in the "Research on Management Consulting" series - presents sixteen chapters that explore these various perspectives, focusing on knowledge management within the context of the management consulting industry, the dynamics...... associated with knowledge sharing and dissemination, methodological approaches to studying knowledge in organizations, and reflections on knowledge management and management consulting. As the chapters underscore, it is important to ensure that KM initiatives are aligned with the needs of the organization...... and its members, that the KM system is "owned" by organizational members with particular emphasis on executive sponsorship and team member acceptance, and that it be understood as an ongoing process rather than simply another management objective or faddish consulting tool. The focus, therefore, should...

  18. Data requirements and maintenance of records for spent fuel management: A review

    International Nuclear Information System (INIS)

    2006-11-01

    Data collection and maintenance are an essential part of activities required in the lifetime management of spent fuel. Key data on spent fuel are required from the earliest phase of any project. To allow informed decisions for spent fuel management to be made, the data need to be maintained throughout the lifetime of spent fuel management including storage, transport, reprocessing or disposal. This publication is intended to provide a state-of-the-art review of spent fuel data management, including what data need to be gathered for the relevant activities in spent fuel management and how to maintain them by the responsible bodies at various stages of the nuclear fuel cycle. It provides some insights on a rational approach to spent fuel data management, considering the common requirements involved in spent fuel management for any Member State. In this regard, the information provided in these sections is mostly generic. After the introductory Section 1 and the Section 2 on data requirements for spent fuel management, Section 3 examines technical parameters that could specify spent fuel characteristics and associated conditions, followed by Section 4 on life cycle management of spent fuel data which includes the maintenance of records and other issues. Finally, some specific examples of the approaches already developed by a number of utilities and national organisations to characterise and track their spent-fuel data are presented in the Annex

  19. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Dixon, R.S.

    1984-12-01

    The Canadian Nuclear Fuel Waste Management Program involves research into the storage and transportation of used nuclear fuel, immobilization of fuel waste, and deep geological disposal of the immobilized waste. The program is now in the fourth year of a ten-year generic research and development phase. The objective of this phase of the program is to assess the safety and environmental aspects of the deep underground disposal of immobilized fuel waste in plutonic rock. The objectives of the research for each component of the program and the progress made to the end of 1983 are described in this report

  20. The final management of nuclear fuel. Legal and economic aspects

    International Nuclear Information System (INIS)

    Villota, C. de

    2009-01-01

    This article gives a brief summary of the characteristics of spent fuel and the lines of action considered for its management. It describes the legal framework that supports the Radioactive Waste Management Plan (PGRR), which contains the lines applicable to Final Spent Fuel Management, as well as the evolution of this legal framework. The article contains the 2008 updated costs of the various items of the PGRR, with a more detailed description of those related to this type of fuel, as well the source and amount of the financial contributions to the fund for meeting these costs, including how they have evolved over time. finally, it provides some personal reflections on this issue. (Author)

  1. Fuel management at Washington State Ferries

    International Nuclear Information System (INIS)

    Brodeur, P.; Olds, J.

    2008-01-01

    This presentation discussed Washington State Ferry (WSF) operations and provided details of a biodiesel research and demonstration project. Washington has the largest ferry system in the United States, with a total of 28 vessels that operate on 10 routes through 20 terminals. Routes vary by transit times, navigational challenges, and the proximity to population centres. WSF fuel and emissions management initiatives include exhaust emission studies, clean fuel initiatives, machinery upgrades, fuel conservation initiatives, and biodiesel testing. The organization is also using waste heat recovery and a positive restraint system. The WSF biodiesel pilot program was conducted using soy-derived fuels with a purifier disk stack. The program is in agreement with recent legislation requiring that 2 per cent of annual diesel fuel sales are from biodiesel fuels, and state legislation requiring that state agencies use a minimum of 20 per cent biodiesel blends in diesel-powered vessels and vehicles. Details of project partnerships were included. tabs., figs

  2. The morphology of durability issues in PEM fuel cells

    International Nuclear Information System (INIS)

    Kundu, S.; Fowler, M.; Simon, L.; Grot, S.

    2004-01-01

    'Full text:' The work presented here examines durability issues in PEM fuel cell materials by examining material morphology and linking morphological features to performance. Scanning electron microscope (SEM) techniques have been able to identify a variety of features on the catalyst layer, each with their own implication to the overall performance and durability of the membrane electrode assembly (MEA). These features include cracking, delamination of the catalyst layer, catalyst clustering, electrolyte clustering, and thickness variations. Links between several of these features and catalyst dispersion conditions was also examined, showing that how the material was manufactured influences the type of morphological features present. The SEM has also been used with accelerated aging techniques to closely examine aging of the gas diffusion layer (GDL). It can be shown that over time the GDL will loose its hydrophobic character and hence become more susceptible to flooding in a fuel cell. The impact of morphological changes were determined using fuel cell models and experimental work. The ultimate aim of this work is to provide material developers with the tools and knowledge necessary to design better materials and therefore bring fuel cells closer to commercialization. (author)

  3. Inventory management systems : Control and information issues

    NARCIS (Netherlands)

    Janssen, F.B.S.L.P.

    1998-01-01

    This dissertation addresses the management of inventory systems. The thesis starts with an exposition on mathematical models that can be used in inventory theory. Then we deal with some information issues related to the demand process. Namely, how to control products that have intermittent demand.

  4. Regulatory issues for nuclear power plant life management

    International Nuclear Information System (INIS)

    Roe, J.

    2000-01-01

    The workshop of 26-27 june 2000, on nuclear power Plant LIfe Management (PLIM), also included working groups in which major issues facing PLIM activities for nuclear power plants were identified and discussed. The second group was on Regulation. The Regulatory Working Group will attempt to identify some of the more pertinent issues affecting nuclear plant regulation in a changing PLIM environment, to identify some possible actions to be taken to address these issues, and to identify some of the parties responsible for taking these actions. Some preliminary regulatory issues are noted below. This is not intended to be a comprehensive list of such issues but rather is intended to stimulate discussion among the experts attending this Workshop. One of the concerns in the regulatory arena is how the structural integrity of the plants can be assured for an extended lifetime. Technological advances directed toward the following are likely to be important factors in the regulatory process of life extension. - Preventive and corrective maintenance (e.g., water chemistry control, pressure vessel annealing, and replacement of core internals). - Ageing and degradation mechanisms and evaluation (e.g., embrittlement, wear, corrosion/erosion, fatigue, and stress corrosion). - Monitoring, surveillance, and inspection (e.g., fatigue monitoring and non-destructive testing). - Optimisation of maintenance (e.g., using risk-based analysis). On the business side, there is concern about technical support by manufacturers, fuel companies, and construction companies. Maintaining a strong technical base and skilled workers in a potentially declining environment is another concern in the regulatory community. Waste management and decommissioning remain significant issue regarding PLIM. These issues affect all three areas of concern - technology, business, and regulation. It is against this background, that the issues put forth in this paper are presented. The objective of presenting these

  5. Spent fuel storage - dry storage options and issues

    International Nuclear Information System (INIS)

    Akins, M.J.

    2007-01-01

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

  6. Estimating Fuel Cycle Externalities: Analytical Methods and Issues, Report 2

    Energy Technology Data Exchange (ETDEWEB)

    Barnthouse, L.W.; Cada, G.F.; Cheng, M.-D.; Easterly, C.E.; Kroodsma, R.L.; Lee, R.; Shriner, D.S.; Tolbert, V.R.; Turner, R.S.

    1994-07-01

    of complex issues that also have not been fully addressed. This document contains two types of papers that seek to fill part of this void. Some of the papers describe analytical methods that can be applied to one of the five steps of the damage function approach. The other papers discuss some of the complex issues that arise in trying to estimate externalities. This report, the second in a series of eight reports, is part of a joint study by the U.S. Department of Energy (DOE) and the Commission of the European Communities (EC)* on the externalities of fuel cycles. Most of the papers in this report were originally written as working papers during the initial phases of this study. The papers provide descriptions of the (non-radiological) atmospheric dispersion modeling that the study uses; reviews much of the relevant literature on ecological and health effects, and on the economic valuation of those impacts; contains several papers on some of the more complex and contentious issues in estimating externalities; and describes a method for depicting the quality of scientific information that a study uses. The analytical methods and issues that this report discusses generally pertain to more than one of the fuel cycles, though not necessarily to all of them. The report is divided into six parts, each one focusing on a different subject area.

  7. Fuel Cycle Externalities: Analytical Methods and Issues, Report 2

    International Nuclear Information System (INIS)

    Barnthouse, L.W.; Cada, G.F.; Cheng, M.-D.; Easterly, C.E.; Kroodsma, R.L.; Lee, R.; Shriner, D.S.; Tolbert, V.R.; Turner, R.S.

    1994-01-01

    The activities that produce electric power typically range from extracting and transporting a fuel, to its conversion into electric power, and finally to the disposition of residual by-products. This chain of activities is called a fuel cycle. A fuel cycle has emissions and other effects that result in unintended consequences. When these consequences affect third parties (i.e., those other than the producers and consumers of the fuel-cycle activity) in a way that is not reflected in the price of electricity, they are termed ''hidden'' social costs or externalities. They are the economic value of environmental, health and any other impacts, that the price of electricity does not reflect. How do you estimate the externalities of fuel cycles? Our previous report describes a methodological framework for doing so--called the damage function approach. This approach consists of five steps: (1) characterize the most important fuel cycle activities and their discharges, where importance is based on the expected magnitude of their externalities, (2) estimate the changes in pollutant concentrations or other effects of those activities, by modeling the dispersion and transformation of each pollutant, (3) calculate the impacts on ecosystems, human health, and any other resources of value (such as man-made structures), (4) translate the estimates of impacts into economic terms to estimate damages and benefits, and (5) assess the extent to which these damages and benefits are externalities, not reflected in the price of electricity. Each step requires a different set of equations, models and analysis. Analysts generally believe this to be the best approach for estimating externalities, but it has hardly been used. The reason is that it requires considerable analysis and calculation, and to this point in time, the necessary equations and models have not been assembled. Equally important, the process of identifying and estimating externalities leads to a number of complex issues

  8. Practice management: observations, issues, and empirical evidence.

    Science.gov (United States)

    Wong, H M; Braithwaite, J

    2001-02-01

    The primary objective of this study is to provide objective, empirical, evidence-based practice management information. This is a hitherto under-researched area of considerable interest for both the practitioner and educator. A questionnaire eliciting a mix of structured and free text responses was administered to a random sample of 480 practitioners who are members of the American Academy of Periodontology. Potential respondents not in private practice were excluded and the next listed person substituted. The results provide demographic and descriptive information about some of the main issues and problems facing practice managers, central to which are information technology (IT), financial, people management, and marketing. Human resource and marketing management appear to represent the biggest challenges. Periodontists running practices would prefer more information, development, and support in dealing with IT, finance, marketing, and people management. The empirical evidence reported here suggests that although tailored educational programs on key management issues at both undergraduate and postgraduate levels have become ubiquitous, nevertheless some respondents seek further training opportunities. Evidence-based practice management information will be invaluable to the clinician considering strategic and marketing planning, and also for those responsible for the design and conduct of predoctoral and postdoctoral programs.

  9. Spent fuel management in Japan - Facts and prospects

    International Nuclear Information System (INIS)

    Nagano, K.

    2002-01-01

    This paper discusses recent developments and future issues related to spent fuel management in Japan. With increasing pressure of spent fuel discharge from the power plants in operation and, in contrast, uncertainties in their processing and management services, spent fuel storage in short and medium terms has been receiving the highest priority in nuclear policy discussions in Japan. While small-scale interim storage devices, as well as capacity expansion (re-racking, etc.) and shared uses of existing devices, are introduced at number of power stations, large scale AFR (away from reactor) 'Storage of Recycle Fuel Resources' is expected to come in a medium and long-run. Commercial operation of 'Storage of Recycle Fuel Resources' is allowed its way, as the bill of amendment to the law for regulation of nuclear power reactors and other nuclear-related activities has passed in the Diet. In the meantime, the Atomic Energy Commission has launched working group discussions for revision of 'The Long-term Program of Research, Development and Utilization of Nuclear Energy' to be completed in 2000. This revision is hoped to set up a stage of national debate of nuclear policy, which might lead to fill conceptual gaps between bodies promoting nuclear development and general public. The author's attempt to illustrate the role of storage in spent fuel management is also presented from a theoretical point of view. (author)

  10. Comparison of spent nuclear fuel management alternatives

    International Nuclear Information System (INIS)

    Beebe, C.L.; Caldwell, M.A.

    1996-01-01

    This paper reports the process an results of a trade study of spent nuclear fuel (SNF)management alternatives. The purpose of the trade study was to provide: (1) a summary of various SNF management alternatives, (2) an objective comparison of the various alternatives to facilitate the decision making process, and (3) documentation of trade study rational and the basis for decisions

  11. Spent fuel management: Current status and prospects

    International Nuclear Information System (INIS)

    1988-12-01

    The main objective of the Advisory Group on Spent Fuel Management is to review the world-wide situation in Spent Fuel Management, to define the most important directions of national efforts and international cooperation in this area, to exchange information on the present status and progress in performing the back-end of Nuclear Fuel Cycle and to elaborate the general recommendations for future Agency programmes in the field of spent fuel management. This report which is a result of the third IAEA Advisory Group Meeting (the first and second were held in 1984 and 1986) is intended to provide the reader with an overview of the status of spent fuel management programmes in a number of leading countries, with a description of the past and present IAEA activities in this field of Nuclear Fuel Cycle and with the Agency's plans for the next years, based on the proposals and recommendations of Member States. A separate abstract was prepared for each of 14 papers presented at the advisory group meeting. Refs, figs and tabs

  12. Safety aspects of dry spent fuel storage and spent fuel management

    International Nuclear Information System (INIS)

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

    2014-01-01

    The storage of spent nuclear fuel (SF) and high-level radioactive waste (HLW) must conform to safety requirements. Safety aspects like safe enclosure of radioactive materials, safe removal of decay heat, nuclear criticality safety and avoidance of unnecessary radiation exposure must be achieved throughout the 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. In Germany dual purpose casks for SF or HLW are used for safe transportation and interim storage. TUV and BAM, who work as independent experts for the competent authorities, present the storage licensing process including sites and casks and inform about spent nuclear fuel management and issues concerning dry storage of spent nuclear fuel, based on their long experience in these fields (authors)

  13. Safety Issues with Hydrogen as a Vehicle Fuel

    Energy Technology Data Exchange (ETDEWEB)

    L. C. Cadwallader; J. S. Herring

    1999-09-01

    This report is an initial effort to identify and evaluate safety issues associated with the use of hydrogen as a vehicle fuel in automobiles. Several forms of hydrogen have been considered: gas, liquid, slush, and hydrides. The safety issues have been discussed, beginning with properties of hydrogen and the phenomenology of hydrogen combustion. Safety-related operating experiences with hydrogen vehicles have been summarized to identify concerns that must be addressed in future design activities and to support probabilistic risk assessment. Also, applicable codes, standards, and regulations pertaining to hydrogen usage and refueling have been identified and are briefly discussed. This report serves as a safety foundation for any future hydrogen safety work, such as a safety analysis or a probabilistic risk assessment.

  14. Safety Issues with Hydrogen as a Vehicle Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Cadwallader, Lee Charles; Herring, James Stephen

    1999-10-01

    This report is an initial effort to identify and evaluate safety issues associated with the use of hydrogen as a vehicle fuel in automobiles. Several forms of hydrogen have been considered: gas, liquid, slush, and hydrides. The safety issues have been discussed, beginning with properties of hydrogen and the phenomenology of hydrogen combustion. Safety-related operating experiences with hydrogen vehicles have been summarized to identify concerns that must be addressed in future design activities and to support probabilistic risk assessment. Also, applicable codes, standards, and regulations pertaining to hydrogen usage and refueling have been identified and are briefly discussed. This report serves as a safety foundation for any future hydrogen safety work, such as a safety analysis or a probabilistic risk assessment.

  15. Situation and perspective of spent fuel management in Spain

    International Nuclear Information System (INIS)

    Lopez Garcia, A.

    2009-01-01

    Between september 2006 and september 2007, the Foundation for Energy Studies carried out the study Radioactive Waste Management: Situation, Analysis and Perspectives. This study focuses specially on spent fuel and high level radioactive waste management. The different aspects covered in this study are as follows: -Description of the different applicable technologies -Analysis and comparison of the different options of spent fuel management, including the strategic and economic aspects. - Situation, strategies and forecasts in the main countries. -Analysis of the situation and alternatives for the spent fuel management in spain. Although the report focuses principally pn the technological and environmental aspects other issues related with the management of these materials were considered, such as the strategic, economic and institutional aspects as well as the social acceptation. In answer to the request of the SNE publication, the article enclosed is a summary of one of the chapters of this study, and more particularly the one dedicated to the situation of spent fuel and high level radioactive waste management in Spain. (Author)

  16. Generic waste management concepts for six LWR fuel cycles

    International Nuclear Information System (INIS)

    DePue, J.D.

    1979-04-01

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

  17. Spent fuel management of NPPs in Argentina

    International Nuclear Information System (INIS)

    Alvarez, D.E.; Lee Gonzalez, H.M.

    2010-01-01

    There are two Nuclear Power Plants in operation in Argentina: 'Atucha I' (unique PHWR design) in operation since 1974, and 'Embalse' (typical Candu reactor) which started operation in 1984. Both NPPs are operated by 'Nucleoelectrica Argentina S.A' which is responsible for the management and interim storage of spent fuel till the end of the operative life of the plants. A third NPP, 'Atucha II' is under construction, with a similar design of Atucha I. The legislative framework establishes that after final shutdown of a NPP the spent fuel will be transferred to the 'National Atomic Energy Commission', which is also responsible for the decommissioning of the Plants. In Atucha I, the spent fuel is stored underwater, until another option is implemented meanwhile in Embalse the spent fuel is stored during six years in pools and then it is moved to a dry storage. A decision about the fuel cycle back-end strategy will be taken before year 2030. (authors)

  18. Waste management and the holistic fuel cycle

    International Nuclear Information System (INIS)

    Holmes, R.G.G.; Robbins, R.A.; Eilbeck, A.

    1996-01-01

    This paper outlines a holistic approach to the nuclear fuel cycle and the impact that waste management can have on the holistic approach. The philosophy includes regarding irradiated fuel as a resource rather than a waste that can be used as a source of fissile material to be recycled, either Uranium returned to fuel or Plutonium in mixed oxide fuels (MOX) for fast and impact of those compounds that leave the cycle (solid waste, liquid effluent and gaseous effluent) are minimized. This can only be achieved by applying a full life cycle analysis of process benefits. The paper describes some of the work in waste management but notes that waste and its generation must be seen as an integral part of any developed strategy. (authors)

  19. Spent nuclear fuel transportation: public issues and answers

    International Nuclear Information System (INIS)

    Hoffman, W.D.

    1986-01-01

    The court-ordered shipping of 750 spent nuclear fuel assemblies from West Valley, New York back to their utility owners has generated considerable public and media interest. This paper discusses the specific concerns of the general public over the West Valley shipments, the issues raised by opposition groups, the interest of public officials and emergency preparedness teams as well as the media coverage generated. An analysis is performed on the effectiveness of the West Valley and utility public information programs utilized in addressing these issues, concerns and interests. Emphasis is placed on communications which work to facilitate the shipments and generate fuel transport acceptance. Information programs are discussed which increase preparedness for nuclear shipments by emergency response teams and build public confidence in their safety. The paper also examines communications which could have further enhanced the shipping campaign to date. Finally, plans are discussed for media preparation with interview training and press conferences. Emphasis is placed on materials provided for the media which have served to generate more favorable print and air time

  20. Spent nuclear fuel transportation: Public issues and answers

    International Nuclear Information System (INIS)

    Hoffman, W.D.

    1986-01-01

    The court-ordered shipping of 750 spent nuclear fuel assemblies from West Valley, New York back to their utility owners has generated considerable public and media interest. This paper discusses the specific concerns of the general public over the West Valley shipments, the issues raised by opposition groups, the interests of public officials and emergency preparedness teams as well as the media coverage generated. An analysis is performed on the effectiveness of the West Valley and utility public information programs utilized in addressing these issues, concerns and interests. Emphasis is placed on communications which work to facilitate the shipments and generate fuel transport acceptance. Information programs are discussed which increase preparedness for nuclear shipments by emergency response teams and build public confidence in their safety. The paper also examines communications which could have further enhanced the shipping campaigns to date. Finally, plans are discussed for media preparation with interview training and press conferences. Emphasis is placed on materials provided for the media which has served to generate more favorable print and air time

  1. Effective time management – selected issues

    Directory of Open Access Journals (Sweden)

    Aneta Olejniczak

    2013-03-01

    Full Text Available Deliberations included in this article contain the basic issues related to the subject of time management. As we know, people who waste their time the most, most complain about the lack of the time. We should treat our time, time of our co-workers, and friends as a valuable, but limited wealth. Principles of effective time management can be applied in any scientific and research institutions, companies or corporations. The benefits of a good and effective time management will be felt not only by ourselves but also by our friends and family. Detailed formulation of objectives, identification and elimination of time wasters and postponing work on later (Procrastination, using methods of time management and systematic control will allow for efficient use of time. A good plan is the basis for optimal and meaningful use of time.

  2. Scaling issues in sustainable river basin management

    Science.gov (United States)

    Timmerman, Jos; Froebich, Jochen

    2014-05-01

    Sustainable river basin management implies considering the whole river basin when managing the water resources. Management measures target at dividing the water over different uses (nature, agriculture, industry, households) thereby avoiding calamities like having too much, too little or bad quality water. Water management measures are taken at the local level, usually considering the sub-national and sometimes national effects of such measures. A large part of the world's freshwater resources, however, is contained in river basins and groundwater systems that are shared by two or more countries. Sustainable river basin management consequently has to encompass local, regional, national and international scales. This requires coordination over and cooperation between these levels that is currently compressed into the term 'water governance' . Governance takes into account that a large number of stakeholders in different regimes (the principles, rules and procedures that steer management) contribute to policy and management of a resource. Governance includes the increasing importance of basically non-hierarchical modes of governing, where non-state actors (formal organizations like NGOs, private companies, consumer associations, etc.) participate in the formulation and implementation of public policy. Land use determines the run-off generation and use of irrigation water. Land use is increasingly determined by private sector initiatives at local scale. This is a complicating factor in the governance issue, as in comparison to former developments of large scale irrigation systems, planning institutions at state level have then less insight on actual water consumption. The water management regime of a basin consequently has to account for the different scales of water management and within these different scales with both state and non-state actors. The central elements of regimes include the policy setting (the policies and water management strategies), legal setting

  3. Perturbation theory in nuclear fuel management optimization

    International Nuclear Information System (INIS)

    Ho, L.W.

    1981-01-01

    Nuclear in-core fuel management involves all the physical aspects which allow optimal operation of the nuclear fuel within the reactor core. In most nuclear power reactors, fuel loading patterns which have a minimum power peak are economically desirable to allow the reactors to operate at the highest power density and to minimize the possibility of fuel failure. In this study, perturbation theory along with a binary fuel shuffling technique is applied to predict the effects of various core configurations, and hence, the optimization of in-core fuel management. The computer code FULMNT has been developed to shuffle the fuel assemblies in search of the lowest possible power peaking factor. An iteration approach is used in the search routine. A two-group diffusion theory method is used to obtain the power distribution for the iterations. A comparison of the results of this method with other methods shows that this approach can save computer time. The code also has a burnup capability which can be used to check power peaking throughout the core life

  4. Management of cladding hulls and fuel hardware

    International Nuclear Information System (INIS)

    1985-01-01

    The reprocessing of spent fuel from power reactors based on chop-leach technology produces a solid waste product of cladding hulls and other metallic residues. This report describes the current situation in the management of fuel cladding hulls and hardware. Information is presented on the material composition of such waste together with the heating effects due to neutron-induced activation products and fuel contamination. As no country has established a final disposal route and the corresponding repository, this report also discusses possible disposal routes and various disposal options under consideration at present

  5. Fuel management codes for fast reactors

    International Nuclear Information System (INIS)

    Sicard, B.; Coulon, P.; Mougniot, J.C.; Gouriou, A.; Pontier, M.; Skok, J.; Carnoy, M.; Martin, J.

    The CAPHE code is used for managing and following up fuel subassemblies in the Phenix fast neutron reactor; the principal experimental results obtained since this reactor was commissioned are analyzed with this code. They are mainly concerned with following up fuel subassembly powers and core reactivity variations observed up to the beginning of the fifth Phenix working cycle (3/75). Characteristics of Phenix irradiated fuel subassemblies calculated by the CAPHE code are detailed as at April 1, 1975 (burn-up steel damage)

  6. Management issues regarding the contingent workforce

    Energy Technology Data Exchange (ETDEWEB)

    Bowen-Smed, S. [Bowen Workforce Solutions, Calgary, AB (Canada)

    2004-07-01

    Fifty per cent of corporate leaders in Calgary today will be eligible for retirement over the next 5 years. In addition, 53 per cent of the entire Calgary workforce is 45 years or older. This paper suggests that only companies that seek aggressive programs to engage immigrants and contractors will weather the skills shortages anticipated in the future. It was noted that contractors care about aligning values to organizations, regardless of the project length, and that professional development is a key consideration when it comes to selecting their next project. Contingent workforce issues include: effectiveness; classification; risk; and cost. It was stated that effectiveness of the contingent workforce is an employer's responsibility. Factors that would strengthen the relationship between corporations and contractors include: proper orientation to manage expectations; training to improve productivity; tracking to enhance the quality of the workforce; and a management process to ensure adherence to protocol. It was concluded that the contingent workforce is an essential component to human capital management strategy, but that key issues must be managed to avoid unnecessary costs. In addition, effectiveness improves when processes are implemented. It was also suggested that technology is an essential component of the solution. Outsourcing is an effective approach to managing the contingent workforce. tabs., figs.

  7. Equity issues in radioactive waste management

    International Nuclear Information System (INIS)

    Kasperson, R.E.

    1984-01-01

    The 15 papers in this book deal with the equity issues of locus, legacy and labor/laity as they occur in the nuclear industry's handling of radioactive wastes. The intent is to identify and clarify inequities in alternative approaches to radioactive waste management in a way that will inform current public policy deliberations and planning. The papers are arranged in five parts which put the problem in perspective, then define the locus, the legacy, and the labor problem, and conclude with a set of proposals for a more equitable management. A separate abstract was prepared for each of the 15 chapters selected for INS, EDB, and EPA

  8. Fouling issues within CANDU fuel bay purification systems

    International Nuclear Information System (INIS)

    Angell, P.; Murray, J.

    2003-01-01

    Similar to all nuclear power stations, CANDU stations store their spent fuel in large open fuel bays to allow the fuel bundles to cool down. Over the years there have been a number of minor issues relating to the operation of the fuel bays, and the annual operational and maintenance costs to the stations are in the order of $1-2M. Ontario Power Generation (OPG) stations have been treating the fuel bays of their CANDU stations with hydrogen peroxide. While this treatment has been effective for the control of microbial corrosion and algal problems, an ongoing problem with the rapid plugging of the purification system filters and the presence of a thin translucent film on the surface of the water has been reported. Analysis suggested that the translucent film was of biological origin and initially it was suspected as being responsible for the plugging of the filters. Samples of the bay water, translucent film and filters were collected for microbial analysis. From all samples a number of bacterial species was isolated, all of which had the enzyme catalase that is responsible for the microbial breakdown of hydrogen peroxide, and many of the isolates were found to be capable of producing extracellular polymeric substance (slime). Observation of the filter revealed that no slime layer was present on the outer surface of the filter. This suggested that the plugging was not the result of removal of slime from the bay. Rather it suggested that the plugging was the result of microbial colonization and growth within the matrix of the filter. The large surface area of the filter matrix provides ideal conditions for biofilm growth and the flow of water provides a ready supply of nutrients. Based on a careful review of the chemistry specifications and requirements for the fuel bay water it was suggested that the filters, as currently used, were unnecessary and could be either removed or valved out, thereby eliminating the high costs associated with their operation and

  9. Development of advanced spent fuel management process

    International Nuclear Information System (INIS)

    Park, Seong Won; Shin, Y. J.; Cho, S. H.

    2004-03-01

    The research on spent fuel management focuses on the maximization of the disposal efficiency by a volume reduction, the improvement of the environmental friendliness by the partitioning and transmutation of the long lived nuclides, and the recycling of the spent fuel for an efficient utilization of the uranium source. In the second phase which started in 2001, the performance test of the advanced spent fuel management process consisting of voloxidation, reduction of spent fuel and the lithium recovery process has been completed successfully on a laboratory scale. The world-premier spent fuel reduction hot test of a 5 kgHM/batch has been performed successfully by joint research with Russia and the valuable data on the actinides and FPs material balance and the characteristics of the metal product were obtained with experience to help design an engineering scale reduction system. The electrolytic reduction technology which integrates uranium oxide reduction in a molten LiCl-Li 2 O system and Li 2 O electrolysis is developed and a unique reaction system is also devised. Design data such as the treatment capacity, current density and mass transfer behavior obtained from the performance test of a 5 kgU/batch electrolytic reduction system pave the way for the third phase of the hot cell demonstration of the advanced spent fuel management technology

  10. Development of advanced spent fuel management process

    International Nuclear Information System (INIS)

    Shin, Young Joon; Cho, S. H.; You, G. S.

    2001-04-01

    Currently, the economic advantage of any known approach to the back end fuel cycle of a nuclear power reactor has not been well established. Thus the long term storage of the spent fuel in a safe manner is one of the important issues to be resolved in countries where the nuclear power has a relatively heavy weight in power production of that country. At KAERI, as a solution to this particular issue midterm storage of the spent fuel, an alternative approach has been developed. This approach includes the decladding and pulverization process of the spent PWR fuel rod, the reducing process from the uranium oxide to a metallic uranium powder using Li metal in a LiCl salt, the continuous casting process of the reduced metal, and the recovery process of Li from mixed salts by the electrolysis. We conducted the laboratory scale tests of each processes for the technical feasibility and determination for the operational conditions for this approach. Also, we performed the theoretical safety analysis and conducted integral tests for the equipment integration through the Mock-up facility with non-radioactive samples. There were no major issues in the approach, however, material incompatibility of the alkaline metal and oxide in a salt at a high temperature and the reactor that contains the salt became a show stopper of the process. Also the difficulty of the clear separation of the salt with metals reduced from the oxide became a major issue

  11. Accelerated fuel depreciation as an economic incentive for low-leakage fuel management

    International Nuclear Information System (INIS)

    Downar, T.J.

    1986-01-01

    An analysis is presented which evaluates the tax depreciation advantage which results from the increased rate of fuel depletion achieved in the current low-leakage fuel-management LWR core reload designs. An analytical fuel-cycle cost model is used to examine the important cost parameters which are then validated using the fuel-cycle cost code CINCAS and data from the Maine Yankee PWR. Results show that low-leakage fuel management, through the tax depreciation advantage from accelerated fuel depletion, provides an improvement of several percent in fuel-cycle costs compared to traditional out-in fuel management and a constant fuel depletion rate. (author)

  12. Management issues for high performance storage systems

    Energy Technology Data Exchange (ETDEWEB)

    Louis, S. [Lawrence Livermore National Lab., CA (United States); Burris, R. [Oak Ridge National Lab., TN (United States)

    1995-03-01

    Managing distributed high-performance storage systems is complex and, although sharing common ground with traditional network and systems management, presents unique storage-related issues. Integration technologies and frameworks exist to help manage distributed network and system environments. Industry-driven consortia provide open forums where vendors and users cooperate to leverage solutions. But these new approaches to open management fall short addressing the needs of scalable, distributed storage. We discuss the motivation and requirements for storage system management (SSM) capabilities and describe how SSM manages distributed servers and storage resource objects in the High Performance Storage System (HPSS), a new storage facility for data-intensive applications and large-scale computing. Modem storage systems, such as HPSS, require many SSM capabilities, including server and resource configuration control, performance monitoring, quality of service, flexible policies, file migration, file repacking, accounting, and quotas. We present results of initial HPSS SSM development including design decisions and implementation trade-offs. We conclude with plans for follow-on work and provide storage-related recommendations for vendors and standards groups seeking enterprise-wide management solutions.

  13. Burnup credit demands for spent fuel management in Ukraine

    International Nuclear Information System (INIS)

    Medun, V.

    2001-01-01

    In fact, till now, burnup credit has not be applied in Ukrainian nuclear power for spent fuel management systems (storage and transport). However, application of advanced fuel at VVER reactors, arising spent fuel amounts, represent burnup credit as an important resource to decrease spent fuel management costs. The paper describes spent fuel management status in Ukraine from viewpoint of subcriticality assurance under spent fuel storage and transport. It also considers: 1. Regulation basis concerning subcriticality assurance, 2. Basic spent fuel and transport casks characteristics, 3. Possibilities and demands for burnup credit application at spent fuel management systems in Ukraine. (author)

  14. Fuel-Cycle and Nuclear Material Disposition Issues Associated with High-Temperature Gas Reactors

    International Nuclear Information System (INIS)

    Shropshire, D.E.; Herring, J.S.

    2004-01-01

    The objective of this paper is to facilitate a better understanding of the fuel-cycle and nuclear material disposition issues associated with high-temperature gas reactors (HTGRs). This paper reviews the nuclear fuel cycles supporting early and present day gas reactors, and identifies challenges for the advanced fuel cycles and waste management systems supporting the next generation of HTGRs, including the Very High Temperature Reactor, which is under development in the Generation IV Program. The earliest gas-cooled reactors were the carbon dioxide (CO2)-cooled reactors. Historical experience is available from over 1,000 reactor-years of operation from 52 electricity-generating, CO2-cooled reactor plants that were placed in operation worldwide. Following the CO2 reactor development, seven HTGR plants were built and operated. The HTGR came about from the combination of helium coolant and graphite moderator. Helium was used instead of air or CO2 as the coolant. The helium gas has a significant technical base due to the experience gained in the United States from the 40-MWe Peach Bottom and 330-MWe Fort St. Vrain reactors designed by General Atomics. Germany also built and operated the 15-MWe Arbeitsgemeinschaft Versuchsreaktor (AVR) and the 300-MWe Thorium High-Temperature Reactor (THTR) power plants. The AVR, THTR, Peach Bottom and Fort St. Vrain all used fuel containing thorium in various forms (i.e., carbides, oxides, thorium particles) and mixtures with highly enriched uranium. The operational experience gained from these early gas reactors can be applied to the next generation of nuclear power systems. HTGR systems are being developed in South Africa, China, Japan, the United States, and Russia. Elements of the HTGR system evaluated included fuel demands on uranium ore mining and milling, conversion, enrichment services, and fuel fabrication; fuel management in-core; spent fuel characteristics affecting fuel recycling and refabrication, fuel handling, interim

  15. Fuel cycle integration issues associated with P/T technology

    International Nuclear Information System (INIS)

    Michaels, G.E.; Ludwig, S.B.

    1992-01-01

    The three primary interfaces between a generic partitioning and transmutation (P/T) technology and the existing United States fuel cycle are the light-water reactor (LWR) spent fuel inventory, the reprocessed uranium (RU) stream, and the high-level waste stream. The features and implications of these three interfaces are reviewed and their implications for P/T system design and for waste management are assessed. The variability of transuranic nuclide composition in the LWR spent fuel is calculated and its potential implications for transmutation system core design are discussed. The radiological characteristics of the RU stream are presented, and options for disposition of the stream are reviewed. Most P/T scenarios assume that RU will be recycled to LWRs. This study demonstrates, however, that LWR recycle cannot totally consume the reprocessed stream, and disposal of a waste uranium steam with high levels of radiologically-significant isotopes will still be necessary. The radioactivity of the tails stream for enrichment plants resulting from a dedicated RU campaign is calculated. The tendency of gaseous diffusion plant enrichment technology to deplete the tails stream of minor uranium isotopes is seen as a benefit and an advantage over Atomic Vapor Laser Isotope Separation-type technology. Finally, the implications of P/T on LWR-origin wastes reporting to the repository is discussed, and several significant differences between LWR-origin waste originating from transmutation systems are assessed

  16. International symposium on nuclear fuel cycle and reactor strategy: Adjusting to new realities. Key issue papers

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    The key issue papers review the following issues: global energy outlook; present status and environmental implications of the different fuel cycles; future fuel cycle and reactor strategies; safety, health and environmental implications of the different fuel cycles; non-proliferation and safeguards aspects; international cooperation. Refs, figs, tabs.

  17. International symposium on nuclear fuel cycle and reactor strategy: Adjusting to new realities. Key issue papers

    International Nuclear Information System (INIS)

    1997-06-01

    The key issue papers review the following issues: global energy outlook; present status and environmental implications of the different fuel cycles; future fuel cycle and reactor strategies; safety, health and environmental implications of the different fuel cycles; non-proliferation and safeguards aspects; international cooperation. Refs, figs, tabs

  18. German Approach to Spent Fuel Management

    International Nuclear Information System (INIS)

    Jussofie, A.; Graf, R.; Filbert, W.

    2010-01-01

    The management of spent fuel was based on two powerful columns until 30 June 2005, i. e. reprocessing and direct disposal. After this date any delivery of spent fuel to reprocessing plants was prohibited so that the direct disposal of unreprocessed spent fuel is the only available option in Germany today. The main steps of the current concept are: (i) Intermediate storage of spent fuel, which is the only step in practice. After the first cooling period in spent fuel storage pools it continues into cask-receiving dry storage facilities. Identification of casks, 'freezing' of inventories in terms of continuity of knowledge, monitoring the access to spent fuel, verifying nuclear material movements in terms of cask transfers and ensurance against diversion of nuclear material belong to the fundamental safeguards goals which have been achieved in the intermediate storage facilities by containment and surveillance techniques in unattended mode. (ii) Conditioning of spent fuel assemblies by separating the fuel rods from structural elements. Since the pilot conditioning facility in Gorleben has not yet come into operation, the underlying safeguards approach which focuses on safeguarding the key measurement points - the spent fuel related way in and out of the facility - has not been applied yet. (iii) Disposal in deep geological formations, but no decision has been made so far neither regarding the location of a geological repository nor regarding the safeguards approach for the disposal concept of spent fuel. The situation was complicated by a moratorium which suspended the underground exploration of the Gorleben salt dome as potential geological repository for spent fuel. The moratorium expires in October 2010. Nevertheless, considerable progress has been made in the development of disposal concepts. According to the basic, so-called POLLUX (registered) -concept spent fuel assemblies are to be conditioned after dry storage and reloaded into the POLLUX (registered) -cask

  19. Fuel Retrieval and Management of Fuel Element Debris

    International Nuclear Information System (INIS)

    Chande, Shridhar; Lachaume, J. L.

    2013-01-01

    Nuclear accidents involving core meltdown have not been so rare. While the first occurred in early fifties, it is reported that about 20 have occurred worldwide in military and commercial reactors. The more recent and major accidents are 1. Three Mile Island, USA in 1979: Approximately half the core was melted, and flowed to the bottom of the reactor pressure vessel however the pressure vessel remained intact and contained the damaged fuel. 2. Chernobyl, former USSR in 1984: Explosive release of radioactive material occurred. About 6 tons of fuel was dispersed as air-borne particles. Most of the core was damaged or melted. 3. Fukushima, Japan 2011: Three units suffered melt down. In unit 1 almost all the fuel assemblies melted and accumulated at the bottom of the vessel. It is reported that the vessel failed and the molten corium has penetrated the concrete. In the units 2 and 3, partial melting of cores has occurred. In several of these cases, fuel retrieval and management activities have been carried out. The experience and insights gained from these activities will be extremely useful for planning and execution of similar activities in future if ever they are needed. The purpose of this session was to exchange this experience and also to share the lessons learned. This is of particularly important, at this juncture, when planning and preparation for retrieval of damaged cores in Fukushima NPP is in progress. (author)

  20. Comprehensive studies on regulatory issues of spent fuel pools

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    An existence of safety issues in the spent fuel pool (SFP) was recognized by the nuclear accident at the Fukushima Daiichi Nuclear Power Station, and many reports on the accident describe needs of countermeasures for SFP under sever accidents. For research planning, thermal hydraulic behaviors of SFP and possibility of occurrence of re-criticality conditions in SFP were studied by computational approaches. In the studies on thermal hydraulic behaviors, possibilities of adiabatic conditions in a spent fuel bundle were identified because natural circulation cooling of air could be terminated due to flow path blockage by pool water and steam cooling could be terminated due to reduction of pool water evaporation originated from cold water injection by emergency water supply. In the re-criticality study, in the case of the un-borated lack, it was shown that the neutron multiplication factor became larger than unity when the difference of water levels inside and outside the channel box larger than some values. (author)

  1. Development of advanced spent fuel management process. System analysis of advanced spent fuel management process

    International Nuclear Information System (INIS)

    Ro, S.G.; Kang, D.S.; Seo, C.S.; Lee, H.H.; Shin, Y.J.; Park, S.W.

    1999-03-01

    The system analysis of an advanced spent fuel management process to establish a non-proliferation model for the long-term spent fuel management is performed by comparing the several dry processes, such as a salt transport process, a lithium process, the IFR process developed in America, and DDP developed in Russia. In our system analysis, the non-proliferation concept is focused on the separation factor between uranium and plutonium and decontamination factors of products in each process, and the non-proliferation model for the long-term spent fuel management has finally been introduced. (Author). 29 refs., 17 tabs., 12 figs

  2. Strategic Issues in University Information Management

    Science.gov (United States)

    Roosendaal, Hans E.

    This chapter represents a specific view on university management. It sequentially discusses different organizational levels of e-teaching, starting with general management, e-science developments and what this means to universities, and business models followed by focusing on specific teaching issues. The chapter sets out to discuss the development of the university from a loose federation of faculties into a more integrated university, such as, e.g., an entrepreneurial university. This development is also driven by the introduction of the bachelors/masters system - a process which leads to the need for an institutional strategy introducing institutional quality management and has to be accompanied by the independent accreditation of research and teaching. Applying the model of strategic positioning to the university as a whole leads to the introduction of the university entrepreneur. The model is used to describe structural issues and the relations between the primary processes of research and teaching with the secondary processes. e-science is introduced as a further step toward the universal sharing of scientific results and to analyze the kind of incentives that will be required to attain this goal of making information an even more integral part of the research and teaching process.

  3. In-core fuel management: New challenges

    International Nuclear Information System (INIS)

    Kolmayer, A.; Vallee, A.; Mondot, J.

    1992-01-01

    Experience accumulated by pressurized water reactor (PWR) utilities allows them to improve their strategies in the use of eventual margins to core design limits. They are used for nuclear steam supply system (NSSS) power upgrading, to improve operating margins, or to adapt fuel management to specific objectives. As a result, in-core fuel management strategies have become very diverse: UO 2 or mixed-oxide loading, out-in or in-out fuel loading patterns, extended or annual cycle lengths with margins on design limits such as moderator temperature coefficients, boron concentrations, or peaking factors. Perspectives also appear concerning use of existing plutonium stocks or actinide incineration. Burnable poisons are most often needed to satisfactorily achieve these goals. Among them, gadolinia are now largely used, owing to their excellent performance. More than 24 Framatome first cores and reloads, representing more than 3000 gadolinia-bearing rods, have been irradiated since 1983

  4. Practice and prospect of advanced fuel management and fuel technology application in PWR in China

    International Nuclear Information System (INIS)

    Xiao Min; Zhang Hong; Ma Cang; Bai Chengfei; Zhou Zhou; Wang Lei; Xiao Xiaojun

    2015-01-01

    Since Daya Bay nuclear power plant implemented 18-month refueling strategy in 2001, China has completed a series of innovative fuel management and fuel technology projects, including the Ling Ao Advanced Fuel Management (AFM) project (high-burnup quarter core refueling) and the Ningde 18-month refueling project with gadolinium-bearing fuel in initial core. First, this paper gives brief introduction to China's advanced fuel management and fuel technology experience. Second, it introduces practices of the advanced fuel management in China in detail, which mainly focuses on the implementation and progress of the Ningde 18-month refueling project with gadolinium-bearing fuel in initial core. Finally, the paper introduces the practices of advanced fuel technology in China and gives the outlook of the future advanced fuel management and fuel technology in this field. (author)

  5. Residents' values and fuels management approaches

    Science.gov (United States)

    Gwo-Bao Liou; Christine Vogt; Greg Winter; Sarah McCaffrey

    2008-01-01

    The research utilizes the Forest Value and Salient Value Similarity Scales to examine homeowners' value orientations and relate them to attitudes toward and support for fuels management approaches. Data were collected from homeowners living in the wildland-urban interface of the Huron- Manistee National Forest at two time periods, in 2002 and 2006. The panel data...

  6. Decommissioning and material recycling. Radiation risk management issues

    International Nuclear Information System (INIS)

    Dodd, D.H.

    1996-09-01

    Once nuclear fuel cycle facilities have permanently stopped operations they have to be decommissioned. The decommissioning of a nuclear facility involves the surveillance and dismantling of the facility systems and buildings, the management of the materials resulting from the dismantling activities and the release of the site for further use. The management of radiation risks associated with these activities plays an important role in the decommissioning process. Existing legislation covers many aspects of the decommissioning process. However, in most countries with nuclear power programmes legislation with respect to decommissioning is incomplete. In particular this is true in the Netherlands, where government policy with respect to decommissioning is still in development. Therefore a study was performed to obtain an overview of the radiation risk management issues associated with decommissioning and the status of the relevant legislation. This report describes the results of that study. It is concluded that future work at the Netherlands Energy Research Foundation on decommissioning and radiation risk management issues should concentrate on surveillance and dismantling activities and on criteria for site release. (orig.)

  7. Road safety issues for bus transport management.

    Science.gov (United States)

    Cafiso, Salvatore; Di Graziano, Alessandro; Pappalardo, Giuseppina

    2013-11-01

    Because of the low percentage of crashes involving buses and the assumption that public transport improves road safety by reducing vehicular traffic, public interest in bus safety is not as great as that in the safety of other types of vehicles. It is possible that less attention is paid to the significance of crashes involving buses because the safety level of bus systems is considered to be adequate. The purpose of this study was to evaluate the knowledge and perceptions of bus managers with respect to safety issues and the potential effectiveness of various technologies in achieving higher safety standards. Bus managers were asked to give their opinions on safety issues related to drivers (training, skills, performance evaluation and behaviour), vehicles (maintenance and advanced devices) and roads (road and traffic safety issues) in response to a research survey. Kendall's algorithm was used to evaluate the level of concordance. The results showed that the majority of the proposed items were considered to have great potential for improving bus safety. The data indicated that in the experience of the participants, passenger unloading and pedestrians crossing near bus stops are the most dangerous actions with respect to vulnerable users. The final results of the investigation showed that start inhibition, automatic door opening, and the materials and internal architecture of buses were considered the items most strongly related to bus passenger safety. Brake assistance and vehicle monitoring systems were also considered to be very effective. With the exception of driver assistance systems for passenger and pedestrian safety, the perceptions of the importance of other driver assistance systems for vehicle monitoring and bus safety were not unanimous among the bus company managers who participated in this survey. The study results showed that the introduction of new technologies is perceived as an important factor in improving bus safety, but a better understanding

  8. Fact sheet on spent fuel management

    International Nuclear Information System (INIS)

    2006-01-01

    The IAEA gives high priority to safe and effective spent fuel management. As an example of continuing efforts, the 2003 International Conference on Storage of Spent Fuel from Power Reactors gathered 125 participants from 35 member states to exchange information on this important subject. With its large number of Member States, the IAEA is well-positioned to gather and share information useful in addressing Member State priorities. IAEA activities on this topic include plans to produce technical documents as resources for a range of priority topics: spent fuel performance assessment and research, burnup credit applications, cask maintenance, cask loading optimization, long term storage requirements including records maintenance, economics, spent fuel treatment, remote technology, and influence of fuel design on spent fuel storage. In addition to broader topics, the IAEA supports coordinated research projects and technical cooperation projects focused on specific needs. The proceedings of the 2003 IAEA conference on storage of spent fuel from power reactors has been ranked in the top twenty most accessed IAEA publications. These proceedings are available for free downloads at http://www-pub.iaea.org/MTCD/publications/PubDetails.asp?pubId=6924]. The IAEA organized and held a 2004 meeting focused on long term spent fuel storage provisions in Central and Eastern Europe, using technical cooperation funds to support participation by these Member States. Over ninety percent of the participants in this meeting rated its value as good or excellent, with participants noting that the IAEA is having a positive effect in stimulating communication, cooperation, and information dissemination on this important topic. The IAEA was advised in 2004 that results from a recent coordinated research project (IAEA-TECDOC-1343) were used by one Member State to justify higher clad temperatures for spent fuel in dry storage, leading to more efficient storage and reduced costs. Long term

  9. Fuel cells and electricity companies - new risk management opportunities

    International Nuclear Information System (INIS)

    Whale, M.

    2004-01-01

    'Full text:' Deregulation, distributed generation, combined heat and power, renewables, fuel cells, hydrogen. Power companies are facing a rapidly evolving environment that is testing their ability to effectively deploy capital and earn profits. While recent deregulation trends have shifted the structure of power markets into separating generators from distributors, the improving economic value proposition offered by smaller scale distributed generation technologies - such as fuel cells - would seem to be a conflicting development. In this complex and changing environment, decisions based on the economic reality of the capital markets are likely to prevail. By examining the opportunity to enhance risk management offered by stationary fuel cells, particularly in CHP applications, we provide a context for the issues being discussed in today's sessions focusing on power companies and electric utilities. Our risk management perspective suggests a pathway for implementing fuel cells in combined heat and power applications that large power generators can introduce in increasingly smaller sizes. With capital costs of fuel cells high and risk tolerance of power companies low, the challenge for smaller technology developers will be to reduce the apparently long time horizon that persists for substantial deployment. (author)

  10. Fuel cycle and waste management: A perspective from British nuclear fuels plc

    International Nuclear Information System (INIS)

    Holmes, R.G.G.; Fairhall, G.A.; Robbins, R.A.

    1996-01-01

    The phrase fuel cycle and waste management implies two separate and distinct activities. British Nuclear Fuels plc (BNFL) has adopted a holistic approach to the fuel cycle that integrates the traditional fuel cycle activities of conversion to uranium hexafluoride, fuel fabrication, power generation, and reprocessing with waste arisings, its subsequent treatment, and disposal

  11. Fuel processing for PEM fuel cells: transport and kinetic issues of system design

    Science.gov (United States)

    Zalc, J. M.; Löffler, D. G.

    In light of the distribution and storage issues associated with hydrogen, efficient on-board fuel processing will be a significant factor in the implementation of PEM fuel cells for automotive applications. Here, we apply basic chemical engineering principles to gain insight into the factors that limit performance in each component of a fuel processor. A system consisting of a plate reactor steam reformer, water-gas shift unit, and preferential oxidation reactor is used as a case study. It is found that for a steam reformer based on catalyst-coated foils, mass transfer from the bulk gas to the catalyst surface is the limiting process. The water-gas shift reactor is expected to be the largest component of the fuel processor and is limited by intrinsic catalyst activity, while a successful preferential oxidation unit depends on strict temperature control in order to minimize parasitic hydrogen oxidation. This stepwise approach of sequentially eliminating rate-limiting processes can be used to identify possible means of performance enhancement in a broad range of applications.

  12. Sustainomics of the AMBIDEXTER-NEC Fuel Cycle and Management

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Se Kee; Lee, Young Joon; Ham, Tae Kyu; Seo, Myung Hwan; Hong, Sung Taek; Kwon, Tae An [Ajou University, Suwon (Korea, Republic of)

    2009-05-15

    Energy issues these days become planetary concerns, recognized as the major driver for the resiliency of the earth in the sustainomics framework of the society, economy and environment axes. In the circumstances, in order for the nuclear to take advantage of its GHG-free nature, criticisms associated with the fuel cycle should be defied. As long as the uranium fuel cycle persists, problems bearing on the HLW management and the proliferation prevention could be neither completely decoupled nor independently resolved. Geopolitics around the Korean peninsula makes them be more complicated. Reference of the AMBIDEXTER fuel cycle relies on the DUPIC technology. Combined with fluoride volatility process, desired quantity of uranium contents in the PWR spent fuel powder could be removed. Then, the reactor system runs with the fluorides salt of this uranium-reduced DUPIC fuel material. Surplus uranium from the AMBIDEXTER-DUPIC1 processes should satisfy the LLW classification criteria. So far, the sustainomics goal of the AMBIDEXTER fuel cycle focuses on generating energy from the HLW, meanwhile, converting into LLW without jeopardizing proliferation transparency.

  13. Nuclear-fuel-cycle education: Module 5. In-core fuel management

    International Nuclear Information System (INIS)

    Levine, S.H.

    1980-07-01

    The purpose of this project was to develop a series of educational modules for use in nuclear-fuel-cycle education. These modules are designed for use in a traditional classroom setting by lectures or in a self-paced, personalized system of instruction. This module on in-core fuel management contains information on computational methods and theory; in-core fuel management using the Virginia Polytechnic Institute and State University computer modules; pressurized water reactor in-core fuel management; boiling water reactor in-core fuel management; and in-core fuel management for gas-cooled and fast reactors

  14. Nuclear waste management: A review of issues

    International Nuclear Information System (INIS)

    Angino, E.E.

    1985-01-01

    The subject of radioactive waste management and burial is a subject that raises strong emotional and political issues and generates sharp technical differences of opinion. The overall problem can be subdivided into the three major categories of (1) credibility and emotionalism, (2) technology, and (3) nuclear waste isolation and containment. An area of concern desperately in need of attention is that of proper public education on all aspects of the high-level radioactive-waste (rad-waste) burial problem. A major problem related to the rad-waste issue is the apparent lack of an official, all-encompassing U.S. policy for nuclear waste management, burial, isolation, and regulation. It is clear from all past technical reports that disposal of rad wastes in an appropriate geologic horizon is the best ultimate solution to the waste problem. After 25 y of dealing with the high-level radioactive waste problem, the difficulty is that no proposed plan has to date been tested properly. It is this indecision and reaction that has contributed in no small way to the public perception of inability to solve the problem. One major change that has occurred in the last few years was the enactment of the Nuclear Waste Policy Act of 1982. This act mandates deadlines, guidelines, and state involvement. It is time that strong differences of opinions be reconciled. One must get on with the difficult job of selecting the best means of isolating and burying these wastes before the task becomes impossible

  15. Used Fuel Management System Interface Analyses - 13578

    Energy Technology Data Exchange (ETDEWEB)

    Howard, Robert; Busch, Ingrid [Oak Ridge National Laboratory, P.O. Box 2008, Bldg. 5700, MS-6170, Oak Ridge, TN 37831 (United States); Nutt, Mark; Morris, Edgar; Puig, Francesc [Argonne National Laboratory (United States); Carter, Joe; Delley, Alexcia; Rodwell, Phillip [Savannah River National Laboratory (United States); Hardin, Ernest; Kalinina, Elena [Sandia National Laboratories (United States); Clark, Robert [U.S. Department of Energy (United States); Cotton, Thomas [Complex Systems Group (United States)

    2013-07-01

    Preliminary system-level analyses of the interfaces between at-reactor used fuel management, consolidated storage facilities, and disposal facilities, along with the development of supporting logistics simulation tools, have been initiated to provide the U.S. Department of Energy (DOE) and other stakeholders with information regarding the various alternatives for managing used nuclear fuel (UNF) generated by the current fleet of light water reactors operating in the United States. An important UNF management system interface consideration is the need for ultimate disposal of UNF assemblies contained in waste packages that are sized to be compatible with different geologic media. Thermal analyses indicate that waste package sizes for the geologic media under consideration by the Used Fuel Disposition Campaign may be significantly smaller than the canisters being used for on-site dry storage by the nuclear utilities. Therefore, at some point along the UNF disposition pathway, there could be a need to repackage fuel assemblies already loaded and being loaded into the dry storage canisters currently in use. The implications of where and when the packaging or repackaging of commercial UNF will occur are key questions being addressed in this evaluation. The analysis demonstrated that thermal considerations will have a major impact on the operation of the system and that acceptance priority, rates, and facility start dates have significant system implications. (authors)

  16. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Rummery, T.E.; Rosinger, E.L.J.

    1983-05-01

    The Canadian Nuclear Fuel Waste Management Program is now well established. This report outlines the generic research and technological development underway in this program to assess the concept of immobilization and subsequent disposal of nuclear fuel waste deep in a stable plutonic rock in the Canadian Shield. The program participants, funding, schedule and associated external review processes are briefly outlined. The major scientific and engineering components of the program, namely, immobilization studies, geoscience research and environmental and safety assessment, are described in more detail

  17. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Rummery, T.E.; Rosinger, E.L.J.

    1984-12-01

    The Canadian Nuclear Fuel Waste Management Program is in the fourth year of a ten-year generic research and development phase. The objective of this phase of the program is to assess the basic safety and environmental aspects of the concept of isolating immobilized fuel waste by deep underground disposal in plutonic rock. The major scientific and engineering components of the program, namely immobilization studies, geoscience research, and environmental and safety assessment, are described. Program funding, scheduling and associated external review processes are briefly outlined

  18. Perturbation theory in nuclear fuel management optimization

    International Nuclear Information System (INIS)

    Ho, L.W.; Rohach, A.F.

    1982-01-01

    Perturbation theory along with a binary fuel shuffling technique is applied to predict the effects of various core configurations and, hence, the optimization of in-core fuel management. The computer code FULMNT has been developed to shuffle the fuel assemblies in search of the lowest possible power peaking factor. An iteration approach is used in the search routine. A two-group diffusion theory method is used to obtain the power distribution for the iterations. A comparison of the results of this method with other methods shows that this approach can save computer time and obtain better power peaking factors. The code also has a burnup capability that can be used to check power peaking throughout the core life

  19. Development of advanced spent fuel management process

    International Nuclear Information System (INIS)

    Ro, Seung Gy; Shin, Y. J.; Do, J. B.; You, G. S.; Seo, J. S.; Lee, H. G.

    1998-03-01

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

  20. Core design and fuel management studies

    International Nuclear Information System (INIS)

    Min, Byung Joo; Chan, P.

    1997-06-01

    The design target for the CANDU 9 requires a 20% increase in electrical power output from an existing 480-channel CANDU core. Assuming a net electrical output of 861 MW(e) for a natural uranium fuelled Bruce-B/Darlington reactor in a warm water site, the net electrical output of the reference CANDU 9 reactor would be 1033 MW(e). This report documents the result of the physics studies for the design of the CANDU 9 480/SEU core. The results of the core design and fuel management studies of the CANDU 9 480/SEU reactor indicated that up to 1033 MW(e) output can be achieved in a 480-channel CANDU core by using SEU core can easily be maintained indefinitely using an automated refuelling program. Fuel performance evaluation based on the data of the 500 FPDs refuelling simulation concluded that SEU fuel failure is not expected. (author). 2 tabs., 38 figs., 5 refs

  1. Fuel mechanical design as a boundary condition for fuel management optimization

    International Nuclear Information System (INIS)

    Wunderlich, F.; Aisch, F.W.; Heins, L.

    1988-01-01

    The incentive to reduce fuel cycle costs as well as the amount of active waste requires, among others, measures to optimize fuel management. Improved fuel management in this sense calls, e.g., for reduction of parasitic neutron absorption, for reduction of neutron leakage, and particularly for burnup extension. Such measures result in increased demands for fuel mechanical design. In the first part of this paper their impact on fuel mechanical behaviour is described. In the second part, some examples of practical importance for the interaction between fuel management optimization and fuel mechanical design are discussed. (orig.) [de

  2. Using climate information for fuels management

    Science.gov (United States)

    Kolden, Crystal A.; Brown, Timothy J.

    2008-01-01

    Climate has come to the forefront of wildfire discussions in recent years as research contributes to the general understanding of how climate influences fuels availability to burn, the occurrence of severe fire weather conditions and other wildfire parameters. This understanding has crossed over into wildfire management applications through the creation of tools like climate forecasts for wildfire and drought indices, which are now widely used in wildfire suppression and mitigation planning. The overall question is how can climate information help fire managers meet management objectives? Climate underlies weather. For example, a number of days could be generally wet, but that may occur in the context of a two-year overall drought. Knowing the baseline climate is not only critical to preventing escaped prescribed fires, but also how it may affect fire behavior, fire effects and whether or not fire managers will meet their fuels management objectives. Thus, for fire managers to use prescribed and WFU fire safely and effectively, and to minimize the number of escaped fires and conversions to suppression, they need to understand how current climate conditions will impact the use of fire. One example is the need to use prescribed fire under set “burn windows”. Since meteorological conditions vary considerably from year to year for a given day, fire managers will be more successful in utilizing burn windows effectively if they understand those climate thresholds conducive to an increased number of safe burn windows, and are able to predict and take advantage of those burn windows. While climate and wildfire has been studied extensively, climate and fire use has not. The initial goal of this project was to assess how climate impacts prescribed fire use in a more general sense. After a preliminary informal survey in the spring of 2003, we determined that 1) there is insufficient data (less than 10 years) to conduct empirical correlative studies similar to those of

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-12-01

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

  4. Environmental management at Nuclear Fuel Complex

    International Nuclear Information System (INIS)

    Choudhary, S.; Kalidas, R.

    2005-01-01

    Nuclear Fuel Complex (NFC) a unit of Department of Atomic Energy (DAE) is manufacturing and supplying fuel assemblies and structurals for Atomic Power Reactors, Seamless Stainless Steel/ Special Alloy Tubes and high purity/special materials for various industries including Atomic Energy, Space and Electronics. NFC is spread over about 200 acres area. It consists of various chemical, metallurgical, fabrication and assembly plants engaged in processing uranium from concentrate to final fuel assembly, processing zirconium from ore to metallic products and processing various special high purity materials from ore or intermediate level to the final product. The plants were commissioned in the early seventies and capacities of these plants have been periodically enhanced to cater to the growing demands of the Indian Nuclear Industry. In the two streams of plants processing Uranium and zirconium, various types and categories including low level radioactive wastes are generated. These require proper handling and disposal. The overall management of radioactive and other waste aims at minimizing the generation and release to the environment. In this presentation, the environment management methodologies as practiced in Nuclear Fuel Complex are discussed. (author)

  5. Research reactor spent fuel management in Argentina

    International Nuclear Information System (INIS)

    Audero, M.A.; Bevilacqua, A.M.; Mehlich, A.M.; Novara, O.

    2002-01-01

    The research reactor spent fuel (RRSF) management strategy will be presented as well as the interim storage experience. Currently, low-enriched uranium RRSF is in wet interim storage either at reactor site or away from reactor site in a centralized storage facility. High-enriched uranium RRSF from the centralized storage facility has been sent to the USA in the framework of the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program. The strategy for the management of the RRSF could implement the encapsulation for interim dry storage. As an alternative to encapsulation for dry storage some conditioning processes are being studied which include decladding, isotopic dilution, oxidation and immobilization. The immobilized material will be suitable for final disposal. (author)

  6. Waste management in MOX fuel fabrication plants

    International Nuclear Information System (INIS)

    Schneider, V.

    1982-01-01

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

  7. Environmental management in Framatome nuclear fuel

    International Nuclear Information System (INIS)

    Thiebaut, B.; Ferre, A.

    1999-01-01

    Environmental preservation is both a national regulatory requirement and a condition for economic and social development. The various industrial sites belonging to the Framatome Nuclear Fuel Organisation, whose activities range from the processing and transformation of Zirconium alloy products to the fabrication of fuel assemblies, have always demonstrated that protection of the environment was their prime concern by implementing low pollution level processes and reducing and/or recycling industrial waste and effluents. As early as January 1996, a directive issued by the Framatome Group defined its environmental policy and responsibilities in the matter. Within the Framatome Nuclear Fuel Organization, this directive has been applied by implementation of: low level pollution processes; better performance of recycling of effluents, by-products and waste; environmental information policy. In all its plants, the Framatome Nuclear Fuel Organization has decided to pursue and to step up its environmental protection policy by: officializing its action through compliance with ISO standard 14001 and certification of all its industrial sites by 2001 at the latest; launching new actions and extra investment programs. In this context, FBFC has applied for a modification of the decrees concerning the dumping of liquid and gas effluents at the Romans factory. (authors)

  8. Spent fuel management in Hungary: Current status and prospects

    International Nuclear Information System (INIS)

    Ferenczi, G.

    1996-01-01

    The Paks Nuclear Power Plant Ltd. operates the only NPP of Hungary, consisting of a 4 WWER-440 type units. Since 1989, approximately 40-50 % of the total yearly electricity generation of the country has been supplied by this plant. The fresh fuel is imported from Russia (previously from the Soviet Union) and the spent fuel assemblies are shipped back to Russia for later reprocessing after 5 years of decay storage in the spent fuel pools of the plant. Seeing the political and economical changes that started in Russia, the Paks NPP's management made a decision in 1990 to study the implementation of an independent spent fuel storage facility (ISFSF) at the Paks site and in 1992 to choose the GEC-ALSTHOM's MVDS. On the basis of the Construction License issued by the HAEC, the construction of the ISFSF was started in March 1995. The paper gives general information on the spent fuel arisings, the storage at the site, the shipment to Russia and on the implementation of the ISFSF. (author). 3 refs

  9. Climate and transboundary water management issues

    International Nuclear Information System (INIS)

    Bjonback, D.

    1991-01-01

    The potential effects of climate change on transboundary river systems, major water uses, interjurisdictional arrangements, and water issues affecting water management in the Great Plains of Canada are discussed. Three atmospheric general circulation models (GCM) have been applied for a two times carbon dioxide concentration scenario for the Saskatchewan River system. The models were the Goddard Institute for Space Studies (GISS) model, the Geophysical Fluid Dynamics Laboratory (GFDL) model, and the Oregon State University (OSU) model. For all models, soil moisture on the plains was reduced. The GISS model predicted slightly higher runoff for plains-originating streams, and a substantial increase in runoff (32%) in the Rockies. The GFDL model predicted lower runoffs in the plains and Rockies, with some locations near the Alberta-Saskatchewan border indicating zero runoff. The OSU model results generally bracketed the GISS and GFDL results, with total runoff approximating 1951-1980 mean. The GISS model indicated an increase in net basin supply of 28%, while the GFDL model, due to lower runoff and high soil moisture defecits, showed a decrease of 38%. For policy making, monitoring, and research, the GFDL model results can provide important guidelines. Greater attention to demand management and conservation will have short-term benefits in stretching the limited water resource base to support a larger economy, while providing flexibility to cope with future climate as it evolves. 1 ref

  10. Management reporting in gas and fuel

    International Nuclear Information System (INIS)

    Taylor, J.L.; Foot, B.G.

    1997-01-01

    Gas and Fuel is the sole supplier of reticulated natural gas to 1.3 m customers in the State of Victoria, Australia. Reporting is performed monthly and is tailored to satisfy the requirements of the Board, executive management and business units. The reports include profit and cash statements, gas sales data, capital expenditure, benchmarks, operational data and human resources information. The reports are a mixture of written commentary, accounting statements and graphical presentations. The reports are used at monthly Board and executive meetings to review performance and manage the business. (au)

  11. The management of nuclear fuel waste

    International Nuclear Information System (INIS)

    1980-06-01

    A Select Committee of the Legislature of Ontario was established to examine the affairs of Ontario Hydro, the provincial electrical utility. The Committee's terms of reference included examination of the waste management program being carried out jointly by the Ontario provincial government and the Canadian federal government. Public hearings were held which included private citizens as well as officials of organizations in the nuclear field and independent experts. Recommendations were made concerning the future direction of the Canadian fuel waste management program. (O.T.)

  12. The Spent Fuel Management in Finland and Modifications of Spent Fuel Storages

    International Nuclear Information System (INIS)

    Maaranen, Paeivi

    2014-01-01

    The objective of this presentation is to share the Finnish regulator's (STUK) experiences on regulatory oversight of the enlargement of a spent fuel interim storage. An overview of the current situation of spent fuel management in Finland will also be given. In addition, the planned modifications and requirements set for spent fuel storages due to the Fukushima accident are discussed. In Finland, there are four operating reactors, one under construction and two reactors that have a Council of State's Decision-in-Principle to proceed with the planning and licensing of a new reactor. In Olkiluoto, the two operating ASEA-Atom BWR units and the Areva EPR under construction have a shared interim storage for the spent fuel. The storage was designed and constructed in 1980's. The option for enlarging the storage was foreseen in the original design. Considering three operating units to produce their spent fuel and the final disposal to begin in 2022, extra space in the spent fuel storage is estimated to be needed in around 2014. The operator decided to double the number of the spent fuel pools of the storage and the construction began in 2010. The capacity of the enlarged spent fuel storage is considered to be sufficient for the three Olkiluoto units. The enlargement of the interim storage was included in Olkiluoto NPP 1 and 2 operating license. The licensing of the enlargement was conducted as a major plant modification. The operator needed the approval from STUK to conduct the enlargement. Prior to the construction of this modification, the operator was required to submit the similar documentation as needed for applying for the construction license of a nuclear facility. When conducting changes in an old nuclear facility, the new safety requirements have to be followed. The major challenge in the designing the enlargement of the spent fuel storage was to modify it to withstand a large airplane crash. The operator chose to cover the pools with protecting slabs and also to

  13. Issues of high-burnup fuel for advanced nuclear reactors

    International Nuclear Information System (INIS)

    Belac, J.; Milisdoerfer, L.

    2004-12-01

    A brief description is given of nuclear fuels for Generation III+ and IV reactors, and the major steps needed for a successful implementation of new fuels in prospective types of newly designed power reactors are outlined. The following reactor types are discussed: gas cooled fast reactors, heavy metal (lead) cooled fast reactors, molten salt cooled reactors, sodium cooled fast reactors, supercritical water cooled reactors, and very high temperature reactors. The following are regarded as priority areas for future investigations: (i) spent fuel radiotoxicity; (ii) proliferation volatility; (iii) neutron physics characteristics and inherent safety element assessment; technical and economic analysis of the manufacture of advanced fuels; technical and economic analysis of the fuel cycle back end, possibilities of spent nuclear fuel reprocessing, storage and disposal. In parallel, work should be done on the validation and verification of analytical tools using existing and/or newly acquired experimental data. (P.A.)

  14. A Comparison of Materials Issues for Cermet and Graphite-Based NTP Fuels

    Science.gov (United States)

    Stewart, Mark E.; Schnitzler, Bruce G.

    2013-01-01

    This paper compares material issues for cermet and graphite fuel elements. In particular, two issues in NTP fuel element performance are considered here: ductile to brittle transition in relation to crack propagation, and orificing individual coolant channels in fuel elements. Their relevance to fuel element performance is supported by considering material properties, experimental data, and results from multidisciplinary fluid/thermal/structural simulations. Ductile to brittle transition results in a fuel element region prone to brittle fracture under stress, while outside this region, stresses lead to deformation and resilience under stress. Poor coolant distribution between fuel element channels can increase stresses in certain channels. NERVA fuel element experimental results are consistent with this interpretation. An understanding of these mechanisms will help interpret fuel element testing results.

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  16. Main attributes influencing spent nuclear fuel management

    International Nuclear Information System (INIS)

    Andreescu, N.; Ohai, D.

    1997-01-01

    All activities regarding nuclear fuel, following its discharge from the NPP, constitute the spent fuel management and are grouped in two possible back end variants, namely reprocessing (including HLW vitrification and geological disposal) and direct disposal of spent fuel. In order to select the appropriate variant it is necessary to analyse the aggregate fulfillment of the imposed requirements, particularly of the derived attributes, defined as distinguishing characteristics of the factors used in the decision making process. The main identified attributes are the following: - environmental impact, - availability of suitable sites, - non-proliferation degree, -strategy of energy, - technological complexity and technical maturity, -possible further technical improvements, - size of nuclear programme, - total costs, - public acceptance, - peculiarity of CANDU fuel. The significance of the attributes in the Romanian case, taking into consideration the present situation, as a low scenario and a high scenario corresponding to an important development of the nuclear power, after the year 2010, is presented. According to their importance the ranking of attributes is proposed . Subsequently, the ranking could be used for adequate weighing of attributes in order to realize a multi-criteria analysis and a relevant comparison of back end variants. (authors)

  17. Fuels planning: science synthesis and integration; social issues fact sheet 15: Landscape change and aesthetics

    Science.gov (United States)

    Christine Esposito

    2006-01-01

    Fuels management produces changes in the landscape that can impact scenic beauty. If people do not consider a forest to be scenic, they may think that the low scenic quality is a result of poor management or ecological health. This fact sheet looks at the relevency of the effects of natural and human-caused landscape changes, when planning fuels management.

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

    International Nuclear Information System (INIS)

    Held, C.; Moraw, G.; Schneeberger, M.; Szeless, A.

    1977-01-01

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

  19. CORD, PWR Core Design and Fuel Management

    International Nuclear Information System (INIS)

    Trkov, Andrej

    1996-01-01

    1 - Description of program or function: CORD-2 is intended for core design applications of pressurised water reactors. The main objective was to assemble a core design system which could be used for simple calculations (such as frequently required for fuel management) as well as for accurate calculations (for example, core design after refuelling). 2 - Method of solution: The calculations are performed at the cell level with a lattice code in the supercell approximation to generate the single cell cross sections. Fuel assembly cross section homogenization is done in the diffusion approximation. Global core calculations can be done in the full three-dimensional cartesian geometry. Thermohydraulic feedbacks can be accounted for. The Effective Diffusion Homogenization method is used for generating the homogenized cross sections. 3 - Restrictions on the complexity of the problem: The complexity of the problem is selected by the user, depending on the capacity of his computer

  20. Spent fuel management: reprocessing or storage

    International Nuclear Information System (INIS)

    Lima Soares, M.L. de; Oliveira Lopes, M.J. de

    1986-01-01

    A review of the spent fuel management concepts generally adopted in several countries is presented, including an analysis of the brazilian situation. The alternatives are the reprocessing, the interim storage and the final disposal in a repository after appropriate conditioning. The commercial operating reprocessing facilities in the Western World are located in France and in the United Kingdom. In the USA the anti-reprocessing policy from 1977 changed in 1981, when the government supported the resumption of commercial reprocessing and designated the private sector as responsible for providing these services. Small scale facilities are operating in India, Italy, Japan and West Germany. Pilot plants for LWR fuel are being planned by Spain, Pakistan and Argentina. (Author) [pt

  1. Spent fuel management: reprocessing or storage

    International Nuclear Information System (INIS)

    Lima Soares, M.L. de; Oliveira Lopes, M.J. de.

    1986-01-01

    A review of the spent fuel management concepts generally adopted in several countries is presented, including an analysis of the brazilian situation. The alternatives are the reprocessing, the interim storage and the final disposal in a repository after appropriate conditioning. The commercial operating reprocessing facilities in the Western World are located in France and in the United Kingdom. In the USA the anti-reprocessing policy from 1977 changed in 1981, when the Government supported the resumption of commercial reprocessing and designated the private sector as responsible for providing these services. Small scale facilities are operating in India, Italy, Japan and West Germany. Pilot plant for LWR fuel are being planned by Spain, Pakistan and Argentina. (Author) [pt

  2. Review of decommissioning, spent fuel and radwaste management in Slovakia

    International Nuclear Information System (INIS)

    Jamrich, J.

    2000-01-01

    Two nuclear power plants with two WWER reactors are currently under operation in Jaslovske Bohunice and NPP A-1 is under decommissioning on the same site. At the second nuclear site in the Slovak Republic in Mochovce third nuclear power plant with two units is in operation. In accordance with the basic Slovak legislation (Act on Peaceful Utilisation of Nuclear Energy) defining the responsibilities, roles and authorities for all organisations involved in the decommissioning of nuclear installations Nuclear Regulatory Authority requires submission of conceptual decommissioning plans by the licensee. The term 'decommissioning' is used to describe the set of actions to be taken at the end of the useful life of a facility, in order to retire the facility from service while, simultaneously, ensuring proper protection of the workers, the general public and the environment. This set of activities is in principle comprised of planning and organisation of decommissioning inclusive strategy development, post-operational activities, implementation of decommissioning (physical and radiological characterisation, decontamination, dismantling and demolition, waste and spent fuel management), radiological, aspects, completion of decommissioning as well as ensuring of funding for these activities. Responsibility for nuclear installations decommissioning, radwaste and spent fuel, management in Slovakia is with a subsidiary of Slovak Electric called Nuclear Installations Decommissioning Radwaste and Spent Fuel Management (acronym SE VYZ), established on January 1, 1996. This paper provides description of an approach to planning of the NPP A-1 and NPPs with WWER reactors decommissioning, realisation of treatment, conditioning and disposal of radwaste, as well as spent fuel management in Slovakia. It takes into account that detail papers on all these issues will follow later during this meeting. (author)

  3. National briefing summaries: Nuclear fuel cycle and waste management

    International Nuclear Information System (INIS)

    Schneider, K.J.; Bradley, D.J.; Fletcher, J.F.; Konzek, G.J.; Lakey, L.T.; Mitchell, S.J.; Molton, P.M.; Nightingale, R.E.

    1991-04-01

    Since 1976, the International Program Support Office (IPSO) at the Pacific Northwest Laboratory (PNL) has collected and compiled publicly available information concerning foreign and international radioactive waste management programs. This National Briefing Summaries is a printout of an electronic database that has been compiled and is maintained by the IPSO staff. The database contains current information concerning the radioactive waste management programs (with supporting information on nuclear power and the nuclear fuel cycle) of most of the nations (except eastern European countries) that now have or are contemplating nuclear power, and of the multinational agencies that are active in radioactive waste management. Information in this document is included for three additional countries (China, Mexico, and USSR) compared to the prior issue. The database and this document were developed in response to needs of the US Department of Energy

  4. National briefing summaries: Nuclear fuel cycle and waste management

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, K.J.; Bradley, D.J.; Fletcher, J.F.; Konzek, G.J.; Lakey, L.T.; Mitchell, S.J.; Molton, P.M.; Nightingale, R.E.

    1991-04-01

    Since 1976, the International Program Support Office (IPSO) at the Pacific Northwest Laboratory (PNL) has collected and compiled publicly available information concerning foreign and international radioactive waste management programs. This National Briefing Summaries is a printout of an electronic database that has been compiled and is maintained by the IPSO staff. The database contains current information concerning the radioactive waste management programs (with supporting information on nuclear power and the nuclear fuel cycle) of most of the nations (except eastern European countries) that now have or are contemplating nuclear power, and of the multinational agencies that are active in radioactive waste management. Information in this document is included for three additional countries (China, Mexico, and USSR) compared to the prior issue. The database and this document were developed in response to needs of the US Department of Energy.

  5. Management of radioactive wastes from the nuclear fuel cycle

    International Nuclear Information System (INIS)

    1976-01-01

    The increased emphasis in many countries on the development and utilization of nuclear power is leading to an expansion of all sectors of the nuclear fuel cycle, giving rise to important policy issues and radioactive-waste management requirements. Consequently, the IAEA and the Nuclear Energy Agency of OECD felt that it would be timely to review latest technology for the management of the radioactive wastes arising from nuclear fuel cycle facilities, to identify where important advances have been made, and to indicate those areas where further technological development is needed. Beginning in 1959, the IAEA, either by itself or jointly with OECD/NEA has held seven international symposia on the management of radioactive wastes. The last symposium, on the management of radioactive wastes from fuel reprocessing, was held jointly by the IAEA and OECD/NEA in Paris in November 1972. An objective of the 1976 symposium was to update the information presented at the previous symposia with the latest technological developments and thinking regarding the management and disposal of all categories of radioactive wastes. Consequently, although the scope of the symposium was rather broad, attention was focussed on operational experience and progress in unresolved areas of radioactive waste management. The programme dealt primarily with the solidification of liquid radioactive wastes and disposal of the products, especially the high-level fission products and actinide-containing waste from fuel reprocessing. Other topics covered policy and planning, treatment of hulls and solvent, management of plutonium-contaminated waste, and removal of gaseous radionuclides. The major topic of interest was the current state of the technology for the reduction and incorporation of the high-level radioactive liquid from fuel reprocessing into solid forms, such as calcines, glasses or ceramics, for safe interim storage and eventual disposal. The approaches to vitrification ranged from two stage

  6. Human factors and safety issues associated with actinide retrieval from spent light water reactor fuel assemblies

    International Nuclear Information System (INIS)

    Spelt, P.F.

    1992-01-01

    A major problem in environmental restoration and waste management is the disposition of used fuel assemblies from the many light water reactors in the United States, which present a radiation hazard to those whose job is to dispose of them, with a similar threat to the general environment associated with long-term storage in fuel repositories around the country. Actinides resident in the fuel pins as a result of their use in reactor cores constitute a significant component of this hazard. Recently, the Department of Energy has initiated an Actinide Recycle Program to study the feasibility of using pyrochemical (molten salt) processes to recover actinides from the spent fuel assemblies of commercial reactors. This project concerns the application of robotics technology to the operation and maintenance functions of a plant whose objective is to recover actinides from spent fuel assemblies, and to dispose of the resulting hardware and chemical components from this process. Such a procedure involves a number of safety and human factors issues. The purpose of the project is to explore the use of robotics and artificial intelligence to facilitate accomplishment of the program goals while maintaining the safety of the humans doing the work and the integrity of the environment. This project will result in a graphic simulation on a Silicon Graphics workstation as a proof of principle demonstration of the feasibility of using robotics along with an intelligent operator interface. A major component of the operator-system interface is a hybrid artificial intelligence system developed at Oak Ridge National Laboratory, which combines artificial neural networks and an expert system into a hybrid, self-improving computer-based system interface. 10 refs

  7. Integrating fuel treatment into ecosystem management: A proposed project planning process

    Science.gov (United States)

    Keith D. Stockmann; Kevin D. Hyde; J. Greg Jones; Dan R. Loeffler; Robin P. Silverstein

    2010-01-01

    Concern over increased wildland fire threats on public lands throughout the western United States makes fuel reduction activities the primary driver of many management projects. This single-issue focus recalls a management planning process practiced frequently in recent decades - a least-harm approach where the primary objective is first addressed and then plans are...

  8. Nuclear Spent Fuel Management in Spain

    International Nuclear Information System (INIS)

    Zuloaga, P.

    2015-01-01

    The radioactive waste management policy is established by the Spanish Government through the Ministry of Industry, Tourism and Commerce. This policy is described in the Cabinet-approved General Radioactive Waste Plan. ENRESA is the Spanish organization in charge of radioactive waste and nuclear SFM and nuclear installations decommissioning. The priority goal in SFM is the construction of the centralized storage facility named Almacén Temporal Centralizado (ATC), whose generic design was approved by the safety authority, Consejo de Seguridad Nuclear. This facility is planned for some 6.700 tons of heavy metal. The ATC site selection process, based on a volunteer community’s scheme, has been launched by the Government in December 2009. After the selection of a site in a participative and transparent process, the site characterization and licensing activities will support the construction of the facility. Meanwhile, extension of the on-site storage capacity has been implemented at the seven nuclear power plants sites, including past reracking at all sites. More recent activities are: reracking performed at Cofrentes NPP; dual purpose casks re-licensing for higher burnup at Trillo NPP; transfer of the spent fuel inventory at Jose Cabrera NPP to a dry-storage system, to allow decommissioning operations; and licence application of a dry-storage installation at Ascó NPP, to provide the needed capacity until the ATC facility operation. For financing planning purposes, the long-term management of spent fuel is based on direct disposal. A final decision about major fuel management options is not made yet. To assist the decision makers a number of activities are under way, including basic designs of a geological disposal facility for clay and granite host rocks, together with associated performance assessment, and supported by a R&D programme, which also includes research projects in other options like advanced separation and transmutation. (author)

  9. Multinational approaches relevant to spent fuel management

    International Nuclear Information System (INIS)

    Pellaud, B.

    2007-01-01

    The storage of spent fuel is a suitable candidate for a multilateral approach, primarily at the regional level. Small countries with only a few nuclear power plants would benefit economically from large joint facilities. The storage of special nuclear materials in a few safe and secure facilities would also enhance safeguards and physical protection. However, the final disposal of spent fuel and high level radioactive waste is the best candidate for a multilateral approach. It would offer major economic benefits and substantial non-proliferation benefits in spite of the legal, political and public acceptance challenges to be expected in most countries. The transfer of nuclear waste from the exporting country to the host country of an interim storage facility or of a final repository would be done under bilateral or multilateral agreements at the commercial and governmental levels, in accordance with the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. Bilateral or international oversight of joint facilities should be arranged, as needed, to achieve the confidence of the partners as to the safety and physical security of the proposed facility. Such monitoring should cover the adequacy of the technical design, its safety features, its environmental impact, the physical security of nuclear materials and possibly the financial management of the joint venture. After the initial choice of bilateral arrangements, some kind of international monitoring may become appropriate. Various organizations could fulfil such a function, in particular, the IAEA. Such monitoring would have nothing to do with nuclear safeguards; repository monitoring would be a parallel but independent activity of the IAEA. (author)

  10. Fuel-management simulations for once-through thorium fuel cycle in CANDU reactors

    International Nuclear Information System (INIS)

    Chan, P.S.W.; Boczar, P.G.; Ellis, R.J.; Ardeshiri, F.

    1999-01-01

    High neutron economy, on-power refuelling and a simple fuel bundle design result in unsurpassed fuel cycle flexibility for CANDU reactors. These features facilitate the introduction and exploitation of thorium fuel cycles in existing CANDU reactors in an evolutionary fashion. Detailed full-core fuel-management simulations concluded that a once-through thorium fuel cycle can be successfully implemented in an existing CANDU reactor without requiring major modifications. (author)

  11. Ciclon: A neutronic fuel management program for PWR's consecutive cycles

    International Nuclear Information System (INIS)

    Aragones, J.M.

    1977-01-01

    The program description and user's manual of a new computer code is given. Ciclon performs the neutronic calculation of consecutive reload cycles for PWR's fuel management optimization. Fuel characteristics and burnup data, region or batch sizes, loading schemes and state of previously irradiated fuel are input to the code. Cycle lengths or feed enrichments and burnup sharing for each region or batch are calculate using different core neutronic models and printed or punched in standard fuel management format. (author) [es

  12. Alternative fuels and advanced technology vehicles : issues in Congress

    Science.gov (United States)

    2009-02-13

    Alternative fuels and advanced technology vehicles are seen by proponents as integral to improving urban air quality, decreasing dependence on foreign oil, and reducing emissions of greenhouse gases. However, major barriers especially economics curre...

  13. Risk Management Issues - An Aerospace Perspective

    Science.gov (United States)

    Perera, Jeevan S.

    2011-01-01

    Phased-approach for implementation of risk management is necessary. Risk management system will be simple, accessible and promote communication of information to all relevant stakeholders for optimal resource allocation and risk mitigation. Risk management should be used by all team members to manage risks--risk office personnel. Each group is assigned Risk Integrators who are facilitators for effective risk management. Risks will be managed at the lowest-level feasible, elevate only those risks that require coordination or management from above. Risk reporting and communication is an essential element of risk management and will combine both qualitative and quantitative elements.. Risk informed decision making should be introduced to all levels of management. Provide necessary checks and balances to insure that risks are caught/identified and dealt with in a timely manner, Many supporting tools, processes & training must be deployed for effective risk management implementation. Process improvement must be included in the risk processes.

  14. Addressing the long time horizon for managing used nuclear fuel

    International Nuclear Information System (INIS)

    Hodge, R.A.

    2006-01-01

    The time horizon that must be considered in developing an approach to managing used nuclear fuel extends many thousands of years. Such a time horizon is without precedent in environmental, economic, social, technical and public policy terms. As a first step in addressing this issue, the Nuclear Waste Management Organization convened a team of 33 individuals to undertake a formal scenarios exercise. Such an exercise is a way of framing potential futures that might occur. There is no intent to predict the future. This exercise represents the first time that the scenarios technique has been used for such a long time horizon. The approach involved identifying two principle axes of potential change: (1) social - political - environmental well-being; and (2) magnitude of the used nuclear fuel challenge. Using this organizing template, four scenarios were developed reaching out 25 years, and an additional twelve were developed at 175 years branching out from the original four. In addition, a series of sixteen possible 'end-points' were identified to span conditions 500 years out and for 10,000 years a large number of 'what- ifs' were developed. The scenarios, end-points, and what- ifs were then used to identify a number of criteria that could be used for testing proposed management options and their capacity to deal with future conditions. This paper describes this work and the role that it has played in the deliberations of the Nuclear Waste Management Organization. (author)

  15. Nuclear fuel management optimization for LWRs

    International Nuclear Information System (INIS)

    Turinsky, Paul J.

    1997-01-01

    LWR in core nuclear fuel management involves the placement of fuel and control materials so that a specified objective is achieved within constraints. Specifically, one is interested in determining the core loading pattern (LP of fuel assemblies and burnable poisons and for BWR, also control rod insertion versus cycle exposure. Possible objectives include minimization of feed enrichment and maximization of cycle energy production, discharge burnup or thermal margin. Constraints imposed relate to physical constraints, e.g. no discrete burnable poisons in control rod locations, and operational and safety constraints, e.g. maximum power peaking limit. The LP optimization problem is a large scale, nonlinear, mixed-integer decision variables problem with active constraints. Even with quarter core symmetry imposed, there are above 10 100 possible LPs. The implication is that deterministic optimization methods are not suitable, so in this work we have pursued using the stochastic Simulated Annealing optimization method. Adaptive penalty functions are used to impose certain constraints, allowing unfeasible regions of the search space to be transverse. Since ten of thousands of LPs must be examined to achieve high computational efficiency, higher-order Generalized Perturbation Theory is utilized to solve the Nodal Expansion Method for of the two-group neutron diffusion. These methods have been incorporated into the FORMOSA series of codes and used to optimize PWR and BWR reload cores. (author). 9 refs., 3 tabs

  16. Fuel cycle management by the electric enterprises and spanish nuclear Power plants

    International Nuclear Information System (INIS)

    Celma, E. M.; Gonzalez, C.; Lopez, J. V.; Melara, J.; Lopez, L.; Martinez, J. C.; Culbras, F.; Blanco, J.; Francia, L.

    2015-01-01

    The Nuclear Fuel Group reports to the Technology Committee of the UNESA Nuclear Energy Committee, and is constituted by representatives of both the Spanish Utilities and the Nuclear Power Plants. The Group addresses the nuclear plant common issues in relation to the operation and management of the nuclear fuel in their different stages of the Fuel Cycle. The article reviews the activities developed by the Group in the Front-End, mainly in the monitoring of international programs that define criteria to improve the Fuel Reliability and in the establishment of common bases for the implementation of changes in the regulation applying the nuclear fuel. Concerning the Back-End the Group focuses on those activities of coordination with third parties related to the management of used fuel. (Author)

  17. Identity Management issues in Cloud Computing

    OpenAIRE

    Saini, Smita; Mann, Deep

    2014-01-01

    Cloud computing is providing a low cost on demand services to the users, omnipresent network,large storage capacity due to these features of cloud computing web applications are moving towards the cloud and due to this migration of the web application,cloud computing platform is raised many issues like privacy, security etc. Privacy issue are major concern for the cloud computing. Privacy is to preserve the sensitive information of the cloud consumer and the major issues to the privacy are un...

  18. Reputationsorientiertes Themen- und Issues-Management : Konzeption, Regelbetrieb, Weiterentwicklung

    OpenAIRE

    Fahrenbach, Christian

    2011-01-01

    Die Dissertation untersucht, wie Organisationen ein reputationsorientiertes Themen- und Issues-Management aufbauen, betreiben und weiterentwickeln können. Dazu wird das operative Modell des Issues Managements mit dem strategischen Zielkonstrukt Reputation verbunden. Zu Beginn der Arbeit beschreiben zwei Theorie-Kapitel ausführlich Relevanz und die Steuerung von Reputation und im Issues Management. Auf dieser Basis wird ein praxisorientiertes integriertes Modell entwickelt. Es beschreibt da...

  19. Aspects regarding the fuel management for PHWR nuclear reactors

    International Nuclear Information System (INIS)

    Dragusin, O.; Bobolea, A.; Voicu, A.

    2001-01-01

    Fuel management for PHWR nuclear reactors is completely different from the PWR reactors fuel management. PHWR reactor fuel loading procedures are repeated after an interval of time, as defined and specified in the project documentation, using a fuel machine that can be attached to the terminal fittings of horizontal pressure tubes while the reactor is a full power. Another aspect of fuel management policy is related to the possibility of bi-directional loading of the reactor, with the primary advantage of uniform and symmetrical characteristics. (authors)

  20. Implementation of burnup credit in spent fuel management systems. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-08-01

    The purpose of this Technical Committee Meeting was to explore the status of international activities related to the use of burnup credit for spent fuel applications. This was the second major meeting on the issues of burnup credit for spent fuel management systems held since the IAEA began to monitor the uses of burnup credit in spent fuel management systems in 1997. Burnup credit for wet and dry storage systems is needed in many Member States to allow for increased initial fuel enrichment, and to increase the storage capacity and thus to avoid the need for extensive modifications of the spent fuel management systems involved. This document contains 31 individual papers presented at the Meeting; each of the papers was indexed separately.

  1. Implementation of burnup credit in spent fuel management systems. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2001-08-01

    The purpose of this Technical Committee Meeting was to explore the status of international activities related to the use of burnup credit for spent fuel applications. This was the second major meeting on the issues of burnup credit for spent fuel management systems held since the IAEA began to monitor the uses of burnup credit in spent fuel management systems in 1997. Burnup credit for wet and dry storage systems is needed in many Member States to allow for increased initial fuel enrichment, and to increase the storage capacity and thus to avoid the need for extensive modifications of the spent fuel management systems involved. This document contains 31 individual papers presented at the Meeting; each of the papers was indexed separately

  2. Facts and issues of direct disposal of spent fuel; Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Parks, P.B.

    1993-10-01

    This report reviews those facts and issues that affect the direct disposal of spent reactor fuels. It is intended as a resource document for those impacted by the current Department of Energy (DOE) guidance that calls for the cessation of fuel reprocessing. It is not intended as a study of the specific impacts (schedules and costs) to the Savannah River Site (SRS) alone. Commercial fuels, other low enriched fuels, highly enriched defense-production, research, and naval reactor fuels are included in this survey, except as prevented by rules on classification.

  3. Fuels planning: science synthesis and integration; social issues fact sheet 12: Keys to successful collaboration

    Science.gov (United States)

    Christine Esposito

    2006-01-01

    Collaborating on fire and fuels management with a host of public and private partners may seem like an impossible undertaking, and presents many challenges. This fact sheet reviews tips for what to focus on as you embark on a collaborative fuels management project.Other...

  4. Some Issues on Management Information System Course Teaching

    OpenAIRE

    Chen, Dingquan

    2008-01-01

    This paper discuses the following issues about Management Information System course for the major of information management & Information System: Teaching Object, the difference between Information System Analysis and Design course, teaching content, and experiment plan.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-10-15

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

  6. International Atomic Energy Agency (IAEA) Activity on Technical Influence of High Burnup UOX and MOX Water Reactor Fuel on Spent Fuel Management

    International Nuclear Information System (INIS)

    Lovasic, Z.; Einziger, R.

    2009-01-01

    This paper briefly reviews the results of the International Atomic Energy Agency (IAEA) project investigating the influence of high burnup and mixed-oxide (MOX) fuels, from water power reactors, on spent fuel management. These data will provide information on the impacts, regarding spent fuel management, for those countries operating light-water reactors (LWR)s and heavy-water reactors (HWR)s with zirconium alloy-clad uranium dioxide (UOX) fuels, that are considering the use of higher burnup UOX or the introduction of reprocessing and MOX fuels. The mechanical designs of lower burnup UOX and higher burnup UOX or MOX fuel are very similar, but some of the properties (e.g., higher fuel rod internal pressures; higher decay heat; higher specific activity; and degraded cladding mechanical properties of higher burnup UOX and MOX spent fuels) may potentially significantly affect the behavior of the fuel after irradiation. These properties are reviewed. The effects of these property changes on wet and dry storage, transportation, reprocessing, re-fabrication of fuel, and final disposal were evaluated, based on regulatory, safety, and operational considerations. Political and strategic considerations were not taken into account since relative importance of technical, economic and strategic considerations vary from country to country. There will also be an impact of these fuels on issues like non-proliferation, safeguards, and sustainability, but because of the complexity of factors affecting those issues, they are only briefly discussed. Data gaps were also identified during this investigation. The pros and cons of using high burnup UOX or MOX, for each applicable issue in each stage of the back end of the fuel cycle, were evaluated and are discussed.. Although, in theory, higher burnup fuel and MOX fuels mean a smaller quantity of spent fuel, the potential need for some changes in design of spent fuel storage, transportation, handling, reprocessing, re-fabrication, and

  7. Issues and trends in radioactive waste management in Turkey

    International Nuclear Information System (INIS)

    Osmanlioglu, A.E.

    2002-01-01

    This paper focuses on issues associated with the waste management aspects of Turkey. Predisposal management of radioactive wastes covers a broad range of activities. This also includes waste identification, characterization and conditioning. Experience gained over years shows that current predisposal waste management practices are well advanced. The paper concludes these activities based on experience gained by CWPSF (CNAEM Waste Processing and Storage Facility) and includes issues and trends in radioactive waste management. In addition general information is presented on ongoing national projects and IAEA research projects on various issues of waste management. (author)

  8. In-core fuel management benchmarks for PHWRs

    International Nuclear Information System (INIS)

    1996-06-01

    Under its in-core fuel management activities, the IAEA set up two co-ordinated research programmes (CRPs) on complete in-core fuel management code packages. At a consultant meeting in November 1988 the outline of the CRP on in-core fuel management benchmars for PHWRs was prepared, three benchmarks were specified and the corresponding parameters were defined. At the first research co-ordination meeting in December 1990, seven more benchmarks were specified. The objective of this TECDOC is to provide reference cases for the verification of code packages used for reactor physics and fuel management of PHWRs. 91 refs, figs, tabs

  9. The Brazilian experience with alcohol fuel: microeconomic and environmental issues

    International Nuclear Information System (INIS)

    Seroa da Motta, R.

    1990-01-01

    Producers and consumers in Brazil are not longer regarding alcohol (ethanol) as a valuable fuel choice. Although the falling of oil prices has contributed to this situation, the lack of concern on microeconomic behaviour has also played an important role. Furthermore, environmental gains derived from the use of a mixture of alcohol and gasoline have been forgotten when alcohol fuel is evaluated. From the Brazilian experience some fruitful lessons can be learnt, to support research efforts for renewable energy programmes in Europe and the U.S.A. (author)

  10. Embedded generation and network management issues

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    This report focuses on the characteristics of power generators that are important to accommodation in a distribution system. Part 1 examines the differences between transmission and distribution systems, and issues such as randomness, diversity, predictability, and controllability associated with accommodation in a distribution system. Part 2 concentrates on technical and operational issues relating to embedded generation, and the possible impact of the New Electricity Trading Arrangements. Commercial issues, contractual relationships for network charging and provision of services, and possible ways forward are examined in the last three parts of the report.

  11. Utilities' view on the fuel management of nuclear power plants

    International Nuclear Information System (INIS)

    Held, C.; Moraw, G.; Schneeberger, M.; Szeless, A.

    1977-01-01

    Utilities engagement in nuclear power requires an increasing amount of fuel management activities by the utilities in order to meet all tasks involved. These activities comprise essentially two main areas: - activities to secure the procurement of all steps of the fuel cycle from the head to the back end; - activities related to the incore fuel managment. A general survey of the different steps of the nuclear fuel cycle is presented together with the related activities and responsibilities which have to be realized by the utilities. Starting in the past, today's increasing utility involvement in the nuclear fuel management is shown, as well as future fuel management trends. The scope of utilities' fuel management activities is analyzed with respect to organizational aspects, technical aspects, safeguarding aspects, and financial aspects. Utilities taking active part in the fuel management serves to achieve high availability and flexibility of the nuclear power plant during the whole plant life as well as safe waste isolation. This can be assured by continuous optimization of all fuel management aspects of the power plant or on a larger scale of a power plant system, i.e., utility activities to minimize the effects of fuel cycle on the environment, which includes optimization of fuel behaviour, radiation exposure to public and personnel, and utility technical and economic evaluations of out- and incore fuel management. These activities of nuclear power producing utilities in the field of nuclear fuel cycle are together with a close cooperation with fuel industry as well as national and international authorities a necessary basis for the further utilization of nuclear power

  12. Analysis of back-end fuel-cycle issues in the ROK

    Energy Technology Data Exchange (ETDEWEB)

    Forrest, R.; Braun, C., E-mail: rforrest@gmail.com, E-mail: cbraun@stanford.edu [Stanford Univ., Center for International Security and Cooperation (CISAC), Stanford, CA (United States)

    2014-07-01

    We discuss mid and near term issues related to spent nuclear fuel (SNF) management in the Republic of Korea (ROK). Currently, 23 operational reactors in the ROK produce SNF that is stored mostly in pools adjacent to each reactor. It is expected that, due to the limited capacity of these pools, they will be saturated within the decade. The ROK may arrange for several additional years of pool storage via various mechanisms such as high density racking and intra-site SNF transhipment. However, these short term measures will quickly run their course, and the fundamental problem of SNF disposition will remain. We model the future of SNF pools of all reactors located on each of the reactor sites to verify declared saturation dates under constraints of current policy. Using this model we can examine the effect of current and planned mitigation measures in addressing short-term saturation. We then propose simple additional measures requiring changes in policy and calculate additional time such measures would afford. Projecting further into the future, we can then calculate saturation timelines under various fuel cycle scenarios and how such timelines would allow transition to future proposed closed cycles. Among other observations, we determine that even with the timely success of the ongoing pyroprocessing effort, interim SNF storage will be required. It follows that this would most logically be a single, centralized dry cask storage facility commonly called an Independent Spent Fuel Storage Installation (ISFSI). The purpose of this study is to inform a larger project between CISAC and the East Asia Institute (EAI) to examine important issues in nuclear security and energy in the ROK. (author)

  13. Development of pyrochemical spent fuel management in the UK

    Energy Technology Data Exchange (ETDEWEB)

    Banfield, Zara; Cogan, John; Farrant, Dave; Gaubert, Emmanuel; Hopkins, Phil; Lewin, Bob [BNFL - Nexia Solutions Limited, Workington Facility, B291 Trenches, Sellafield (United Kingdom)

    2006-07-01

    . Other major sections of investigation are electrochemical reduction and anode processes. These are essential to be able to validate the flowsheet and assess whether pyrochemical processes offer a viable nuclear fuel management option. The scientific and engineering work has resulted in patent applications in most work areas. This paper examines these issues more fully and includes details of specific work in the engineering and scientific areas. (authors)

  14. Development of pyrochemical spent fuel management in the UK

    International Nuclear Information System (INIS)

    Banfield, Zara; Cogan, John; Farrant, Dave; Gaubert, Emmanuel; Hopkins, Phil; Lewin, Bob

    2006-01-01

    major sections of investigation are electrochemical reduction and anode processes. These are essential to be able to validate the flowsheet and assess whether pyrochemical processes offer a viable nuclear fuel management option. The scientific and engineering work has resulted in patent applications in most work areas. This paper examines these issues more fully and includes details of specific work in the engineering and scientific areas. (authors)

  15. Acceptance of failed SNF [spent nuclear fuel] assemblies by the Federal Waste Management System

    International Nuclear Information System (INIS)

    1990-03-01

    This report is one of a series of eight prepared by E. R. Johnson Associates, Inc. (JAI) under ORNL's contract with DOE's OCRWM Systems Integration Program and in support of the Annual Capacity Report (ACR) Issue Resolution Process. The report topics relate specifically to the list of high priority technical waste acceptance issues developed jointly by DOE and a utility-working group. JAI performed various analyses and studies on each topic to serve as starting points for further discussion and analysis leading eventually to finalizing the process by which DOE will accept spent fuel and waste into its waste management system. The eight reports are concerned with the conditions under which spent fuel and high level waste will be accepted in the following categories: failed fuel; consolidated fuel and associated structural parts; non-fuel-assembly hardware; fuel in metal storage casks; fuel in multi-element sealed canisters; inspection and testing requirements for wastes; canister criteria; spent fuel selection for delivery; and defense and commercial high-level waste packages. This document discusses acceptance of failed spent fuel assemblies by the Federal Waste Management System. 18 refs., 7 figs., 25 tabs

  16. Hydrocarbon Biocomponents use in Aviation Fuels - Preliminary Analysis of Issues

    Directory of Open Access Journals (Sweden)

    Gawron Bartosz

    2015-01-01

    Full Text Available Article is related to the aspect of the introduction of biofuels to power turbine aircraft engines. The paper presents the current trends in the use of alternative fuels in aviation and the problems connected with the introduction of hydrocarbon biocomponents. It is pointed to the need to take research and implementation works in the field of the subject, also in Poland.

  17. Nuclear fuel cycle and reactor strategies: Adjusting to new realities. Key issue papers

    International Nuclear Information System (INIS)

    1997-01-01

    The international symposium ''Nuclear Fuel Cycle and Reactor Strategy: Adjusting to new Realities'' was organized to face the new realities in the nuclear fuel cycle and to consider options on how these new realities could be addressed. The Key Issue Papers treat the various subjects from both short and long term perspectives. In so doing, they address the likely development of all aspects concerning the nuclear fuel cycle up to the year 2050

  18. Providing flexibility in spent fuel and vitrified waste management

    International Nuclear Information System (INIS)

    Bradley, N.; O'Tallamhain, C.; Brown, G.A.

    1986-01-01

    The UK Central Electricity Generating Board is pondering a decision to build a dry vault store as a buffer in its overall AGR spent fuel management programme. The application of the dry vault is not limited to fuel from gas cooled reactors, it can be used for spent LWR fuel and vitrified waste. A cutaway diagram of such a vault is presented. (UK)

  19. Controversial Issues in Thyroid Cancer Management.

    Science.gov (United States)

    Tuttle, R Michael

    2018-04-13

    The lack of prospective randomized clinical trials for most management topics in differentiated thyroid cancer force us to make management recommendations based on retrospective observational data which is often incomplete, subject to selection bias, and conflicting. Therefore, it is not surprising that many aspects of thyroid cancer management remain controversial and not well defined. This review will examine the controversies surrounding three important topics in thyroid cancer management: (1) the option of thyroid lobectomy as initial therapy for thyroid cancer, (2) the proper use of preoperative neck imaging to optimize the completeness of the initial surgical procedure, and (3) the selective use RAI therapy as remnant ablation, adjuvant treatment or treatment of known persistent/recurrent disease. As thyroid cancer management moves toward a much more risk adapted approach to personalized management recommendations, clinicians and patients must balance the risks and benefits of the potential management options to arrive at a management plan that is optimized based on both patient preferences/values and the philosophy/experience of the local disease management team. Copyright © 2018 by the Society of Nuclear Medicine and Molecular Imaging, Inc.

  20. 1st Fire Behavior and Fuels Conference: Fuels Management-How to Measure Success

    Science.gov (United States)

    Patricia L. Andrews

    2006-01-01

    The 1st Fire Behavior and Fuels Conference: Fuels Management -- How to Measure Success was held in Portland, Oregon, March 28-30, 2006. The International Association of Wildland Fire (IAWF) initiated a conference on this timely topic primarily in response to the needs of the U.S. National Interagency Fuels Coordinating Group (http://www.nifc.gov/).

  1. Scope and procedures of fuel management for PWR nuclear power plant

    International Nuclear Information System (INIS)

    Yao Zenghua

    1997-01-01

    The fuel management scope of PWR nuclear power plant includes nuclear fuel purchase and spent fuel disposal, ex-core fuel management, in-core fuel management, core management and fuel assembly behavior follow up. A suit of complete and efficient fuel management procedures have to be created to ensure the quality and efficiency of fuel management work. The hierarchy of fuel management procedure is divided into four levels: main procedure, administration procedure, implement procedure and technic procedure. A brief introduction to the fuel management scope and procedures of PWR nuclear power plant are given

  2. Knowledge Management Issues in Academic Libraries in Imo State ...

    African Journals Online (AJOL)

    This paper explored the Knowledge Management (KM) issues in academic libraries. It discussed these issues - types of knowledge and knowledge management practices; the technologies and mechanisms of acquiring; creating; sharing, transferring etc knowledge in the present day knowledge era. It highlighted the ...

  3. A study on the safety of spent fuel management. A scenario study on spent fuel management

    Energy Technology Data Exchange (ETDEWEB)

    Chun, Kwan Sik; Park, Hyun Soo; Ahn, Jin Soo; Hwang, Joo Ho; Choi, Jong Won; Kim, Yeon Soo; Park, Ju Hwan; Chung, Choong Hwan [Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)

    1992-03-01

    In order to produce data applicable for the long-term policy making of spent fuel management and to suggest a basic scenario suitable to domestic situation, the pre-conceptual design of reference disposal facilities for the spent fuel and the vitrified high level radioactive waste from its reprocessing, has been performed. From the results of the pre-conceptual study, further research and development areas to accumulate the disposal technology are suggested. In addition, the physico-chemical properties and functional characteristics of domestic bentonite are analyzed to assess its applicability as a buffer material which would play a major role for the safe disposal of highly active waste including spent fuels. (Author).

  4. Information Systems Management: an Australian view of the key issues

    Directory of Open Access Journals (Sweden)

    Graham Pervan

    1994-05-01

    Full Text Available Studies investigating the key issues in IS management serve to better understand the concerns of IS managers and help to guide IS researchers in choosing IS management problems worthy of investigation. This paper presents results from a study of the key issues facing the IS managers of Australia's largest 300 organisations which is part of a three-yearly longitudinal study. In order to gain consensus on the relative importance of the key issues, a three-round Delphi method was applied. The results reveal that IS strategic planning continues to be the paramount issue in our industry, as are many issues associated with IS strategic planning, including responsiveness of the IT infrastructure, effective use of the data resource, IS for competitive advantage, and a comprehensive information architecture. A greater emphasis on quality is also revealed in highly rated issues such as effective use of the data resource, data integrity and quality assurance, and the quality of software development

  5. Product Life Cycle - Quality Management Issues

    DEFF Research Database (Denmark)

    Alting, Leo; Majstorovic, Vidosav D.

    2004-01-01

    The strategic goal of our country is European and world integration. Within this context the management of sustainable development considered from the aspect of product’s life cycle and its quality management represents a real challenge for researchers, economy and educational system. The aim...

  6. Core fuel management using TVS-2M fuel assembly and economic analysis

    International Nuclear Information System (INIS)

    Xu Min; Wang Hongxia; Li Youyi

    2014-01-01

    To improve the economic efficiency, TVS-2M fuel assembly was considered to apply in Tianwan Nuclear Power Plant units 3, 4. Using KASKAD program package, a preliminary research and design was carried out for the Tianwan Nuclear Power Plant loading TVS-2M fuel assembly from the first cycle to equilibrium cycle. An improved fuel management program was obtained, and the economic analysis of the two fuel management programs with or without TVS-2M assembly was studied. The analysis results show that TVS-2M fuel assembly can improve the economic efficiency of the plant remarkably. (authors)

  7. PFP issues/assumptions development and management planning guide

    International Nuclear Information System (INIS)

    SINCLAIR, J.C.

    1999-01-01

    The PFP Issues/Assumptions Development and Management Planning Guide presents the strategy and process used for the identification, allocation, and maintenance of an Issues/Assumptions Management List for the Plutonium Finishing Plant (PFP) integrated project baseline. Revisions to this document will include, as attachments, the most recent version of the Issues/Assumptions Management List, both open and current issues/assumptions (Appendix A), and closed or historical issues/assumptions (Appendix B). This document is intended be a Project-owned management tool. As such, this document will periodically require revisions resulting from improvements of the information, processes, and techniques as now described. Revisions that suggest improved processes will only require PFP management approval

  8. Information Systems Management: an Australasian view of key issues - 1996

    Directory of Open Access Journals (Sweden)

    Graham Pervan

    1997-11-01

    Full Text Available As part of a longitudinal study of key information systems management issues, a survey of Australasia's largest 500 organisations was conducted to identify which issues were perceived by the IS executives as being important, problematic and critical over the next three to five years. The most critical issues were revealed to be a mix of technology management issues (IT infrastructure, communications, disaster recovery, strategic management issues (competitive advantage, IS planning, aligning the IS organisation, people management issues (organisational learning, educating senior management in IT, systems development and data management issues (effective use of the data resource, and end-user computing. This reflects the need for a balance of business, technical, and people skills in an IS executive. Non-critical issues were mostly related to systems development and the individual technologies which must be integrated and managed to ensure a responsive IT infrastructure. The study also reveals that some issues are much more important than problematic (disaster recovery, competitive advantage, information architecture, and IS alignment while others are much more problematic than important (end-user computing, IS role and contribution, and BPR. The former reflects a growing level of knowledge in handling these issues, while the latter reflects a continuing problem with them. The differences between this study and similar studies conducted in 1988 and 1992 show that there is a growing confidence in the IS executive's ability to manage the strategic issues, a continuing concern about providing a responsive IT infrastructure (especially communications, and a continuing concern with educating all 'customers' in the organisation in the effective use of IT, including senior management.

  9. Licensing of spent fuel dry storage and consolidated rod storage: A Review of Issues and Experiences

    Energy Technology Data Exchange (ETDEWEB)

    Bailey, W.J.

    1990-02-01

    The results of this study, performed by Pacific Northwest Laboratory (PNL) and sponsored by the US Department of Energy (DOE), respond to the nuclear industry's recommendation that a report be prepared that collects and describes the licensing issues (and their resolutions) that confront a new applicant requesting approval from the US Nuclear Regulatory Commission (NRC) for dry storage of spent fuel or for large-scale storage of consolidated spent fuel rods in pools. The issues are identified in comments, questions, and requests from the NRC during its review of applicants' submittals. Included in the report are discussions of (1) the 18 topical reports on cask and module designs for dry storage fuel that have been submitted to the NRC, (2) the three license applications for dry storage of spent fuel at independent spent fuel storage installations (ISFSIs) that have been submitted to the NRC, and (3) the three applications (one of which was later withdrawn) for large-scale storage of consolidated fuel rods in existing spent fuel storage pools at reactors that were submitted tot he NRC. For each of the applications submitted, examples of some of the issues (and suggestions for their resolutions) are described. The issues and their resolutions are also covered in detail in an example in each of the three subject areas: (1) the application for the CASTOR V/21 dry spent fuel storage cask, (2) the application for the ISFSI for dry storage of spent fuel at Surry, and (3) the application for full-scale wet storage of consolidated spent fuel at Millstone-2. The conclusions in the report include examples of major issues that applicants have encountered. Recommendations for future applicants to follow are listed. 401 refs., 26 tabs.

  10. Producing Liquid Fuels from Coal: Prospects and Policy Issues

    Science.gov (United States)

    2008-01-01

    fraction of the weight of a plant. Most of the material in plants is cellulose , hemicellulose, or lignin . None of these substances is amenable to the...conventional fuel involved in producing the biomass. This is especially the case for non-food-crop biomass, such as corn stover, switchgrass, prairie...conversion of cellulosic materials, starches, or sugars to alcohols. Coal-to-Liquids Technologies 39 Unfortunately, annual variations in weather

  11. Policy and Management Issues in Contemporary Nigerian ...

    African Journals Online (AJOL)

    AFRREV IJAH: An International Journal of Arts and Humanities. Journal Home · ABOUT THIS JOURNAL · Advanced Search · Current Issue · Archives · Journal Home > Vol 2, No 4 (2013) >. Log in or Register to get access to full text downloads.

  12. Concussion Management in Schools: Issues and Implications

    Science.gov (United States)

    Canto, Angela I.; Pierson, Eric E.

    2015-01-01

    The school psychology literature base is lacking in information and resources for working with students with traumatic brain injuries, and concussions specifically. This special issue includes five articles from school psychology based researchers committed to increasing the awareness of the identification, assessment, and intervention for…

  13. Update on Canada's nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Allan, C.J.

    1992-09-01

    The Canadian Nuclear Fuel Waste Management Program (CNFWMP) was launched in 1978 as a joint initiative by the governments of Canada and Ontario. Under the program, AECL has been developing and assessing a generic concept to dispose of nuclear fuel waste in plutonic rock of the Canadian Shield. The disposal concept has been referred for review under the Environmental Assessment and Review Process. AECL will submit an Environmental Impact Statement (EIS) to an Environmental Assessment Panel, which was appointed in late 1989. Hearings will be held in areas that have a particular interest in the concept and its application. At the end of the review, the Panel will make recommendations as to the acceptability of the concept and the course of future action. The federal government will decide on the next steps to be taken. In the spring of 1990 public open houses were held to tell prospective participants how to enter the process. Sessions designed to assist the Panel in determining the scope of the EIS took place in the autumn of 1990. In June 1991 the Panel issued for comment a set of draft guidelines for the EIS. More than 30 groups and individuals submitted comments. The final guidelines were issued in March 1992, and AECL expects to submit its EIS to the Panel in 1993. If the concept review is completed by 1995 and if the concept is approved, disposal could begin some time after 2025. (L.L.) (12 refs.)

  14. Advanced Fuel Cell System Thermal Management for NASA Exploration Missions

    Science.gov (United States)

    Burke, Kenneth A.

    2009-01-01

    The NASA Glenn Research Center is developing advanced passive thermal management technology to reduce the mass and improve the reliability of space fuel cell systems for the NASA exploration program. An analysis of a state-of-the-art fuel cell cooling systems was done to benchmark the portion of a fuel cell system s mass that is dedicated to thermal management. Additional analysis was done to determine the key performance targets of the advanced passive thermal management technology that would substantially reduce fuel cell system mass.

  15. The continual fuel management modification in Qinshan project II

    International Nuclear Information System (INIS)

    Ye Guodong; Pan Zefei; Zhang Xingtian

    2010-01-01

    The fuel management strategy is the basis of the nuclear power plants. The performance of the fuel management strategy affects the plants' safety and economy indicators directly. The paper summarizes all the modifications on the fuel management work in Qinshan Project II since the plant was established. It includes the surveillance system of physics tests, fetching in high performance fuel assemblies, reloading pattern optimization, and the modifications of the final safety analysis report. At the same time, it evaluates the benefit of the modifications in the few years. The experience in this paper is much helpful and could be implemented on the same type plants. (authors)

  16. APPLIED ISSUES ABOUT BANKING RISK MANAGEMENT

    Directory of Open Access Journals (Sweden)

    Elena Geanina Clipici

    2017-09-01

    Full Text Available The following paper emphasizes the need to deepen the understanding of the notion of banking risk management by explaining the significant risks the bank encounters during financial exercises as well as their additional entries. The study of the paper will focus on UniCredit Bank during the years 2014 and  2015 on all types of risks, in which we will provide comprehensive data on how the UniCredit Bank management applies its risk policies.

  17. 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

  18. Environmental survey of the reprocessing and waste management portions of the LWR fuel cycle: a task force report

    International Nuclear Information System (INIS)

    Bishop, W.P.; Miraglia, F.J. Jr.

    1976-10-01

    This Supplement deals with the reprocessing and waste management portions of the nuclear fuel cycle for uranium-fueled reactors. The scope of the report is limited to the illumination of fuel reprocessing and waste management activities, and examination of the environmental impacts caused by these activities on a per-reactor basis. The approach is to select one realistic reprocessing and waste management system and to treat it in enough depth to illuminate the issues involved, the technology available, and the relationships of these to the nuclear fuel cycle in general and its environmental impacts

  19. Environmental survey of the reprocessing and waste management portions of the LWR fuel cycle: a task force report

    Energy Technology Data Exchange (ETDEWEB)

    Bishop, W.P.; Miraglia, F.J. Jr. (eds.)

    1976-10-01

    This Supplement deals with the reprocessing and waste management portions of the nuclear fuel cycle for uranium-fueled reactors. The scope of the report is limited to the illumination of fuel reprocessing and waste management activities, and examination of the environmental impacts caused by these activities on a per-reactor basis. The approach is to select one realistic reprocessing and waste management system and to treat it in enough depth to illuminate the issues involved, the technology available, and the relationships of these to the nuclear fuel cycle in general and its environmental impacts.

  20. Qinshan NPP in-core fuel management improvement

    International Nuclear Information System (INIS)

    Kong Deping; Liao Zejun; Wu Xifeng; Wei Wenbin; Wang Yongming; Li Hua

    2006-01-01

    In the 10-year operation of Qinshan Nuclear Power Plant, the initial designed reloading strategy has been improved step by step based on the operation experiences and the advanced domestic and international fuel management methods. Higher burnup has been achieved and more economic operation gained through the loading pattern improvement and the fuel enrichment increased. The article introduces the in-core fuel management strategy improvement of Qinshan Nuclear Power Plant in its 10-year operation. (authors)

  1. Development of information management system on LWR spent fuel

    International Nuclear Information System (INIS)

    Lee, B. D.; Lee, S. H.; Song, D. Y.; Jeon, I.; Park, S. J.; Seo, D. S.

    2002-01-01

    LWRs in Korea should manage all the information of spent fuel to implement the obligations under Korea-IAEA safeguards agreement and to perform the nuclear material accountancy work at the facility level. The information management system on LWR spent fuel was developed to manage all movement records from receipt to shipment of LWR fuels, and to get the necessary information such as nuclear fuel inventory lists and status, maps of fresh fuel storage, reactor and spent fuel pool, receipt and shipment records and so on. This information management system has a function to setup the system environments to cover the various kinds of storage types for all LWRs ; reactor, spent fuel pool and fresh fuel storage. The movements of nuclear fuel between the storages can be easily done by double click of the mouse to the destination. It also has a several error checking routines for maintaining the correct accounting data. Using this information management system of LWR spent fuel, facility operators can perform efficiently and effectively the safeguards related works including nuclear material accountancy at each facility

  2. PORTABLE PEM FUEL CELL SYSTEM: WATER AND HEAT MANAGEMENT

    Directory of Open Access Journals (Sweden)

    SITI NAJIBAH ABD RAHMAN

    2016-07-01

    Full Text Available Portable polymer electrolyte membrane (PEM fuel cell power generator is a PEM fuel cell application that is used as an external charger to supply the demand for high energy. Different environments at various ambient temperatures and humidity levels affect the performance of PEM fuel cell power generators. Thermal and water management in portable PEM fuel cells are a critical technical barrier for the commercialization of this technology. The size and weight of the portable PEM fuel cells used for thermal and water management systems that determine the performance of portable PEM fuel cells also need to be considered. The main objective of this paper review was to determine the importance of water and thermal management systems in portable PEM fuel cells. Additionally, this review investigated heat transfer and water transport in PEM fuel cells. Given that portable PEM fuel cells with different powers require different thermal and water management systems, this review also discussed and compared management systems for low-, medium-, and high-power portable PEM fuel cells.

  3. Development of information management system on LWR spent fuel

    Energy Technology Data Exchange (ETDEWEB)

    Lee, B. D.; Lee, S. H.; Song, D. Y.; Jeon, I.; Park, S. J.; Seo, D. S. [KAERI, Taejon (Korea, Republic of)

    2002-10-01

    LWRs in Korea should manage all the information of spent fuel to implement the obligations under Korea-IAEA safeguards agreement and to perform the nuclear material accountancy work at the facility level. The information management system on LWR spent fuel was developed to manage all movement records from receipt to shipment of LWR fuels, and to get the necessary information such as nuclear fuel inventory lists and status, maps of fresh fuel storage, reactor and spent fuel pool, receipt and shipment records and so on. This information management system has a function to setup the system environments to cover the various kinds of storage types for all LWRs ; reactor, spent fuel pool and fresh fuel storage. The movements of nuclear fuel between the storages can be easily done by double click of the mouse to the destination. It also has a several error checking routines for maintaining the correct accounting data. Using this information management system of LWR spent fuel, facility operators can perform efficiently and effectively the safeguards related works including nuclear material accountancy at each facility.

  4. Practical constraints on fuel management a utility perspective

    International Nuclear Information System (INIS)

    Grier, C.A.

    1986-01-01

    The practical and potential constraints of performing fuel management at a large utility are reviewed. Based on approximately six years of experience in performing fuel management the constraints due to commercial, technical, utility system, design methods, and personnel and computer resources are discussed in detail

  5. Impact of advanced fuel cycle options on waste management policies

    International Nuclear Information System (INIS)

    Gordelier, Stan; Cavedon, Jean-Marc

    2006-01-01

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

  6. Core management and fuel handling for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

    This Safety Guide supplements and elaborates upon the safety requirements for core management and fuel handling that are presented in Section 5 of the Safety Requirements publication on the operation of nuclear power plants. The present publication supersedes the IAEA Safety Guide on Safety Aspects of Core Management and Fuel Handling, issued in 1985 as Safety Series No. 50-SG-010. It is also related to the Safety Guide on the Operating Organization for Nuclear Power Plants, which identifies fuel management as one of the various functions to be performed by the operating organization. The purpose of this Safety Guide is to provide recommendations for core management and fuel handling at nuclear power plants on the basis of current international good practice. The present Safety Guide addresses those aspects of fuel management activities that are necessary in order to allow optimum reactor core operation without compromising the limits imposed by the design safety considerations relating to the nuclear fuel and the plant as a whole. In this publication, 'core management' refers to those activities that are associated with fuel management in the core and reactivity control, and 'fuel handling' refers to the movement, storage and control of fresh and irradiated fuel. Fuel management comprises both core management and fuel handling. This Safety Guide deals with fuel management for all types of land based stationary thermal neutron power plants. It describes the safety objectives of core management, the tasks that have to be accomplished to meet these objectives and the activities undertaken to perform those tasks. It also deals with the receipt of fresh fuel, storage and handling of fuel and other core components, the loading and unloading of fuel and core components, and the insertion and removal of other reactor materials. In addition, it deals with loading a transport container with irradiated fuel and its preparation for transport off the site. Transport

  7. Core management and fuel handling for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2002-01-01

    This Safety Guide supplements and elaborates upon the safety requirements for core management and fuel handling that are presented in Section 5 of the Safety Requirements publication on the operation of nuclear power plants. The present publication supersedes the IAEA Safety Guide on Safety Aspects of Core Management and Fuel Handling, issued in 1985 as Safety Series No. 50-SG-010. It is also related to the Safety Guide on the Operating Organization for Nuclear Power Plants, which identifies fuel management as one of the various functions to be performed by the operating organization. The purpose of this Safety Guide is to provide recommendations for core management and fuel handling at nuclear power plants on the basis of current international good practice. The present Safety Guide addresses those aspects of fuel management activities that are necessary in order to allow optimum reactor core operation without compromising the limits imposed by the design safety considerations relating to the nuclear fuel and the plant as a whole. In this publication, 'core management' refers to those activities that are associated with fuel management in the core and reactivity control, and 'fuel handling' refers to the movement, storage and control of fresh and irradiated fuel. Fuel management comprises both core management and fuel handling. This Safety Guide deals with fuel management for all types of land based stationary thermal neutron power plants. It describes the safety objectives of core management, the tasks that have to be accomplished to meet these objectives and the activities undertaken to perform those tasks. It also deals with the receipt of fresh fuel, storage and handling of fuel and other core components, the loading and unloading of fuel and core components, and the insertion and removal of other reactor materials. In addition, it deals with loading a transport container with irradiated fuel and its preparation for transport off the site. Transport

  8. SOME ISSUES OF THE AIRPORT MANAGEMENT

    Directory of Open Access Journals (Sweden)

    Marian Ovidiu

    2012-07-01

    Full Text Available Internationally, the recommended standards for the operation and management of civil-use airports are provided by the International Civil Aviation Organization (ICAO. In most individual countries, airports are managed directly by the government, most often under the ministry of transport. In some countries, including EU countries, some airports are privately owned and operated, although, despite private ownership, they are still subject to much of the country’s regulations regarding aviation operations. The complex system of civil airports is made up of individual airport facilities of varying sizes, serving various purposes, all organized into plans of regional, national, and international levels. The range of rules, regulations, and policies, administered from varying levels of government, cover the full spectrum of airport and aviation system operations. Furthermore, a large number of professional and industry organizations play a large part in influencing the policies by which airport management must operate their facilities. By understanding where an airport manager’s airport falls within the civil aviation system, what rules must be followed, and what sources of support and assistance exist, the task of efficiently managing the complex system that is an airport, becomes highly facilitated.

  9. China's spent nuclear fuel management: Current practices and future strategies

    International Nuclear Information System (INIS)

    Zhou Yun

    2011-01-01

    Although China's nuclear power industry is relatively young and the management of its spent nuclear fuel is not yet a concern, China's commitment to nuclear energy and its rapid pace of development require detailed analyses of its future spent fuel management policies. The purpose of this study is to provide an overview of China's fuel cycle program and its reprocessing policy, and to suggest strategies for managing its future fuel cycle program. The study is broken into four sections. The first reviews China's current nuclear fuel cycle program and facilities. The second discusses China's current spent fuel management methods and the storage capability of China's 13 operational nuclear power plants. The third estimates China's total accumulated spent fuel, its required spent fuel storage from present day until 2035, when China expects its first commercialized fast neutron reactors to be operational, and its likely demand for uranium resources. The fourth examines several spent fuel management scenarios for the present period up until 2035; the financial cost and proliferation risk of each scenario is evaluated. The study concludes that China can and should maintain a reprocessing operation to meet its R and D activities before its fast reactor program is further developed. - Highlights: → This study provides an overview of China's fuel cycle program and its reprocessing policy.→ This study suggests strategies for managing its future fuel cycle program.→ China will experience no pressure to lessen the burden of spent fuel storage in the next 30 years.→ China should maintain sufficient reprocessing operations to meet its demands for R and D activities.→ China should actively invest on R and D activities of both fuel cycling and fast reactor programs.

  10. On-site interim storage of spent nuclear fuel: Emerging public issues

    International Nuclear Information System (INIS)

    Feldman, D.L.; Tennessee Univ., Knoxville, TN

    1992-01-01

    Failure to consummate plans for a permanent repository or above- ground interim Monitored Retrievable Storage (MRS) facility for spent nuclear fuel has spurred innovative efforts to ensure at-reactor storage in an environmentally safe and secure manner. This article examines the institutional and socioeconomic impacts of Dry Cask Storage Technology (DCST)-an approach to spent fuel management that is emerging as the preferred method of on-site interim spent fuel storage by utilities that exhaust existing storage capacity

  11. Configuration Management Issues at Research Reactors

    International Nuclear Information System (INIS)

    Morris, Charles R.

    2013-01-01

    Configuration Management (from IAEA TECDOC 1651): • The Main Functions of the configuration management process are to: • maintain design requirements of structures, systems and components; • track current as-built drawings, documents, and design basis library; • confirm design change packages demonstrate compliance to design basis in calculations, procurement, safety reviews, update of affected documents, and SSC data; • confirm work orders demonstrate compliance to mandated preventive maintenance; • surveillance, parts replacement and design change installation requirements; • demonstrate procurement of spare parts qualified to meet design basis for proper make, model and quality-level for the SSC location and form, fit and function

  12. Pediatric Cushing′s disease: Management Issues

    Directory of Open Access Journals (Sweden)

    Martin O Savage

    2012-01-01

    Full Text Available Cushing′s disease (CD, caused by an ACTH-secreting pituitary corticotroph adenoma, is the commonest cause of Cushing syndrome in children over 5 years of age. It is rare in the pediatric age range and presents difficult diagnostic and therapeutic challenges. Key presenting features include weight gain, growth failure and change in facial appearance. Most pediatric endocrinologists have limited experience managing children or adolescents with CD and thus benefit from close consultation with adult colleagues. We describe a diagnostic protocol which broadly follows the model for adult patients. Treatment strategies are examined and appraised. The management of pediatric CD patients after cure is also discussed.

  13. Sustainable Nuclear Fuel Cycles and World Regional Issues

    Directory of Open Access Journals (Sweden)

    Aleksandra Schwenk-Ferrero

    2012-06-01

    Full Text Available In the present paper we have attempted to associate quantified impacts with a forecasted nuclear energy development in different world regions, under a range of hypotheses on the energy demand growth. It gives results in terms of availability of uranium resources, required deployment of fuel cycle facilities and reactor types. In particular, the need to achieve short doubling times with future fast reactors is investigated and quantified in specific world regions. It has been found that a crucial feature of any world scenario study is to provide not only trends for an idealized “homogeneous” description of the global world, but also trends for different regions in the world. These regions may be selected using rather simple criteria (mostly of a geographical type, in order to apply different hypotheses for energy demand growth, fuel cycle strategies and the implementation of various reactor types for the different regions. This approach was an attempt to avoid focusing on selected countries, in particular on those where no new significant energy demand growth is expected, but instead to provide trends and conclusions that account for the features of countries that will be major players in the world energy development in the future.

  14. Forest Management_MCD Issue2 2007

    African Journals Online (AJOL)

    for biodiversity on Earth, and this biodiversity is found mainly in Madagascar's .... Standardized models are appropriate .... this had little effect on its forest management policy until very recently. ... In the mid - 1980s, Madagascar's political climate began to change as ..... A selection correction for cloud cover in satellite images.

  15. Environmental conflicts: Key issues and management implications ...

    African Journals Online (AJOL)

    Environmental crises and problems throughout the world are widespread and increasing rapidly. In relation to these concerns, the article discusses the following aspects: people and the environment, environmental conflicts, climate change and environmental conflicts, and management implications. The section on people ...

  16. Career Management Issues of Female Business Expatriates.

    Science.gov (United States)

    Selmer, Jan; Leung, Alicia S. M.

    2002-01-01

    Responses to a career management survey from 309 male and 79 female business expatriates revealed that, controlling for demographic differences, females could less often meet their career goals with the corporation. They were less likely to regard expatriation as a useful career move. Explanations were derived from relevant research literature.…

  17. In-core fuel management activities in China

    International Nuclear Information System (INIS)

    Ruan Keqiang; Chen Renji; Hu Chuanwen

    1990-01-01

    The development of nuclear power in China has reached such a stage that PWR in-core fuel management becomes an urgent problem. At present the main effort is concentrated on solving the Qinshan nuclear power plant and Daya Bay nuclear power plant fuel management problems. For the Qinshan PWR (300 MWe) two packages of in-core fuel management code were developed, one with simplified nodal diffusion method and the other uses advanced Green's function nodal method. Both were used in the PWR core design. With the help of the two code packages first two cycles of the Qinshan PWR core burn-up were calculated. Besides, several research works are under way in the following areas: improvement of the nodal diffusion method and other coarse mesh method in terms of computing speed and accuracy; backward diffusion technique for fuel management application; optimization technique in the fuel loading pattern searching. As for the Daya Bay PWR plant (twin 900 MWe unit), the problem about using what kind of code package for in-core fuel management is still under discussion. In principle the above mentioned code packages are also applicable to it. Besides PWR, in-core fuel management research works are also under way for research reactors, for example, heavy water research reactor and high flux research reactor in some institutes in China. China also takes active participation in international in-core fuel management activities. (author). 19 refs

  18. Development of advanced mixed oxide fuels for plutonium management

    International Nuclear Information System (INIS)

    Eaton, S.; Beard, C.; Buksa, J.; Butt, D.; Chidester, K.; Havrilla, G.; Ramsey, K.

    1997-06-01

    A number of advanced Mixed Oxide (MOX) fuel forms are currently being investigated at Los Alamos National Laboratory that have the potential to be effective plutonium management tools. Evolutionary Mixed Oxide (EMOX) fuel is a slight perturbation on standard MOX fuel, but achieves greater plutonium destruction rates by employing a fractional nonfertile component. A pure nonfertile fuel is also being studied. Initial calculations show that the fuel can be utilized in existing light water reactors and tailored to address different plutonium management goals (i.e., stabilization or reduction of plutonium inventories residing in spent nuclear fuel). In parallel, experiments are being performed to determine the feasibility of fabrication of such fuels. Initial EMOX pellets have successfully been fabricated using weapons-grade plutonium

  19. Development of advanced mixed oxide fuels for plutonium management

    International Nuclear Information System (INIS)

    Eaton, S.; Beard, C.; Buksa, J.; Butt, D.; Chidester, K.; Havrilla, G.; Ramsey, K.

    1997-01-01

    A number of advanced Mixed Oxide (MOX) fuel forms are currently being investigated at Los Alamos National Laboratory that have the potential to be effective plutonium management tools. Evolutionary Mixed Oxide (EMOX) fuel is a slight perturbation on standard MOX fuel, but achieves greater plutonium destruction rates by employing a fractional nonfertile component. A pure nonfertile fuel is also being studied. Initial calculations show that the fuel can be utilized in existing light water reactors and tailored to address different plutonium management goals (i.e., stabilization or reduction of plutonium inventories residing in spent nuclear fuel). In parallel, experiments are being performed to determine the feasibility of fabrication of such fuels. Initial EMOX pellets have successfully been fabricated using weapons-grade plutonium. (author)

  20. Advanced nuclear fuel cycles and radioactive waste management

    International Nuclear Information System (INIS)

    2006-01-01

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

  1. Social science to improve fuels management: a synthesis of research relevant to communicating with homeowners about fuels management

    Science.gov (United States)

    Martha C. Monroe; Lisa Pennisi; Sarah McCaffrey; Dennis Mileti

    2006-01-01

    A series of syntheses were commissioned by the USDA Forest Service to aid in fuels mitigation project planning. This synthesis focuses on how managers can most effectively communicate with the public about fuels management efforts. It summarizes what is known about the techniques of persuasive communication programs and provides an outline of the characteristics of...

  2. Fuels planning: science synthesis and integration; social issues fact sheet 05: The importance of working locally

    Science.gov (United States)

    Rocky Mountain Research Station USDA Forest Service

    2004-01-01

    People who evaluate their actions in terms of what others think are often said to be guided by community norms. With respect to fuels management, this means that when you are "selling" a property owner on taking steps to reduce fuels, you are not just "selling" to one person, but to a network of people. This fact sheet discusses three tools to help...

  3. Fuel reprocessing and waste management in the UK

    International Nuclear Information System (INIS)

    Heafield, W.; Griffin, N.L.

    1994-01-01

    The currently preferred route for the management of irradiated fuel in the UK is reprocessing. This paper, therefore, concentrates on outlining the policies, practices and achievement of British Nuclear Fuels plc (BNFL) associated with the management of its irradiated fuel facilities at Sellafield. The paper covers reprocessing and how the safe management of each of the major waste categories is achieved. BNFL's overall waste management policy is to develop, in close consultation with the regulatory authorities, a strategy to minimize effluent discharges and provide a safe, cost effective method of treating and preparing for disposal all wastes arising on the site

  4. Canada's imminent decision on nuclear fuel management: decision making at the intersection of science, politics, and society

    Energy Technology Data Exchange (ETDEWEB)

    Isaacs, T. [Lawrence Livermore National Laboratory, Livermore, California (United States)

    2005-07-01

    This paper outlines the science, politics and the decision making process in implementing a nuclear fuel management program. It discusses the issues in the light of Canada's imminent decision on nuclear fuel management. The paper discusses the technical as well as the institutional challenge in nuclear waste management. It discusses some of the key elements of the Canadian approach and concludes with some key recommendation in the way forward.

  5. Critical management system for nuclear fuels

    International Nuclear Information System (INIS)

    Tai, Ichiro; Seki, Eiji.

    1981-01-01

    Purpose: To enable to provide display for the scale of accidents and critical state by detecting gamma-rays issued from nuclear fuels by gamma-ray level indicators to obtain outputs in proportion to the input level of the gamma-rays based on the detected pulse signals. Constitution: The gamma-ray level indicators comprises a plastic scintillator that emits light upon input of gamma-rays and a photomultiplier that amplifies weak fluorescence obtained from the scintillator. The photomultiplier is applied with a high voltage from a power source. A pre-amplifier amplifies pulse signals corresponding to individual gamma-rays at a high amplification factor and send them to a pulse counter circuit if the detected signal level from the gamma-ray level indicators is low, or amplifies the pulse detection signals at a low amplification factor and sends them to a voltage pulse averaging circuit if the detection signal level is high. A signal procession circuit selects the output from the pulse counter circuit or the voltage pulse averaging circuit. Thus, the system has a linear characteristic over a wide range equivalent to a wide range of incident gamma-rays. (Horiuchi, T.)

  6. Trends and Issues in California's Low Carbon Fuel Standard - Learning from Response to Existing Climate Policy

    Science.gov (United States)

    Witcover, J.

    2015-12-01

    Debate over lower greenhouse gas (GHG) emissions from transportation has included heated discussion about appropriate policies and their cost and feasibility. One prominent policy mechanism, a carbon intensity standard, rates transport fuels based on analysis of lifecycle GHG emissions, and targets lower fuel pool carbon intensity through a market mechanism that uses a system of tradable, bankable credits and deficits. California instituted such a policy -- the Low Carbon Fuel Standard (LCFS) - in 2010, which targets a 10% carbon intensity (CI) reduction by 2020. The program rolled out amid concerns over slow development of new fuels expected to be very low carbon (such as cellulosic) and has faced court challenges that added considerable policy uncertainty. Since the program's start, state transport energy mix has shifted modestly but noticeably. Looking ahead, emerging issues for the program include amendments and re-adoption in response to a court ruling, potential interaction with California's multi-sector cap on carbon emissions (which started covering transport fuels in 2015), and impacts from similar CI standards in other jurisdictions. This study provides an analysis of fuel mix changes since the LCFS was implemented in 2011, and a discussion of emerging issues focusing on policy interaction. Descriptive statistics on alternative fuel use, available fuel pathways, and CI ratings are presented based on data from the California Air Resources Board (which runs the program). They document a shift towards more alternative fuels in a more diverse mix, with lower average CI ratings for most alternative fuel types. Financial incentives for various fuels are compared under the LCFS and the US federal Renewable Fuel Standard; disincentives from conceptually different carbon pricing schemes under the LCFS and the Cap-and-Trade are also outlined. The results provide important information on response to an existing market-based policy mechanism for addressing GHG

  7. Architectural mismatch issues in identity management deployment

    DEFF Research Database (Denmark)

    Andersen, Mads Schaarup

    2010-01-01

    Integrating Commercial Off-The-Shelf products in a company's software product portfolio offers business value, but introduces challenges from a software architecture perspective. In this paper, the research challenges in relation to identity management in the Danish municipality administration...... system called Opus, are outlined. Opus BRS is the identity management part of Opus. Opus integrates SAP, legacy mainframe systems, and other third party systems of the individual municipality. Each of these systems define their own software architecture and access control model, leading to architectural...... mismatch with an impact on security, usability, and maintainability. The research project is discussed and access control and identity provisioning are recognized as the major areas of interest in relation to the mismatch challenges. The project is carried out in close cooperation with KMD, one...

  8. Prudency reviews, cash management issues emerge

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    Utility management is paying increasing attention to the broadening of regulatory commission prudency reviews to cover operating generating plants as well as those under construction. Utilities can expect a prudency review after a major outage, and should investigate the possibility for legal action against a third party or be prepared to defend itself. The Shoreham nuclear plant serves as a warning to utilities of the need for on-going documentation of cost-benefit analyses conducted during the construction period. Utility managers should demand a prudency standard from their regulators, and minority owners in large projects should make independent prudency findings. There is also a growing need for utilities to develop intelligent strategies for handling excess cash. Methods for handling cash flow include the financial investment, grid refurbishment, dividend payout, decapitalization, and diversification

  9. Quality management issues in nondestructive inspection

    International Nuclear Information System (INIS)

    Li Shuliang

    2008-01-01

    Considering the practical problems in NDT in scientific research and production, this paper put forward the concept to take the functional authorities and related research divisions as customers, and provides the operable way for the management and control of the control points, and for the control and check in the manufacture check-up, in the scientific research. This paper also proposes more strict requirements on NDT for the disposal of nonconformity product, in order to further improve the technology of NDT. (author)

  10. Contemporary management issues confronting fisheries science

    Science.gov (United States)

    Frank, Kenneth T.; Brickman, David

    2001-06-01

    Stock collapses have occurred worldwide. The most frequently cited cause is over-fishing, suggesting that fisheries management has been ineffective in controlling exploitation rates. The progression of a fishery from an over-exploited to a collapsed state involves impairment of the reproductive capacity of the target species, i.e. recruitment over-fishing. In many cases, this occurs by reduction of the spawning stock biomass (SSB) through the systematic elimination of spawning components within a stock complex. While operational definitions of minimum levels of SSB have been developed, they have seldom been applied and never adopted in a Canadian groundfish management context. The answer to the question of how much is enough to perpetuate a stock under exploitation has been illusive. Serebryakov [J. Cons. Int. Explor. Mer, 47 (1990) 267] has advocated definition of critical levels of SSB based on survival rates (R/SSB). We review his method and discuss the utility of the approach. An alternative approach to the problem of estimating minimum SSB is through a fundamental revision of the traditional stock and recruitment relationship. Explicit theoretical SSB thresholds below which reproduction/recruitment is severely impaired based upon density-dependent mating success (or Allee effects) is considered a superior approach to the question of how much is enough because of its ecological grounding. However, the successful application of this approach will require re-definition of the space/time scales of the management unit. Finally, support is growing for the establishment of closed areas or "no-take zones" as an alternative approach to managing the problems of fishing a stock complex by enabling sub-populations to escape fishing. While the expected benefits of areas protected from fishing are numerous, clear demonstrations of benefits of such areas in marine temperate ecosystems are lacking. In fact, unintended negative consequences may result from such actions.

  11. Nuclear power, nuclear fuel cycle and waste management, 1980-1993

    International Nuclear Information System (INIS)

    1994-06-01

    This document lists all sales publications of the International Atomic Energy Agency dealing with Nuclear Power, Nuclear Fuel Cycle and Waste Management, issued during the period 1980-1993. It gives a short abstract of these publications along with contents and their costs in Austrian Schillings

  12. Nuclear power. Nuclear fuel cycle and waste management. 1990-2002. International Atomic Energy Agency publications

    International Nuclear Information System (INIS)

    2002-02-01

    This document lists all sales publications of the International Atomic Energy Agency dealing with Nuclear Power, Nuclear Fuel Cycle and Waste Management, issued during the period 1990-2002. It gives a short abstract of these publications along with contents and their costs

  13. History and update of the U.S. program for the management of used nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Isaacs, T. [US Blue Ribbon Commission, Washington, DC (United States)

    2015-07-01

    This paper discusses the history and gives an update of the US program for the management of used nuclear fuel. The key issue in the deliberation was the option of long-term monitored storage versus disposal capability. The decision was to give future generations the option of disposal.

  14. Safety issues in cultural heritage management and critical infrastructures management

    Science.gov (United States)

    Soldovieri, Francesco; Masini, Nicola; Alvarez de Buergo, Monica; Dumoulin, Jean

    2013-12-01

    This special issue is the fourth of its kind in Journal of Geophysics and Engineering , containing studies and applications of geophysical methodologies and sensing technologies for the knowledge, conservation and security of products of human activity ranging from civil infrastructures to built and cultural heritage. The first discussed the application of novel instrumentation, surface and airborne remote sensing techniques, as well as data processing oriented to both detection and characterization of archaeological buried remains and conservation of cultural heritage (Eppelbaum et al 2010). The second stressed the importance of an integrated and multiscale approach for the study and conservation of architectural, archaeological and artistic heritage, from SAR to GPR to imaging based diagnostic techniques (Masini and Soldovieri 2011). The third enlarged the field of analysis to civil engineering structures and infrastructures, providing an overview of the effectiveness and the limitations of single diagnostic techniques, which can be overcome through the integration of different methods and technologies and/or the use of robust and novel data processing techniques (Masini et al 2012). As a whole, the special issue put in evidence the factors that affect the choice of diagnostic strategy, such as the material, the spatial characteristics of the objects or sites, the value of the objects to be investigated (cultural or not), the aim of the investigation (knowledge, conservation, restoration) and the issues to be addressed (monitoring, decay assessment). In order to complete the overview of the application fields of sensing technologies this issue has been dedicated to monitoring of cultural heritage and critical infrastructures to address safety and security issues. Particular attention has been paid to the data processing methods of different sensing techniques, from infrared thermography through GPR to SAR. Cascini et al (2013) present the effectiveness of a

  15. Spent fuel management: Current status and prospects 1995. Proceedings of a regular advisory group meeting

    International Nuclear Information System (INIS)

    1996-08-01

    Spent fuel management has always been one of the important stages in the nuclear fuel cycle and it is still one of the most vital problems common to all countries with nuclear reactors. It begins with the discharge of spent fuel from a power or a research reactor and ends with its ultimate disposition, either by direct disposal or by reprocessing of the spent fuel. Two options exist - an open, once-through cycle with direct disposal of the spent fuel and a closed cycle with reprocessing of the spent fuel and recycling of plutonium and uranium in new mixed oxide fuels. The selection of a spent fuel strategy is a complex procedure in which many factors have to be weighed, including political, economic and safeguards issues as well as protection of the environment. This report gives an overview of the status of spent fuel management programmes in a number of countries, a description of the current status and prospects of activities in this field and recommendations of the participants. Refs, figs, tabs

  16. Present status and environmental implications of the different fuel cycles. Key issue paper no. 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    For decades plutonium has been a key focus of international discussions of both non-proliferation and the future of the nuclear fuel cycle. This paper is intended to address the management of separated plutonium in the civil fuel cycle in the near term - until 2015 - describing both the technologies employed and the policies of key countries. This paper also addresses technology and policy for the management of weapons plutonium being declared excess to defence needs. Refs, figs, tabs.

  17. Management issues with exogenous steroid therapy

    Directory of Open Access Journals (Sweden)

    Hiren Patt

    2013-01-01

    Full Text Available Glucocorticoids (GCs are extensively used for various inflammatory and autoimmune disorders, but long term use of these agents is not without complications. Almost every GC formulations (e.g. oral, topical, inhaled, etc. can cause systemic side effects. It can range from minor side effects (e.g. weight gain to life-threatening effects (e.g. adrenal suppression, sepsis, etc., which may require immediate intervention. Therefore, the decision to institute steroid therapy always requires careful consideration of the relative risk and benefit in each patient. The objectives of this study are to discuss monitoring of patients on GCs and management of the complications of GCs.

  18. Managing the Organizational Culture: A Technological Issue

    Directory of Open Access Journals (Sweden)

    Takhir U. Bazarov

    2011-01-01

    Full Text Available Organizational culture presents an interest for research and practice of social psychology. This article is intended to discuss the problem of managing the organizational structure on two levels that contain most topical problems: general methodological level and technological level. Organizational culture is a system with its distinct features that consists of units and sub-systems with their specific features. An organizational-culture system comprises several levels: leader's personality level (as well as the personality level in general, level of executive team (as well as of a small group in general, level of organization in general (level of a large group.

  19. Management issues with exogenous steroid therapy

    Science.gov (United States)

    Patt, Hiren; Bandgar, Tushar; Lila, Anurag; Shah, Nalini

    2013-01-01

    Glucocorticoids (GCs) are extensively used for various inflammatory and autoimmune disorders, but long term use of these agents is not without complications. Almost every GC formulations (e.g. oral, topical, inhaled, etc.) can cause systemic side effects. It can range from minor side effects (e.g. weight gain) to life-threatening effects (e.g. adrenal suppression, sepsis, etc.), which may require immediate intervention. Therefore, the decision to institute steroid therapy always requires careful consideration of the relative risk and benefit in each patient. The objectives of this study are to discuss monitoring of patients on GCs and management of the complications of GCs. PMID:24910822

  20. Management functions, issues, and configuration alternatives: TO support a transportation management configuration study: [Final report

    International Nuclear Information System (INIS)

    1987-01-01

    The Office of Civilian Radioactive Waste Management (OCRWM) of the Department of Energy (DOE) is responsible for the safe transporation and disposal of spent nuclear fuel from utility-owned nuclear power generation reactors and high-level radioactive waste from both defense and civilian generators to long-term storage repositories. Given the volume, duration, and sensitivity of the operation, DOE is seeking not only the safest and best transportation system but also the most effective and resource-efficient management concept. Within the general guidelines of the Nuclear Waste Policy Act (NWPA) of 1982 calling for the fullest possible use of private industry contracts, this study examines the technical and administrative functions as well as the key issues to be addressed in the formation of a management structure. In order to stand alone as a comprehensive treatment of the total requirement, the material contained in many seperate and sometimes divergent DOE/OCRWM documents was evaluated and is compiled here. An attempt was made to succinctly define the nature of the problem, the objectives and scope of both the operating and management systems, and then to dissect the functions required in order to meet the objectives and operating functions are listed and described

  1. STRATEGIC ISSUES GROUNDWATER EXTRACTION MANAGEMENT IN RUSSIA

    Directory of Open Access Journals (Sweden)

    Ekaterina I. Golovina

    2017-05-01

    Full Text Available Water is a key component of our environment; it is a renewable, limited and vulnerable natural resource, which provides economic, social, and environmental well-being of the population. The most promising source of drinking water supply is groundwater usage. Drinking and industrial groundwater is one of the most important components of the groundwater mineral resource base in the Russian Federation. Modern system of groundwater extraction management and state regulation is currently imperfect and has definite disadvantages, among them - lack of control over natural resources by the state, an old system of tax rates for the use of groundwater, commercialization stage of licensing, the budget deficit, which is passed on other spheres of the national economy. This article provides general information about the state of groundwater production and supply in Russia, negative trends of groundwater usage, some actions for the improvement in the system of groundwater’s fund management are suggested. The most important amendments of the law “About mineral resources” are overviewed, effects of these changes are revealed and recommendations for future groundwater extraction regulation are given.

  2. Gender Issues in the Management of Infertility in Developing Countries

    African Journals Online (AJOL)

    Gender Issues in the Management of Infertility in Developing Countries. Editorial. Infertility ... heritage has become morbidly adherent in the mind of even the highly ... the respondents preferred male to female children, and this was attributed to ...

  3. Cost analysis of spent nuclear fuel management

    International Nuclear Information System (INIS)

    Robertson, D.L.M.; Ford, L.M.

    1993-01-01

    The Department of Energy Civilian Radioactive Waste Management System (CRWMS) is chartered to develop a waste management system for the safe disposal of spent nuclear fuel (SNF) from the 131 nuclear power reactors in the United States and a certain amount of high level waste (HLW) from reprocessing operations. The current schedule is to begin accepting SNF in 1998 for storage at a Monitored Retrievable Storage (MRS) facility. Subsequently, beginning in 2010, the system is scheduled to begin accepting SNF at a permanent geologic repository in 2010 and HLW in 2015. At this time, a MRS site has not been selected. Yucca Mountain, Nevada is currently being evaluated as the candidate site for the repository for permanent geologic disposal of SNF. All SNF, with the possible exception of the SNF from the western reactors, is currently planned to be shipped to or through the MRS site en route to the repository. The repository will operate in an acceptance and performance confirmation phase for a 50 year period beginning in 2010 with an additional nine year closure and five year decontamination and decommissioning period. The MRS has a statutory maximum capacity of 15,000 Metric Tons Uranium (MTU), with a further restriction that it may not store more than 10,000 MTU until the repository begins accepting waste. The repository is currently scheduled to store 63,000 MTU of SNF and an additional 7,000 MTU equivalent of HLW for a total capacity of 70,000 MTU. The amended act specified the MRS storage limits and identified Yucca Mountain as the only site to be characterized. Also, an Office of the Nuclear Waste Negotiator was established to secure a voluntary host site for the MRS. The MRS, the repository, and all waste containers/casks will go through a Nuclear Regulatory Commission licensing process much like the licensing process for a nuclear power plant. Environmental assessments and impact statements will be prepared for both the MRS and repository

  4. Development of Advanced Spent Fuel Management Process

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Chung Seok; Choi, I. K.; Kwon, S. G. (and others)

    2007-06-15

    As a part of research efforts to develop an advanced spent fuel management process, this project focused on the electrochemical reduction technology which can replace the original Li reduction technology of ANL, and we have successfully built a 20 kgHM/batch scale demonstration system. The performance tests of the system in the ACPF hot cell showed more than a 99% reduction yield of SIMFUEL, a current density of 100 mA/cm{sup 2} and a current efficiency of 80%. For an optimization of the process, the prevention of a voltage drop in an integrated cathode, a minimization of the anodic effect and an improvement of the hot cell operability by a modulation and simplization of the unit apparatuses were achieved. Basic research using a bench-scale system was also carried out by focusing on a measurement of the electrochemical reduction rate of the surrogates, an elucidation of the reaction mechanism, collecting data on the partition coefficients of the major nuclides, quantitative measurement of mass transfer rates and diffusion coefficients of oxygen and metal ions in molten salts. When compared to the PYROX process of INL, the electrochemical reduction system developed in this project has comparative advantages in its application of a flexible reaction mechanism, relatively short reaction times and increased process yields.

  5. Development of Advanced Spent Fuel Management Process

    International Nuclear Information System (INIS)

    Seo, Chung Seok; Choi, I. K.; Kwon, S. G.

    2007-06-01

    As a part of research efforts to develop an advanced spent fuel management process, this project focused on the electrochemical reduction technology which can replace the original Li reduction technology of ANL, and we have successfully built a 20 kgHM/batch scale demonstration system. The performance tests of the system in the ACPF hot cell showed more than a 99% reduction yield of SIMFUEL, a current density of 100 mA/cm 2 and a current efficiency of 80%. For an optimization of the process, the prevention of a voltage drop in an integrated cathode, a minimization of the anodic effect and an improvement of the hot cell operability by a modulation and simplization of the unit apparatuses were achieved. Basic research using a bench-scale system was also carried out by focusing on a measurement of the electrochemical reduction rate of the surrogates, an elucidation of the reaction mechanism, collecting data on the partition coefficients of the major nuclides, quantitative measurement of mass transfer rates and diffusion coefficients of oxygen and metal ions in molten salts. When compared to the PYROX process of INL, the electrochemical reduction system developed in this project has comparative advantages in its application of a flexible reaction mechanism, relatively short reaction times and increased process yields

  6. Criticality issues with highly enriched fuels in a repository environment

    International Nuclear Information System (INIS)

    Taylor, L.L.; Sanchez, L.C.; Rath, J.S.

    1998-03-01

    This paper presents preliminary analysis of a volcanic tuff repository containing a combination of low enrichment commercial spent nuclear fuels (SNF) and DOE-owned SNF packages. These SNFs were analyzed with respect to their criticality risks. Disposal of SNF packages containing significant fissile mass within a geologic repository must comply with current regulations relative to criticality safety during transportation and handling within operational facilities. However, once the repository is closed, the double contingency credits for criticality safety are subject to unremediable degradation, (e.g., water intrusion, continued presence of neutron absorbers in proximity to fissile material, and fissile material reconfiguration). The work presented in this paper focused on two attributes of criticality in a volcanic tuff repository for near-field and far-field scenarios: (1) scenario conditions necessary to have a criticality, and (2) consequences of a nuclear excursion that are components of risk. All criticality consequences are dependent upon eventual water intrusion into the repository and subsequent breach of the disposal package. Key criticality parameters necessary for a critical assembly are: (1) adequate thermal fissile mass, (2) adequate concentration of fissile material, (3) separation of neutron poison from fissile materials, and (4) sufficient neutron moderation (expressed in units of moderator to fissile atom ratios). Key results from this study indicated that the total energies released during a single excursion are minimal (comparable to those released in previous solution accidents), and the maximum frequency of occurrence is bounded by the saturation and temperature recycle times, thus resulting in small criticality risks

  7. Management of endometrial cancer: issues and controversies.

    Science.gov (United States)

    Bogani, G; Dowdy, S C; Cliby, W A; Ghezzi, F; Rossetti, D; Frigerio, L; Mariani, A

    2016-01-01

    Although endometrial cancer (EC) is the most common gynecologic cancer in developed countries, several aspects of its management are still controversial. In particular, the need to perform lymphadenectomy represents an important matter of discussion. Because of the discordant results in the literature, it is still not possible to draft any definitive conclusions regarding the therapeutic value of lymph node dissection. The present review discusses the role of lymphadenectomy in the setting of EC, risk factors for lymphatic spread, identification of patients at risk for lymph node dissemination, and the current evidence for adjuvant therapies in patients with positive nodes. Reasons for the difficulty in demonstrating any therapeutic value of pelvic and para-aortic lymphadenectomy are also discussed.

  8. An integrative framework for managing project issues across stakeholder groups

    NARCIS (Netherlands)

    van Offenbeek, Marjolein A.G.; Vos, Janita F.J.

    2016-01-01

    The stakeholders and the issues associated with a project are different concepts but closely interconnected. Despite this, the project stakeholder management literature falls short in analyzing the linkages between the stakeholders and the issues they bring. This paper develops a multilayered

  9. Management of super-grade plutonium in spent nuclear fuel

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  10. Safety aspects in fuel reprocessing and radioactive waste management

    International Nuclear Information System (INIS)

    Agarwal, K.

    2018-01-01

    Nuclear energy is used for generation of electricity and for production of a wide range of radionuclides for use in research and development, healthcare and industry. Nuclear industry uses nuclear fission as source of energy so a large amount of energy is available from very small amount of fuel. As India has adopted c losed fuel cycle , spent nuclear fuel from nuclear reactor is considered as a material of resource and reprocessed to recovery valuable fuel elements. Main incentive of reprocessing is to use the uranium resources effectively by recovering/recycling Pu and U present in the spent fuel. This finally leads to a very small percentage of residual material present in spent nuclear fuel requiring their management as radioactive waste. Another special feature of the Indian Atomic Energy Program is the attention paid from the very beginning to the safe management of radioactive waste

  11. Spent fuel management fee methodology and computer code user's manual

    International Nuclear Information System (INIS)

    Engel, R.L.; White, M.K.

    1982-01-01

    The methodology and computer model described here were developed to analyze the cash flows for the federal government taking title to and managing spent nuclear fuel. The methodology has been used by the US Department of Energy (DOE) to estimate the spent fuel disposal fee that will provide full cost recovery. Although the methodology was designed to analyze interim storage followed by spent fuel disposal, it could be used to calculate a fee for reprocessing spent fuel and disposing of the waste. The methodology consists of two phases. The first phase estimates government expenditures for spent fuel management. The second phase determines the fees that will result in revenues such that the government attains full cost recovery assuming various revenue collection philosophies. These two phases are discussed in detail in subsequent sections of this report. Each of the two phases constitute a computer module, called SPADE (SPent fuel Analysis and Disposal Economics) and FEAN (FEe ANalysis), respectively

  12. Application of fuel management calculation codes for CANDU reactor

    International Nuclear Information System (INIS)

    Ju Haitao; Wu Hongchun

    2003-01-01

    Qinshan Phase III Nuclear Power Plant adopts CANDU-6 reactors. It is the first time for China to introduce this heavy water pressure tube reactor. In order to meet the demands of the fuel management calculation, DRAGON/DONJON code is developed in this paper. Some initial fuel management calculations about CANDU-6 reactor of Qinshan Phase III are carried out using DRAGON/DONJON code. The results indicate that DRAGON/DONJON can be used for the fuel management calculation for Qinshan Phase III

  13. Fuels planning: science synthesis and integration; social issues fact sheet 17: Considering social acceptability of fuels treatments

    Science.gov (United States)

    Christine Esposito

    2006-01-01

    When making decisions about fuels treatments, forest managers need to assess not only the biological impacts of a treatment, but the social impacts as well. Social acceptability is based on value judgments by people-their notions of what is "good" and what is "better." This fact sheet discusses six questions that may be useful for framing initial...

  14. Vision and framework for technical and management support to facilitate foreign spent fuel storage and geologic disposal in Russia

    International Nuclear Information System (INIS)

    Halsey, W.G.; Jardine, L.J.; Smith, C.F.

    1999-01-01

    This 'Technical and Management Support' program would facilitate the transfer of spent fuel from commercial power plants in Taiwan to a storage and geologic repository site near Krasnoyarsk, Russia. This program resolves issues of disposition of Taiwan spent fuel (including US origin fuel) and provides revenue for Russia to develop an integrated spent fuel storage and radioactive waste management system including a geologic repository. LLNL has ongoing contracts and collaborations with all the principal parties and is uniquely positioned to facilitate the development of such a program. A three-phase approach over 20 years is proposed: namely, an initial feasibility investigation followed by an engineering development phase, and then implementation

  15. The nuclear fuel cycle: Issues and challenges. Introductory statement to the Scientific Forum. 21 September 2004, Vienna, Austria

    International Nuclear Information System (INIS)

    ElBaradei, M.

    2004-01-01

    The Director General remarked that in planning this year's Forum, three emerging trends were considered: first, the increasing recognition of the role of energy in sustainable development, and the rise in global electricity demand; second, the steadily growing awareness of the contribution that nuclear power is making to greenhouse gas mitigation strategies in some countries; and third, the increasing reliance placed on peaceful nuclear applications in the medical, agricultural and industrial sectors in which research reactors play a vital role.The resulting Forum agenda is focused on a number of particular aspects of the nuclear fuel cycle: advanced fuel cycle and reactor concepts; waste and spent fuel management issues; and topics related to the research reactor fuel cycle. Advanced Fuel Cycle and Reactor Concepts Civilian nuclear power now has more than half a century of experience more than 11 000 reactor-years. For a large segment of the first generation of power reactors, we are reaching the stage where choices must be made between retiring these facilities or extending their licensed lifetimes. At the same time, new advanced and innovative fuel cycles and reactor designs are being explored not only to replace the plants being retired, but also to support the expansion of nuclear power in response to growing global energy needs. Advanced fuel cycles, both 'once-through and 'closed', are being developed with a number of technical objectives, including: more efficient utilization of fissile and fertile materials; enhanced proliferation resistance through, inter alia, passive control of nuclear materials using new fuel types and configurations; greater reliance on passive safety features; and technology advances to mitigate the volume and radio-toxicity of high level and long lived wastes. These technical innovations will need to be complemented by new approaches to relevant policy and institutional issues for example, through increased harmonization of

  16. Acceptance of spent nuclear fuel in multiple element sealed canisters by the Federal Waste Management System

    International Nuclear Information System (INIS)

    1990-03-01

    This report is one of a series of eight prepared by E.R. Johnson Associates, Inc. (JAI) under ORNL's contract with DOE's OCRWM Systems Integration Program and in support of the Annual Capacity Report (ACR) Issue Resolution Process. The report topics relate specifically to the list of high priority technical waste acceptance issues developed jointly by DOE and a utility-working group. JAI performed various analyses and studies on each topic to serve as starting points for further discussion and analysis leading eventually to finalizing the process by which DOE will accept spent fuel and waste into its waste management system. The eight reports are concerned with the conditions under which spent fuel and high level waste will be accepted in the following categories: (1) failed fuel; (2) consolidated fuel and associated structural parts; (3) non-fuel-assembly hardware; (4) fuel in metal storage casks; (5) fuel in multi-element sealed canisters; (6) inspection and testing requirements for wastes; (7) canister criteria; (8) spent fuel selection for delivery; and (9) defense and commercial high-level waste packages. 14 refs., 27 figs

  17. Acceptance of non-fuel assembly hardware by the Federal Waste Management System

    International Nuclear Information System (INIS)

    1990-03-01

    This report is one of a series of eight prepared by E. R. Johnson Associates, Inc. (JAI) under ORNL's contract with DOE's OCRWM Systems Integration Program and in support of the Annual Capacity Report (ACR) Issue Resolution Process. The report topics relate specifically to the list of high-priority technical waste acceptance issues developed jointly by DOE and a utility-working group. JAI performed various analyses and studies on each topic to serve as starting points for further discussion and analysis leading eventually to finalizing the process by which DOE will accept spent fuel and waste into its waste management system. The eight reports are concerned with the conditions under which spent fuel and high-level waste will be accepted in the following categories: failed fuel; consolidated fuel and associated structural parts; non-fuel-assembly hardware; fuel in metal storage casks; fuel in multi-element sealed canisters; inspection and testing requirements for wastes; canister criteria; spent fuel selection for delivery; and defense and commercial high-level waste packages. 14 refs., 12 figs., 43 tabs

  18. Major design issues of molten carbonate fuel cell power generation unit

    Energy Technology Data Exchange (ETDEWEB)

    Chen, T.P.

    1996-04-01

    In addition to the stack, a fuel cell power generation unit requires fuel desulfurization and reforming, fuel and oxidant preheating, process heat removal, waste heat recovery, steam generation, oxidant supply, power conditioning, water supply and treatment, purge gas supply, instrument air supply, and system control. These support facilities add considerable cost and system complexity. Bechtel, as a system integrator of M-C Power`s molten carbonate fuel cell development team, has spent substantial effort to simplify and minimize these supporting facilities to meet cost and reliability goals for commercialization. Similiar to other fuels cells, MCFC faces design challenge of how to comply with codes and standards, achieve high efficiency and part load performance, and meanwhile minimize utility requirements, weight, plot area, and cost. However, MCFC has several unique design issues due to its high operating temperature, use of molten electrolyte, and the requirement of CO2 recycle.

  19. A cost-benefit analysis of spent fuel management

    International Nuclear Information System (INIS)

    Lamorlette, G.

    2001-01-01

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

  20. Modular approach to LWR in-core fuel management

    International Nuclear Information System (INIS)

    Urli, N.; Pevec, D.; Coffou, E.; Petrovic, B.

    1980-01-01

    The most important methods in the LWR in-core fuel management are reviewed. A modular approach and optimization by use of infinite multiplication factor and power form-factor are favoured. A computer program for rotation of fuel assemblies at reloads has been developed which improves further fuel economy and reliability of nuclear power plants. The program has been tested on the PWR core and showed to decrease the power form-factors and flatten the radial power distribution. (author)

  1. The verification of PWR-fuel code for PWR in-core fuel management

    International Nuclear Information System (INIS)

    Surian Pinem; Tagor M Sembiring; Tukiran

    2015-01-01

    In-core fuel management for PWR is not easy because of the number of fuel assemblies in the core as much as 192 assemblies so many possibilities for placement of the fuel in the core. Configuration of fuel assemblies in the core must be precise and accurate so that the reactor operates safely and economically. It is necessary for verification of PWR-FUEL code that will be used in-core fuel management for PWR. PWR-FUEL code based on neutron transport theory and solved with the approach of multi-dimensional nodal diffusion method many groups and diffusion finite difference method (FDM). The goal is to check whether the program works fine, especially for the design and in-core fuel management for PWR. Verification is done with equilibrium core search model at three conditions that boron free, 1000 ppm boron concentration and critical boron concentration. The result of the average burn up fuel assemblies distribution and power distribution at BOC and EOC showed a consistent trend where the fuel with high power at BOC will produce a high burn up in the EOC. On the core without boron is obtained a high multiplication factor because absence of boron in the core and the effect of fission products on the core around 3.8 %. Reactivity effect at 1000 ppm boron solution of BOC and EOC is 6.44 % and 1.703 % respectively. Distribution neutron flux and power density using NODAL and FDM methods have the same result. The results show that the verification PWR-FUEL code work properly, especially for core design and in-core fuel management for PWR. (author)

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

    International Nuclear Information System (INIS)

    Wati, Nurokhim

    2008-01-01

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

  3. Safety issues in established predisposal waste management practices

    International Nuclear Information System (INIS)

    Thomas, W.

    2000-01-01

    Radioactive wastes generated at various stages in the nuclear fuel cycle vary considerably in relation to volume, physical and chemical properties, and radioactivity. The management of these wastes prior to disposal has to be adapted to these conditions, which calls for suitable characterization and minimization, collection, interim storage and conditioning of the wastes. Experience gained over decades shows that current predisposal waste management practices are well advanced. Whereas problems related to inadequate waste management practices in the past have been encountered at several sites and need ongoing remedial actions, modern practices have good safety records. Considerable development and improvement of waste management practices have been achieved and as a consequence of delays in implementing repositories in several countries they remain important tasks. Decommissioning and dismantling of nuclear facilities also have to be taken into account. In most cases, these activities can be performed using existing technical means and practices. No significant safety concerns have been found for the long term storage of spent fuel and vitrified waste. Dry storage has reached technical maturity and appears to be attractive, especially for aged fuel. It has, however, to be stressed that long term storage is not the ultimate solution. Continued efforts to implement repositories are mandatory in order to maintain a credible and responsible strategy for waste management. (author)

  4. Dialogue, Language and Identity: Critical Issues for Networked Management Learning

    Science.gov (United States)

    Ferreday, Debra; Hodgson, Vivien; Jones, Chris

    2006-01-01

    This paper draws on the work of Mikhail Bakhtin and Norman Fairclough to show how dialogue is central to the construction of identity in networked management learning. The paper is based on a case study of a networked management learning course in higher education and attempts to illustrate how participants negotiate issues of difference,…

  5. Pwani Yetu: Issue 4. April 1999.Tanzania Coastal Management Partnership.

    OpenAIRE

    Tanzania Coastal Management Partnership

    1999-01-01

    The Newsletter of the Tanzania Coastal Management Partnership - Pwani Yetu - 'our coast', is produced every other month in both Kiswahili and English and circulated to all coastal management partners from national level, coastal communities and the private sector. Pwani Yetu reports on coastal and marine activities, including issues on conservation, environment, and social economic development. 'Research Group' TCMP.

  6. Operations Management of Logistics and Supply Chain: Issues and Directions

    OpenAIRE

    Li, Xiang

    2014-01-01

    There has been consensus that logistics as well as supply chain management is a vital research field, yet with few literature reviews on this topic. This paper sets out to propose some hot issues in the current research, through a review of related literature from the perspective of operations management. In addition, we generate some insights and future research directions in this field.

  7. Resensi Buku Islamic Perspective on Management: Contemporary Issues

    OpenAIRE

    Kusuma, Bayu Mitra Adhyatma

    2016-01-01

    Judul buku : Islamic Perspective on Management: ContemporaryIssuesPenulis : Nor ‘Azizah Kamri, dkk.Penerbit : YaPEIM Management Academy (kerjasamadengan University of Malaya Press)Tebal : xiv + 463 halamanCetakan pertama : November 2013Kota terbit : Kuala Lumpur

  8. Critical issues facing R&D managers in China

    NARCIS (Netherlands)

    de Boer, S.J.; Gan, Weibing; Shan, Guogang

    1998-01-01

    R&D managers in China experienced significant changes in the past decade, in particular because of Government policies of economic reform and opening to the outside world. These developments have brought about a number of rather specific R&D management issues and problems. The paper addresses the

  9. Radioactive waste management of experimental DUPIC fuel fabrication process

    International Nuclear Information System (INIS)

    Lee, H. H.; Park, J. J.; Shin, J. M.; Yang, M. S.; Hong, K. P.

    2001-01-01

    The concept of DUPIC(Direct Use of Spent PWR Fuel in CANDU Reactors) is a dry processing technology to manufacture CANDU compatible DUPIC fuel from spent PWR fuel material. Real spent PWR fuel was used in IMEF M6 hot cell to carry out DUPIC experiment. Afterwards, about 200 kg-U of spent PWR fuel is supposed to be used till 2006. This study has been conducted in some hot cells of PIEF and M6 cell of IMEF. There are various forms of nuclear material such as rod cut, powder, green pellet, sintered pellet, fabrication debris, fuel rod, fuel bundle, sample, and process waste produced from various manufacturing experiment of DUPIC fuel. After completing test, the above nuclear wastes and test equipment etc. will be classified as radioactive waste, transferred to storage facility and managed rigorously according to domestic and international laws until the final management policy is determined. It is desirable to review management options in advance for radioactive waste generated from manufacturing experiment of DUPIC nuclear fuel as well as residual nuclear material and dismantled equipment. This paper includes basic plan for DUPIC radwaste, arising source and estimated amount of radioactive waste, waste classification and packing, transport cask, transport procedures

  10. MISER-I: a computer code for JOYO fuel management

    International Nuclear Information System (INIS)

    Yamashita, Yoshioki

    1976-06-01

    A computer code ''MISER-I'' is for a nuclear fuel management of Japan Experimental Fast Breeder Reactor JOYO. The nuclear fuel management in JOYO can be regarded as a fuel assembly management because a handling unit of fuel in JOYO plant is a fuel subassembly (core and blanket subassembly), and so the recording of material balance in computer code is made with each subassembly. The input information into computer code is given with each subassembly for a transfer operation, or with one reactor cycle and every one month for a burn-up in reactor core. The output information of MISER-I code is the fuel assembly storage record, fuel storage weight record in each material balance subarea at any specified day, and fuel subassembly transfer history record. Change of nuclear fuel composition and weight due to a burn-up is calculated with JOYO-Monitoring Code by off-line computation system. MISER-I code is written in FORTRAN-IV language for FACOM 230-48 computer. (auth.)

  11. Management issues in the metabolic syndrome.

    Science.gov (United States)

    Deedwania, P C; Gupta, R

    2006-10-01

    The metabolic syndrome or cardiovascular dysmetabolic syndrome is characterized by obesity, central obesity, insulin resistance, atherogenic dyslipidemia, and hypertension. The major risk factors leading to this syndrome are physical inactivity and an atherogenic diet and cornerstone clinical feature is abdominal obesity or adiposity. In addition, patients usually have elevated triglycerides, low HDL cholesterol, elevated LDL cholesterol, other abnormal lipid parameters, hypertension, and elevated fasting blood glucose. Impaired fibrinolysis, increased susceptibility to thrombotic events, and raised inflammatory markers are also observed. Given that India has the largest number of subjects with type-2 diabetes in the world it can be extrapolated that this country also has the largest number of patients with the metabolic syndrome. Epidemiological studies confirm a high prevalence. Therapeutic approach involves intervention at a macro-level and control of multiple risk factors using therapeutic lifestyle approaches (diet control and increased physical activity, pharmacotherapy - anti-obesity agents) for control of obesity and visceral obesity, and targeted approach for control of individual risk factors. Pharmacological therapy is a critical step in the management of patients with metabolic syndrome when lifestyle modifications fail to achieve the therapeutic goals. Anti-obesity drugs such as sibutramine and orlistat can be tried to reduce weight and central obesity and jointly control the metabolic syndrome components. Other than weight loss, there is no single best therapy and treatment should consist of treatment of individual components of the metabolic syndrome. Newer drugs such as the endocannabinoid receptor blocker,rimonabant, appear promising in this regard. Atherogenic dyslipidemia should be controlled initially with statins if there is an increase in LDL cholesterol. If there are other lipid abnormalities then combination therapy of statin with fibrates

  12. Make use of EDF orientations in PWR fuel management

    International Nuclear Information System (INIS)

    Gloaguen, A.

    1989-01-01

    The EDF experience acquired permits to allow the PWR fuel performances and to make use of better management. In this domain low progress can be given considerable financial profits. The industrial and commercial structures, the time constant of the fuel cycle, has for consequence that the electric utilities can take advantage only progressively of the expected profits [fr

  13. Monitoring instrumentation spent fuel management program. Final report

    International Nuclear Information System (INIS)

    1979-01-01

    Preliminary monitoring system methodologies are identified as an input to the risk assessment of spent fuel management. Conceptual approaches to instrumentation for surveillance of canister position and orientation, vault deformation, spent fuel dissolution, temperature, and health physics conditions are presented. In future studies, the resolution, reliability, and uncertainty associated with these monitoring system methodologies will be evaluated

  14. Management of spent fuel; Gestion del combustible irradiado

    Energy Technology Data Exchange (ETDEWEB)

    Estrampes Blanch, J.

    2015-07-01

    The management of irradiated fuel has become one of the materials that more time and resources deals within their responsibilities that also cover other areas such as the design of the new cycles, supply of fresh fuel, tracking operation cycles and strategies of power changes. (Author)

  15. Application of genetic algorithm in reactor fuel management

    International Nuclear Information System (INIS)

    Peng Gang

    2002-01-01

    The genetic algorithm (GA) has been used in reactor fuel management of core arrangement optimal calculation. The chromosome coding method has been selected, and the parameters in GA operators have been improved, so the quality and efficiency of calculation in GA program have been greatly improved. According to the result, better core fuel position arrangement can be obtained from the GA calculation

  16. Fuels Management-How to Measure Success: Conference Proceedings

    Science.gov (United States)

    Patricia L. Andrews; Bret W. Butler

    2006-01-01

    Fuels management programs are designed to reduce risks to communities and to improve and maintain ecosystem health. The International Association of Wildland Fire initiated the 1st Fire Behavior and Fuels Conference to address development, implementation, and evaluation of these programs. The focus was on how to measure success. Over 500 participants from several...

  17. Modeling the optimal management of spent nuclear fuel

    International Nuclear Information System (INIS)

    Nachlas, J.A.; Kurstedt, H.A. Jr.; Swindle, D.W. Jr.; Korcz, K.O.

    1977-01-01

    Recent governmental policy decisions dictate that strategies for managing spent nuclear fuel be developed. Two models are constructed to investigate the optimum residence time and the optimal inventory withdrawal policy for fuel material that presently must be stored. The mutual utility of the models is demonstrated through reference case application

  18. Social and Environmental Issues in Corporative Management: A Romanian Story

    Directory of Open Access Journals (Sweden)

    Cornelia DASCĂLU

    2011-12-01

    Full Text Available The complex process of monitoring entities environmental impact entails ability, respect for the environment and reduction of the ecological footprint. This research defines Romanian trends as regards the effects and actions to adapt to climate change and characterizes corporate management in terms of compliance with environmental management systems requirements. The main objective is to assess the current state of environmental management implementation and identifies relevant social and environmental issues that companies use to include in corporate management. The current agenda would allow developing a framework for environmental management implementation in Romanian entities, in order to assume the corporate social responsibility.

  19. Managing nuclear wastes: an overview of the issues

    International Nuclear Information System (INIS)

    Cummings, R.G.; Utton, A.E.

    1981-01-01

    The issues involving nuclear waste management are reviewed. The author points out the need for a critical overview of research priorities concerning nuclear waste management (NWM), and he discusses the uncertainties surrounding the scope of the problem (i.e., the controversy concerning the extent of dangers to public health and safety associated with the transport and storage of nuclear wastes). This article, intended as a introdution to the other nuclear waste management papers in the journal, also briefly discusses the papers

  20. Nontechnical issues in waste management: ethical, institutional, and political concerns

    International Nuclear Information System (INIS)

    Hebert, J.A.; Rankin, W.L.; Brown, P.G.; Schuller, C.R; Smith, R.F.; Goodnight, J.A.; Lippek, H.E.

    1978-05-01

    The report consists of a presentation and distillation of major nontechnical issues surrounding commercial waste management, followed by ethical, institutional, and political analyses of these issues. The ethical analysis consists of a discusson of what is meant by ''ethics'' and ''morality'' in the waste management context and an illustrative attempt at an ethical analysis of the commercial nuclear waste problem. Two institutional analyses are presented: one is an analysis of the possible problems of long-term human institutions in waste management; the other is a presentation of institutional arrangements for the short term. A final chapter discusses issues and concerns involving intergovernmental relations--that is, local, state, and federal interface problems in waste management

  1. Nontechnical issues in waste management: ethical, institutional, and political concerns

    Energy Technology Data Exchange (ETDEWEB)

    Hebert, J.A.; Rankin, W.L.; Brown, P.G.; Schuller, C.R; Smith, R.F.; Goodnight, J.A.; Lippek, H.E.

    1978-05-01

    The report consists of a presentation and distillation of major nontechnical issues surrounding commercial waste management, followed by ethical, institutional, and political analyses of these issues. The ethical analysis consists of a discusson of what is meant by ''ethics'' and ''morality'' in the waste management context and an illustrative attempt at an ethical analysis of the commercial nuclear waste problem. Two institutional analyses are presented: one is an analysis of the possible problems of long-term human institutions in waste management; the other is a presentation of institutional arrangements for the short term. A final chapter discusses issues and concerns involving intergovernmental relations--that is, local, state, and federal interface problems in waste management.

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

    International Nuclear Information System (INIS)

    1985-01-01

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

  3. Review of spent fuel related issues in SKB's SR 97

    Energy Technology Data Exchange (ETDEWEB)

    Grambow, B. [Ecole des Mines de Nantes (France). SUBATECH-Laboratory

    2000-12-01

    The solid waste form 'spent fuel' constitutes both the dominant radionuclide source as well as a first radionuclide retention barrier of a planned future high level nuclear waste isolation systems in deep granite formations. In order to evaluate the performance of spent fuel as part of the multibarrier containment system in a deep repository, the radionuclide release properties in groundwater must be predicted over very long time periods. Radionuclide release is not an inherent materials property of the fuel but depends, besides fuel specific parameters, mainly on time but as well on the geochemical and hydraulic environment of the disposal location. The study SR 97 documents the large effort of SKB to assess the long-term performance of a repository containing spent nuclear fuel. Scenario and consequence analyses are clearly described, considering major physical and chemical interactions of the various components of the multi-barrier isolation system. The approach attempts to assess both a realistic and a pessimistic evolution scenario. The present report attempts to evaluate whether this approach is thoroughly carried through to assess the performance of spent nuclear fuel in a repository. Main issues are radionuclide inventories and inventory distribution between structural parts of the fuel assembly and the fuel matrix, potential fuel alteration prior to water access, as well as models for fuel matrix dissolution and instant release fractions. Uncertainties in radionuclide inventories are discussed and were found for many radionuclides to be higher than assumed in SR 97. This is particularly true for Cl-36. This nuclide is a potential key biosphere dose contributor in various international safety assessments. Of particular importance are uncertainties related to the partition of radionuclides between metallic parts of the fuel assembly and the fuel matrix, since inventories of metallic parts are considered to be released instantaneously. Using C-14 as

  4. Nuclear fuel cycle and waste management in France

    International Nuclear Information System (INIS)

    Sousselier, Yves.

    1981-05-01

    After a short description of the nuclear fuel cycle mining, milling, enrichment and reprocessing, radioactive waste management in France is exposed. The different types of radioactive wastes are examined. Storage, solidification and safe disposal of these wastes are described

  5. Radioactive waste management and advanced nuclear fuel cycle technologies

    International Nuclear Information System (INIS)

    2007-01-01

    In 2007 ENEA's Department of Nuclear Fusion and Fission, and Related Technologies acted according to national policy and the role assigned to ENEA FPN by Law 257/2003 regarding radioactive waste management and advanced nuclear fuel cycle technologies

  6. Comparative techniques for nuclear fuel cycle waste management systems

    International Nuclear Information System (INIS)

    Pelto, P.J.; Voss, J.W.

    1979-09-01

    A safety assessment approach for the evaluation of predisposal waste management systems is described and applied to selected facilities in the light water reactor (LWR) once-through fuel cycle and a potential coprocessed UO 2 -PuO 2 fuel cycle. This approach includes a scoping analysis on pretreatment waste streams and a more detailed analysis on proposed waste management processes. The primary evaluation parameters used in this study include radiation exposures to the public from radionuclide releases from normal operations and potential accidents, occupational radiation exposure from normal operations, and capital and operating costs. On an overall basis, the waste management aspects of the two fuel cycles examined are quite similar. On an individual facility basis, the fuel coprocessing plant has the largest waste management impact

  7. Management number identification method for nuclear fuel assembly

    International Nuclear Information System (INIS)

    Furuya, Nobuo; Mori, Kazuma.

    1995-01-01

    In the present invention, a management number indicated to appropriate portions of a fuel assembly can be read with no error for the management of nuclear fuel materials in the nuclear fuel assembly (counting management) and physical protection: PP. Namely, bar codes as a management number are printed by electrolytic polishing to one or more portions of a side surface of an upper nozzle of the assembly, an upper surface of a clamp and a side surface of a lower nozzle. The bar codes are read by a reader at one or more portions in a transporting path for transporting the fuel assembly and at a fuel detection device disposed in a fuel storage pool. The read signals are inputted to a computer. With such procedures, the nuclear fuel assembly can be identified with no error by reading the bar codes and without applying no danger to a human body. Since the reader is disposed in the course of the transportation and test for the assembly, and the read signals are inputted to the computer, the management for the counting number and PP is facilitated. (I.S.)

  8. Advanced CANDU reactors fuel analysis through optimal fuel management at approach to refuelling equilibrium

    International Nuclear Information System (INIS)

    Tingle, C.P.; Bonin, H.W.

    1999-01-01

    The analysis of alternate CANDU fuels along with natural uranium-based fuel was carried out from the view point of optimal in-core fuel management at approach to refuelling equilibrium. The alternate fuels considered in the present work include thorium containing oxide mixtures (MOX), plutonium-based MOX, and Pressurised Water Reactor (PWR) spent fuel recycled in CANDU reactors (Direct Use of spent PWR fuel in CANDU (DUPIC)); these are compared with the usual natural UO 2 fuel. The focus of the study is on the 'Approach to Refuelling Equilibrium' period which immediately follows the initial commissioning of the reactor. The in-core fuel management problem for this period is treated as an optimization problem in which the objective function is the refuelling frequency to be minimized by adjusting the following decision variables: the channel to be refuelled next, the time of the refuelling and the number of fresh fuel bundles to be inserted in the channel. Several constraints are also included in the optimisation problem which is solved using Perturbation Theory. Both the present 37-rod CANDU fuel bundle and the proposed CANFLEX bundle designs are part of this study. The results include the time to reach refuelling equilibrium from initial start-up of the reactor, the average discharge burnup, the average refuelling frequency and the average channel and bundle powers relative to natural UO 2 . The model was initially tested and the average discharge burnup for natural UO 2 came within 2% of the industry accepted 199 MWh/kgHE. For this type of fuel, the optimization exercise predicted the savings of 43 bundles per full power year. In addition to producing average discharge burnups and other parameters for the advanced fuels investigated, the optimisation model also evidenced some problem areas like high power densities for fuels such as the DUPIC. Perturbation Theory has proven itself to be an accurate and valuable optimization tool in predicting the time between

  9. Influence of safety limitations on the fuel cycle management

    Energy Technology Data Exchange (ETDEWEB)

    Mancini, G

    1972-05-03

    The choice of an optimum fuel cycle has been up to now governed from the safety point of view, by the setting of very general limitations on few parameters, as for instance on the fuel temperature and on the surface temperature. As a better understanding of the design and materials limitations become available, the philosophy of the fuel cycle optimisation can be improved. The aim of this contribution is to shortly revise the safety aspects involved in the choice of a fuel cycle management and thereafter try to draw some general conclusions.

  10. Environmental, health, and safety issues of fuel cells in transportation. Volume 1: Phosphoric acid fuel-cell buses

    Energy Technology Data Exchange (ETDEWEB)

    Ring, S

    1994-12-01

    The U.S. Department of Energy (DOE) chartered the Phosphoric Acid Fuel-Cell (PAFC) Bus Program to demonstrate the feasibility of fuel cells in heavy-duty transportation systems. As part of this program, PAFC- powered buses are being built to meet transit industry design and performance standards. Test-bed bus-1 (TBB-1) was designed in 1993 and integrated in March 1994. TBB-2 and TBB-3 are under construction and should be integrated in early 1995. In 1987 Phase I of the program began with the development and testing of two conceptual system designs- liquid- and air-cooled systems. The liquid-cooled PAFC system was chosen to continue, through a competitive award, into Phase H, beginning in 1991. Three hybrid buses, which combine fuel-cell and battery technologies, were designed during Phase III. After completing Phase II, DOE plans a comprehensive performance testing program (Phase HI) to verify that the buses meet stringent transit industry requirements. The Phase III study will evaluate the PAFC bus and compare it to a conventional diesel bus. This NREL study assesses the environmental, health, and safety (EH&S) issues that may affect the commercialization of the PAFC bus. Because safety is a critical factor for consumer acceptance of new transportation-based technologies the study focuses on these issues. The study examines health and safety together because they are integrally related. In addition, this report briefly discusses two environmental issues that are of concern to the Environmental Protection Agency (EPA). The first issue involves a surge battery used by the PAFC bus that contains hazardous constituents. The second issue concerns the regulated air emissions produced during operation of the PAFC bus.

  11. Spent fuel interim management: 1995 update

    International Nuclear Information System (INIS)

    Anderson, C.K.

    1995-01-01

    The problems of interim away-from-reactor spent fuel storage and storage in spent fuel pools at the reactor site are discussed. An overview of the state-of-the-art in the USA, Europe, and Japan is presented. The technical facilities for away-from-reactor storage are briefly described, including wet storage pools, interactive concrete systems, metallic containers, and passive concrete systems. Reprocessing technologies are mostly at the design stage only. It is predicted that during the 20 years to come, about 50 000 tonnes of spent fuel will be stored at reactor sites regardless of the advance of spent fuel reprocessing or interim storage projects. (J.B.). 4 tabs., 2 figs

  12. Swedish spent fuel management systems, facilities and operating experiences

    International Nuclear Information System (INIS)

    Vogt, J.

    1998-01-01

    About 50% of the electricity in Sweden is generated by means of nuclear power from 12 LWR reactors located at four sites and with a total capacity of 10,000 MW. The four utilities have jointly created SKB, the Swedish Nuclear Fuel and Waste Management Company, which has been given the mandate to manage the spent fuel and radioactive waste from its origin at the reactors to the final disposal. SKB has developed a system for the safe handling of all kinds of radioactive waste from the Swedish nuclear power plants. The keystones now in operation of this system are a transport system, a central interim storage facility for spent nuclear fuel (CLAB), a final repository for short-lived, low and intermediate level waste (SFR). The remaining, system components being planned are an encapsulation plant for spent nuclear fuel and a deep repository for encapsulated spent fuel and other long-lived radioactive wastes. (author)

  13. Comparison of spent fuel management fee collection alternatives

    International Nuclear Information System (INIS)

    White, M.K.; Engel, R.L.

    1979-01-01

    Five alternative methods for recovering the costs of spent fuel management were evaluated. These alternatives consist of collecting the fee for various components of spent fuel management cost (AFR basin storage, transportation from AFR basin to the repository, packaging, repository, R and D, and government overhead) at times ranging from generation of power to delivery of the spent fuel to the government. The five fee collection mechanisms were analyzed to determine how well they serve the interests of the public and the electricity ratepayer

  14. A discrete optimization method for nuclear fuel management

    International Nuclear Information System (INIS)

    Argaud, J.P.

    1993-01-01

    Nuclear fuel management can be seen as a large discrete optimization problem under constraints, and optimization methods on such problems are numerically costly. After an introduction of the main aspects of nuclear fuel management, this paper presents a new way to treat the combinatorial problem by using information included in the gradient of optimized cost function. A new search process idea is to choose, by direct observation of the gradient, the more interesting changes in fuel loading patterns. An example is then developed to illustrate an operating mode of the method. Finally, connections with classical simulated annealing and genetic algorithms are described as an attempt to improve search processes. 16 refs., 2 figs

  15. Recent developments in spent fuel management in Norway - 59260

    International Nuclear Information System (INIS)

    Bennett, Peter J.; Oberlaender, Barbara C.

    2012-01-01

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

  16. Environmental Justice, Place and Nuclear Fuel Waste Management in Canada

    International Nuclear Information System (INIS)

    Kuhn, Richard G.

    2006-01-01

    The purpose of this paper is to outline the basis of a Nuclear Fuel Waste management strategy for Canada, taking into account the unique legal tenets (Aboriginal rights; federal - provincial jurisdiction) and the orientation that the Nuclear Waste Management Organization (NWMO) has taken to date. The focus of the paper are grounded in notions of environmental justice. Bullard's definition provides a useful guideline: 'the fair treatment and meaningful involvement of all people regardless of race, colour, national origin or income with respect to the development, implementation and enforcement of environmental laws, regulations and policies'. The overriding concern is to work towards a process that is inclusive and just. Prior to developing a specific strategy to site a NFW disposal facility, we maintain that the NWMO needs to first address three fundamental issues: Expand its mandate to include the future of nuclear energy in Canada; Provide an inclusive role for First Nations (Aboriginal people) in all stages of the process; Adhere to the requirement of specifying an economic region and deal more overtly with the transportation of NF

  17. Environmental Justice, Place and Nuclear Fuel Waste Management in Canada

    Energy Technology Data Exchange (ETDEWEB)

    Kuhn, Richard G. [Univ. of Guelph (Canada). Dept. of Geography; Murphy, Brenda L. [Wilfrid Launer Univ., Brantford (Canada)

    2006-09-15

    The purpose of this paper is to outline the basis of a Nuclear Fuel Waste management strategy for Canada, taking into account the unique legal tenets (Aboriginal rights; federal - provincial jurisdiction) and the orientation that the Nuclear Waste Management Organization (NWMO) has taken to date. The focus of the paper are grounded in notions of environmental justice. Bullard's definition provides a useful guideline: 'the fair treatment and meaningful involvement of all people regardless of race, colour, national origin or income with respect to the development, implementation and enforcement of environmental laws, regulations and policies'. The overriding concern is to work towards a process that is inclusive and just. Prior to developing a specific strategy to site a NFW disposal facility, we maintain that the NWMO needs to first address three fundamental issues: Expand its mandate to include the future of nuclear energy in Canada; Provide an inclusive role for First Nations (Aboriginal people) in all stages of the process; Adhere to the requirement of specifying an economic region and deal more overtly with the transportation of NF.

  18. Multi-purpose container technologies for spent fuel management

    International Nuclear Information System (INIS)

    2000-12-01

    The management of spent nuclear fuel is an integral part of the nuclear fuel cycle. Spent fuel management resides in the back end of the fuel cycle, and is not revenue producing as electric power generation is. It instead results in a cost associated power generation. It is a major consideration in the nuclear power industry today. Because technologies, needs and circumstances vary from country to country, there is no single, standardized approach to spent fuel management. The projected cumulative amount of spent fuel generated worldwide by 2010 will be 330 000 t HM. When reprocessing is accounted for, that amount is likely to be reduced to 215 000 t HM, which is still more than twice as much as the amount now in storage. Considering the limited capacity of at-reactor (AR) storage, various technologies are being developed for increasing storage capacities. At present, many countries are developing away-from-reactor (AFR) storage in the form of pool storage or as dry storage. Further these AFR storage systems may be at-reactor sites or away-from-reactor sites (e.g. centrally located interim storage facilities, serving several reactors). The dry storage technologies being developed are varied and include vaults, horizontal concrete modules, concrete casks, and metal casks. The review of the interim storage plans of several countries indicates that the newest approaches being pursued for spent fuel management use dual-purpose and multi-purpose containers. These containers are envisaged to hold several spent fuel assemblies, and be part of the transport, storage, and possibly geological disposal systems of an integrated spent fuel management system

  19. Adaptive management of natural resources-framework and issues

    Science.gov (United States)

    Williams, B.K.

    2011-01-01

    Adaptive management, an approach for simultaneously managing and learning about natural resources, has been around for several decades. Interest in adaptive decision making has grown steadily over that time, and by now many in natural resources conservation claim that adaptive management is the approach they use in meeting their resource management responsibilities. Yet there remains considerable ambiguity about what adaptive management actually is, and how it is to be implemented by practitioners. The objective of this paper is to present a framework and conditions for adaptive decision making, and discuss some important challenges in its application. Adaptive management is described as a two-phase process of deliberative and iterative phases, which are implemented sequentially over the timeframe of an application. Key elements, processes, and issues in adaptive decision making are highlighted in terms of this framework. Special emphasis is given to the question of geographic scale, the difficulties presented by non-stationarity, and organizational challenges in implementing adaptive management. ?? 2010.

  20. The management issues of implementing telecommuting: a case study

    OpenAIRE

    Bane, Chuck Howard, Jr.

    1993-01-01

    Approved for public release; distribution is unlimited. This thesis is a case study of the implementation of telecommuting by CalComp at the Telecommuting Workcenter of Riverside County and is a real life example of the management issues that surround telecommuting. The issues brought forth in this study will enable those responsible for implementing a telecommuting program to better understand the impact of this change on their organization and how a telecommuting center may be used in th...

  1. Towards Cloud Computing SLA Risk Management: Issues and Challenges

    OpenAIRE

    Morin, Jean-Henry; Aubert, Jocelyn; Gateau, Benjamin

    2012-01-01

    Cloud Computing has become mainstream technology offering a commoditized approach to software, platform and infrastructure as a service over the Internet on a global scale. This raises important new security issues beyond traditional perimeter based approaches. This paper attempts to identify these issues and their corresponding challenges, proposing to use risk and Service Level Agreement (SLA) management as the basis for a service level framework to improve governance, risk and compliance i...

  2. Fuel management in CANDU reactors: Daniel Rozon's contribution

    International Nuclear Information System (INIS)

    Rozon, D.; Varin, E.; Chambon, R.

    2010-01-01

    The CANDU fuel management optimization problem is in many ways different from LWRs fuel management, because of the on-line refueling and the complete 3-D geometry problem. Daniel Rozon was an outstanding leader in the understanding and resolution of this optimization problem and remained during his entire career. Daniel Rozon and his students have used the generalized adjoint formalism implemented in standard mathematical programming methods to solve the optimization of the exit burnup in the reactor as well as the optimization of control rod worth or fuel enrichment. We have summarized here the theoretical basis of fuel management and resolution methods, the latest approaches of optimization and results as obtained using the OPTEX code. (author)

  3. National briefing summaries: Nuclear fuel cycle and waste management

    International Nuclear Information System (INIS)

    Schneider, K.J.; Harmon, K.M.; Lakey, L.T.; Silviera, D.J.; Leigh, I.W.

    1987-09-01

    This report is a compilation of publicly-available information concerning the nuclear fuel cycle and radioactive waste management strategies and programs of 20 nations and three international agencies that have publicized their activities in this field. The information in this document is compiled to provide summary information on radioactive waste management activities in other countries. This document indicates what is occurring in other countries with regard to strategies, activities, and facilities. This document first presents a short overview of the activities and trends for managing low- to high-level radioactive waste and spent fuel by the entities covered in this review. This is followed by information for each country for nuclear power; fuel cycle and waste management strategy/policy; highlights and major milestones; institutional considerations/organizations; nuclear fuel production; fuel recycle; spent fuel storage and transport; waste conditioning, storage and transport; surface and near-surface waste disposal; geologic waste disposal; management of uranium mine and mill wastes; decommissioning; international; and references. 406 refs

  4. Yugoslav spent nuclear fuel management program and international perspectives

    International Nuclear Information System (INIS)

    Pesic, M.; Subotic, K.; Sotic, O.; Plecas, I.; Ljubenov, V.; Peric, A.; Milosevic, M.

    2002-01-01

    Spent nuclear fuel stored in the Vinca Institute of Nuclear Sciences, Yugoslavia, consists of about 2.5 tons of metal uranium (initial enrichment 2%) and about 20 kg uranium dioxide (dispersed in aluminum matrix, initial fuel uranium enrichment 80%). This spent nuclear fuel is generated in operation of the RA heavy water research reactor during 1959-1984 period. Both types of fuel are of ex-USSR origin, have the same shape and dimensions and approximately the same initial mass of 235 nuclide. They are known as the TVR-S type of fuel elements. The total of 8030 spent fuel elements are stored at the RA research reactor premises, almost all in the spent fuel pool filled by ordinary water. The last used 480 high-enriched uranium spent fuel elements are kept in the drained RA reactor core since 1984. Fuel layer of both enrichments is covered with thin aluminium cladding. Due to non-suitable chemical parameters of water in the spent fuel storage pool, the corrosion processes penetrated aluminium cladding and aluminium walls od storage containers during storage period long from 20 to 40 years. Activity of fission products ( 137 Cs) is detected in water samples during water inspection in 1996 and experts of the lAEA Russia and USA were invited to help. By end of 2001, some remediation of the water transparency of the storage pool and inspections of water samples taken from the storage containers with the spent fuel elements were carried out by the Vinca Institute staff and with the help of experts from the Russia and the IAEA. Following new initiatives on international perspective on spent fuel management, a proposal was set by the IAEA, and was supported by the governments of the USA and the Russian Federation to ship the spent fuel elements of the RA research reactor to Mayak spent fuel processing plant in Russia. This paper describes current status of the reactor RA spent fuel elements, initiative for new Yugoslav spent fuel management program speculates on some of the

  5. Safety issues in urban transit facilities for hydrogen-fueled buses

    International Nuclear Information System (INIS)

    Hay, R.H.; Ducharme, P.

    2004-01-01

    'Full text:' The Canadian Transportation Fuel Cell Alliance (CTFCA), created by the Canadian Government as part of its 2000 Climate Change Action Plan, has commissioned MARCON-DDM's Hydrogen Intervention Team (HIT) to provide a roadmap for urban transit systems that wish to move to hydrogen fuel cell-powered bus fleets. HIT is currently in the process of gathering information from hydrogen technology providers, bus manufacturers, fuelling system providers and urban transit systems in Canada, the US and Europe. In September, HIT will be in a position to provide a hands-on perspective of the introduction of fuel-cell buses in the Canadian environment. Part of the process of adding hydrogen-fueled busses to urban transit systems involves phasing in the new technology to minimize the economic cost. This involves substituting hydrogen buses into the normal bus procurement life cycle and maximizing the use of existing facilities for garaging, maintenance and fueling. Using a schematic outline of an urban transit system, this presentation will outline the safety issues specific to hydrogen in such systems, particularly for garaging, maintenance and fueling components. It will then outline how safety of these component is addressed in current and proposed codes, standards and recommended practices. Based on these requirements the impact of the introduction of hydrogen-fueled buses on each component of the transit system will be addressed in terms of the adaptations of current facilities and practices or the requirements for new facilities and practices. (author)

  6. Mechanical design issues and resolutions of a dual cooled fuel for the OPR-1000

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyung-Kyu, E-mail: hkkim1@kaeri.re.kr [Innovative Nuclear Fuel Division, Korea Atomic Energy Research Institute, 1045 Daedeokdaero, Yuseong, Daejeon, 305-353 (Korea, Republic of); Kim, Jae-Yong; Yoon, Kyung-Ho [Innovative Nuclear Fuel Division, Korea Atomic Energy Research Institute, 1045 Daedeokdaero, Yuseong, Daejeon, 305-353 (Korea, Republic of)

    2011-06-15

    Highlights: > Thickness of outer cladding tube is determined by using the elastic buckling criterion. > Growth difference of the inner and outer claddings will not cause fuel rod bowing. > Structural components are designed without a drastic change of the conventional ones. - Abstract: A dual cooled fuel is recently brought into focus due to its potential of considerable power uprating. The purpose of present work is to realize the innovative concept of a dual cooled fuel to be a fuel assembly structure compatible with the OPR-1000 system. Under the framework, the critical issues such as the outer cladding thickness and the growth difference of the inner and outer cladding tubes are dealt with in this paper. We designed the thickness of outer cladding tube by using the elastic buckling criterion and safety factor analysis. From the concern of the inner cladding's bowing during irradiation, it was suggested that the outer cladding would grow more than the inner one by applying different microstructures to the inner and outer cladding tubes. It was noted that the gap between fuel rods would not be narrowed further during the different irradiation growth. The structural components such as fuel rod supporting structure, top and bottom end pieces and guide tubes could be designed without a drastic change of those of the conventional fuel. Candidate designs of the components are also presented.

  7. Spanish high level radioactive waste management system issues

    International Nuclear Information System (INIS)

    Espejo, J.M.; Beceiro, A.R.

    1992-01-01

    The Empresa Nacional de Residuos Radiactivos, S.A. (ENRESA) has been limited liability company to be responsible for the management of all kind of radioactive wastes in Spain. This paper provides an overview of the strategy and main lines of action stated in the third General Radioactive Waste Plan, currently in force, for the management of spent nuclear fuel and high - level wastes, as well as an outline of the main related projects, either being developed or foreseen. Aspects concerning the organizational structure, the economic and financing system and the international cooperation are also included

  8. Spanish high level radioactive waste management system issues

    International Nuclear Information System (INIS)

    Ulibarri, A.; Veganzones, A.

    1993-01-01

    The Empresa Nacional de Residuous Radiactivos, S.A. (ENRESA) was set up in 1984 as a state-owned limited liability company to be responsible for the management of all kinds of radioactive wastes in Spain. This paper provides an overview of the strategy and main lines of action stated in the third General Radioactive Waste Plan, currently in force, for the management of spent nuclear fuel and high-level wastes, as well as an outline of the main related projects, either being developed or foreseen. Aspects concerning the organizational structure, the economic and financing system and the international co-operational are also included

  9. Assessment of the implementation issues for fuel cells in domestic and small scale stationary power generation and CHP applications

    Energy Technology Data Exchange (ETDEWEB)

    Graham, G.; Cruden, A.; Hart, J.

    2002-07-01

    This report discusses implementation issues associated with the use of fuel cells in <10 kW domestic, small-scale power generation and combined heat and power (CHP) operations in the UK. The report examines the key issues (fuel cell system standards and certification, fuel infrastructure, commercial issues and competing CHP technologies), before discussing non-technical issues including finance, ownership, import and export configuration, pricing structure, customer acceptability, installation, operation and training of servicing and commissioning personnel. The report goes on to discuss market and technical drivers, grid connection issues and solutions, operations and maintenance. Recommendations for the future are made.

  10. New Brunswick Market Design Committee : Congestion management issues

    International Nuclear Information System (INIS)

    2001-01-01

    The restructuring of the New Brunswick wholesale power market comprises a number of issues that need to be resolved concerning transmission system related policy decisions and detailed design issues. The wholesale market structure, ownership structure, and means of preventing market power abuses all have an impact on the resolution of many of those issues. Some transmission related decisions regarding congestion management must be made, and they are examined in this document. The report includes a discussion of the issues related to congestion on the transmission system, a review of the decisions that remain to be made while proposing a number of alternatives, reviews decisions that other jurisdictions have made in somewhat similar circumstances. Finally, the advantages and disadvantages of each alternative are identified. Several high level transmission tariff design issues requiring to be addressed later in greater detail are listed in this document. 1 tab

  11. ENS RRFM 2005: 9th international topical meeting on research reactor fuel management. Transactions

    International Nuclear Information System (INIS)

    2005-01-01

    The ENS topical meeting on research reactor fuel management is an annual conference launched successfully in 1997. It has since then grown into well established international forum for the exchange and expertise on all significant aspects of the nuclear fuel cycle of research reactors. Oral presentations at this meeting were divided in the following four sessions: International Topics; Fuel Development, Qualification, Fabrication and Licensing; Reactor Operation, Fuel Safety and Core Conversion; Spent Fuel Management, Back-end Options, Transportation. The three poster sessions were devoted to fuel development, qualification, fabrication and licensing; reactor operation, fuel safety, core conversion, spent fuel; spent fuel management, fuel cycle back-end options, transportation

  12. Issues Raised in Relation to Radioactive Waste Management

    International Nuclear Information System (INIS)

    Atherton, Elizabeth

    2003-01-01

    Nirex has undertaken various consultations with different stakeholders to identify their issues and concerns about radioactive waste management in general and specific aspects of Nirex's work. This paper will outline what dialogue techniques Nirex has undertaken and the issues and concerns that people have raised during the events. It will outline some of the work that Nirex is undertaking to address stakeholders' issues and concerns. Nirex has used a variety of dialogue techniques co-ordinated under the Nirex Involvement Programme to engage with stakeholders about the work we undertake. We are now trying to address the issues, concerns, scenarios and questions raised in our work programme. Key lessons that we have learned in undertaking the dialogues include: The importance of appropriate facilitation and organisation of meetings; The need for a clear purpose for meetings; Being flexible to the needs of the attendees and the issues they raise; Providing feedback to those who participate and following up issues. Through engaging with the public Nirex has learned that: Radioactive waste is not an everyday concern for people; The public can, will and want to engage with the issue of radioactive waste management. This includes engaging with the ethical debate. To facilitate this Nirex and others need to: Provide information in a neutral form outlining the pros and cons and including various people's opinions; Use proactive techniques to allow access and space for people to discuss the issues; Demonstrate how people's opinions have been taken into account. People understand the issues very differently to the way institutions understand them. There is a need for institutions to learn to understand public concerns and the ways in which the public understand issues, as well as for the public to understand the institutional positions better. We are using these insights to develop our future work in this area

  13. Spent fuel management in South Africa

    International Nuclear Information System (INIS)

    Bredell, P.J.; Stott, A.K.

    1998-01-01

    Eskom, the South African utility, operates one of the largest electricity networks in the world. However, only 6% of the South African generating capacity is nuclear; the remainder is coal fired and hydroelectric. The nuclear component consists of the Koeberg Nuclear Power Plant, comprising two French supplied PWRs of 920 MWe each, situated approximately 45 kilometres from cape Town. Construction started in 1976 and the two reactors reached criticality in 1984 and 1985 respectively. South Africa also has an Oak Ridge type research reactor, called SAFARI, operated by the South African Atomic Energy Corporation (AEC) at their Pelindaba site near Pretoria. This research reactor was commissioned in 1965, and has been in operation ever since. South Africa has a National Radioactive Waste Disposal facility called Vaalputs, some 600 km north of Cape Town. The facility, operated by AEC, is presently licensed only for the disposal of low and intermediate radioactive level wastes. Vaalputs offers unique features as a potential interim spent fuel storage and final disposal site, such as favorable geology (granite), low seismicity, low population density, remoteness from industrial centres and and conditions. Therefore, this site has been investigated by the AEC as a potential interim spent fuel storage site, but has not yet been licensed for this purpose. Hence, all spent fuel is currently stored on the two sites at Koeberg and Pelindaba respectively. The spent fuel storage pools at Koeberg have recently been enlarged to accommodate the lifetime spent fuel arisings of the plant. Since late 1997, the Safari spent fuel is stored in a pipe storage facility, constructed away from the reactor on the Pelindaba site. (author)

  14. Overview of Contemporary Issues of Forest Research and Management in China

    Science.gov (United States)

    He, Hong S.; Shifley, Stephen R.; Thompson, Frank R.

    2011-12-01

    With 207 million ha of forest covering 22% of its land area, China ranks fifth in the world in forest area. Rapid economic growth, climate change, and forest disturbances pose new, complex challenges for forest research and management. Progress in meeting these challenges is relevant beyond China, because China's forests represent 34% of Asia's forests and 5% of the worlds' forests. To provide a broader understanding of these management challenges and of research and policies that address them, we organized this special issue on contemporary forest research and management issues in China. At the national level, papers review major forest types and the evolution of sustainable forestry, the development of China's forest-certification efforts, the establishment of a forest inventory system, and achievements and challenges in insect pest control in China. Papers focused on Northern China address historical, social, and political factors that have shaped the region's forests; the use of forest landscape models to assess how forest management can achieve multiple objectives; and analysis and modeling of fuels and fire behavior. Papers addressing Central and South China describe the "Grain for Green" program, which converts low productivity cropland to grassland and woodland to address erosion and soil carbon sequestration; the potential effects of climate change on CO2 efflux and soil respiration; and relationships between climate and net primary productivity. China shares many forest management and research issues with other countries, but in other cases China's capacity to respond to forest management challenges is unique and bears watching by the rest of the world.

  15. Demonstration of Passive Fuel Cell Thermal Management Technology

    Science.gov (United States)

    Burke, Kenneth A.; Jakupca, Ian; Colozza, Anthony; Wynne, Robert; Miller, Michael; Meyer, Al; Smith, William

    2012-01-01

    The NASA Glenn Research Center is developing advanced passive thermal management technology to reduce the mass and improve the reliability of space fuel cell systems for the NASA Exploration program. The passive thermal management system relies on heat conduction within highly thermally conductive cooling plates to move the heat from the central portion of the cell stack out to the edges of the fuel cell stack. Using the passive approach eliminates the need for a coolant pump and other cooling loop components within the fuel cell system which reduces mass and improves overall system reliability. Previous development demonstrated the performance of suitable highly thermally conductive cooling plates and integrated heat exchanger technology to collect the heat from the cooling plates (Ref. 1). The next step in the development of this passive thermal approach was the demonstration of the control of the heat removal process and the demonstration of the passive thermal control technology in actual fuel cell stacks. Tests were run with a simulated fuel cell stack passive thermal management system outfitted with passive cooling plates, an integrated heat exchanger and two types of cooling flow control valves. The tests were run to demonstrate the controllability of the passive thermal control approach. Finally, successful demonstrations of passive thermal control technology were conducted with fuel cell stacks from two fuel cell stack vendors.

  16. RA3: Application of a calculation model for fuel management with SEFE (Slightly Enriched Fuel Elements)

    International Nuclear Information System (INIS)

    Estryk, G.; Higa, M.

    1993-01-01

    The RA-3 (5 MW, MTR) reactor is mainly utilized to produce radioisotopes (Mo-99, I-131, etc.). It started operating with Low Enrichment Uranium (LEU) in 1990, and spends around 12 fuels per year. Although this consumption is small compared to a nuclear power station. It is important to do a good management of them. The present report describes: - A reactor model to perform the Fuel Shuffling. - Results of fuel management simulations for 2 and a half years of operation. Some features of the calculations can be summarized as follows: 1) A 3D calculation model is used with the code PUMA. It does not have experimental adjustments, except for some approximations in the reflector representation and predicts: power, flux distributions and reactivity of the core in an acceptable way. 2) Comparisons have been made with the measurements done in the commissioning with LEU fuels, and it has also been compared with the empirical method (the previous one) which had been used in the former times of operation with LEU fuel. 3) The number of points of the model is approximately 13500, an it can be run in 80386 personal computer. The present method has been verified as a good tool to perform the simulations for the fuel management of RA-3 reactor. It is expected to produce some economic advantages in: - Achieving a better utilization of the fuels. - Leaving more time of operation for radioisotopes production. The activation measurements through the whole core required by the previous method can be significantly reduced. (author)

  17. Operations Management of Logistics and Supply Chain: Issues and Directions

    Directory of Open Access Journals (Sweden)

    Xiang Li

    2014-01-01

    Full Text Available There has been consensus that logistics as well as supply chain management is a vital research field, yet with few literature reviews on this topic. This paper sets out to propose some hot issues in the current research, through a review of related literature from the perspective of operations management. In addition, we generate some insights and future research directions in this field.

  18. Data management issues in mobile ad hoc networks.

    Science.gov (United States)

    Hara, Takahiro

    2017-01-01

    Research on mobile ad hoc networks (MANETs) has become a hot research topic since the middle 1990's. Over the first decade, most research focused on networking techniques, ignoring data management issues. We, however, realized early the importance of data management in MANETs, and have been conducting studies in this area for 15 years. In this review, we summarize some key technical issues related to data management in MANETs, and the studies we have done in addressing these issues, which include placement of data replicas, update management, and query processing with security management. The techniques proposed in our studies have been designed with deep considerations of MANET features including network partitioning, node participation/disappearance, limited network bandwidth, and energy efficiency. Our studies published in early 2000's have developed a new research field as data management in MANETs. Also, our recent studies are expected to be significant guidelines of new research directions. We conclude the review by discussing some future directions for research.

  19. Implementing adaptive phased management (APM) for Canada's used nuclear fuel

    International Nuclear Information System (INIS)

    King, F.

    2008-01-01

    This paper discusses the implementation of Adaptive Phased Management (APM) for Canada's used nuclear fuel. APM is a combination of technology and management system. The technology involves centralized containment and isolation in deep geological repository in a suitable rock formation, as well as shallow storage where used fuel remains retrievable. In both cases there is continuous monitoring. The management system consists of public engagement, phased decision-making, continuous learning and adaption, open and inclusive. Finally, it involves seeking an in formed willing host community

  20. Radiological impacts of spent nuclear fuel management options

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  1. Gas-cooled Fast Reactor (GFR) fuel and In-Core Fuel Management

    International Nuclear Information System (INIS)

    Weaver, K.D.; Sterbentz, J.; Meyer, M.; Lowden, R.; Hoffman, E.; Wei, T.Y.C.

    2004-01-01

    The Gas-Cooled Fast Reactor (GCFR) has been chosen as one of six candidates for development as a Generation IV nuclear reactor based on: its ability to fully utilize fuel resources; minimize or reduce its own (and other systems) actinide inventory; produce high efficiency electricity; and the possibility to utilize high temperature process heat. Current design approaches include a high temperature (2 850 C) helium cooled reactor using a direct Brayton cycle, and a moderate temperature (550 C - 650 C) helium or supercritical carbon dioxide (S-CO 2 ) cooled reactor using direct or indirect Brayton cycles. These design choices have thermal efficiencies that approach 45% to 50%, and have turbomachinery sizes that are much more compact compared to steam plants. However, there are challenges associated with the GCFR, which are the focus of current research. This includes safety system design for decay heat removal, development of high temperature/high fluence fuels and materials, and development of fuel cycle strategies. The work presented here focuses on the fuel and preliminary in-core fuel management, where advanced ceramic-ceramic (cercer) dispersion fuels are the main focus, and average burnups to 266 M Wd/kg appear achievable for the reference Si C/(U,TRU)C block/plate fuel. Solid solution (pellet) fuel in composite ceramic clad (Si C/Si C) is also being considered, but remains as a backup due to cladding fabrication challenges, and high centerline temperatures in the fuel. (Author)

  2. Waste management and the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Molinari, J.

    1982-01-01

    The present lecture deals with energy needs and nuclear power, the importance of waste and its relative place in the fuel cycle, the games of controversies over nuclear waste in the strategies of energy and finally with missions and functions of the IAEA for privileging the rational approach and facilitating the transfer of technology. (RW)

  3. Fuels planning: science synthesis and integration; social issues fact sheet 02: Developing personal responsibility for fuels reduction: Types of information to encourage proactive behavior

    Science.gov (United States)

    Rocky Mountain Research Station USDA Forest Service

    2004-01-01

    Fuels management responsibilities may include providing local property owners with the information for taking responsibility for reducing fuels on their land. This fact sheet discusses three different types of information that may be useful in programs to engage property owners in fuel reduction activities.

  4. EDF advanced fuel management strategies for the next century

    International Nuclear Information System (INIS)

    Kocher, A.; Charmensat, P.; Larderet, M.

    1999-01-01

    The French nuclear fleet represents 57 PWRs in operation, accounting for 80 % of France's total electricity production. The performance achieved by EDF reactors, in terms of availability (82.6% in 1997) and good cost control, have allowed to improve the nuclear KWh cost by 2% since 1992. The implementation of longer fuel cycles on the 1300 MW reactors from 1996 has contributed to this improvement and, as competitiveness is one of the main challenges for EDF, improving core management strategies is still at the order of the day. With this aim, a thinking process has been initiated to evaluate the benefit brought by the use of a fuel assembly like ALLIANCE, the new fuel product developed by Framatome-Fragema and FCF (Framatome Cogema Fuels) in close cooperation with EDF. The considered product provides enhanced performance, particularly as regards discharge burnup (at least up to 70 GWd/t) and thermal-hydraulic and mechanical behaviour. Fuel management improvements rely on the expertise gained by Framatome through designing core management strategies in a wide range of operating conditions prevailing in nuclear reactors all over the world. It will however be taken into account the necessity for EDF to adopt a policy of stepwise change owing to the potential impact of a 'series effect' on its numerous units. The proposed paper will describe innovative fuel managements, achievable thanks to advanced fuel assembly performance, that are jointly investigated by EDF and Framatome. It includes the following optimization schemes: extending cycle length by using higher enrichments up to 5%, while keeping the same reload size (1/3 core for example for the 1300 MW reactors); decreasing reload size (from 1/3 to 1/4 core), while keeping the same cycle length, using more enriched (up to 5 %) fuel assemblies; reaching annual cycle, with maximization of fuel cycle cost optimization (1/5 core). Beyond such schemes, combinations of optimized loading patterns and neutronic features of

  5. Equilibrium transuranic management scheme for diverse fuel cycle analysis

    International Nuclear Information System (INIS)

    Haas, Jason; Lee, John C.

    2008-01-01

    A key issue cited in the U.S. Department of Energy's report to Congress (2003) on the research path for the Advanced Fuel Cycle Initiative (AFCI) is an accurate estimation of life cycle costs for the construction, operation, decontamination and decommissioning of all fuel cycle facilities. In this report we discuss the methodology and validation of a fuel cycle model based on equilibrium operation. We apply our model to a diverse set of advanced reactors and fuel types in order to determine the most effective transmuting system while simultaneously minimizing fuel cycle costs. Our analysis shows that a nearly instant equilibrium modeling of fuel cycle scenarios can accurately approximate the detailed complex dynamic models developed by national laboratories. Our analysis also shows that the cost of transmuting Spent Nuclear Fuel (SNF) from a UO 2 fueled Pressurized Water Reactor (PWR) is minimized by utilizing the thorium cycle in sodium cooled fast reactors and is near the cost for long term repository storage of SNF at Yucca Mountain. (authors)

  6. Issues relating to spent nuclear fuel storage on the Oak Ridge Reservation

    International Nuclear Information System (INIS)

    Klein, J.A.; Turner, D.W.

    1994-01-01

    Currently, about 2,800 metric tons of spent nuclear fuel (SNF) is stored in the US, 1,000 kg of SNF (or about 0.03% of the nation's total) are stored at the US Department of Energy (DOE) complex in Oak Ridge, Tennessee. However small the total quantity of material stored at Oak Ridge, some of the material is quite singular in character and, thus, poses unique management concerns. The various types of SNF stored at Oak Ridge will be discussed including: (1) High-Flux Isotope Reactor (HFIR) and future Advanced Neutron Source (ANS) fuels; (2) Material Testing Reactor (MTR) fuels, including Bulk Shielding Reactor (BSR) and Oak Ridge Research Reactor (ORR) fuels; (3) Molten Salt Reactor Experiment (MSRE) fuel; (4) Homogeneous Reactor Experiment (HRE) fuel; (5) Miscellaneous SNF stored in Oak Ridge National Laboratory's (ORNL's) Solid Waste Storage Areas (SWSAs); (6) SNF stored in the Y-12 Plant 9720-5 Warehouse including Health. Physics Reactor (HPRR), Space Nuclear Auxiliary Power (SNAP-) 10A, and DOE Demonstration Reactor fuels

  7. Editorial safety science special issue road safety management.

    NARCIS (Netherlands)

    Wegman, F.C.M. & Hagezieker, M.P.

    2014-01-01

    The articles presented in this Special Issue on Road Safety Management represent an illustration of the growing interest in policy-related research in the area of road safety. The complex nature of this type of research combined with the observation that scientific journals pay limited attention to

  8. Risk management in HIV/AIDS: ethical and economic issues ...

    African Journals Online (AJOL)

    Risk management in HIV/AIDS: ethical and economic issues associated with restricting HAART access only to adherent patients. ... Using the software TreeAge Pro 2009, we developed a Markov model to project economic outcomes for a hypothetical cohort of HIV/AIDS patients on HAART. The model compared two ...

  9. Issues and scenarios for nuclear waste management systems analysis

    International Nuclear Information System (INIS)

    Mendel, J.E.

    1980-11-01

    The Planning and Analysis Branch of the Department of Energy's Nuclear Waste Management Programs is developing a new systems integration program. The Pacific Northwest Laboratory was requested to perform a brief scoping analysis of what scenarios, questions, and issues should be addressed by the systems integration program. This document reports on that scoping analysis

  10. Making Informed Decisions: Management Issues Influencing Computers in the Classroom.

    Science.gov (United States)

    Strickland, James

    A number of noninstructional factors appear to determine the extent to which computers make a difference in writing instruction. Once computers have been purchased and installed, it is generally school administrators who make management decisions, often from an uninformed pedagogical orientation. Issues such as what hardware and software to buy,…

  11. Gender Issues in Theatre Management: The Cross-River State ...

    African Journals Online (AJOL)

    This study examined gender issues in the management of the Cross-River State Cultural Centre. Three research questions were formulated for the study and eighty-three respondents were used for the study. The researcher made use of questionnaires, interviews and group discussions for collecting data for the study.

  12. Chaos Theory as a Model for Managing Issues and Crises.

    Science.gov (United States)

    Murphy, Priscilla

    1996-01-01

    Uses chaos theory to model public relations situations in which the salient feature is volatility of public perceptions. Discusses the premises of chaos theory and applies them to issues management, the evolution of interest groups, crises, and rumors. Concludes that chaos theory is useful as an analogy to structure image problems and to raise…

  13. Management of examinations: ethical issues. | Nweze | Edo Journal ...

    African Journals Online (AJOL)

    Talking about the ethical issues, we are all aware of the manner/way in which examination malpractice has eaten deep into the fabrics of our society. Some measures really have to be taken to normalize the examination system in our society. The challenges of examination management are numerous for example, having ...

  14. How Managing Editors View and Deal with Newspaper Ethical Issues.

    Science.gov (United States)

    Anderson, Douglas

    1987-01-01

    Claims there is awareness and concern about journalism ethics among daily newspaper managing editors. Asserts that although ethical issues are being addressed to some degree, greater efforts could be made to see that reporters and editors are apprised of codes of ethics. (MM)

  15. Public Relations Manager Involvement in Strategic Issue Diagnosis.

    Science.gov (United States)

    Lauzen, Martha M.

    1995-01-01

    Reports on an exploratory study that seeks to build theoretical understanding of how public relations practitioner involvement in one type of strategic organizational decision making--strategic issue diagnosis--is related to shared values with top management, diagnosis accuracy, strategy pursued, and the power of the public relations function. (TB)

  16. Nuclear waste management in Canada: critical issues, critical perspectives

    National Research Council Canada - National Science Library

    Johnson, Genevieve Fuji; Durant, Darrin

    2009-01-01

    ... on FSC-certified ancient-forest-free paper (100 percent post-consumer recycled) that is processed chlorineand acid-free. Library and Archives Canada Cataloguing in Publication Nuclear waste management in Canada : critical issues, critical perspectives / edited by Darrin Durant and Genevieve Fuji Johnson. Includes bibliographical references an...

  17. Current Issues for Higher Education Information Resources Management.

    Science.gov (United States)

    CAUSE/EFFECT, 1996

    1996-01-01

    Issues identified as important to the future of information resources management and use in higher education include information policy in a networked environment, distributed computing, integrating information resources and college planning, benchmarking information technology, integrated digital libraries, technology integration in teaching,…

  18. School Discipline: Special Issues. School Management Handbook Number 2.

    Science.gov (United States)

    National Association of Elementary School Principals, Arlington, VA.

    This part of the School Management Handbook provides the elementary school administrator with an overview of civil rights issues affecting school discipline policy. The first section treats the requirements for providing due process and avoiding discrimination against minority groups when following disciplinary procedures. Section 2 covers…

  19. Getting Stakeholder Issues into the Management of Radioactive Waste

    International Nuclear Information System (INIS)

    Atherton, Elizabeth

    2001-01-01

    The issues raised in trying to develop long-term solution(s) for radioactive waste management are multidisciplinary - encompassing social, ethical, scientific and technical issues. Experience in the UK and elsewhere has shown that the process by which decisions are made needs to be accepted as being legitimate by all stakeholders. This paper argues that the key to achieving such acceptance is how one engages with stakeholders at the 'front-end' of any decision-making process. This paper focuses on radioactive waste management as the issue in question and outlines techniques that can be used during the 'front-end' consultation and gives examples of where they have been, and are being, used by Nirex

  20. Getting Stakeholder Issues into the Management of Radioactive Waste

    Energy Technology Data Exchange (ETDEWEB)

    Atherton, Elizabeth [UK Nirex Ltd, Didcot (United Kingdom)

    2001-07-01

    The issues raised in trying to develop long-term solution(s) for radioactive waste management are multidisciplinary - encompassing social, ethical, scientific and technical issues. Experience in the UK and elsewhere has shown that the process by which decisions are made needs to be accepted as being legitimate by all stakeholders. This paper argues that the key to achieving such acceptance is how one engages with stakeholders at the 'front-end' of any decision-making process. This paper focuses on radioactive waste management as the issue in question and outlines techniques that can be used during the 'front-end' consultation and gives examples of where they have been, and are being, used by Nirex.

  1. Management of spent nuclear fuel on the Oak Ridge Reservation, Oak Ridge, Tennessee: Environmental assessment

    International Nuclear Information System (INIS)

    1996-02-01

    On June 1, 1995, DOE issued a Record of Decision [60 Federal Register 28680] for the Department-wide management of spent nuclear fuel (SNF); regionalized storage of SNF by fuel type was selected as the preferred alternative. The proposed action evaluated in this environmental assessment is the management of SNF on the Oak Ridge Reservation (ORR) to implement this preferred alternative of regional storage. SNF would be retrieved from storage, transferred to a hot cell if segregation by fuel type and/or repackaging is required, loaded into casks, and shipped to off-site storage. The proposed action would also include construction and operation of a dry cask SNF storage facility on ORR, in case of inadequate SNF storage. Action is needed to enable DOE to continue operation of the High Flux Isotope Reactor, which generates SNF. This report addresses environmental impacts

  2. Waste management in space: a NASA symposium. Special issue

    Science.gov (United States)

    Wydeven, T. (Principal Investigator)

    1991-01-01

    This special issue contains papers from the NASA Symposium on Waste Processing for Advanced Life Support, which was held at NASA Ames Research Center on September 11-13, 1990. Specialists in waste management from academia, government, and industry convened to exchange ideas and advise NASA in developing effective methods for waste management in a Controlled Ecological Life Support System (CELSS). Innovative and well-established methods were presented to assist in developing and managing wastes in closed systems for future long-duration space missions, especially missions to Mars.

  3. Process management - critical safety issues with focus on risk management

    International Nuclear Information System (INIS)

    Sanne, Johan M.

    2005-12-01

    Organizational changes focused on process orientation are taking place among Swedish nuclear power plants, aiming at improving the operation. The Swedish Nuclear Power Inspectorate has identified a need for increased knowledge within the area for its regulatory activities. In order to analyze what process orientation imply for nuclear power plant safety a number of questions must be asked: 1. How is safety in nuclear power production created currently? What significance does the functional organization play? 2. How can organizational forms be analysed? What consequences does quality management have for work and for the enterprise? 3. Why should nuclear power plants be process oriented? Who are the customers and what are their customer values? Which customers are expected to contribute from process orientation? 4. What can one learn from process orientation in other safety critical systems? What is the effect on those features that currently create safety? 5. Could customer values increase for one customer without decreasing for other customers? What is the relationship between economic and safety interests from an increased process orientation? The deregulation of the electricity market have caused an interest in increased economic efficiency, which is the motivation for the interest in process orientation. among other means. It is the nuclear power plants' owners and the distributors (often the same corporations) that have the strongest interest in process orientation. If the functional organization and associated practices are decomposed, the prerequisites of the risk management regime changes, perhaps deteriorating its functionality. When nuclear power operators consider the introduction of process orientation, the Nuclear Power Inspectorate should require that 1. The operators perform a risk analysis beforehand concerning the potential consequences that process orientation might convey: the analysis should contain a model specifying how safety is currently

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

    International Nuclear Information System (INIS)

    Clausen, A.

    1988-01-01

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

  5. Historical fuel reprocessing and HLW management in Idaho

    International Nuclear Information System (INIS)

    Knecht, D.A.; Staiger, M.D.; Christian, J.D.

    1997-01-01

    This article review some of the key decision points in the historical development of spent fuel reprocessing and waste management practices at the Idaho Chemical Processing Plant that have helped ICPP to successfully accomplish its mission safely and with minimal impact on the environment. Topics include ICPP reprocessing development; batch aluminum-uranium dissolution; continuous aluminum uranium dissolution; batch zirconium dissolution; batch stainless steel dissolution; semicontinuous zirconium dissolution with soluble poison; electrolytic dissolution of stainless steel-clad fuel; graphite-based rover fuel processing; fluorinel fuel processing; ICPP waste management consideration and design decisions; calcination technology development; ICPP calcination demonstration and hot operations; NWCF design, construction, and operation; HLW immobilization technology development. 80 refs., 4 figs

  6. Introduction of HTR-PM Operation and Fuel Management System

    International Nuclear Information System (INIS)

    Liu Fucheng; Luo Yong; Gao Qiang

    2014-01-01

    There is a big difference between High Temperature Gas-cooled Reactor Pebble-modules Demonstration Project(HTR-PM) and PWR in operation mode. HTR-PM is a continually refuelled reactor, and the operation and fuel management of it, which affect each other, are inseparable. Therefore, the analysis of HTR-PM fuel management needs to be carried out “in real time”. HTR-PM operation and fuel management system is developed for on-power refuelling mode of HTR-PM. The system, which calculates the core neutron flux and power distribution, taking high-temperature reactor physics analysis software-VSOP as a basic tool, can track and predict the core state online, and it has the ability to restructure core power distribution online, making use of ex-core detectors to correct and check tracking calculation. Based on the ability to track and predict, it can compute the core parameters to provide support for the operation of the reactor. It can also predict the operation parameters of the reactor to provide reference information for the fuel management.The contents of this paper include the development purposes, architecture, the main function modules, running process, and the idea of how to use the system to carry out HTR-PM fuel management. (author)

  7. Fuel isolation research for the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    1982-06-01

    This document is intended to give a broad outline of the Fuel Isolatikn program and to indicate how this program fits into the overall framework of the Canadian Nuclear Fuel Waste Management Program. Similar activities in other countries are described, and the differences in philosophy behind these and the Canadian program are highlighted. A program plan is presented that outlines the development of research programs that contribute to the safety assessment of the disposal concept and the development of technology required for selection and optimization of a feasible fuel isolation system. Some indication of the work that might take place beyond concept assessment, at the end of the decade, is also given. The current program is described in some detail, with emphasis on what the prkgram has achieved to date and hopes to achieve in the future for the concept assessment phase of the waste management program. Finally, some major capital facilities associated with the fuel isolation program are described

  8. A Study on the Structural Integrity Issues of a Dual-Cooled Fuel Rod

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyung-Kyu; Lee, Kang-Hee; Lee, Young-Ho; Yoon, Kyung-Ho; Kim, Jae-Yong; Song, Kun-Woo [Korea Atomic Energy Research Institute, 1045 Daedeokdaero Yuseong Daejeon 305-353 (Korea, Republic of)

    2009-06-15

    A dual-cooled fuel rod has an internal coolant flow passage in addition to the external one. A remarkable power up-rate can be achieved due to the increased surface area, which may draw great interests from the fuel researchers, designers and vendors. However, it requires effective resolution to the difficult technical issues when a fuel assembly is to be realized. It becomes much more difficult if a tough boundary condition needs to be satisfied such as a compatibility with the existing reactor internal structures. This kind of challenge is tackled through a national R and D project in Korea: to develop the structural components of a dual-cooled fuel that should be compatible with the current OPR 1000 (Korea Standard Nuclear Power Plant) internal structures. Fuel rod supporting structures, top and bottom end pieces and guide tubes are the components. Besides, the fuel rod components have to be developed as well since the fuel rod's geometry becomes much different from the conventional rod's one. The dimension change may well affect the above mentioned structural components. As a part of the work, structural integrity of the components of a dual-cooled fuel rod is studied in this paper. The investigated topics are: i) the thickness determination of a cladding tube (especially outer tube of a large diameter), ii) vibration issue of an inner cladding tube, iii) design concern of plenum spring and spacer. The cladding thickness issue arises due to the increased outside diameter of a fuel rod, which is caused by an internal flow passage formation. Among the criteria for the thickness determination, an elastic buckling criteria was focused on. Theoretical background for the well-known formula (such as a stability problem) was revisited. Verification tests were carried out independently with using a cladding tube of PHWR fuel rod. Results showed that the formula was not conservative to apply for the cladding thickness determination. Minimum thickness for the

  9. How to manage sustainable supply chain? The issue of maturity

    Directory of Open Access Journals (Sweden)

    Agata Rudnicka

    2016-12-01

    Full Text Available Background: The issue of managing sustainability in supply chain seems to be more and more complex. There are many aspects that need to be taken into consideration when planning, implementing and monitoring environmental and social conditions of supply chains. Despite many works, already published, on the concept of sustainable development (SD is seems that the issue of assessment and especially the issue of maturity in the light of the SD concept is still not developed enough. Methods: The general aim of the paper is the analysis of the maturity issue in the context of sustainability. The main objective is to conceptualize the idea of maturity in sustainable supply chain. Beside the literature research the own proposition of theoretical model was described. Results: The article describes the issue of maturity as an element of managing sustainable development in the supply chain. The author presented a theoretical model of the maturity. Moreover the author gave some recommendations how to manage the sustainability issues in supply chain in more mature approach and introduced some useful tools among which are: certification, code of conduct and code of ethics, audits, projects etc. Conclusions: The issue of maturity seems to be very useful for proper understanding the idea of sustainable development in supply chain. The developed model can be used as self-assessment method to check at which level of implementation the idea of SD is analyzed in supply chain. Furthermore, the next phase of the planned research in form of practical verification of the model was advised as well as a research of identification of new factors and tools in analyzed area.

  10. Issues for the long term management of radioactive waste

    International Nuclear Information System (INIS)

    Schneider, T.; Schieber, C.; Lavelle, S.

    2006-01-01

    High-level radioactive waste are currently managed in interim storage installations, providing an adequate protection of the public and the workers for the short term period. However, the long-term persistence of the radioactivity of the waste gives a new timescale dimension, never experimented by the society for the development of protection systems. In the framework of the European Commission research project 'COWAM-2' (COmmunity WAste Management) dedicated to the governance of radioactive waste management, the issues of 'long term governance' have been addressed by exploring the elements which can contribute to a better integration of the technical and societal time dimensions, taking into account technical, ethical, economic and organizational considerations. The originality of this project is to address the various issues within working groups involving stakeholders from different origins and European countries together with a research team. After a discussion on the time dimensions to be taken into account from the technical and societal perspective, this paper presents, mainly based on the findings of the COWAM-2 project, a brief analysis of the ethical criteria to be considered when future generations are concerned as well as some performance criteria regarding long term governance. Finally, it proposes a discussion on the interest for the radiation protection experts to engage a process with stakeholders concerned by radioactive waste management in order to favour the emergence of a sustainable management responding to the issues at stake and including radiation protection considerations for long term periods. (authors)

  11. Issues for the long term management of radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, T.; Schieber, C. [CEPN, 92 - Fontenay-aux-Roses (France); Lavelle, S. [ICAM, 59 - Lille (France)

    2006-07-01

    High-level radioactive waste are currently managed in interim storage installations, providing an adequate protection of the public and the workers for the short term period. However, the long-term persistence of the radioactivity of the waste gives a new timescale dimension, never experimented by the society for the development of protection systems. In the framework of the European Commission research project 'COWAM-2' (COmmunity WAste Management) dedicated to the governance of radioactive waste management, the issues of 'long term governance' have been addressed by exploring the elements which can contribute to a better integration of the technical and societal time dimensions, taking into account technical, ethical, economic and organizational considerations. The originality of this project is to address the various issues within working groups involving stakeholders from different origins and European countries together with a research team. After a discussion on the time dimensions to be taken into account from the technical and societal perspective, this paper presents, mainly based on the findings of the COWAM-2 project, a brief analysis of the ethical criteria to be considered when future generations are concerned as well as some performance criteria regarding long term governance. Finally, it proposes a discussion on the interest for the radiation protection experts to engage a process with stakeholders concerned by radioactive waste management in order to favour the emergence of a sustainable management responding to the issues at stake and including radiation protection considerations for long term periods. (authors)

  12. Status of the Canadian Nuclear Fuel Waste Management Program

    International Nuclear Information System (INIS)

    Lyon, R.B.

    1985-10-01

    The Canadian Nuclear Fuel Waste Management Program is in the fifth year of a ten-year generic research and development phase. The major objective of this phase of the program is to assess the basic safety and environmental aspects of the concept of isolating immobilized fuel waste by deep underground disposal in plutonic rock. The major scientific and engineering components of the program, namely immobilization studies, geoscience research, and environmental and safety assessment, are well established

  13. Interactive color graphics system for BWR fuel management

    International Nuclear Information System (INIS)

    Reese, A.P.

    1986-01-01

    An interactive color graphics system has been developed by the General Electric Company for fuel management engineers. The system consists of a Hewlett-Packard color graphics workstation in communication with a host mainframe. The system aids in such tasks as fuel cycle optimization, refueling bundle shuffle and control blade sequence design. Since being installed in 1983 turn-around time for a typical cycle reload and control blade pattern design has been reduced by a factor of four

  14. A comparative study of fuel management in PWR reactors

    International Nuclear Information System (INIS)

    Barroso, D.E.G.; Nair, R.P.K.; Vellozo, S.O.

    1981-01-01

    A study about fuel management in PWR reactors, where not only the conventional uranium cycle is considered, but also the thorium cycle as an alternative is presented. The final results are presented in terms of U 3 O 8 demand and SWU and the approximate costs of the principal stages of the fuel cycle, comparing with the stardand cycle without recycling. (E.G.) [pt

  15. Value issues and stakeholders' views in radioactive waste management

    International Nuclear Information System (INIS)

    Colglazier, E.W.; Dungan, D.L.; Reaven, S.J.

    1987-01-01

    The authors review a study in progress that is examining the role played by ethical and value issues in high-level and low-level radioactive waste management. For each policy issue, they attempt to separate its ''value concerns'' into three categories, called procedural, distributional, and evidential aspects. These categories refer to concerns about fairness and appropriateness of process, outcomes, and scientific evidence, respectively. For each value concern, attempt to state the rationale used by key stakeholder groups in justifying their policy positions and to extract the ''underlying general principles'' (UGP's) that appear to be the basis for the arguments. By examining patterns of UGP's across groups for an issue, and across issues for a group, the authors hope to explain the patterns of UGP's in terms of more fundamental attributes of stakeholders' ''world views'' and notions about science and society

  16. Fuels planning: science synthesis and integration; social issues fact sheet 14: Landscape preference in forested ecosystems

    Science.gov (United States)

    Christine Esposito

    2006-01-01

    It is important to understand what types of landscape settings most people prefer to be able to plan fuels treatment and other forest management activities that will be acceptable to the general public. This fact sheet considers the four common elements of visually preferred forest settings: large trees; herbacious, smooth groundcover; open midstory canopy; and vistas...

  17. Key management issue in SCADA networks: A review

    Directory of Open Access Journals (Sweden)

    Abdalhossein Rezai

    2017-02-01

    Full Text Available Supervisory Control And Data Acquisition (SCADA networks have a vital role in Critical Infrastructures (CIs such as public transports, power generation systems, gas, water and oil industries, so that there are concerns on security issues in these networks. The utilized Remote Terminal Units (RTUs and Intelligence Electronic Devices (IEDs in these networks have resource limitations, which make security applications a challenging issue. Efficient key management schemes are required besides lightweight ciphers for securing the SCADA communications. Many key management schemes have been developed to address the tradeoff between SCADA constrain and security, but which scheme is the most effective is still debatable. This paper presents a review of the existing key management schemes in SCADA networks, which provides directions for further researches in this field.

  18. Physics operating experience and fuel management of RAPS-1

    International Nuclear Information System (INIS)

    Nakra, A.N.; Purandare, H.D.; Srinivasan, K.R.; Rastogi, B.P.

    1976-01-01

    Rajasthan Atomic Power Station Unit-1 achieved criticality on August 11, 1972. Thereafter the reactor was brought to power, in November, 1972. Due to non-availability of the depleted fuel, the loading of which was necessary to obtain full power to begin with, the core was loaded with all natural uranium fuel and only 70% of the full power could be achieved. During the reactor operation for the last three years, the reactor has seen more than one effective full power year and about 1400 fresh fuel bundles have been loaded in the core. The reactor was subjected to about 150 power cycles resulting in more than 30% variation in operating power level and about 10 fuel bundles have failed. For satisfactory fuel management and refuelling decisions, a three dimensional simulator TRIVENI was developed. This was extensively tested during the start-up experiments and was found to be a satisfactory tool for day to day operation of the plant. In this paper, a brief account of analysis of the start-up experiments, approach to full power, power distortions and flux peaking, fuel management service and analysis of the failed fuel data has been given. (author)

  19. LWR Spent Fuel Management for the Smooth Deployment of FBR

    International Nuclear Information System (INIS)

    Fukasawa, T.; Yamashita, J.; Hoshino, K.; Sasahira, A.; Inoue, T.; Minato, K.; Sato, S.

    2015-01-01

    Fast breeder reactors (FBR) and FBR fuel cycle are indispensable to prevent the global warming and to secure the long-term energy supply. Commercial FBR expects to be deployed from around 2050 until around 2110 in Japan by the replacement of light water reactors (LWR) after their 60 years life. The FBR deployment needs Pu (MOX) from the LWR-spent fuel (SF) reprocessing. As Japan can posses little excess Pu, its balance control is necessary between LWR-SF management (reprocessing) and FBR deployment. The fuel cycle systems were investigated for the smooth FBR deployment and the effectiveness of proposed flexible system was clarified in this work. (author)

  20. Fuel management simulation for CANFLEX-RU in CANDU 6

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Chang Joon; Suk, Ho Chun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    Fuel management simulations have been performed for CANFLEX-09% RU fuel in the CANDU 6 reactor. In this study, the bi-directional 4-bundle shift fuelling scheme was assumed. The lattice cell and time-average calculation were carried out. The refuelling simulation calculations were performed for 600 full power days. Time-averaged results show good axial power profile with the CANFLEX-RU fuel. During the simulation period, the maximum channel and bundle power were maintained below the licensing limit of CANDU 6 reactor. 7 refs., 4 figs. (Author)

  1. Review of the nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Hatcher, S.R.

    1980-06-01

    Progress over the previous year in the nuclear fuel waste management program is reviewed. Universities, industry and consultants have become increasingly involved, and the work is being overseen by a Technical Advisory Committee. The program has also been investigated by Ontario's Porter Commission and Select Committe on Ontario Hydro Affairs. A public information program has been extended to cover most of the Canadian Shield region of Ontario. Ontario Hydro is studying spent fuel storage and transportation, while AECL is covering immobilization of spent fuel or processing wastes, geotechnical and geochemical research in the laboratory and in the field, design of disposal facilities, and environmental and safety assessments. (L.L.)

  2. Fuel management simulation for CANFLEX-RU in CANDU 6

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Chang Joon; Suk, Ho Chun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1998-12-31

    Fuel management simulations have been performed for CANFLEX-09% RU fuel in the CANDU 6 reactor. In this study, the bi-directional 4-bundle shift fuelling scheme was assumed. The lattice cell and time-average calculation were carried out. The refuelling simulation calculations were performed for 600 full power days. Time-averaged results show good axial power profile with the CANFLEX-RU fuel. During the simulation period, the maximum channel and bundle power were maintained below the licensing limit of CANDU 6 reactor. 7 refs., 4 figs. (Author)

  3. Management and disposal of spent nuclear fuel

    International Nuclear Information System (INIS)

    1987-05-01

    The programme consists of the long-term and short-term programme, the continued bedrock investigations, the underground research laboratory, the decision-making procedure in the site selection process and information questions during the site selection process. The National Board for Spent Nuclear Fuel hereby subunits both the SKB's R and D Programme 86 and the Board's statement concerning the programme. Decisions in the matter have been made by the Board's executive committee. (DG)

  4. Long-term management of radioactive waste - will the Price-Anderson system work for third party liability issues arising from the Nuclear Waste Policy Act of 1982

    International Nuclear Information System (INIS)

    Kuznick, S.K.

    1985-01-01

    Two pieces of legislation have been enacted in the United States to provide a framework for the management of radioactive waste and spent nuclear fuel: the Low-level Radioactive Waste Policy Act (1980) and the Nuclear Waste Policy Act of 1982. Neither of these statutes provide a means for resolving third party liability issues arising out of radioactive waste management. However, the Price Anderson Act (originally enacted in 1957) provides a system of financial protection that can be applied to waste management activities and that can resolve most issues pertaining to liability for nuclear damage that may result from long-term management of radioactive waste and spent nuclear fuel. (NEA) [fr

  5. Management of spent fuel in Republic of Korea

    International Nuclear Information System (INIS)

    Pak, Hyun-Soo; Seo, In-Seok; Pak, Sang-Ki.

    1989-01-01

    At present in Republic of Korea, 8 PWR and 1 CANDU power plants are in operation or under construction, and the total capacity of power generation facilities has become 7.6 GWe. In addition, two PWRs of more than 900 MWe each are expected to be constructed by mid 1990s. More than 50 % of the electric power demand was supplied by nuclear power generation since 1987, but the spent fuel generated in nuclear power plants is stored in storage water tanks in respective reactor sites. The total capacity of spent fuel to be stored in the AR facilities of 9 nuclear power plants is about 2730 MTU, and the spent fuel released from these reactors since 1980 is about 810 MTU. The present capacity of AR storage pools seems to be used up by mid 1990s. According to the revised Atomic Energy Acts in May, 1986, the government is to take the responsibility of spent fuel management, and the policy of constructing the storage facilities outside reactor sites by the end of 1997 was established by the Atomic Energy Commission. The responsibility of the management of spent fuel that exceeds the present capacity of AR pools is to be taken by KEPCO, therefore the preliminary analysis of the feasible option on the extension of AR facilities and the comprehensive management plan for spent fuel placing emphasis on the research and development of away-from-reactor storage were decided. (Kako, I.)

  6. Effect of advanced fuel cycles on waste management policies

    International Nuclear Information System (INIS)

    Cavedon, J.M.; Haapalehto, T.

    2005-01-01

    The study aims at analysing a range of future fuel cycle options from the perspective of their impact on waste repository demand and specification. The study would focus on: Assessment of the characteristics of radioactive wastes arising from advanced nuclear fuel cycle options, repository performance analysis studies using source terms for waste arising from such advanced nuclear fuel cycles, identification of new options for waste management and disposal. Three families of fuel cycles having increasing recycling capabilities are assessed. Each cycle is composed of waste generating and management processes. Examples of waste generating processes are fuel factories (7 types) and reprocessing plants (7 types). Packaging and conditioning plants (7) and disposal facilities are examples of waste management processes. The characteristic of all these processes have been described and then total waste flows are summarised. In order to simplify the situation, three waste categories have been defined based on the IAEA definitions in order to emphasize the major effects of different types of waste. These categories are: short-life waste for surface or sub-surface disposal, long-life low heat producing waste for geological disposal, high-level waste for geological disposal. The feasibilities of the fuel cycles are compared in terms of economics, primary resource consumption and amount of waste generated. The effect of high-level waste composition for the repository performance is one of the tools in these comparisons. The results of this will be published as an NEA publication before the end of 2005. (authors)

  7. Mutual influences of reactor operation and fuel cycle management

    International Nuclear Information System (INIS)

    Lewiner, C.; Schaerer, R.

    1989-01-01

    OPEN (Organisation des Producteurs d'Energie Nucleaire) comprises the electricity producers from seven European countries which now operate or intend to operate nuclear power plants. Its activities include the study of technical, economic and legal subjects related to nuclear electricity. A continuous analysis of the fuel cycle market has been pursued within OPEN for almost 15 years. For the past few years, OPEN has also been concerned with the subject of fuel management in the reactors operated by its members. The purpose of this effort was to obtain an overall picture of possible fuel improvements and to evaluate the effects, in particular the economic ones, of diverse fuel reload managements and of reprocessed uranium and plutonium recycling. The conclusions of this study are as follows: Increase in burn-ups produces notable savings in electricity generating costs. It also permits adaptation of fuel loading mode to the desirable irradiation campaign length. This allows for better management of the country's overall means of electricity generation (nuclear, fossil-fuelled or hydro plants), and adjustment to the electrical demand. These new reload schemes have various impacts on natural uranium consumption and enrichment, but, above all, they affect directly all fuel cycle operations linked to the number of assemblies (fabrication, reprocessing, etc.). 6 figs

  8. A durable and dependable solution for RTR spent fuel management

    International Nuclear Information System (INIS)

    Thomasson, J.

    1999-01-01

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

  9. Review on Malaysian Rail Transit Operation and Management System: Issues and Solution in Integration

    Science.gov (United States)

    Masirin, Mohd Idrus Mohd; Salin, Aminah Mohd; Zainorabidin, Adnan; Martin, David; Samsuddin, Norshakina

    2017-08-01

    In any context, operation and management of transportation systems are key issues which may affect both life quality and economic development. In large urban agglomerations, an efficient public transportation system may help abate the negative externalities of private car use such as congestion, air and noise pollution, accident and fuel consumption, without excessively penalizing user travel times or zone accessibility. Thus, this study is conducted to appraise the Malaysian rural rail transit operation and management system, which are considered important as there are many issues and solution in integration of the services that need to be tackled more conscientiously. The purpose of this paper is to describe some of the most important issues on integration of services and rail transit system in Malaysian and how to solve or reduce these problems and conflicts. In this paper, it consists of the historical development of rail transit construction in Malaysia. This paper also attempts to identify the important issues related to rail transit services and integration in Malaysian rural rail operation and management system. Comparison is also conducted with other countries such as UK, France, and Japan. Finally, a critical analysis is presented in this paper by looking at the possible application for future Malaysian rail transit operation system and management, especially focusing on enhancing the quality of Malaysian rural rail transit. In conclusion, this paper is expected to successfully review and appraise the existing Malaysian rural rail transit operation and management system pertaining to issues & solution in integration. It is also hoped that reformation or transformation of present service delivery quality of the rail transit operation and management will enable Malaysia to succeed in transforming Malaysian transportation system to greater heights.

  10. Considerations Regarding ROK Spent Nuclear Fuel Management Options

    International Nuclear Information System (INIS)

    Braun, Chaim; Forrest, Robert

    2013-01-01

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

  11. Nuclear power, nuclear fuel cycle and waste management, 1986-1999. International Atomic Energy Agency publications

    International Nuclear Information System (INIS)

    2000-04-01

    This catalogue lists all sales publications of the International Atomic Energy Agency dealing with nuclear power and nuclear fuel cycle and waste management and issued during the period of 1986-1999. Some earlier titles which form part of an established series or are still considered of importance have been included. Most publications are in English. Proceedings of conferences, symposia and panels of experts may contain papers in languages other than English, but all of these papers have abstracts in English

  12. Nuclear and radiological safety nuclear power nuclear fuel cycle and waste management

    International Nuclear Information System (INIS)

    1997-05-01

    This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Nuclear and Radiological Safety, Nuclear Power and Nuclear Fuel Cycle and Waste Management and issued during the period of 1995-1996. Most publications are in English. Proceedings of conferences, symposia and panels of experts may contain some papers in languages other than English (Arabic, Chinese, French, Russian or Spanish), but all these papers have abstracts in English

  13. Canadian high-level radioactive waste management system issues

    International Nuclear Information System (INIS)

    Allan, C.J.; Gray, B.R.

    1992-01-01

    In Canada responsibility for the management of radioactive wastes rests with the producer of those wastes. This fundamental principle applies to such diverse wastes as uranium mine and mill tailings, low-level wastes from universities and hospitals, wastes produced at nuclear research establishments, and wastes produced at nuclear generating stations. The federal government has accepted responsibility for historical wastes for which the original producer can no longer be held accountable. Management of radioactive wastes is subject to the regulatory control of the Atomic Energy Control Board, the federal agency responsible for regulating the nuclear industry. In this paper the authors summarize the current situation concerning the management of high level (used nuclear fuel) wastes. In 1981 the two governments also announced that selection of a disposal site would not proceed, and responsibility for site selection and operation would not be assigned until the Concept for used fuel disposal had been reviewed and assessed. Thus the concept assessment is generic rather than site specific. The Concept that has been developed has been designed to conform with safety and performance criteria established by the Atomic Energy Control Board. It is based on burial deep in plutonic rock of the Canadian Shield, using a multi-barrier approach with a series of engineered and natural barriers: these include the waste form, container, buffer and backfill, and the host rock

  14. U.S. nuclear fuel cycle regulatory issues on exclusion, exemption, and clearance

    International Nuclear Information System (INIS)

    Meck, R.A.

    1997-01-01

    The U.S. Nuclear Regulatory Commission is considering the use of exclusion and clearance in connection with the nuclear fuel cycle regulations. Clearance of licensed lands, buildings, structures, materials, and equipment could expose members of the public to radiation in addition to background. Establishing and implementing dose criteria for allowed concentrations of radioactivity in the various media raise challenging issues for the regulator. Clearance also raises significant regulatory issues, and these issues reflect trade-offs between concerns for protecting public health and safety, as well as other socioeconomic values and concerns. At the heart of the issues are the adequacy of risk analyses, acceptability of risks, underlying rationales, feasibility and cost of implementation, and exposures of the public to man-made radiation in relation to natural sources of radiation. (author)

  15. Spent Nuclear Fuel Project Configuration Management Plan

    International Nuclear Information System (INIS)

    Reilly, M.A.

    1995-01-01

    This document is a rewrite of the draft ''C'' that was agreed to ''in principle'' by SNF Project level 2 managers on EDT 609835, dated March 1995 (not released). The implementation process philosphy was changed in keeping with the ongoing reengineering of the WHC Controlled Manuals to achieve configuration management within the SNF Project

  16. Spent Nuclear Fuel Project Document Management Plan

    International Nuclear Information System (INIS)

    Connor, M.D.; Harizison, G.L.; Rice, W.C.

    1995-12-01

    The SNF Project Document Management Plan identifies and describes the currently available systems and processes for implementing and maintaining an effective document control and records management program. This program governs the methods by which documents are generated, released, distributed, maintained current, retired, and ultimately disposed

  17. 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).

  18. Problems in complying with regulations related to low activity materials: Nuclear fuel cycle issues

    International Nuclear Information System (INIS)

    Coates, R.

    1997-01-01

    The range of issues relating to exemption and clearance within the nuclear fuel cycle is reviewed. It is concluded that current regulatory systems and the underpinning technical criteria are potentially inflexible and over-conservative, resulting in an imbalance in the use of society's resources. Proposals are developed for establishing practical requirements which would ensure that resource allocation is commensurate with the magnitude of the risks and in broad proportion to the other risks affecting society. Such an approach would be consistent with the concept of sustainability and could support wider public acceptance of these issues. Within this approach the practical distinction between exemption and clearance is challenged. (author)

  19. An overview on the nuclear spent fuel management in Romania

    International Nuclear Information System (INIS)

    Radu, M.

    2001-01-01

    The sources of radioactive waste in Romania are users of radiation and radioactive materials in industry (including nuclear electricity generation), medicine, agriculture and research and also the processing of materials that are naturally radioactive, such as uranium ores. The different types of radioactive waste are classified into four categories of waste: excepted waste, low level waste, medium level waste and high level waste. A spent fuel management sub-programme as a part of the Radioactive Waste Management programme was initiated by the former Romanian Electricity Company (RENEL) in 1992. Within the frame of R and D of the Radioactive Waste and Spent Fuel Management Programme, the topics cover investigations, studies and research to identify the sites and the conceptual designs for a Spent Fuel Interim Storage Facility (SFISF) and also a Spent Fuel Disposal Facility (SFDF). Changes in the organization of the nuclear activities of RENEL, involving both responsibilities and financing aspects, led to interruption of the programme. The programme includes study of the main methods and the existing technologies for the design, operation and safety of an interim storage facility (including transport aspects). It also includes analysis of details on the site selection for this facility and for a spent fuel final disposal facility. The achievement of the spent fuel interim storage facility is proceeding. The results from the studies performed in the last years will permit us to prepare the feasibility study next year and the documentation required by our regulatory body for starting the process to obtain a license for a SFISF at Cernavoda. A second phase is the assessment of a long term strategy to select and adopt a proven disposal technology for spent fuel, corresponding with a selected site. The status of the work performed in the frame of this programme and also the situation of the spent fuel from research reactors are presented. (author)

  20. Research reactor utilization, safety, decommissioning, fuel and waste management. Posters of an international conference

    International Nuclear Information System (INIS)

    2005-01-01

    self assessments. Current developments in research reactor design criteria. Calculation methods and codes. Regulatory aspects and experience with current research reactor issues. Quality assurance programmes during the various stages of a reactor life. Training and qualification of reactor operating personnel and regulators. Modifications in operating procedures and training and qualification. In-service and special inspections with respect to ageing. c) Fuel cycle issues covering new high-density fuel development. Fuel fabrication and performance. Fuel qualification programmes. Core conversion. Fuel management (including spent fuel storage). Spent fuel transportation. Final disposition. d) Reactor Decommissioning including Preliminary decommissioning planning (long term). Creation of data base for decommissioning (e.g. during refurbishment). Final decommissioning planning. Extensive research and development activities associated with decommissioning of research reactors. On-going/recently completed research reactor decommissioning projects. e) Waste management (operational waste management) and decommissioning waste management

  1. Management of spent oxide fuel from thermal reactors: the environmental and radiological effects of alternative approaches

    International Nuclear Information System (INIS)

    Martin, A.; Fry, T.M.; Edmunds, J.

    1983-07-01

    The report presents the results of a study of the environmental and radiological effects of alternative approaches to the management of spent oxide fuel from the UK nuclear power programme. The two main alternatives are extended storage of the fuel, pending decisions on fissile material recycle, and reprocessing of the fuel commencing in the early 1990s. A review is made of experience in spent fuel storage, of the technical issues in long-term storage and of the possible needs of the UK nuclear programme. The main environmental and radiological effects of reprocessing considered in the study are the generation of radioactive wastes, the release of radioactivity in effluents with the resulting radiation exposure of the public, and occupational radiation exposure. The influence of the delay between reprocessing and fabrication of mixed oxide fuel on the environmental and radiological effects of plutonium recycle is investigated and it is shown that the effects would be minimised if reprocessing were delayed until there was a requirement for recycle. Strategies for the management of heavy elements other than plutonium are discussed and results are presented illustrating aspects of actinide management. (author)

  2. CRACKEL: a computer code for CFR fuel management calculations

    International Nuclear Information System (INIS)

    Burstall, R.F.; Ball, M.A.; Thornton, D.E.J.

    1975-12-01

    The CRACKLE computer code is designed to perform rapid fuel management surveys of CFR systems. The code calculates overall features such as reactivity, power distributions and breeding gain, and also calculates for each sub-assembly plutonium content and power output. A number of alternative options are built into the code, in order to permit different fuel management strategies to be calculated, and to perform more detailed calculations when necessary. A brief description is given of the methods of calculation, and the input facilities of CRACKLE, with examples. (author)

  3. Program summary. Nuclear waste management and fuel cycle programs

    International Nuclear Information System (INIS)

    1982-07-01

    This Program Summary Document describes the US Department of Energy (DOE) Nuclear Waste Management and Fuel Cycle Programs. Particular emphasis is given to near-term, specifically Fiscal Year (FY) 1982, activities. The overall objective of these programs will be achieved by the demonstration of: (1) safe radioactive waste management practices for storage and disposal of high-level waste and (2) advanced technologies necessary to close the nuclear fuel cycle on a schedule which would assure a healthy future for the development of nuclear power in this country

  4. Overview of the spent fuel management policy in Finland

    International Nuclear Information System (INIS)

    Manninen, Jussi

    1985-01-01

    The basic factors affecting the spent fuel management policy are highlighted: small size of the nuclear programme in the worldwide scale, no recycling of plutonium envisaged, no governmental organizations for back-end operations foreseen. The prinsiple objective of the policy permanent disposal of high-level wastes irrevocably outside the domestic territory, and the limited success in its implementation are discussed. The preparations of the implementation of the back-up alternative, direct disposal of spent fuel in the Finnish bedrock are described. The basic philosophy behind the system of funding the future waste management costs is clarified. (author)

  5. Reactivity management and burn-up management on JRR-3 silicide-fuel-core

    International Nuclear Information System (INIS)

    Kato, Tomoaki; Araki, Masaaki; Izumo, Hironobu; Kinase, Masami; Torii, Yoshiya; Murayama, Yoji

    2007-08-01

    On the conversion from uranium-aluminum-dispersion-type fuel (aluminide fuel) to uranium-silicon-aluminum-dispersion-type fuel (silicide fuel), uranium density was increased from 2.2 to 4.8 g/cm 3 with keeping uranium-235 enrichment of 20%. So, burnable absorbers (cadmium wire) were introduced for decreasing excess reactivity caused by the increasing of uranium density. The burnable absorbers influence reactivity during reactor operation. So, the burning of the burnable absorbers was studied and the influence on reactor operation was made cleared. Furthermore, necessary excess reactivity on beginning of operation cycle and the time limit for restart after unplanned reactor shutdown was calculated. On the conversion, limit of fuel burn-up was increased from 50% to 60%. And the fuel exchange procedure was changed from the six-batch dispersion procedure to the fuel burn-up management procedure. The previous estimation of fuel burn-up was required for the planning of fuel exchange, so that the estimation was carried out by means of past operation data. Finally, a new fuel exchange procedure was proposed for effective use of fuel elements. On the procedure, burn-up of spent fuel was defined for each loading position. The average length of fuel's staying in the core can be increased by two percent on the procedure. (author)

  6. Waste management, final waste disposal, fuel cycle

    International Nuclear Information System (INIS)

    Rengeling, H.W.

    1991-01-01

    Out of the legal poblems that are currently at issue, individual questions from four areas are dealt with: privatization of ultimate waste disposal; distribution of responsibilities for tasks in the field of waste disposal; harmonization and systematization of regulations; waste disposal - principles for making provisions for waste disposal - proof of having made provisions for waste disposal; financing and fees. A distinction has to be made between that which is legally and in particular constitutionally imperative or, as the case may be, permissible, and issues where there is room for political decision-making. Ultimately, the deliberations on the amendment are completely confined to the sphere of politics. (orig./HSCH) [de

  7. U.S. -- EC fuel cycle study: Background document to the approach and issues

    Energy Technology Data Exchange (ETDEWEB)

    Cantor, Robin; Russell, Lee; Krupnick, Alan; Smith, Hilary; Schaffhauser, Jr., A.; Barnthouse, Larry; Cada, Glen; Kroodsma, Roger; Turner, Robb; Easterly, Clay; Jones, Troyce; Burtraw, Dallas; Harrington, Winston; Freeman, A. Myrick

    1992-11-01

    In February 1991, DOE and the Commission of the European Communities (EC), signed a joint statement regarding the external costs of fuel cycles. This 18-month agreement committed their respective organizations to develop a comparative analytical methodology and to develop the best range of estimates of external costs from secondary sources'' for eight fuel cycles and four conservation options. In our study, a fuel cycle is defined as the series of physical and chemical processes and activities that are required to generate electricity from a specific fuel or resource. This foundation phase of the study is primarily limited to developing and demonstrating methods for estimating impacts and their monetized value, what we term damages'' or benefits,'' leaving aside the extent to which such damages have been internalized. However, Appendix C provides the conceptual framework for evaluating the extent of internalization. This report is a background document to introduce the study approach and to discuss the major conceptual and practical issues entailed by the incremental damage problem. As a background document, the report seeks to communicate an overview of the study and the important methodological choices that were made to conduct the research. In successive sections of the report, the methodological tools used in the study are discussed; the ecological and health impacts are reviewed using the coal fuel cycle as a reference case; and, in the final chapter, the methods for valuing impacts are detailed.

  8. US--EC fuel cycle study: Background document to the approach and issues

    International Nuclear Information System (INIS)

    1992-11-01

    In February 1991, DOE and the Commission of the European Communities (EC), signed a joint statement regarding the external costs of fuel cycles. This 18-month agreement committed their respective organizations to ''develop a comparative analytical methodology and to develop the best range of estimates of external costs from secondary sources'' for eight fuel cycles and four conservation options. In our study, a fuel cycle is defined as the series of physical and chemical processes and activities that are required to generate electricity from a specific fuel or resource. This foundation phase of the study is primarily limited to developing and demonstrating methods for estimating impacts and their monetized value, what we term ''damages'' or ''benefits,'' leaving aside the extent to which such damages have been internalized. However, Appendix C provides the conceptual framework for evaluating the extent of internalization. This report is a background document to introduce the study approach and to discuss the major conceptual and practical issues entailed by the incremental damage problem. As a background document, the report seeks to communicate an overview of the study and the important methodological choices that were made to conduct the research. In successive sections of the report, the methodological tools used in the study are discussed; the ecological and health impacts are reviewed using the coal fuel cycle as a reference case; and, in the final chapter, the methods for valuing impacts are detailed

  9. Modeling Water Management in Polymer-Electrolyte Fuel Cells

    Energy Technology Data Exchange (ETDEWEB)

    Department of Chemical Engineering, University of California, Berkeley; Weber, Adam; Weber, Adam Z.; Balliet, Ryan; Gunterman, Haluna P.; Newman, John

    2007-09-07

    on the cathode) and the resulting effects of the kinetic reactions. Next, at low currents, the behavior of a PEFC is dominated by kinetic losses. These losses mainly stem from the high overpotential of the oxygen-reduction reaction (ORR). As the current is increased, ohmic losses become a factor in lowering the overall cell potential. These ohmic losses are mainly from ionic losses in the electrodes and separator. At high currents, mass-transport limitations become increasingly important. These losses are due to reactants not being able to reach the electrocatalytic sites. Key among the issues facing PEFCs today is water management. Due to their low operating temperature (< 100 C), water exists in both liquid and vapor phases. Furthermore, state-of-the-art membranes require the use of water to provide high conductivity and fast proton transport. Thus, there is a tradeoff between having enough water for proton conduction (ohmic losses), but not too much or else the buildup of liquid water will cause a situation in which the reactant-gas-transport pathways are flooded (mass-transfer limitations). Figure 3 displays experimental evidence of the effects of water management on performance. In Figure 3(a), a neutron image of water content displays flooding near the outlet of the cell due to accumulation of liquid water and a decrease in the gas flowrates. The serpentine flow field is clearly visible with the water mainly underneath the ribs. Figure 3(b) shows polarization performance at 0.4 and 0.8 V and high-frequency resistance at 0.8 V as a function of cathode humidification temperature. At low current densities, as the inlet air becomes more humid, the membrane resistance decreases, and the performance increases. At higher current densities, the same effect occurs; however, the higher temperatures and more humid air also results in a lower inlet oxygen partial pressure.

  10. Current status on the spent fuel dry storage management in Taiwan

    International Nuclear Information System (INIS)

    Chen, H.T.; Liu, C.H.

    2006-01-01

    Full text: Full text: One of the high priority issues for the continuous operation of nuclear power plants is how to manage and store spent fuel. In recent years, interim dry storage of spent fuel has become a significant solution in extending the storage capacity at a nuclear reactor site that lacks sufficient spent fuel pool storage capacity as in the world, and also in Taiwan. Although the re-racking project for the spent fuel pools has been undertaken, the Taiwan Power Company (TPC) Chinshan nuclear power plant still will lose its full core reserve by the year 2010. TPC has declared to build an on-site interim dry storage facility, this followed by geological disposal represents the most suitable option at this time. TPC is expected to submit the application for construction permit in 2006; preoperational test and storage should be put into operation by the end of 2008. Interim dry storage is a passive system. Materials used play a crucial role in the safety function of cask. The competent authority of spent fuel management in Taiwan, FCMA/AEC, will carry out a confirmatory evaluation regarding heat dissipation, structural seismic analysis, and radiation shielding to assure available safety function for casks after reviewing safety analysis report submitted by TPC. Third party inspection has been required to enhance quality assurance program and foreign technical consultation will be arranged. Although the security level for such facility will be kept to the same level as an NPP, a comprehensive analysis against a commercial airplane attack on cask should be made and addressed in the supplement of SAR. Licensing hearing is also required before issuing the construction permit. The paper presents the review plan and regulatory requirements for the licensing of an interim dry storage of spent fuel, the licensing procedure, and the development of dry storage cask for spent fuel in Taiwan

  11. Solid Waste Management in Nigeria: Problems and Issues.

    Science.gov (United States)

    AGUNWAMBA

    1998-11-01

    / This paper is a presentation of the problems of solid waste management in Nigeria and certain important issues that must be addressed in order to achieve success. At the core of the problems of solid waste management are the absence of adequate policies, enabling legislation, and an environmentally stimulated and enlightened public. Government policies on the environment are piecemeal where they exist and are poorly implemented. Public enlightenment programs lacked the needed coverage, intensity, and continuity to correct the apathetic public attitude towards the environment. Up to now the activities of the state environmental agencies have been hampered by poor funding, inadequate facilities and human resources, inappropriate technology, and an inequitable taxation system. Successful solid waste management in Nigeria will require a holistic program that will integrate all the technical, economic, social, cultural, and psychological factors that are often ignored in solid waste programs.KEY WORDS: Solid waste; Management; Problems; Solutions; Nigeria

  12. Japan's spent fuel and plutonium management challenge

    International Nuclear Information System (INIS)

    Katsuta, Tadahiro; Suzuki, Tatsujiro

    2011-01-01

    Japan's commitment to plutonium recycling has been explicitly stated in its long-term program since 1956. Despite the clear cost disadvantage compared with direct disposal or storage of spent fuel, the Rokkasho reprocessing plant started active testing in 2006. Japan's cumulative consumption of plutonium has been only 5 tons to date and its future consumption rate is still uncertain. But once the Rokkasho reprocessing plant starts its full operation, Japan will separate about 8 tons of plutonium annually. Our analysis shows that, with optimum use of available at-reactor and away-from-reactor storage capacity, there would be no need for reprocessing until the mid-2020s. With an additional 30,000 tons of away-from-reactor (AFR) spent-fuel storage capacity reprocessing could be avoided until 2050. Deferring operation of the Rokkasho plant, at least until the plutonium stockpile had been worked down to the minimum required level, would also minimize international concern about Japan's plutonium stockpile. The authors are happy to acknowledge Frank von Hippel, Harold Feiveson, Jungming Kang, Zia Mian, M.V. Ramana, and other IPFM members, as well as the generous grant from the MacArthur Foundation for helping make this research possible.

  13. Analysis of fuel management in the KIPT neutron source facility

    Energy Technology Data Exchange (ETDEWEB)

    Zhong Zhaopeng, E-mail: zzhong@anl.gov [Nuclear Engineering Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States); Gohar, Yousry; Talamo, Alberto [Nuclear Engineering Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States)

    2011-05-15

    Research highlights: > Fuel management of KIPT ADS was analyzed. > Core arrangement was shuffled in stage wise. > New fuel assemblies was added into core periodically. > Beryllium reflector could also be utilized to increase the fuel life. - Abstract: Argonne National Laboratory (ANL) of USA and Kharkov Institute of Physics and Technology (KIPT) of Ukraine have been collaborating on the conceptual design development of an experimental neutron source facility consisting of an electron accelerator driven sub-critical assembly. The neutron source driving the sub-critical assembly is generated from the interaction of 100 KW electron beam with a natural uranium target. The sub-critical assembly surrounding the target is fueled with low enriched WWR-M2 type hexagonal fuel assemblies. The U-235 enrichment of the fuel material is <20%. The facility will be utilized for basic and applied research, producing medical isotopes, and training young specialists. With the 100 KW electron beam power, the total thermal power of the facility is {approx}360 kW including the fission power of {approx}260 kW. The burnup of the fissile materials and the buildup of fission products continuously reduce the system reactivity during the operation, decrease the neutron flux level, and consequently impact the facility performance. To preserve the neutron flux level during the operation, the fuel assemblies should be added and shuffled for compensating the lost reactivity caused by burnup. Beryllium reflector could also be utilized to increase the fuel life time in the sub-critical core. This paper studies the fuel cycles and shuffling schemes of the fuel assemblies of the sub-critical assembly to preserve the system reactivity and the neutron flux level during the operation.

  14. Analysis of fuel management in the KIPT neutron source facility

    International Nuclear Information System (INIS)

    Zhong Zhaopeng; Gohar, Yousry; Talamo, Alberto

    2011-01-01

    Research highlights: → Fuel management of KIPT ADS was analyzed. → Core arrangement was shuffled in stage wise. → New fuel assemblies was added into core periodically. → Beryllium reflector could also be utilized to increase the fuel life. - Abstract: Argonne National Laboratory (ANL) of USA and Kharkov Institute of Physics and Technology (KIPT) of Ukraine have been collaborating on the conceptual design development of an experimental neutron source facility consisting of an electron accelerator driven sub-critical assembly. The neutron source driving the sub-critical assembly is generated from the interaction of 100 KW electron beam with a natural uranium target. The sub-critical assembly surrounding the target is fueled with low enriched WWR-M2 type hexagonal fuel assemblies. The U-235 enrichment of the fuel material is <20%. The facility will be utilized for basic and applied research, producing medical isotopes, and training young specialists. With the 100 KW electron beam power, the total thermal power of the facility is ∼360 kW including the fission power of ∼260 kW. The burnup of the fissile materials and the buildup of fission products continuously reduce the system reactivity during the operation, decrease the neutron flux level, and consequently impact the facility performance. To preserve the neutron flux level during the operation, the fuel assemblies should be added and shuffled for compensating the lost reactivity caused by burnup. Beryllium reflector could also be utilized to increase the fuel life time in the sub-critical core. This paper studies the fuel cycles and shuffling schemes of the fuel assemblies of the sub-critical assembly to preserve the system reactivity and the neutron flux level during the operation.

  15. Addressing ethical considerations about nuclear fuel waste management

    International Nuclear Information System (INIS)

    Greber, M.A.

    1996-01-01

    Ethical considerations will be important in making decisions about the long-term management of nuclear fuel waste. Public discussions of nuclear fuel waste management are dominated by questions related to values, fairness, rights and responsibilities. To address public concerns, it is important to demonstrate that ethical responsibilities associated with the current management of the waste are being fulfilled. It is also important to show that our responsibilities to future generations can be met, and that ethical principles will be applied to the implementation of disposal. Canada's nuclear fuel waste disposal concept, as put forward in an Environmental Impact Statement by Atomic Energy of Canada Limited (AECL), is currently under public review by a Federal Environmental Assessment Panel. Following this review, recommendations will be made about the direction that Canada should take for the long-term management of this waste. This paper discusses the ethical principles that are seen to apply to geological disposal and illustrates how the Canadian approach to nuclear fuel waste management can meet the challenge of fulfilling these responsibilities. The author suggests that our ethical responsibilities require that adaptable technologies to site, design, construct, operate decommission and close disposal facilities should de developed. We cannot, and should not, present future generations from exercising control over what they inherit, nor control whether they modify or even reverse today's decisions if that is what they deem to be the right thing to do. (author)

  16. CPP-603 Underwater Fuel Storage Facility Site Integrated Stabilization Management Plan (SISMP), Volume I

    International Nuclear Information System (INIS)

    Denney, R.D.

    1995-10-01

    The CPP-603 Underwater Fuel Storage Facility (UFSF) Site Integrated Stabilization Management Plan (SISMP) has been constructed to describe the activities required for the relocation of spent nuclear fuel (SNF) from the CPP-603 facility. These activities are the only Idaho National Engineering Laboratory (INEL) actions identified in the Implementation Plan developed to meet the requirements of the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1 to the Secretary of Energy regarding an improved schedule for remediation in the Defense Nuclear Facilities Complex. As described in the DNFSB Recommendation 94-1 Implementation Plan, issued February 28, 1995, an INEL Spent Nuclear Fuel Management Plan is currently under development to direct the placement of SNF currently in existing INEL facilities into interim storage, and to address the coordination of intrasite SNF movements with new receipts and intersite transfers that were identified in the DOE SNF Programmatic and INEL Environmental Restoration and Waste Management Environmental Impact Statement Record, of Decision. This SISMP will be a subset of the INEL Spent Nuclear Fuel Management Plan and the activities described are being coordinated with other INEL SNF management activities. The CPP-603 relocation activities have been assigned a high priority so that established milestones will be meet, but there will be some cases where other activities will take precedence in utilization of available resources. The Draft INEL Site Integrated Stabilization Management Plan (SISMP), INEL-94/0279, Draft Rev. 2, dated March 10, 1995, is being superseded by the INEL Spent Nuclear Fuel Management Plan and this CPP-603 specific SISMP

  17. Behavioral issues in operations management new trends in design, management, and methodologies

    CERN Document Server

    2013-01-01

    Behavioral Operations Management  has been identified in the last years as one of the most promising emerging fields in Operations Management. Behavioral Issues in Operations Management  explains and examines up-to-date research in this field, which works to analyze the impact of human behavior on the management of complex operating systems.   A collection of studies from leading scholars presents different methodologies and approaches, supported by real data and case studies. Issues such as building trust and strong cooperative relationships with suppliers, enhancing motivation and designing proper incentives for stimulating more effective decision maker behaviours are considered. The main decision-making processes affected by behavioral issues are also analyzed with a focus on new product development, logistics, and supply chain integration.   The broad coverage of methodologies and practical implications makes Behavioral Issues in Operations Management an ideal reference for both researchers developing...

  18. Centralized disassembly and packaging of spent fuel in the DOE spent fuel management system

    International Nuclear Information System (INIS)

    Johnson, E.R.

    1986-01-01

    In October 1984, E.R. Johnson Associates, Inc. (JAI) initiated a study of the prospective use of a centralized facility for the disassembly and packaging of spent fuel to support the various elements of the US Dept. of Energy (DOE) spent fuel management system, including facilities for monitored retrievable storage (MRS) and repositories. It was DOE's original plan to receive spent fuel at each repository where it would be disassembled and packaged (overpacked) for disposal purposes. Subsequently, DOE considered the prospective use of MRS of spent fuel as an option for providing safe and reliable management of spent fuel. This study was designed to consider possible advantages of the use of centralized facilities for disassembly and packaging of spent fuel at whose location storage facilities could be added as required. The study was divided into three principal technical tasks that covered: (a) development of requirements and criteria for the central disassembly and packaging facility and associated systems. (2) Development of conceptual designs for the central disassembly and packaging facility and associated systems. (3) Estimation of capital and operating costs involved for all system facilities and determination of life cycle costs for various scenarios of operation - for comparison with the reference system

  19. An MCNP simulation for API applications to waste management issues

    International Nuclear Information System (INIS)

    Tunnell, L.N.

    1994-01-01

    Issues associated with waste management have increasingly become a focal point of attention for both the government and private sector since the end of the cold war. The problem are difficult to solve; the solutions are expensive to implement. Consequently, the development of a data simulation system capable of predicting the performance of a real system can save many thousands of dollars in travel expenses, optimization of experimental parameters, etc.. In this effort, computer codes were developed to simulate the production of associated particle imaging data so that its performance in a typical waste management application can be assessed

  20. Social and ethical issues in environmental risk management.

    Science.gov (United States)

    Oughton, Deborah H

    2011-07-01

    The recognition of the social and ethical aspects of radiation risk management has been an important part of international projects following the Chernobyl accident of 1986. This study comments on the science and policy issues in environmental risk assessment, including the social and ethical dimensions of emergency preparedness and remediation experiences gained from the Chernobyl accident. While the unique situation of Fukushima, combined with an earthquake and tsunami, raises its own social and political challenges, it is hoped that some of the lessons learnt from Chernobyl will be relevant to long-term management of the Fukushima site. Copyright © 2011 SETAC.