WorldWideScience

Sample records for long-term interim storage

  1. Safety of Long-term Interim Storage Facilities - Workshop Proceedings

    International Nuclear Information System (INIS)

    2014-01-01

    The objective of this workshop was to discuss and review current national activities, plans and regulatory approaches for the safety of long term interim storage facilities dedicated to spent nuclear fuel (SF), high level waste (HLW) and other radioactive materials with prolonged storage regimes. It was also intended to discuss results of experiments and to identify necessary R and D to confirm safety of fuel and cask during the long-term storage. Safety authorities and their Technical Support Organisation (TSO), Fuel Cycle Facilities (FCF) operating organisations and international organisations were invited to share information on their approaches, practices and current developments. The workshop was organised in an opening session, three technical sessions, and a conclusion session. The technical sessions were focused on: - National approaches for long term interim storage facilities; - Safety requirements, regulatory framework and implementation issues; - Technical issues and operational experience, needs for R and D. Each session consisted of a number of presentations followed by a panel discussion moderated by the session Chairs. A summary of each session and subsequent discussion that ensued are provided as well as a summary of the results of the workshop with the text of the papers given and presentations made

  2. Interim storage is not long-term disposal

    International Nuclear Information System (INIS)

    Vincenti, J.R.

    1994-01-01

    Starting in June 30, 1994 South Carolina enforced an embargo on regular shipments of low-level radioactive waste to the Barnwell repository. The failure of 31 states and their respective compacts to provide access to a long-term disposal facility as stipulated by the low-level radioactive Waste Policy Act of 1980 promotes waste disposal gridlock and anticipates another waste disposal crisis. This article discusses the problem using the following topics: Appalachian Compact Users of Radioactive Isotopes (ACURI) Association's interest; the problem of denial of access to Barnwell; pro and contra interim storage; vital services and benefits at risk; issues at the ACURI meeting; nobel Prize winners use radioactive materials; if perception is reality, politics is prevalent

  3. Corrosion behaviour of metallic containers during long term interim storages

    International Nuclear Information System (INIS)

    Desgranges, C.; Feron, D.; Mazaudier, F.; Terlain, A.

    2001-01-01

    Two main corrosion phenomena are encountered in long term interim storage conditions: dry oxidation by the air when the temperature of high level nuclear wastes containers is high enough (roughly higher than 100 C) and corrosion phenomena as those encountered in outdoor atmospheric corrosion when the temperature of the container wall is low enough and so condensation is possible on the container walls. Results obtained with dry oxidation in air lead to predict small damages (less than 1μm on steels over 100 years at 100 C) and no drastic changes with pollutants. For atmospheric corrosion, first developments deal with a pragmatic method that gives assessments of the indoor atmospheric corrosivities. (author)

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

    International Nuclear Information System (INIS)

    Fernandez-Lopez, Javier

    2014-01-01

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

  5. The challenges facing the long term interim storage

    Energy Technology Data Exchange (ETDEWEB)

    Iracane, D. [CEA Sacaly, Dir. de la Simulation et des Outils Experimentaux-DSOE, 91 - Gif sur Yvette (France); Marvy, A. [CEA Saclay, Dir. du Developpement et de l' Innovation Nucleares-DDIN, 91 - Gif Sur Yvette (France)

    2001-07-01

    In France electricity generation by means of commercial nuclear power plants has come to a point where it contributes to the national demand at a level of 80%. The safety performance of the production system has also reached a high level of both maturity and reliability taking advantage of the cumulative effect of a 30 years long learning experience and ever more stringent safety requirements. The policy to reprocess spent fuel has been overriding but no final decision has yet been made regarding the ultimate disposition of the waste streams. Although studies on deep geological disposal are ongoing, France is also looking at whether and under which conditions a long-term interim storage may provide an effective flexibility to the fuel cycle back-end. We discuss thereafter the needs and the paramount objectives of this latter R and D program. Results are being framed as potential guiding criteria for decision makers and various stakeholders. In first part, we propose a general analysis which emphasises that a long term interim storage is more than a classical nuclear facility because it explicitly requires long-lasting control and creates a burden for Society during many generations. Then, in second part, we offer an overview of the technical results from the R and D program as they stand at the time of writing. As an answer to the Government request, a strong emphasis has been put on this research for three years. Conclusion is an attempt to outline the societal context in which future decisions will have to be made. (author)

  6. The challenges facing the long term interim storage

    International Nuclear Information System (INIS)

    Iracane, D.; Marvy, A.

    2001-01-01

    In France electricity generation by means of commercial nuclear power plants has come to a point where it contributes to the national demand at a level of 80%. The safety performance of the production system has also reached a high level of both maturity and reliability taking advantage of the cumulative effect of a 30 years long learning experience and ever more stringent safety requirements. The policy to reprocess spent fuel has been overriding but no final decision has yet been made regarding the ultimate disposition of the waste streams. Although studies on deep geological disposal are ongoing, France is also looking at whether and under which conditions a long-term interim storage may provide an effective flexibility to the fuel cycle back-end. We discuss thereafter the needs and the paramount objectives of this latter R and D program. Results are being framed as potential guiding criteria for decision makers and various stakeholders. In first part, we propose a general analysis which emphasises that a long term interim storage is more than a classical nuclear facility because it explicitly requires long-lasting control and creates a burden for Society during many generations. Then, in second part, we offer an overview of the technical results from the R and D program as they stand at the time of writing. As an answer to the Government request, a strong emphasis has been put on this research for three years. Conclusion is an attempt to outline the societal context in which future decisions will have to be made. (author)

  7. Model for low temperature oxidation during long term interim storage

    Energy Technology Data Exchange (ETDEWEB)

    Desgranges, Clara; Bertrand, Nathalie; Gauvain, Danielle; Terlain, Anne [Service de la Corrosion et du Comportement des Materiaux dans leur Environnement, CEA/Saclay - 91191 Gif-sur-Yvette Cedex (France); Poquillon, Dominique; Monceau, Daniel [CIRIMAT UMR 5085, ENSIACET-INPT, 31077 Toulouse Cedex 4 (France)

    2004-07-01

    For high-level nuclear waste containers in long-term interim storage, dry oxidation will be the first and the main degradation mode during about one century. The metal lost by dry oxidation over such a long period must be evaluated with a good reliability. To achieve this goal, modelling of the oxide scale growth is necessary and this is the aim of the dry oxidation studies performed in the frame of the COCON program. An advanced model based on the description of elementary mechanisms involved in scale growth at low temperatures, like partial interfacial control of the oxidation kinetics and/or grain boundary diffusion, is developed in order to increase the reliability of the long term extrapolations deduced from basic models developed from short time experiments. Since only few experimental data on dry oxidation are available in the temperature range of interest, experiments have also been performed to evaluate the relevant input parameters for models like grain size of oxide scale, considering iron as simplified material. (authors)

  8. Model for low temperature oxidation during long term interim storage

    International Nuclear Information System (INIS)

    Desgranges, Clara; Bertrand, Nathalie; Gauvain, Danielle; Terlain, Anne; Poquillon, Dominique; Monceau, Daniel

    2004-01-01

    For high-level nuclear waste containers in long-term interim storage, dry oxidation will be the first and the main degradation mode during about one century. The metal lost by dry oxidation over such a long period must be evaluated with a good reliability. To achieve this goal, modelling of the oxide scale growth is necessary and this is the aim of the dry oxidation studies performed in the frame of the COCON program. An advanced model based on the description of elementary mechanisms involved in scale growth at low temperatures, like partial interfacial control of the oxidation kinetics and/or grain boundary diffusion, is developed in order to increase the reliability of the long term extrapolations deduced from basic models developed from short time experiments. Since only few experimental data on dry oxidation are available in the temperature range of interest, experiments have also been performed to evaluate the relevant input parameters for models like grain size of oxide scale, considering iron as simplified material. (authors)

  9. The Safety Assessment of Long term Interim Storage at Sellafield

    International Nuclear Information System (INIS)

    Buchan, Andrew B.

    2014-01-01

    that are most significant in terms of frequency and unmitigated potential consequences PSA looks at the full range of fault sequences and allows full incorporation of the reliability and failure probability of the safety measures and other features of the design and operations SAA considers significant but unlikely accidents where off-site consequences are likely to significantly affect the critical group and provides information on their progression, within the facility and also beyond the site boundary. The paper will illustrate how these techniques have been utilised to facilitate design, operation, resilience evaluation and accident management of facilities supporting long term interim storage at Sellafield. (author)

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

    International Nuclear Information System (INIS)

    Leister, P.

    1999-01-01

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

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

    International Nuclear Information System (INIS)

    Richard, R.F.

    1995-01-01

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

  12. Long-term interim storage concepts with conditioning strategies ensuring compatibility with subsequent disposal or reprocessing

    International Nuclear Information System (INIS)

    Moitrier, C.; Tirel, I.; Villard, C.

    2000-01-01

    The objective of the CEA studies carried out under research topic 3 (long-term interim storage) of the 1991 French radioactive waste management law is to demonstrate the industrial feasibility of a comprehensive, flexible interim storage facility by thoroughly evaluating and comparing all the basic components of various interim storage concepts. In this context, the CEA is considering reference solutions or concepts based on three primary components (the package, the interim storage facility and the site) suitable for determining the specifications of a very long-term solution. Some aspects are examined in greater detail, such as the implementation of long-term technologies, conditioning processes ensuring the absence of water and contamination in the facility, or allowance for radioactive decay of the packages. The results obtained are continually compiled in reports substantiating the design options. These studies should also lead to an overall economic assessment in terms of the capital and operating cost requirements, thereby providing an additional basis for selecting the design options. The comparison with existing industrial facilities highlights the technical and economic progress represented by the new generation of interim storage units. (authors)

  13. On the pathway towards disposal. The need for long-term interim storage of high-level nuclear waste

    International Nuclear Information System (INIS)

    Budelmann, Harald; Koehnke, Dennis; Reichardt, Manuel

    2017-01-01

    The disposal of spent nuclear fuel is a still unsolved problem with social, ethical, economical, ecological and political dimensions. The stagnating decision process on the final repository concept in several countries has the consequence of the inclusion of long-term interim storage into the disposal concept. The contribution discusses several approaches. This opens the question whether the long-term interim storage is a matter of delaying tactic or a pragmatic solution on the way to a final repository.

  14. Dry oxidation behaviour of metallic containers during long term interim storages

    International Nuclear Information System (INIS)

    Desgranges, C.; Terlain, A.; Bertrand, N.; Gauvain, D.

    2004-01-01

    Low-alloyed steels or carbon steels are considered candidate materials for the fabrication of some nuclear waste package containers for long term interim storage. The containers are required to remain retrievable for centuries. One factor limiting their performance on this time scale is corrosion. The estimation of the metal thickness lost by dry oxidation over such long periods requires the construction of reliable models from short-time experimental data. Two complementary approaches for modelling dry oxidation have been considered. First, basic models following simple analytical laws from classical oxidation theories have been adjusted on the apparent activation energy of oxidation deduced from experimental data. Their extrapolation to long oxidation periods confirms that the expected damage due to dry oxidation could be small. Second, a numerical model able to take in consideration several mechanisms controlling the oxide scale growth is under development. Several preliminary results are presented. (authors)

  15. Report on the long-term interim storage of spent fuels and vitrified wastes; Gutachten zur Langzeitzwischenlagerung abgebrannter Brennelemente und verglaster Abfaelle

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-12-03

    Long-term interim storage for several hundred years is an option on the management of high-level radioactive wastes. The decision on final disposal is postponed. Worldwide the long-term interim storage is not part of the disposal concept - a geologic final repository is the ultimate aim. Using today's technology the interim storage over several hundred years is supposed to be uncritical. Aging management is the most important challenge - the renewal of the facilities would have to be expected. Possible social change and their impact on the interim storage problem has not been considered.

  16. Technical study of a thermally dense long term interim storage facility

    International Nuclear Information System (INIS)

    Le Duigou, A.; Badie, M.; Duret, B.; Bricard, A.

    2001-01-01

    The COFRE concept is aimed at the surface and thermal densification of the interim storage facility for irradiated fuels. The facility provides the biological shielding. A conditioning cell is used to load and retrieve the fuel assemblies. The facility container is the second containment barrier. The high power levels are managed by an auxiliary cooling system whose original feature is the passive use of a water evaporation-condensation cycle in a sealed circuit. The removable evaporator abuts the container. The air cooled condenser is placed outside the facility. Contact resistance and heat pipe mode were successfully modelled and are undergoing experimental validation on the THERESE and REBECA loops. (author)

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

    International Nuclear Information System (INIS)

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

    2004-01-01

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

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

    International Nuclear Information System (INIS)

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

    2004-01-01

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

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

    International Nuclear Information System (INIS)

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

    1998-04-01

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

  20. Non steady-state model for dry oxidation of nuclear wastes metallic containers in long term interim storage conditions

    International Nuclear Information System (INIS)

    Bertrand, Nathalie; Desgranges, Clara; Poquillon, Dominique; Monceau, Daniel

    2006-01-01

    For high-level nuclear waste containers in long-term interim storage, dry oxidation will be the first and the main degradation mode. The reason is that, for this kind of waste, the temperature on the surface of the containers will be high enough to avoid any condensation phenomena for several years. Even if the scale growth kinetics is expected to be very slow since the temperature will be moderate at the beginning of the storage (around 300 deg. C) and will keep on decreasing, the metal thickness lost by dry oxidation over such a long period must be evaluated with a good reliability. To achieve this goal, modelling of the oxide scale growth is necessary and this is the aim of the dry oxidation studies, performed in the frame of the COCON programme. All existing oxidation models are based on the two main oxidation theories developed by Wagner between the 1930's and 1970's on the one hand, and by Cabrera and Mott in the 1960 and next by Fromhold on the other hand. These used to be associated with high temperature behaviour for Wagner's theory and with low temperature for the second one. Indeed it is certainly more relevant to consider their range of application in terms of the oxide scale thickness rather than in terms of temperature. The question is posed about which theory should an appropriate model rely on. It can be expected that the oxide scale could have a thickness ranging from a few tens of nanometers up to several tens of micrometers depending on temperature and class of alloys chosen. At the present time, low-alloyed steels or carbon steels are considered candidate materials for high-level nuclear waste containers in long term interim storage. For this type of alloys, the scale formed during the dry oxidation stage will be 'rapidly' thick enough to neglect the Mott field. Hence, in a first step, some basic models based on a parabolic rate assumption, that is to say Wagner's model, have been derived from experimental data on iron and on low-alloy steel

  1. On the pathway towards disposal. The need for long-term interim storage of high-level nuclear waste; Auf dem Weg in die Endlagerung. Die Notwendigkeit der langfristigen Zwischenlagerung hoch radioaktiver Abfaelle

    Energy Technology Data Exchange (ETDEWEB)

    Budelmann, Harald; Koehnke, Dennis; Reichardt, Manuel [Technische Univ. Braunschweig (Germany). Inst. fuer Baustoffe, Massivbau und Brandschutz; Di Nucci, Maria Rosaria; Isidoro Losada, Ana Maria [Freie Univ. Berlin (Germany). Forschungszentrum fuer Umweltpolitik (FFU)

    2017-09-01

    The disposal of spent nuclear fuel is a still unsolved problem with social, ethical, economical, ecological and political dimensions. The stagnating decision process on the final repository concept in several countries has the consequence of the inclusion of long-term interim storage into the disposal concept. The contribution discusses several approaches. This opens the question whether the long-term interim storage is a matter of delaying tactic or a pragmatic solution on the way to a final repository.

  2. Batch-wise final disposal made feasible by long-term interim storage of waste: the choice of the Netherlands

    International Nuclear Information System (INIS)

    Codee, Hans D.K.; Vrijen, Jan

    1991-01-01

    Radioactive waste produced in the Netherlands is managed by COVRA, the Central Organisation for Radioactive Waste. All kinds and categories of radwaste generated in the next 50-100 years will be stored in above ground engineered structures which allow retrieval at all times. After this long-term storage, the wastes will finally be disposed of in a deep geologic repository. At the political level no firm decisions have yet been taken with respect to the final disposal. Disposal in rock salt, which is available in the Netherlands, is explored as an option. Immediate disposal requires the availability of a large amount of money as well as a site. Neither of the two are available at present in the Netherlands, nor are they required at this time. Based on economic considerations, immediate disposal into a rock salt facility in not an acceptable option for the wastes presently produced in the Netherlands. Only after sufficient capital has been generated through an interest bearing fund can this option be considered for implementation

  3. An optimized cask technology for conditioning, transportation and long term interim storage of 'End of Life' nuclear waste

    International Nuclear Information System (INIS)

    Lefort-Mary, Florence; Clement, Gilles; Lamouroux, Christine; Dumont, Bruno

    2016-01-01

    When preparing for the decommissioning of a nuclear facility, during its 'end of life' management and while performing the actual dismantling operations, one has to consider a large diversity of nuclear waste in term of types, volumes and activities. Customers are frequently faced with the obligation to undertake multiple and costly waste management operations including handling, reconditioning or re-transferring from one package to another, for example when moving from on-site storage to transportation. To address this issue, a new - highly flexible - cask system named TN R MW is being developed. This cask has a total weight of 10 T and is compliant with the 2012 IAEA regulations. It is developed on a flexible concept basis, adaptable to the various nuclear needs, including: from IP2 to B(U) / B(U)F; on-site/ international transportation; long term interim storage. Licensing and manufacturing of number of items of this TN R MW family is underway. (authors)

  4. Long term wet spent nuclear fuel storage

    International Nuclear Information System (INIS)

    1987-04-01

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

  5. French Approach for Long Term Storage Safety

    International Nuclear Information System (INIS)

    Marciano, Jacob; Carreton, Jean-Pierre; Lizot, Marie Therese; Lhomme, Veronique

    2014-01-01

    IRSN presents its statement regarding long-term storage facilities; in France, the regulatory documents do not define the long term duration. The storage facility lifetime can only be appreciated according to the needs and materials stored therein. However, the magnitude of the long-term can be estimated at a few hundred years compared to a few decades for current storage. Usually, in France, construction of storage facilities is driven from the necessity various necessities, linked to the management of radioactive material (eg spent fuel) and to the management of radioactive waste. Because of the variety of 'stored materials and objects' (fission product solutions, plutonium oxide powders, activated solids, drums containing technological waste, spent fuel...), a great number of storage facility design solutions have been developed (surface, subsurface areas, dry or wet conditions...) in the World. After describing the main functions of a storage facility, IRSN displays the safety principles and the associated design principles. The specific design principles applied to particular storage (dry or wet spent fuel storage, depleted uranium or reprocessed uranium storage, plutonium storage, waste containing tritium storage, HLW and ILLW storage...) are also presented. Finally, the concerns due to the long-term duration storage and related safety assessment are developed. After discussing these issues, IRSN displays its statement. The authorization procedures governing the facility lifetime are similar to those of any basic nuclear installation, the continuation of the facility operation remaining subject to periodic safety reviews (in France, every 10 years). The applicant safety cases have to show, that the safety requirements are always met; this requires, at minimum, to take into account at the design stage, comfortable design margins. (author)

  6. Long term storage techniques for 85Kr

    International Nuclear Information System (INIS)

    Foster, B.A.; Pence, D.T.; Staples, B.A.

    1975-01-01

    As new nuclear fuel reprocessing plants go on stream, the collection of fission product 85 Kr will be required to avoid potential local release problems and long-term atmospheric buildup. Storage of the collected 85 Kr for a period of at least 100 years will be necessary to allow approximately 99.9 percent decay before it is released. A program designed to develop and evaluate proposed methods for long-term storage of 85 Kr is discussed, and the results of a preliminary evaluation of three methods, high pressure steel cylinders, zeolite encapsulation, and clathrate inclusion are presented. (U.S.)

  7. Long-term data storage in diamond

    OpenAIRE

    Dhomkar, Siddharth; Henshaw, Jacob; Jayakumar, Harishankar; Meriles, Carlos A.

    2016-01-01

    The negatively charged nitrogen vacancy (NV?) center in diamond is the focus of widespread attention for applications ranging from quantum information processing to nanoscale metrology. Although most work so far has focused on the NV? optical and spin properties, control of the charge state promises complementary opportunities. One intriguing possibility is the long-term storage of information, a notion we hereby introduce using NV-rich, type 1b diamond. As a proof of principle, we use multic...

  8. Safety Aspects of Long Term Spent Fuel Dry Storage

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  9. Long-term plutonium storage: Design concepts

    International Nuclear Information System (INIS)

    Wilkey, D.D.; Wood, W.T.; Guenther, C.D.

    1994-01-01

    An important part of the Department of Energy (DOE) Weapons Complex Reconfiguration (WCR) Program is the development of facilities for long-term storage of plutonium. The WCR design goals are to provide storage for metals, oxides, pits, and fuel-grade plutonium, including material being held as part of the Strategic Reserve and excess material. Major activities associated with plutonium storage are sorting the plutonium inventory, material handling and storage support, shipping and receiving, and surveillance of material in storage for both safety evaluations and safeguards and security. A variety of methods for plutonium storage have been used, both within the DOE weapons complex and by external organizations. This paper discusses the advantages and disadvantages of proposed storage concepts based upon functional criteria. The concepts discussed include floor wells, vertical and horizontal sleeves, warehouse storage on vertical racks, and modular storage units. Issues/factors considered in determining a preferred design include operational efficiency, maintenance and repair, environmental impact, radiation and criticality safety, safeguards and security, heat removal, waste minimization, international inspection requirements, and construction and operational costs

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

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  11. Long-term cryogenic space storage system

    Science.gov (United States)

    Hopkins, R. A.; Chronic, W. L.

    1973-01-01

    Discussion of the design, fabrication and testing of a 225-cu ft spherical cryogenic storage system for long-term subcritical applications under zero-g conditions in storing subcritical cryogens for space vehicle propulsion systems. The insulation system design, the analytical methods used, and the correlation between the performance test results and analytical predictions are described. The best available multilayer insulation materials and state-of-the-art thermal protection concepts were applied in the design, providing a boiloff rate of 0.152 lb/hr, or 0.032% per day, and an overall heat flux of 0.066 Btu/sq ft hr based on a 200 sq ft surface area. A six to eighteen month cryogenic storage is provided by this system for space applications.

  12. Long-term data storage in diamond

    Science.gov (United States)

    Dhomkar, Siddharth; Henshaw, Jacob; Jayakumar, Harishankar; Meriles, Carlos A.

    2016-01-01

    The negatively charged nitrogen vacancy (NV−) center in diamond is the focus of widespread attention for applications ranging from quantum information processing to nanoscale metrology. Although most work so far has focused on the NV− optical and spin properties, control of the charge state promises complementary opportunities. One intriguing possibility is the long-term storage of information, a notion we hereby introduce using NV-rich, type 1b diamond. As a proof of principle, we use multicolor optical microscopy to read, write, and reset arbitrary data sets with two-dimensional (2D) binary bit density comparable to present digital-video-disk (DVD) technology. Leveraging on the singular dynamics of NV− ionization, we encode information on different planes of the diamond crystal with no cross-talk, hence extending the storage capacity to three dimensions. Furthermore, we correlate the center’s charge state and the nuclear spin polarization of the nitrogen host and show that the latter is robust to a cycle of NV− ionization and recharge. In combination with super-resolution microscopy techniques, these observations provide a route toward subdiffraction NV charge control, a regime where the storage capacity could exceed present technologies. PMID:27819045

  13. Long-term data storage in diamond.

    Science.gov (United States)

    Dhomkar, Siddharth; Henshaw, Jacob; Jayakumar, Harishankar; Meriles, Carlos A

    2016-10-01

    The negatively charged nitrogen vacancy (NV - ) center in diamond is the focus of widespread attention for applications ranging from quantum information processing to nanoscale metrology. Although most work so far has focused on the NV - optical and spin properties, control of the charge state promises complementary opportunities. One intriguing possibility is the long-term storage of information, a notion we hereby introduce using NV-rich, type 1b diamond. As a proof of principle, we use multicolor optical microscopy to read, write, and reset arbitrary data sets with two-dimensional (2D) binary bit density comparable to present digital-video-disk (DVD) technology. Leveraging on the singular dynamics of NV - ionization, we encode information on different planes of the diamond crystal with no cross-talk, hence extending the storage capacity to three dimensions. Furthermore, we correlate the center's charge state and the nuclear spin polarization of the nitrogen host and show that the latter is robust to a cycle of NV - ionization and recharge. In combination with super-resolution microscopy techniques, these observations provide a route toward subdiffraction NV charge control, a regime where the storage capacity could exceed present technologies.

  14. Dry corrosion prediction of radioactive waste containers in long term interim storage: mechanisms of low temperature oxidation of pure iron and numerical simulation of an oxide scale growth

    International Nuclear Information System (INIS)

    Bertrand, N.

    2006-10-01

    In the framework of research on long term behaviour of radioactive waste containers, this work consists on the one hand in the study of low temperature oxidation of iron and on the other hand in the development of a numerical model of oxide scale growth. Isothermal oxidation experiments are performed on pure iron at 300 and 400 C in dry and humid air at atmospheric pressure. Oxide scales formed in these conditions are characterized. They are composed of a duplex magnetite scale under a thin hematite scale. The inner layer of the duplex scale is thinner than the outer one. Both are composed of columnar grains, that are smaller in the inner part. The outer hematite layer is made of very small equiaxed grains. Markers and tracers experiments show that a part of the scale grows at metal/oxide interface thanks to short-circuits diffusion of oxygen. A model for iron oxide scale growth at low temperature is then deduced. Besides this experimental study, the numerical model EKINOX (Estimation Kinetics Oxidation) is developed. It allows to simulate the growth of an oxide scale controlled by mixed mechanisms, such as anionic and cationic vacancies diffusion through the scale, as well as metal transfer at metal/oxide interface. It is based on the calculation of concentration profiles of chemical species and also point defects in the oxide scale and in the substrate. This numerical model does not use the classical quasi-steady-state approximation and calculates the future of cationic vacancies at metal/oxide interface. Indeed, these point defects can either be eliminated by interface motion or injected in the substrate, where they can be annihilated, considering sinks as the climb of dislocations. Hence, the influence of substrate cold-work can be investigated. The EKINOX model is validated in the conditions of Wagner's theory and is confronted with experimental results by its application to the case of high temperature oxidation of nickel. (author)

  15. Long-term storage of recovered krypton

    International Nuclear Information System (INIS)

    Horii, Yuji; Yamamoto, Yoshimasa

    1983-01-01

    Various storage methods for krypton-85 recovered from a nuclear fuel reprocessing plant are under development in many countries. These methods include:(1) direct storage in pressurized cylinders, (2) storage of krypton adsorbed on charcoal or zeolite in pressurized cylinders and (3) immobilization (encapsulation) in zeolite. A krypton storage facility using pressurized cylinders has been constructed in the krypton recovery pilot plant in Tokaimura and other methods are now under development. These three methods are evaluated and the features of the constructed facility are also reported. (author)

  16. Design review report FFTF interim storage cask

    International Nuclear Information System (INIS)

    Scott, P.L.

    1995-01-01

    Final Design Review Report for the FFTF Interim Storage Cask. The Interim Storage Cask (ISC) will be used for long term above ground dry storage of FFTF irradiated fuel in Core Component Containers (CCC)s. The CCC has been designed and will house assemblies that have been sodium washed in the IEM Cell. The Solid Waste Cask (SWC) will transfer a full CCC from the IEM Cell to the RSB Cask Loading Station where the ISC will be located to receive it. Once the loaded ISC has been sealed at the RSB Cask Loading Station, it will be transferred by facility crane to the DSWC Transporter. After the ISC has been transferred to the Interim Storage Area (ISA), which is yet to be designed, a mobile crane will be used to place the ISC in its final storage location

  17. Choosing a spent fuel interim storage system

    International Nuclear Information System (INIS)

    Roland, V.; Hunter, I.

    2001-01-01

    The Transnucleaire Group has developed different modular solutions to address spent fuel interim storage needs of NPP. These solutions, that are present in Europe, USA and Asia are metal casks (dual purpose or storage only) of the TN 24 family and the NUHOMS canister based system. It is not always simple for an operator to sort out relevant choice criteria. After explaining the basic designs involved on the examples of the TN 120 WWER dual purpose cask and the NUHOMS 56 WWER for WWER 440 spent fuel, we shall discuss the criteria that govern the choice of a given spent fuel interim storage system from the stand point of the operator. In conclusion, choosing and implementing an interim storage system is a complex process, whose implications can be far reaching for the long-term success of a spent fuel management policy. (author)

  18. Interim long-term surveillance plan for the Cheney disposal site near, Grand Junction, Colorado

    International Nuclear Information System (INIS)

    1997-08-01

    This interim long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Cheney Disposal Site in Mesa County near Grand Junction, Colorado. This LSTP describes the long-term surveillance program the DOE will implement to ensure the Cheney disposal site performs as designed and is cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed for custody and long-term care, the Nuclear Regulatory Commission (NRC) requires the DOE to submit such a site-specific LTSP

  19. Seismic Performance of Dry Casks Storage for Long- Term Exposure

    Energy Technology Data Exchange (ETDEWEB)

    Ibarra, Luis [Univ. of Utah, Salt Lake City, UT (United States); Sanders, David [Univ. of Nevada, Reno, NV (United States); Yang, Haori [Oregon State Univ., Corvallis, OR (United States); Pantelides, Chris [Univ. of Utah, Salt Lake City, UT (United States)

    2016-12-30

    The main goal of this study is to evaluate the long-term seismic performance of freestanding and anchored Dry Storage Casks (DSCs) using experimental tests on a shaking table, as well as comprehensive numerical evaluations that include the cask-pad-soil system. The study focuses on the dynamic performance of vertical DSCs, which can be designed as free-standing structures resting on a reinforced concrete foundation pad, or casks anchored to a foundation pad. The spent nuclear fuel (SNF) at nuclear power plants (NPPs) is initially stored in fuel-storage pools to control the fuel temperature. After several years, the fuel assemblies are transferred to DSCs at sites contiguous to the plant, known as Interim Spent Fuel Storage Installations (ISFSIs). The regulations for these storage systems (10 CFR 72) ensure adequate passive heat removal and radiation shielding during normal operations, off-normal events, and accident scenarios. The integrity of the DSCs is important, even if the overpack does not breach, because eventually the spent fuel-rods need to be shipped either to a reprocessing plant or a repository. DSCs have been considered as a temporary storage solution, and usually are licensed for 20 years, although they can be relicensed for operating periods of up to 60 years. In recent years, DSCs have been reevaluated as a potential mid-term solution, in which the operating period may be extended for up to 300 years. At the same time, recent seismic events have underlined the significant risks DSCs are exposed. The consideration of DCSs for storing spent fuel for hundreds of years has created new challenges. In the case of seismic hazard, longer-term operating periods not only lead to larger horizontal accelerations, but also increase the relative effect of vertical accelerations that usually are disregarded for smaller seismic events. These larger seismic demands could lead to casks sliding and tipping over, impacting the concrete pad or adjacent casks. The casks

  20. Federal Interim Storage program

    International Nuclear Information System (INIS)

    Johnson, E.R.; McBride, J.A.

    1984-01-01

    The DOE has developed a program for providing Federal Interim Storage servies for spent nuclear fuel which complies with the requirements of the Nuclear Waste Policy Act of 1982. Although very little constructive activity in providing storage facilities can be undertaken by DOE until fuel has been certified by NRC as eligible for FIS, DOE planning and background information is such as to provide reasonable assurance that its obligations can be fulfilled when the required certifications have been issued. A fee structure providing fuel recovery of all costs associated with the FIS program, as required by the Act, has been developed. It provides for an equitable distribution of costs among users, based on the quantity of fuel requiring storage

  1. Interim storage study report

    Energy Technology Data Exchange (ETDEWEB)

    Rawlins, J.K.

    1998-02-01

    High-level radioactive waste (HLW) stored at the Idaho Chemical Processing Plant (ICPP) in the form of calcine and liquid and liquid sodium-bearing waste (SBW) will be processed to provide a stable waste form and prepare the waste to be transported to a permanent repository. Because a permanent repository will not be available when the waste is processed, the waste must be stored at ICPP in an Interim Storage Facility (ISF). This report documents consideration of an ISF for each of the waste processing options under consideration.

  2. Interim storage report

    International Nuclear Information System (INIS)

    Rawlins, J.K.

    1998-02-01

    High-level radioactive waste (HLW) stored at the Idaho Chemical Processing Plant (ICPP) in the form of calcine and liquid and liquid sodium-bearing waste (SBW) will be processed to provide a stable waste form and prepare the waste to be transported to a permanent repository. Because a permanent repository will not be available when the waste is processed, the waste must be stored at ICPP in an Interim Storage Facility (ISF). This report documents consideration of an ISF for each of the waste processing options under consideration

  3. Sustainable Solutions for Nuclear used Fuels Interim Storage

    International Nuclear Information System (INIS)

    Arslan, Marc; Favet, Dominique; Issard, Herve; Le Jemtel, Amaury; Drevon, Caroline

    2014-01-01

    AREVA has a unique experience in providing sustainable solutions for used fuel management, fitted with the needs of different customers in the world and with regulation in different countries. These solutions entail both recycling and interim storage technologies. In a first part, we will describe the various types of solutions for Interim Storage of UNF that have been implemented around the world for interim storage at reactor or centralized Pad solution in canisters dry storage, vault type storages for dry storage, dry storage of transportation casks (dual purpose) pools for wet storage, The experience for all these different families of interim storages in which AREVA is involved is extensive and will be discussed with respect to the new challenges: increase of the duration of the interim storage (long term interim storage) increase of burn up of the fuels In a second part of the presentation, special recycling features will be presented. In that case, interim storage of the used fuels is ensured in pools. This provides in the long term good conditions for the behaviour of the fuel and its retrievability. With recycling, the final waste (Universal Canister of vitrified fission products and compacted hulls and end pieces): is stable and licensed in many countries for the final disposal (France, UK, Belgium, NL, Switzerland, Germany, Japan, upcoming: Spain, Australia, Italy). Presents neither safety criticality risks nor proliferation risks (AREVA conditioned HLW and LL-ILW are free of IAEA safeguard constraints thanks to AREVA process high recovery and purification yields). It can therefore be safely stored in interim storage for more than 100 years before final disposal. Some economic considerations will also be discussed. In particular, in the case of long term interim storage of used fuels, there are growing uncertainties regarding the future needs of repackaging and transportation, which can result in future cost overruns. Meanwhile, in the recycling policy

  4. Spent fuel interim storage

    International Nuclear Information System (INIS)

    Bilegan, Iosif C.

    2003-01-01

    The official inauguration of the spent fuel interim storage took place on Monday July 28, 2003 at Cernavoda NNP. The inaugural event was attended by local and central public authority representatives, a Canadian Government delegation as well as newsmen from local and central mass media and numerous specialists from Cernavoda NPP compound. Mr Andrei Grigorescu, State Secretary with the Economy and Commerce Ministry, underlined in his talk the importance of this objective for the continuous development of nuclear power in Romania as well as for Romania's complying with the EU practice in this field. Also the excellent collaboration between the Canadian contractor AECL and the Romanian partners Nuclear Montaj, CITON, UTI, General Concret in the accomplishment of this unit at the planned terms and costs. On behalf of Canadian delegation, spoke Minister Don Boudria. He underlined the importance which the Canadian Government affords to the cooperation with Romania aiming at specific objectives in the field of nuclear power such as the Cernavoda NPP Unit 2 and spent fuel interim storage. After traditional cutting of the inaugural ribbon by the two Ministers the festivities continued on the Cernavoda NPP Compound with undersigning the documents regarding the project completion and a press conference

  5. Long-term storage of spent nuclear fuel

    International Nuclear Information System (INIS)

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

    1980-06-01

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

  6. Monitoring and inspection techniques for long term storage of higher activity waste packages

    International Nuclear Information System (INIS)

    Bolton, Gary

    2013-01-01

    In 2009, following recent changes in United Kingdom (UK) Government Policy, the Nuclear Decommissioning Authority (NDA) identified a knowledge gap in the area of long term interim storage of waste packages. A cross-industry Integrated Project Team (IPT) for Interim Storage was created with responsibility for delivering Industry Guidance on the storage of packaged Higher Activity Waste (HAW) for the current UK civil decommissioning and clean-up programmes. This included a remit to direct research and development projects via the NDA's Direct Research Portfolio (DRP) to fill the knowledge gap. The IPT for Interim Storage published Industry Guidance in 2012 which established a method to define generic package performance criteria and made recommendations on monitoring and inspection. The package performance method consists of the following steps; identification of the package safety function, identification of evolutionary processes that may affect safety function performance, determination of measurable indicators of these evolutionary processes and calibration of the indicators into package performance zones. This article provides an overview of three projects funded by the NDA's DRP that the UK National Nuclear Laboratory (NNL) have completed to address monitoring and inspection needs of waste packages in interim storage. (orig.)

  7. Pyrophoricity of uranium in long-term storage environments

    International Nuclear Information System (INIS)

    Solbrig, C.W.; Krsul, J.R.; Olsen, D.N.

    1994-01-01

    A corrosion cycle for uranium is postulated which can be used to assess whether a given storage situation might produce fire hazards and/or continual uranium corrosion. A significant reaction rate of uranium and moisture occurs at room temperature which produces uranium oxide and hydrogen. If the hydrogen cannot escape, it will react slowly with uranium to form uranium hydride. The hydride is pyrophoric at room temperature when exposed to air. Either the hydrogen or the hydride can produce a dangerous situation as demonstrated by two different incidents described here. Long-term corrosion will occur even if the normal precautions are taken as is demonstrated by the long-term storage of stainless steel clad uranium fuel plates. The major initiator of these problems is attributed to any moisture condensed on the metal or any brought in by the cover gas. The postulated corrosion cycle is used to suggest ways to circumvent these problems

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

    International Nuclear Information System (INIS)

    Standring, P.N.

    1999-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Kupca, L [VUJE Inc. (Slovakia)

    2012-07-01

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

  10. Long Term Inactive Well Program requirements : interim directive ID 97-08

    International Nuclear Information System (INIS)

    1997-01-01

    The Alberta Energy and Utilities Board and the petroleum industry have agreed that industry must take proactive measures to reduce the number of long term inactive wells in Alberta. This interim directive outlines the requirements of the Long Term Inactive Well Program, and provides a schedule for industry to reduce the number of inactive wells. EUB estimates that there are currently 35,000 inactive wells in Alberta, 10,000 of which have been inactive for more than 10 consecutive years. These wells pose a financial risk to the Abandonment Fund which was established to help fund the abandonment of orphan wells. The Long Term Inactive Well Program was created based on the recommendations of a joint government/industry committee, and will operate for five years. 5 tabs

  11. Long-term storage of compressed radioactive krypton in cylinders

    International Nuclear Information System (INIS)

    Niephaus, D.; Nommensen, O.; Bruecher, H.

    1982-01-01

    The recommendations of the German Radiation Protection Commission necessitate the separation of the radioactive noble gas krypton-85 (Kr-85) produced in large LWR reprocessing plants from the dissolver off-gas. A possible method of removal is a long-term storage of the compressed noble gas above ground in cylinders. The aim of the present study is to develop such a storage concept and evaluate its feasibility under the aspects of safety and cost. After having been filled, the gas cylinders are placed separately into transport racks serving to protect the cylinders. Following this, the cylinders are transferred out of the filling station in a transport cask, conveyed to the storage building and stored there. The storage building protects the gas cylinders against external impacts. The storage cells constitute a second barrier against the release of Kr-85. The heat produced during decay of the Kr-85 in the gas cylinders is carried off by natural convection of the air circulating in the storage cells. To study possible corrosion attack on special steels due to rubidium, experiments were conducted at 200 0 C during test periods up to 3500h. In order to compare properties at elevated temperatures, corrosion experiments were conducted at 500 0 C, which is far above the maximum licensed storage temperature of 200 0 C. Experiments were conducted concerning the adsorption of krypton on various adsorbents, thus reducing the pressure inside the gas cylinder during storage. A cost estimate based on 1980 prices

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

    International Nuclear Information System (INIS)

    Wasywich, K.M.; Taylor, P.

    1993-01-01

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

  13. Thermal Analysis of the SAFKEG Package for Long Term Storage

    International Nuclear Information System (INIS)

    NARENDRA, GUPTA

    2005-01-01

    Interim plutonium storage for up to 10 years in the K-reactor building is currently being planned at Savannah River Site (SRS). SAFKEG package could be used to store Pu metal and oxide (PuO2) in the K-reactor complex with other packagings like 9975. The SAFKEG is designed for carrying Type-B materials across the DOE complex and meets the 10CFR71 requirements. Thermal analyses were performed to ensure that the temperatures of the SAFKEG components will not exceed their temperature limits under the K-reactor storage conditions. Thermal analyses of the SAFKEG packaging with three content configurations using BNFL 3013 outer container (Rocky Flats, SRS bagless transfer cans, and BNFL inner containers) were performed for storage of PuO2 and plutonium metal

  14. Retention of long-term interim restorations with sodium fluoride enriched interim cement

    Science.gov (United States)

    Strash, Carolyn

    Purpose: Interim fixed dental prostheses, or "provisional restorations", are fabricated to restore teeth when definitive prostheses are made indirectly. Patients undergoing extensive prosthodontic treatment frequently require provisionalization for several months or years. The ideal interim cement would retain the restoration for as long as needed and still allow for ease of removal. It would also avoid recurrent caries by preventing demineralization of tooth structure. This study aims to determine if adding sodium fluoride varnish to interim cement may assist in the retention of interim restorations. Materials and methods: stainless steel dies representing a crown preparation were fabricated. Provisional crowns were milled for the dies using CAD/CAM technology. Crowns were provisionally cemented onto the dies using TempBond NE and NexTemp provisional cements as well as a mixture of TempBond NE and Duraphat fluoride varnish. Samples were stored for 24h then tested or thermocycled for 2500 or 5000 cycles before being tested. Retentive strength of each cement was recorded using a universal testing machine. Results: TempBond NE and NexTemp cements performed similarly when tested after 24h. The addition of Duraphat significantly decreased the retention when added to TempBond NE. NexTemp cement had high variability in retention over all tested time periods. Thermocycling for 2500 and 5000 cycles significantly decreased the retention of all cements. Conclusions: The addition of Duraphat fluoride varnish significantly decreased the retention of TempBond NE and is therefore not recommended for clinical use. Thermocycling significantly reduced the retention of TempBond NE and NexTemp. This may suggest that use of these cements for three months, as simulated in this study, is not recommended.

  15. Long-term storage or disposal of HLW-dilemma

    International Nuclear Information System (INIS)

    Ninkovic, M. M.; Raicevic, J.

    1995-01-01

    In this paper, a new concept approach to HLW management founded on deterministic safety philosophy - i.e. long-term storage with final objective of destroying was justified and proposed instead of multi barrier concept with final disposal in extra stable environmental conditions, which are founded on probabilistic safety approach model. As a support to this new concept some methods for destruction of waste which are now accessible, on scientific stage only, as transmutation in fast reactors and accelerators of heavy ions were briefly discussed . It is justified to believe that industrial technology for destruction of HLW would be developed in not so far future. (author).

  16. Radioactive waste interim storage in Germany

    International Nuclear Information System (INIS)

    2015-12-01

    The short summary on the radioactive waste interim storage in Germany covers the following issues: importance of interim storage in the frame of radioactive waste management, responsibilities and regulations, waste forms, storage containers, transport of vitrified high-level radioactive wastes from the reprocessing plants, central interim storage facilities (Gorleben, Ahaus, Nord/Lubmin), local interim storage facilities at nuclear power plant sites, federal state collecting facilities, safety, radiation exposure in Germany.

  17. Conditioning radium needles for long term storage : Sri Lankan experience

    International Nuclear Information System (INIS)

    Ranjith, H.L.A.; Shantha, T.H.S.; Gunaratne, M.G.J.; De Silva, U.W.K.H.; Perera, H.P.H.

    2000-01-01

    Radium the first radioisotope invented by Madame Curie was used for cancer therapy for the intracavitory treatment of cervical cancers and as oral implants etc. Radium needles and other geometries were made in standard strengths and Radium therapy enjoyed a heyday during the 1st half of the 20th century. Radium-226 is a long-lived radioactive material with a half-life of 1600 years. The use of radium was abandoned in the world in 1980s with the invention of short lived radioactive materials offering remote after loading systems which minimise radiation protection and waste disposal problems associated with long lived radioactive materials. This paper reports the conditioning procedure of the spent radium sources for long term storage (less than 20 years) and transport to national/ international stores if needed. The dose received by those involved in this exercise is also discussed in terms of radiation protection. The Ra was contained for long term storage according to international radiation safety regulations with a surface dose of less than 2 mSv per hour in a conditioned package having 17.5 GBq activity and can be transported to national/international stores if needed. The highest dose received during the exercise is well within the recommended dose limits for occupational exposures (20 and 500 mSv per year) for whole body and extremities respectively

  18. Interim and final storage casks

    International Nuclear Information System (INIS)

    Stumpfrock, L.; Kockelmann, H.

    2012-01-01

    The disposal of radioactive waste is a huge social challenge in Germany and all over the world. As is well known the search for a site for a final repository for high-level waste in Germany is not complete. Therefore, interim storage facilities for radioactive waste were built at plant sites in Germany. The waste is stored in these storage facilities in appropriate storage and transport casks until the transport in a final repository can be carried out. Licensing of the storage and transport casks aimed for use in the public space is done according to the traffic laws and for handling in the storage facility according to nuclear law. Taking into account the activity of the waste to be stored, different containers are in use, so that experience is available from the licensing and operation in interim storage facilities. The large volume of radioactive waste to be disposed of after the shut-down of power generation in nuclear power stations makes it necessary for large quantities of licensed storage and transport casks to be provided soon.

  19. NPP Krsko: LILW Repository or Long Term Storage

    International Nuclear Information System (INIS)

    Lokner, V.; Subasic, D.; Levanat, I.

    2008-01-01

    Construction of the facilities for LILW and SF management, as planned in Decommissioning and LILW and SF management program for NPP Krsko, would be a rather expensive and challenging project for such a small nuclear program. In order to accommodate waste arising from a single nuclear power plant, one LILW repository should be constructed before the end of the NPP operation, then one SF dry storage, and finally one geological repository. This requires relatively urgent identification within Slovenian/Croatian territory of three locations that meet the criteria for establishment of such facilities and are acceptable to the local communities. There are very few such potential locations. The siting process for the first of the three facilities is well under way in Slovenia, because the country wants to have its LILW repository in operation by the year 2013. In order to facilitate public acceptance, Slovenian government has introduced financial incentives to local communities for the repository construction and operation. These 'compensations for limited land use' may significantly increase the overall costs of disposal if the repository is in operation for a long period. In the recent years, however, a possibility of long term storage (LTS) is gaining an increased attention in the waste management community, and has already been introduced e.g. in the Netherlands. It is a particularly viable option for limited waste quantities. Disposal remains the final solution, but present technologies have made possible a relatively inexpensive storage up to about hundred years, which can accommodate LILW, HLW and SF from nuclear programs as well as research reactor waste and NORM. Such storage would be a safe and simple temporary solution, encompassing all immediate and near future waste management needs. In addition, it would increase flexibility and reduce financing requirements for the final waste disposal: providing additional time for reduction of radiation emission and heat

  20. Industrial complementarities between interim storage and reversible geological repository - 59237

    International Nuclear Information System (INIS)

    Hoorelbeke, Jean-Michel

    2012-01-01

    The French Act voted in 2006 made the choice of deep geological disposal as the reference option for the long term management of high level (HLW) and intermediate level long-lived waste. The CIGEO repository project aims at avoiding or limiting burden to future generations, which could not be achieved by the extension in time of interim storage. The reversibility as provided by the Act will maintain a liberty of choice for waste management on a duration which is comparable to new storage facility. Interim storage is required to accommodate waste as long as the repository is not available. The commissioning of the repository in 2025 will not suppress needs for interim storage. The paper describes the complementarities between existing and future interim storage facilities and the repository project: repository operational issues and planning, HLW thermal decay, support for the reversibility, etc. It shows opportunities to prepare a global optimization of waste management including the utilization at best of storage capacities and the planning of waste emplacement in the repository in such a way to facilitate operational conditions and to limit cost. Preliminary simulations of storage-disposal scenarios are presented. Thanks to an optimal use of the waste management system, provision can be made for a progressive increase of waste emplacement flow during the first operation phase of the repository. It is then possible to stabilize the industrial activity level of the repository site. An optimal utilization of interim storage can also limit the diversity of waste packages emplaced simultaneously, which facilitates the operation of the repository. 60 years minimum interim storage duration is generally required with respect to HLW thermal output. Extending this interim storage period may reduce the underground footprint of the repository. Regarding reversibility, the capability to manage waste packages potentially retrieved from the repository should be analyzed. The

  1. Glass packages in interim storage

    International Nuclear Information System (INIS)

    Jacquet-Francillon, N.

    1994-10-01

    This report summarize the current state of knowledge concerning the behavior of type C waste packages consisting of vitrified high-level solutions produced by reprocessing spent fuel. The composition and the physical and chemical properties of the feed solutions are reviewed, and the vitrification process is described. Sodium alumino-borosilicate glass compositions are generally employed - the glass used at la Hague for LWR fuel solutions, for example, contains 45 % SiO 2 . The major physical, chemical, mechanical and thermal properties of the glass are reviewed. In order to allow their thermal power to diminish, the 3630 glass packages produced (as of January 1993) in the vitrification facilities at Marcoule and La Hague are placed in interim storage for several decades. The actual interim storage period has not been defined, as it is closely related to the concept and organization selected for the final destination of the packages: a geological repository. The glass behavior under irradiation is described. Considerable basic and applied research has been conducted to assess the aqueous leaching behavior of nuclear containment glass. The effects of various repository parameters (temperature, flow rate, nature of the environmental materials) have been investigated. The experimental findings have been used to specify a model describing the kinetics of aqueous corrosion of the glass. More generally all the ''source term'' models developed in France by the CEA or by ANDRA are summarized. (author). 152 refs., 33 figs

  2. Dry storage systems using casks for long term storage in an AFR and repository

    International Nuclear Information System (INIS)

    Einfeld, K.; Popp, F.W.

    1986-01-01

    In conclusion it can be stated that two basic routes with respect to spent fuel storage casks are feasible. One is the Multiple Transport Cask, which with certain modifications can be upgraded to meet the criteria for intermediate storage. Its status is characterized by the licensing of several types of Castor Casks for an intermediate storage period of 30 years in the AFR Storage Facility of DWK at Gorleben in the FRG. The other one is the Final Disposal (Repository) Cask, which can be made suitable for long term storage before a final decision with respect to a repository application is taken. The licensing procedure for a Pilot Conditioning Facility with the Pollux Cask System as reference case will be initiated by DWK in the near future. Under the assumption that in addition to the present Multiple Transport/Storage Casks a license for a Final disposal Cask with respect to long term storage is available, the relative merits of different cask storage systems would have to be evaluated

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-07-02

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

  4. Long-term stability of orbits in storage rings

    International Nuclear Information System (INIS)

    Warnock, R.L.; Ruth, R.D.

    1990-06-01

    We describe a numerical method to establish long-term bounds on nonlinear Hamiltonian motion. By bounding the change in a nearly constant action variable, uniformly in initial condition, one can predict stability for N turns by tracking many orbits for a member of turns of N 0 much less than N. In a first application to a model sextupole lattice in a region of strong nonlinearity, we predict stability of betatron motion in two degrees of freedom for 10 8 turns. 5 refs., 3 figs

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

    International Nuclear Information System (INIS)

    2001-01-01

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

  6. Long Term Storage of cytogenetic changes in liquidators of Chernobyl

    International Nuclear Information System (INIS)

    Karpov, V. B.

    2004-01-01

    At present chromosome aberration analysis in lymphocytes as well as micronucleus assay are most reliable methods of bio indication of radiation effects. The problem of persistent of cytogenetic changes during the long term after exposure is very important. The cytogenetic studies of liquidators residents of St. Petersburg and region revealed that the average chromosome aberration rate 4-5 years after the accident constitutes 4.94±0.38, number of aberrant cells was 4.82±0.36, dicentrics -0.23±0.10 per 100 cells, micronucleus number -46.1±2.1 per 100 cells that is significantly higher than in control group. dispersion analysis confirms the reported level of external exposure effects on chromosome aberration rate (?=0.04) in this group of liquidators. In 73 persons from the group of high risk participants of nuclear tests, nuclear submarine personnel 8-45 years after average number of chromosome aberrations was 6.5±0.32; dicentrics - 0.64±0.10, centric rings- 0.04±0.02 per 100 cells, for micronuclei -51.4±2.82 per thousand cells, that is significantly higher than in control group (p<0.01). In 45.2% cases the aberration markers (disentrics and centric rings) were found. The late cytogenetic effects were observed after decades and possibility to use these indicators for long term diagnosis is now under consideration. (Author)

  7. Defining sale ethylene for long term storage of tulip bulbs

    NARCIS (Netherlands)

    Wild, de H.P.J.; Peppelenbos, H.W.; Dijkstra, M.H.G.E.; Gude, H.

    2002-01-01

    The maximum ethylene level that can be permitted in storage rooms, without causing damage to tulip bulbs, is not exactly known. Therefore, a zero-tolerance for the presence of ethylene during storage of tulip bulbs is common practice. This results in excessive ventilation and coherent large energy

  8. Qualification of polysiloxanes for long-term storage of radioactive waste

    International Nuclear Information System (INIS)

    Kucharczyk, P.

    2005-12-01

    At present German policy envisages interim storage of all radioactive waste (for approximately 30 years) until a final repository is available. This therefore leads to higher standards for storage containers. Silicone elastomers (polysiloxanes), materials on the basis of silicon and oxygen with organic substituents, have various physical and chemical properties and seem to be suitable for the long-term storage of low- and intermediate-level radioactive waste. The aim of the present work is the qualification of a new coating material for storage containers. The use of polysiloxanes in other applications was also investigated. An important criterion for the coating is the simplicity of its application. Moreover, it should also have a high adhesion on steel as well as providing protection against corrosion. These properties were investigated for different polysiloxanes. The spraying tests showed that polysiloxane material with a viscosity of up to 45 000 mPas could be applied by the airless spraying method. An elastic coating was produced which could ensure protection against mechanical impacts. In the framework of water vapour experiments, a very high diffusion constant was determined. The corrosion test confirmed that the polysiloxane coating provided only insufficient corrosion protection if the sample was in contact with water and water vapour at the same time. This problem was solved by using an additional priming coat of 60 μm zinc paint. The adhesion test showed that polysiloxanes have different levels of adhesion. The best adhesion was determined for condensation-cured silicones. The addition-cured materials had a lower adhesion, which was improved by the application of a priming coat. The outcome of these investigations is a wide spectrum of applications for polysiloxanes which can be used as firmly adhering coatings or removable decontamination layers. (orig.)

  9. Data storage and retrieval for long-term dog studies

    International Nuclear Information System (INIS)

    Watson, C.R.; Trauger, G.M.; McIntyre, J.M.; Slavich, A.L.; Park, J.F.

    1980-01-01

    Over half of the 500,000 records collected on dogs in the last 20 years in our laboratory have been converted from sequential storage on magnetic tape to direct-access disk storage on a PDP 11/70 minicomputer. An interactive storage and retrieval system, based on a commercially available query language, has been developed to make these records more accessible. Data entry and retrieval are now performed by scientists and technicians rather than by keypunch operators and computer specialists. Further conversion awaits scheduled computer enhancement

  10. Analysis of long-term terrestrial water storage variations in the Yangtze River basin

    NARCIS (Netherlands)

    Huang, Ying; Salama, M.S.; Krol, Martinus S.; van der Velde, R.; Hoekstra, Arjen Ysbert; Zhou, Y.; Su, Zhongbo

    2013-01-01

    In this study, we analyze 32 yr of terrestrial water storage (TWS) data obtained from the Interim Reanalysis Data (ERA-Interim) and Noah model from the Global Land Data Assimilation System (GLDAS-Noah) for the period 1979 to 2010. The accuracy of these datasets is validated using 26 yr (1979–2004)

  11. Quality changes of Antarctic krill powder during long term storage

    DEFF Research Database (Denmark)

    Nielsen, Nina Skall; Lu, Henna Fung Sieng; Bruheim, Inge

    2017-01-01

    of packaging in vacuum was observed. The stability was assessed by changes in concentrations of lipid classes, antioxidants, pyrroles and lipid, and Strecker-derived volatiles. Some degradation occurred during storage at room temperature. Thus, a minor increase in volatiles, an increase in free fatty acids...... and a concomitant decrease in antioxidants, tocopherol, and astaxanthin was observed. In addition, there was a minor decrease in phospholipids and n-3 fatty acids; however, storage at vacuum improved the oxidative stability of krill powder. Practical applications: For the use of krill powder in human nutrition......, it is important, that the quality and stability is sufficiently high to retain the nutritional value during storage. This study contributes with information about the stability during storage up to 12 months at room temperature and the effect of packaging the powder in vacuum. Antarctic krill (Euphausia superba...

  12. Long term storage of finished gasolines in large salt caverns

    Energy Technology Data Exchange (ETDEWEB)

    Koenig, J.W.J. [German Strategic Petroleum Reserve, Hamburg (Germany)

    1995-05-01

    Strategic oil stocking requires large low cost storage facilities. Crude oil has been held in very large salt mines and/or artificially made salt caverns for many years, notably in Europe and the USA. Following crude oil, gasoils and refinery light feed stocks have been tried also. Military organisations tried jet fuel and early cases of underground aviation gasoline storage in steel tanks have been reported.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

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

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

    International Nuclear Information System (INIS)

    Sorenson, Ken B.

    2014-01-01

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

  16. Inventory extension considerations for long-term storage at the nuclear materials storage facility

    International Nuclear Information System (INIS)

    Olinger, C.T.; Stanbro, W.D.; Longmire, V.; Argo, P.E.; Nielson, S.M.

    1996-01-01

    Los Alamos National Laboratory is in the process of modifying its nuclear materials storage facility to a long-term storage configuration. In support of this effort, we examined technical and administrative means to extend periods between physical inventories. Both the frequency and sample size during a physical inventory could significantly impact required sizing of the non-destructive assay (NDA) laboratory as well as material handling capabilities. Several options are being considered, including (1) treating each storage location as a separate vault, (2) minimizing the number of items returned for quantitative analysis by optimizing the use of in situ confirmatory measurements, and (3) utilizing advanced monitoring technologies. Careful consideration of these parameters should allow us to achieve and demonstrate safe and secure storage while minimizing the impact on facility operations and without having to increase the size of the NDA laboratory beyond that required for anticipated shipping and receiving activities

  17. Irradiation of potatoes for long-term storage

    International Nuclear Information System (INIS)

    Srapenjanz, R.

    1976-01-01

    In the USSR gamma irradiation of potatoes is used for extending the storage life. The properties of potatoes are not changed, and the irradiation procedure is lower in cost than chemical treatments for sprout inhibition. Finally, a brief outline is given of investigations on sprout inhibition of potatoes in other socialist countries

  18. Quality Changes During Long Term Farmers’ Stock Storage

    Science.gov (United States)

    Since 2012, U.S. annual peanut production has increased 44% from an average of 2.6 million MT compared with 1.8 million MT (1997 and 2012). This production increase has resulted in longer storage times between harvest and shelling. A study was conducted to observe the changes in quality of farmers...

  19. [Long-term storage of obligate anaerobic microorganisms in glycerol].

    Science.gov (United States)

    Briukhanov, A I; Netrusov, A I

    2006-01-01

    We evaluated the possibility of storing the cultures of obligate anaerobic microorganisms (clostridia. acetogenic and sulfate-reducing bacteria, and methanogenic archaea) in 25% glycerol at -70 degrees C for a long time (up to 3 years). This method of storage is adequate to preserve cell viability in most obligate anaerobes.

  20. Very-long-term storage of fission products

    International Nuclear Information System (INIS)

    Sousselier, Y.; Pradel, J.; Cousin, O.

    The large majority of the fission products, with 99.9 percent of the radioactivity content, do not pose actual problems in storage in a geological formation for which we can guarantee total confinement. Safety of storage in a geological formation for the radionuclides of long half-life is based in particular on the absorption capacity of the geological formations and the example of the Oklo fossil reactor and the retention of Pu which is produced is a striking example. But the problems are not the same, and the properties that we look for in the terrain are not the same. We could thus be led to storage in different geological formations for the fission products and the long-half-life emitters. Their separation is interesting from this point of view, but the date at which the separation is made will not be necessarily that of reprocessing. But there is a question of one or the other, and these storages will offer a very high level of insurance and will present only the potential hazards that are very comparable with those presented by natural conditions

  1. Suitable areas for a long-term radioactive waste storage facility in Portugal

    Energy Technology Data Exchange (ETDEWEB)

    Duarte, P.; Paiva, I.; Trindade, R. [Instituto Tecnologico e Nuclear, Dept. de Proteccao Radiologica e Seguranca Nuclear, Sacavem (Portugal); Mateus, A. [Lisboa Univ., Dept. de Geologia and Creminer, Faculdade de Ciencias (Portugal)

    2006-07-01

    Radioactive wastes in Portugal result mainly from the application of radioactive materials in medicine, research, industry and from U-ores mining and milling activities. Sealed and unsealed sources (including liquid effluents and N.O.R.M.) classified as radioactive wastes have been collected, segregated, conditioned and stored in the Portuguese Radioactive Waste Interim Storage Facility (P.R.W.I.S.F.) since the sixties. The Radiological Protection and Nuclear Safety Department (D.P.R.S.N.) of the Nuclear and Technological Institute (I.T.N.) is responsible for the R.W.I.S.F. management, located nearby Lisbon (S.a.c.a.v. ). Despite recent improvements performed at R.W.I.S.F., the 300 m3 storage capacity will be soon used up if current average store-rate remains unaltered. Being aware of the tendency for radioactive waste production increase in Portugal and of the international rules and recommendations on disposal sites for this kind of wastes, it becomes clear that the P.R.W.I.S.F. must be updated. In this work, a first evaluation of suitable areas to host a long-term radioactive waste storage facility was carried out using a Geographic Information System (G.I.S.) base. Preference and exclusionary criteria were applied, keeping constant the map scale (1:1000000). After processing exclusionary criteria, remaining areas were scored by overlaying three preference criteria. A composite score was determined for each polygon (problem solution) by summing the three preference criteria scores. The highest scores resulted from the combination of these criteria correspond to 4% of the territory, spatially distributed in seven of the eighteen Portuguese mainland administrative districts. Work in progress will use this area as reference for site selection, criss-crossing appropriate criteria for scales ranging from 1:50000 to 1:25000. (authors)

  2. Suitable areas for a long-term radioactive waste storage facility in Portugal

    International Nuclear Information System (INIS)

    Duarte, P.; Paiva, I.; Trindade, R.; Mateus, A.

    2006-01-01

    Radioactive wastes in Portugal result mainly from the application of radioactive materials in medicine, research, industry and from U-ores mining and milling activities. Sealed and unsealed sources (including liquid effluents and N.O.R.M.) classified as radioactive wastes have been collected, segregated, conditioned and stored in the Portuguese Radioactive Waste Interim Storage Facility (P.R.W.I.S.F.) since the sixties. The Radiological Protection and Nuclear Safety Department (D.P.R.S.N.) of the Nuclear and Technological Institute (I.T.N.) is responsible for the R.W.I.S.F. management, located nearby Lisbon (S.a.c.a.v. ). Despite recent improvements performed at R.W.I.S.F., the 300 m3 storage capacity will be soon used up if current average store-rate remains unaltered. Being aware of the tendency for radioactive waste production increase in Portugal and of the international rules and recommendations on disposal sites for this kind of wastes, it becomes clear that the P.R.W.I.S.F. must be updated. In this work, a first evaluation of suitable areas to host a long-term radioactive waste storage facility was carried out using a Geographic Information System (G.I.S.) base. Preference and exclusionary criteria were applied, keeping constant the map scale (1:1000000). After processing exclusionary criteria, remaining areas were scored by overlaying three preference criteria. A composite score was determined for each polygon (problem solution) by summing the three preference criteria scores. The highest scores resulted from the combination of these criteria correspond to 4% of the territory, spatially distributed in seven of the eighteen Portuguese mainland administrative districts. Work in progress will use this area as reference for site selection, criss-crossing appropriate criteria for scales ranging from 1:50000 to 1:25000. (authors)

  3. The effect of long-term storage on nanoleakage.

    Science.gov (United States)

    Li, H P; Burrow, M F; Tyas, M J

    2001-01-01

    To evaluate the durability of dentin bonding over time, the nanoleakage of four dentin bonding systems (Single Bond, Stae, Clearfil SE Bond and PermaQuik) over 24 hours, three months, six months and 12 months, was investigated. Flat occlusal dentin surfaces from extracted human molars were finished with wet 600-grit silicon carbide paper and bonded with one of the dentin bonding systems following manufacturers' instructions. The bonded surface was covered with < 1 mm thick layer of Silux Plus resin composite and light cured for 40 seconds. The specimens in each dentin-bonding group were randomly assigned to four sub-groups and kept in phosphate buffered saline solution (pH 7.4) containing 0.01% sodium azide at 37 degrees C for 24 hours, three, six or 12 months. The margins of all specimens were finished and polished with Sof-Lex disks after initial 24-hour storage. At the end of each storage time, the surrounding tooth surfaces except for 1 mm adjacent to the restoration were coated with nail varnish. The samples were immersed in a 50% w/v solution of silver nitrate for 24 hours, placed in photodeveloping solution and exposed to fluorescent light for eight hours. The samples were cut longitudinally and buccoligually, polished, mounted on stubs, carbon coated and observed in a Field Emission-SEM using backscattered electron mode. The results showed that systems using phosphoric acid as the etchant had a line of silver deposition at the base of the hybrid layer. Silver deposition increased in all systems over 12-months storage, with PermaQuik changing the least. Nanoleakage of the dentin bonding systems increased slightly during the 12-month storage period, indicating that they may be subject to hydrolytic attack over time.

  4. Alternative processes for the long-term storage of Kr-85

    International Nuclear Information System (INIS)

    Penzhorn, R.D.

    1977-12-01

    The forseeable problems which are characteristic of the long-term storage of Kr-85, are discussed on the basis of the chemical, physical and radiological properties of the fission noble gases krypton and xenon as well as rubidium, the daughter nuclide of Kr-85. The various alternatives suggested in the literature for the long-term storage of Kr-85 are reviewed. The technological realization of each of the proposed alternatives is analyzed. (orig.) [de

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

    International Nuclear Information System (INIS)

    Dehaudt, Ph.

    1999-01-01

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

  6. Techniques for long term conditioning and storage of radium sources

    International Nuclear Information System (INIS)

    Dogaru, Gheorghe; Dragolici, Felicia; Nicu, Mihaela

    2008-01-01

    The Horia Hulubei National Institute of Research and Development for Physics and Nuclear Engineering developed its own technology for conditioning the radium spent sealed radioactive sources. The laboratory dedicated to radiological characterization, identification of radium sources as well as the encapsulation of spent sealed radioactive sources was equipped with a local ventilation system, welding devices, tightness test devices as well as radiometric portable devices. Two types of capsules have been designed for conditioning of radium spent sealed radioactive sources. For these kinds of capsules different types of storage packaging were developed. Data on the radium inventory will be presented in the paper. The paper contains the description of the process of conditioning of spent sealed radioactive sources as well as the description of the capsules and packaging. The paper describes the equipment used for the conditioning of the radium spent sealed sources. (authors)

  7. Long-term storage of three unconventional oils

    Directory of Open Access Journals (Sweden)

    Hussein, Ismail H.

    2008-03-01

    Full Text Available Three samples, Sclerocarya birrea oil (SCO, Melon bug oil (Aspongubus viduatus (MBO, and Sorghum bug oil (Agonoscelis pubescens (SBO, were stored (autoxidized in the dark at 30±2 °C for 24 months. Oil aliquots were withdrawn every 2-4 month for analyses of changes in four quality indexes, namely fatty acid composition, tocopherol content, peroxide value and oxidative stability index by Rancimat. After 24 months of storage the fatty acid composition of the three oils showed no change while tocopherol contents were decreased. SCO and MBO showed only slight changes in their oxidative stability as indicated by the peroxide value and induction period during the 24 months of storage. Sorghum bug oil showed a periodical increase in the peroxide value and had less stability as measured by the Rancimat in comparison to other oils.Tres muestras de aceite, Sclerocarya birrea oil (SCO, Melon bug oil (Aspongubus viduatus (MBO, and Sorghum bug oil (Agonoscelis pubescens (SBO, fueron almacenadas en la oscuridad a 30±2 °C durante 24 meses. Cada 2- 4 meses se toman alícuotas para analizar los cambios de calidad. Se determinaron la composición en ácidos grasos, el contenido en tocoferol, el índice de peróxidos y la estabilidad oxidativa mediante el aparato Rancimat. Después de 24 meses de almacenamiento, la composición en ácidos grasos no experimentó variación mientras que el contenido en tocoferol disminuyó en los tres aceites. SCO y MBO mostraron cambios minoritarios como se comprobó por los indices de peroxides y estabilidad a los 24 meses. SBO fue el menos estable de los tres aceites.

  8. Interim storage of radioactive waste packages

    International Nuclear Information System (INIS)

    1998-01-01

    This report covers all the principal aspects of production and interim storage of radioactive waste packages. The latest design solutions of waste storage facilities and the operational experiences of developed countries are described and evaluated in order to assist developing Member States in decision making and design and construction of their own storage facilities. This report is applicable to any category of radioactive waste package prepared for interim storage, including conditioned spent fuel, high level waste and sealed radiation sources. This report addresses the following issues: safety principles and requirements for storage of waste packages; treatment and conditioning methods for the main categories of radioactive waste; examples of existing interim storage facilities for LILW, spent fuel and high level waste; operational experience of Member States in waste storage operations including control of storage conditions, surveillance of waste packages and observation of the behaviour of waste packages during storage; retrieval of waste packages from storage facilities; technical and administrative measures that will ensure optimal performance of waste packages subject to various periods of interim storage

  9. Evaluation of long term radiological impact on population close to remediated uranium mill tailings storages

    International Nuclear Information System (INIS)

    Kerouanton, David; Delgove, Laure

    2008-01-01

    A methodology is elaborated in order to evaluate the long term radiological impact of remediated uranium mill tailings storage. Different scenarios are chosen and modelled to cover future evolution of the tailings storages. Radiological impact is evaluated for different population such as adults and children living in the immediate vicinity or directly on the storage, road workers or walkers on the storage. Equation and methods are detailed. (author)

  10. Iodide and iodate sodalites for the long-term storage of iodine-129

    International Nuclear Information System (INIS)

    Strachan, D.M.; Babad, H.

    1979-01-01

    There exist several proposals for the storage of 129 I. None of these propose the use of a mineral with demonstrated geologic stability. The work described in this paper has identified the minerals iodide and iodate sodalites [Na 8 (AlSiO 4 ) 6 I 2 /(IO 3 ) 2 ] as good candidates for the long-term storage of 129 I. 4 tables

  11. Interim Storage Facility decommissioning. Final report

    International Nuclear Information System (INIS)

    Johnson, R.P.; Speed, D.L.

    1985-01-01

    Decontamination and decommissioning of the Interim Storage Facility were completed. Activities included performing a detailed radiation survey of the facility, removing surface and imbedded contamination, excavating and removing the fuel storage cells, restoring the site to natural conditions, and shipping waste to Hanford, Washington, for burial. The project was accomplished on schedule and 30% under budget with no measurable exposure to decommissioning personnel

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

    Energy Technology Data Exchange (ETDEWEB)

    Saegusa, T [CRIEPI (Japan)

    2012-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Takats, F [TS Enercon Kft. (Hungary)

    2012-07-01

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

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

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  15. Modelling the long-term deployment of electricity storage in the global energy system

    International Nuclear Information System (INIS)

    Despres, Jacques

    2015-01-01

    The current development of wind and solar power sources calls for an improvement of long-term energy models. Indeed, high shares of variable wind and solar productions have short- and long-term impacts on the power system, requiring the development of flexibility options: fast-reacting power plants, demand response, grid enhancement or electricity storage. Our first main contribution is the modelling of electricity storage and grid expansion in the POLES model (Prospective Outlook on Long-term Energy Systems). We set up new investment mechanisms, where storage development is based on several combined economic values. After categorising the long-term energy models and the power sector modelling tools in a common typology, we showed the need for a better integration of both approaches. Therefore, the second major contribution of our work is the yearly coupling of POLES to a short-term optimisation of the power sector operation, with the European Unit Commitment and Dispatch model (EUCAD). The two-way data exchange allows the long-term coherent scenarios of POLES to be directly backed by the short-term technical detail of EUCAD. Our results forecast a strong and rather quick development of the cheapest flexibility options: grid interconnections, pumped hydro storage and demand response programs, including electric vehicle charging optimisation and vehicle-to-grid storage. The more expensive battery storage presumably finds enough system value in the second half of the century. A sensitivity analysis shows that improving the fixed costs of batteries impacts more the investments than improving their efficiency. We also show the explicit dependency between storage and variable renewable energy sources. (author) [fr

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

    International Nuclear Information System (INIS)

    1982-01-01

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

  17. Conceptual designs for a long term 238PuO2 storage vessel

    International Nuclear Information System (INIS)

    Kwon, D.M.; Replogle, W.C.

    1996-08-01

    This is a report on conceptual designs for a long term, 250 years, storage container for plutonium oxide ([sup 238]PuO[sub 2]). These conceptual designs are based on the use of a quartz filter to release the helium generated during the plutonium decay. In this report a review of filter material selection, design concepts, thermal modeling, and filter performance are discussed

  18. Potential long-term storage of the predatory mite Phytoseiulus persimilis

    Science.gov (United States)

    Increasing the ability to store mass-reared natural enemies during periods or seasons of low demand is a critical need of the biocontrol industry. We tested the hypothesis that cryoprotectant or carbohydrate molecules can enhance long-term cold storage of a predatory mite Phytoseiulus persimilis At...

  19. Long-term management impacts on carbon storage in Lake States forests

    Science.gov (United States)

    Matthew Powers; Randall Kolka; Brian Palik; Rachel McDonald; Martin. Jurgensen

    2011-01-01

    We examined carbon storage following 50+ years of forest management in two long-term silvicultural studies in red pine and northern hardwood ecosystems of North America’s Great Lakes region. The studies contrasted various thinning intensities (red pine) or selection cuttings, shelterwoods, and diameter-limit cuttings (northern hardwoods) to unmanaged controls of...

  20. Long-Term Storage of Cryptosporidium parvum for In Vitro Culture

    NARCIS (Netherlands)

    Paziewska-Harris, A.; Schoone, G.; Schallig, H. D. F. H.

    2018-01-01

    The long-term storage of Cryptosporidium life-cycle stages is a prerequisite for in vitro culture of the parasite. Cryptosporidium parvum oocysts, sporozoites, and intracellular forms inside infected host cells were stored for 6-12 mo in liquid nitrogen utilizing different cryoprotectants (dimethyl

  1. Viability staining and animal infectivity of Cryptosporidium andersoni oocysts after long-term storage

    Czech Academy of Sciences Publication Activity Database

    Kváč, Martin; Květoňová, Dana; Salát, Jiří; Ditrich, Oleg

    2007-01-01

    Roč. 100, č. 2 (2007), s. 213-217 ISSN 0932-0113 R&D Projects: GA ČR GA524/05/0992 Institutional research plan: CEZ:AV0Z60220518 Keywords : Cryptosporidium and ersoni * viability * infectivity * long-term storage Subject RIV: EG - Zoology Impact factor: 1.512, year: 2007

  2. Long-term storage of Greater-Than-Class C Low-Level Waste

    International Nuclear Information System (INIS)

    Magleby, M.T.

    1990-01-01

    Under Federal law, the Department of Energy (DOE) is responsible for safe disposal of Greater-Than-Class C Low-Level Waste (GTCC LLW) generated by licenses of the Nuclear Regulatory commission (NRC) or Agreement States. Such waste must be disposed of in a facility licensed by the NRC. It is unlikely that licensed disposal of GTCC LLW will be available prior to the year 2010. Pending availability of disposal capacity, DOE is assessing the need for collective, long-term storage of GTCC LLW. Potential risks to public health and safety caused by long-term storage of GTCC LLW at the place of generation will be evaluated to determine if alternative facilities are warranted. If warranted, several options will be investigated to determine the preferred alternative for long-term storage. These options include modification of an existing DOE facility, development of a new DOE facility, or development of a facility by the private sector with or without DOE support. Reasonable costs for long-term storage would be borne by the waste generators. 5 refs., 1 fig

  3. Red blood cell storage duration and long-term mortality in patients undergoing cardiac intervention

    DEFF Research Database (Denmark)

    Dencker, D; Pedersen, F; Engstrøm, T

    2017-01-01

    OBJECTIVES: To study the effect of red blood cell (RBC) storage duration on long-term mortality in patients undergoing cardiac intervention. BACKGROUND: RBCs undergo numerous structural and functional changes during storage. Observational studies have assessed the association between RBC storage...... duration and patient outcomes with conflicting results. METHODS: Between January 2006 and December 2014, 82 408 patients underwent coronary angiography. Of these, 1856 patients received one to four RBC units within 30 days after this procedure. Patients were allocated according to length of RBC storage...

  4. Laboratory Testing of Solar Combi System with Compact Long Term PCM Heat Storage

    DEFF Research Database (Denmark)

    Johansen, Jakob Berg; Englmair, Gerald; Dannemand, Mark

    2016-01-01

    To enable the transition from fossil fuels as a primary heat source for domestic hot water preparation and space heating solar thermal energy has great potential. The heat from the sun has the disadvantage that it is not always available when there is a demand. To solve this mismatch a thermal...... seasonal storage can be used to store excess heat from the summer to the winter when the demand is higher than the supply. Installing a long term thermal storage in a one family house it needs to be compact and sensible heat storages are not suitable. A latent heat storage with a phase change material (PCM...

  5. Preliminary long-term stability criteria for compressed air energy storage caverns in salt domes

    Energy Technology Data Exchange (ETDEWEB)

    Thoms, R.L.; Martinez, J.D.

    1978-08-01

    Air storage caverns, which are an essential and integral component of a CAES plant, should be designed and operated so as to perform satisfactorily over the intended life of the overall facility. It follows that the long-term ''stability'' of air storage caverns must be considered as a primary concern in projecting the satisfactory operation of CAES facilities. As used in the report, ''stability'' of a storage cavern implies the extent to which an acceptable amount of cavern storage volume can be utilized with routine maintenance for a specified time interval, e.g., 35 years. In this context, cavern stability is relative to both planned utilization and time interval of operation. The objective of the study was to review the existing literature and consult knowledgeable workers in the storage industry, and then report state-of-the-art findings relative to long-term stability of compressed air energy storage caverns in salt domes. Further, preliminary cavern stability criteria were to be presented in a form consistent with the amount of information available on cavern performance in salt domes. Another objective of the study was to outline a methodology for determining the long-term stability of site-specific CAES cavern systems in salt domes.

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

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  7. Introducing Systematic Aging Management for Interim Storage Facilities in Germany

    International Nuclear Information System (INIS)

    Spieth-Achtnich, Angelika; Schmidt, Gerhard

    2014-01-01

    In Germany twelve at-reactor and three central (away from reactor) dry storage facilities are in operation, where the fuel is stored in combined transport-and-storage casks. The safety of the storage casks and facilities has been approved and is licensed for up to 40 years operating time. If the availability of a final disposal facility for the stored wastes (spent fuel and high-level wastes from reprocessing) will be further delayed the renewal of the licenses can become necessary in future. Since 2001 Germany had a regulatory guideline for at-reactor dry interim storage of spent fuel. In this guideline some elements of ageing were implemented, but no systematic approach was made for a state-of-the-art ageing management. Currently the guideline is updated to include all kind of storage facilities (central storages as well) and all kinds of high level waste (also waste from reprocessing). Draft versions of the update are under discussion. In these drafts a systematic ageing management is seen as an instrument to upgrade the available technical knowledge base for possible later regulatory decisions, should it be necessary to prolong storage periods to beyond the currently approved limits. It is further recognized as an instrument to prevent from possible and currently unrecognized ageing mechanisms. The generation of information on ageing can be an important basis for the necessary safety-relevant verifications for long term storage. For the first time, the demands for a systematic monitoring of ageing processes for all safety-related components of the storage system are described. In addition, for inaccessible container components such as the seal system, the neutron shielding, the baskets and the waste inventory, the development of a monitoring program is recommended. The working draft to the revised guideline also contains recommendations on non-technical ageing issues such as the long-term preservation of knowledge, long term personnel planning and long term

  8. Interim dry fuel storage for magnox reactors

    Energy Technology Data Exchange (ETDEWEB)

    Bradley, N [National Nuclear Corporation, Risley, Warrington (United Kingdom); Ealing, C [GEC Energy Systems Ltd, Whetstone, Leicester (United Kingdom)

    1985-07-01

    In the UK the practice of short term buffer storage in water ponds prior to chemical reprocessing had already been established on the early gas cooled reactors in Calder Hall. Thus the choice of water pond buffer storage for MGR power plants logically followed the national policy decision to reprocess. The majority of the buffer storage period would take place at the reprocessing plant with only a nominal of 100 days targeted at the station. Since Magnox clad fuel is not suitable for long term pond storage, alternative methods of storage on future stations was considered desirable. In addition to safeguards considerations the economic aspects of the fuel cycle has influenced the conclusion that today the purchase of a MGR power plant with dry spent fuel storage and without commitment to reprocess would be a rational decision for a country initiating a nuclear programme. Dry storage requirements are discussed and two designs of dry storage facilities presented together with a fuel preparation facility.

  9. Interim dry fuel storage for magnox reactors

    International Nuclear Information System (INIS)

    Bradley, N.; Ealing, C.

    1985-01-01

    In the UK the practice of short term buffer storage in water ponds prior to chemical reprocessing had already been established on the early gas cooled reactors in Calder Hall. Thus the choice of water pond buffer storage for MGR power plants logically followed the national policy decision to reprocess. The majority of the buffer storage period would take place at the reprocessing plant with only a nominal of 100 days targeted at the station. Since Magnox clad fuel is not suitable for long term pond storage, alternative methods of storage on future stations was considered desirable. In addition to safeguards considerations the economic aspects of the fuel cycle has influenced the conclusion that today the purchase of a MGR power plant with dry spent fuel storage and without commitment to reprocess would be a rational decision for a country initiating a nuclear programme. Dry storage requirements are discussed and two designs of dry storage facilities presented together with a fuel preparation facility

  10. Safety and optimization aspects of radioactive waste long-term storage at the ''Vector'' site

    International Nuclear Information System (INIS)

    Tokarevs'kij, O.V.; Kondrat'jev, S.M.; Aleksjejeva, Z.M.; Ribalka, N.V.

    2015-01-01

    The paper analyzes links between the final disposal option and needs for long-term storage of radioactive waste taking into proposals on possible changes in radwaste classification as regards disposal. It considers the conceptual approach to design facilities for long-term storage of long-lived radioactive waste at the Vector site and approaches to apply requirements of regulatory documents, radiation safety principles and criteria for long-term storage of radwaste and safety assessment.

  11. Characterization of pollucite as a material for the long term storage of cesium-137

    International Nuclear Information System (INIS)

    Strachan, D.M.; Schulz, W.W.

    1977-06-01

    Storage of nuclear waste requires materials which are thermodynamically stable. Pollucite (Cs 2 O . Al 2 O 3 . 4SiO 2 ) may be an acceptable material for the long-term storage of the purified 137 CsCl. Pollucite is made at near theoretical yields when CsCl (or any cesium salt) reacts at about 970 0 K with a montmorillonite-containing clay. Pollucite dissolves in deionized water at rates which are less than 2 x 10 -9 kg/(m 2 . s) based on cesium. Microstructural analyses show that cesium reacts with the montmorillonite clay to form ill-defined pollucite crystals which contain low concentrations of the impurities found in the clay. Although further work needs to be done, pollucite is considered to be an excellent material for the long-term storage of 137 Cs

  12. Long-term storage of radioactive waste: IAEA perspectives on safety and sustainability

    International Nuclear Information System (INIS)

    Rowat, J.H.; Louvat, D.; Metcalf, P.E.

    2006-01-01

    As the amounts of radioactive waste in surface storage have increased, concern has grown over the safety and sustainability of storage in the long term. In response to increasing concerns, the International Atomic Energy Agency (IAEA) has included an action to address the safety implications of the long-term storage (LTS) of radioactive waste in its action plan for waste safety; the action plan was endorsed by the IAEA's Member States in 2001. In 2003, the IAEA published a position paper on the safety and sustainability of LTS as part fulfilment of the action in question. A key theme of the position paper is the contrast of safety and sustainability implications of LTS with those of disposal. The present paper provides a summary of the position paper, describes current IAEA activities that deal with the subject of LTS, and discusses findings from the 2004 Cordoba symposium on disposal of low activity radioactive waste that pertain to LTS. (author)

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  14. Final Long-Term Management and Storage of Elemental Mercury Environmental Impact Statement Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    2011-01-01

    Pursuant to the Mercury Export Ban Act of 2008 (P.L. 110-414), DOE was directed to designate a facility or facilities for the long-term management and storage of elemental mercury generated within the United States. Therefore, DOE has analyzed the storage of up to 10,000 metric tons (11,000 tons) of elemental mercury in a facility(ies) constructed and operated in accordance with the Solid Waste Disposal Act, as amended by the Resource Conservation and Recovery Act (74 FR 31723). DOE prepared this Final Mercury Storage EIS in accordance with the National Environmental Policy Act of 1969 (NEPA), as amended (42 U.S.C. 4321 et seq.), the Council on Environmental Quality (CEQ) implementing regulations (40 CFR 1500–1508), and DOE’s NEPA implementing procedures (10 CFR 1021) to evaluate reasonable alternatives for a facility(ies) for the long-term management and storage of elemental mercury. This Final Mercury Storage EIS analyzes the potential environmental, human health, and socioeconomic impacts of elemental mercury storage at seven candidate locations: Grand Junction Disposal Site near Grand Junction, Colorado; Hanford Site near Richland, Washington; Hawthorne Army Depot near Hawthorne, Nevada; Idaho National Laboratory near Idaho Falls, Idaho; Kansas City Plant in Kansas City, Missouri; Savannah River Site near Aiken, South Carolina; and Waste Control Specialists, LLC, site near Andrews, Texas. As required by CEQ NEPA regulations, the No Action Alternative was also analyzed as a basis for comparison. DOE intends to decide (1) where to locate the elemental mercury storage facility(ies) and (2) whether to use existing buildings, new buildings, or a combination of existing and new buildings. DOE’s Preferred Alternative for the long-term management and storage of mercury is the Waste Control Specialists, LLC, site near Andrews, Texas.

  15. Final Long-Term Management and Storage of Elemental Mercury Environmental Impact Statement Volume1

    Energy Technology Data Exchange (ETDEWEB)

    2011-01-01

    Pursuant to the Mercury Export Ban Act of 2008 (P.L. 110-414), DOE was directed to designate a facility or facilities for the long-term management and storage of elemental mercury generated within the United States. Therefore, DOE has analyzed the storage of up to 10,000 metric tons (11,000 tons) of elemental mercury in a facility(ies) constructed and operated in accordance with the Solid Waste Disposal Act, as amended by the Resource Conservation and Recovery Act (74 FR 31723).DOE prepared this Final Mercury Storage EIS in accordance with the National Environmental Policy Act of 1969 (NEPA), as amended (42 U.S.C. 4321 et seq.), the Council on Environmental Quality (CEQ) implementing regulations (40 CFR 1500–1508), and DOE’s NEPA implementing procedures (10 CFR 1021) to evaluate reasonable alternatives for a facility(ies) for the long-term management and storage of elemental mercury. This Final Mercury Storage EIS analyzes the potential environmental, human health, and socioeconomic impacts of elemental mercury storage at seven candidate locations:Grand Junction Disposal Site near Grand Junction, Colorado; Hanford Site near Richland, Washington; Hawthorne Army Depot near Hawthorne, Nevada; Idaho National Laboratory near Idaho Falls, Idaho;Kansas City Plant in Kansas City, Missouri; Savannah River Site near Aiken, South Carolina; and Waste Control Specialists, LLC, site near Andrews, Texas. As required by CEQ NEPA regulations, the No Action Alternative was also analyzed as a basis for comparison. DOE intends to decide (1) where to locate the elemental mercury storage facility(ies) and (2) whether to use existing buildings, new buildings, or a combination of existing and new buildings. DOE’s Preferred Alternative for the long-term management and storage of mercury is the Waste Control Specialists, LLC, site near Andrews, Texas.

  16. Intended long term performances of cementitious engineered barriers for future storage and disposal facilities for radioactive wastes in Romania

    Directory of Open Access Journals (Sweden)

    Sociu F.

    2013-07-01

    Full Text Available Considering the EU statements, Romania is engaged to endorse in the near future the IAEA relevant publications on geological repository (CNCANa, to update the Medium and Long Term National Strategy for Safe Management of Radioactive Waste and to approve the Road Map for Geological Repository Development. Currently, for example, spent fuel is wet stored for 6 years and after this period it is transported to dry storage in MACSTOR-200 (a concrete monolithic module where it is intended to remain at least 50 years. The present situation for radioactive waste management in Romania is reviewed in the present paper. Focus will be done on existent disposal facilities but, also, on future facilities planned for storage / disposal of radioactive wastes. Considering specific data for Romanian radioactive waste inventory, authors are reviewing the advance in the radioactive waste management in Romania considering its particularities. The team tries to highlight the expected limitations and unknown data related with cementitious engineered barriers that has to be faced in the near future incase of interim storage or for the upcoming long periods of disposal.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-07-01

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

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

    International Nuclear Information System (INIS)

    Wetzel, N.; Rabe, O.

    2004-01-01

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

  19. 9975 Shipping Package Performance Of Alternate Materials For Long-Term Storage Application

    International Nuclear Information System (INIS)

    Skidmore, E.; Hoffman, E.; Daugherty, W.

    2010-01-01

    The Model 9975 shipping package specifies the materials of construction for its various components. With the loss of availability of material for two components (cane fiberboard overpack and Viton(reg s ign) GLT O-rings), alternate materials of construction were identified and approved for use for transport (softwood fiberboard and Viton(reg s ign) GLT-S O-rings). As these shipping packages are part of a long-term storage configuration at the Savannah River Site, additional testing is in progress to verify satisfactory long-term performance of the alternate materials under storage conditions. The test results to date can be compared to comparable results on the original materials of construction to draw preliminary conclusions on the performance of the replacement materials.

  20. Influence of long-term storage on fire hazard properties of metal nanopowders

    Science.gov (United States)

    Kyrmakova, O. S.; Sechin, A. I.; Nazarenko, O. B.

    2017-08-01

    The production and application of nanomaterials is rapidly expanding. Therefore the problem of their properties change during long-term storage becomes essential. The properties of metal nanopowders after long-term storage under ambient conditions were studied and the results are presented in this work. The aluminum, iron, zinc, and copper nanopowders produced by the method of electrical explosion of wires were investigated in this work. The investigation was carried out by X-ray and thermal analysis. The estimation of the flame propagation velocity in the bulk layer of nanopowders was carried out. The characteristics of the nanopowders of nanometals studied are given in terms of their fire hazard. The results can be used for diagnostic of fire hazard of nanomaterials and protection of the enterprises against fire and explosion.

  1. Synaptic remodeling, synaptic growth and the storage of long-term memory in Aplysia.

    Science.gov (United States)

    Bailey, Craig H; Kandel, Eric R

    2008-01-01

    Synaptic remodeling and synaptic growth accompany various forms of long-term memory. Storage of the long-term memory for sensitization of the gill-withdrawal reflex in Aplysia has been extensively studied in this respect and is associated with the growth of new synapses by the sensory neurons onto their postsynaptic target neurons. Recent time-lapse imaging studies of living sensory-to-motor neuron synapses in culture have monitored both functional and structural changes simultaneously so as to follow remodeling and growth at the same specific synaptic connections continuously over time and to examine the functional contribution of these learning-related structural changes to the different time-dependent phases of memory storage. Insights provided by these studies suggest the synaptic differentiation and growth induced by learning in the mature nervous system are highly dynamic and often rapid processes that can recruit both molecules and mechanisms used for de novo synapse formation during development.

  2. Developing new transportable storage casks for interim dry storage

    International Nuclear Information System (INIS)

    Hayashi, K.; Iwasa, K.; Araki, K.; Asano, R.

    2004-01-01

    Transportable storage metal casks are to be consistently used during transport and storage for AFR interim dry storage facilities planning in Japan. The casks are required to comply with the technical standards of regulations for both transport (hereinafter called ''transport regulation'') and storage (hereafter called ''storage regulation'') to maintain safety functions (heat transfer, containment, shielding and sub-critical control). In addition to these requirements, it is not planned in normal state to change the seal materials during storage at the storage facility, therefore it is requested to use same seal materials when the casks are transported after storage period. The dry transportable storage metal casks that satisfy the requirements have been developed to meet the needs of the dry storage facilities. The basic policy of this development is to utilize proven technology achieved from our design and fabrication experience, to carry out necessary verification for new designs and to realize a safe and rational design with higher capacity and efficient fabrication

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

    International Nuclear Information System (INIS)

    Kato, Osamu; Ito, Chihiro; Saegusa, Toshiari

    1996-01-01

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

  4. Post-thaw sperm characteristics following long-term storage of boar semen in liquid nitrogen.

    Science.gov (United States)

    Fraser, L; Strzeżek, J; Kordan, W

    2014-06-30

    This study investigated the effect of long-term liquid nitrogen storage of semen from individual boars on post-thaw sperm characteristics. Ejaculates, collected from five Polish large white (PLW) and five Polish landrace (PLR) boars, were frozen using a standard cryopreservation protocol. Post-thaw analysis was performed within a week (Period 1) and 42-48 months (Period 2) of semen storage in liquid nitrogen. Post-thaw sperm assessments included total motility, mitochondrial function (JC-1/PI assay), plasma membrane integrity (SYBR-14/PI assay), osmotic resistance test (ORT), lipid peroxidation (LPO) status and DNA fragmentation, analysed by the neutral Comet assay. Individual boar variability within breed and cryostorage periods had significant effects on the analysed parameters of frozen-thawed spermatozoa. Prolonged semen storage in liquid nitrogen (Period 2) induced a marked reduction in post-thaw sperm motility, mitochondrial function and plasma membrane integrity in most of the boars. Post-thaw semen of eight boars exhibited a marked decrease in osmotic resistance of the sperm acrosomal membrane, whereas a significant increase in the sperm cryo-susceptibility to induced LPO and DNA fragmentation was observed only in three boars after long-term semen storage. Additionally, frozen-thawed spermatozoa of PLR boars exhibited significantly lower osmotic resistance of the acrosomal membrane than PLW boars following prolonged semen storage in liquid nitrogen. The results of this study provide evidence of ageing processes in frozen-thawed boar spermatozoa following prolonged cryostorage. It seems that, even though cryopreservation allows long-term semen storage in liquid nitrogen, spermatozoa from individual boars are more susceptible to cryo-induced damage. Copyright © 2014 Elsevier B.V. All rights reserved.

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

    International Nuclear Information System (INIS)

    Pettersson, K.; Jansson, L.

    1979-01-01

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

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

    International Nuclear Information System (INIS)

    Pettersson, K.; Jansson, L.

    1979-06-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-07-01

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

  8. Fifth Interim Status Report: Model 9975 PCV O-Ring Fixture Long-Term Leak Performance

    International Nuclear Information System (INIS)

    Daugherty, W.; Hoffman, E.

    2010-01-01

    A series of experiments to monitor the aging performance of Viton reg. GLT O-rings used in the Model 9975 package has been ongoing for six years at the Savannah River National Laboratory. Sixty-seven mock-ups of 9975 Primary Containment Vessels (PCVs) were assembled and heated to temperatures ranging from 200 to 450 F. They were leak-tested initially and have been tested at nominal six month intervals to determine if they meet the criterion of leaktightness defined in ANSI standard N14.5-97. Fourteen additional tests were initiated in 2008 with GLT-S O-rings heated to temperatures ranging from 200 to 400 F. High temperature aging continues for 36 GLT O-ring fixtures at 200--350 F. Room temperature leak test failures have been experienced in 5 of the GLT O-ring fixtures aging at 300 and 350 F, and in all 3 of the GLT O-ring fixtures aging at higher temperatures. No failures have yet been observed in GLT O-ring fixtures aging at 200 F for 30--48 months, which is still bounding to O-ring temperatures during storage in KAMS. High temperature aging continues for 6 GLT-S O-ring fixtures at 200--300 F. Room temperature leak test failures have been experienced in all 8 of the GLT-S O-ring fixtures aging at 350 and 400 F. No failures have yet been observed in GLT-S O-ring fixtures aging at 200 or 300 F for 19 months. For O-ring fixtures that have failed the room temperature leak test and been disassembled, the O-rings displayed a compression set ranging from 51--95%. This is significantly greater than seen to date for packages inspected during KAMS field surveillance (23% average). For GLT O-rings, service life based on the room temperature leak rate criterion is comparable to that predicted by compression stress relaxation (CSR) data at higher temperatures (350--400 F). While there are no comparable failure data yet at aging temperatures below 300 F, extrapolations of the data for GLT O-rings suggests that CSR model predictions provide a conservative prediction of service

  9. Concrete storage cask for interim storage of spent nuclear fuel

    International Nuclear Information System (INIS)

    Nabemoto, Toyonobu; Fujiwara, Hiroaki; Kobayashi, Shunji; Shionaga, Ryosuke

    2004-01-01

    Experiments and analytical evaluation of the fabrication, non-destructive inspection and structural integrity of reinforced concrete body for storage casks were carried out to demonstrate the concrete storage cask for spent fuel generated from nuclear power plants. Analytical survey on the type of concrete material and fabrication method of the storage cask was performed and the most suitable fabrication method for the concrete body was identified to reduce concrete cracking. The structural integrity of the concrete body of the storage cask under load conditions during storage was confirmed and the long term integrity of concrete body against degradation dependent on environmental factors was evaluated. (author)

  10. Long-term storage method for soft X-ray irradiated 'Hyuganatsu' pollen

    International Nuclear Information System (INIS)

    Yano, S.; Tanaka, M.; Ohara, N.

    2008-01-01

    The long-term storage conditions for 'Hyuganatsu ' pollen that had been irradiated with soft X-rays was examined. This study, was aimed at production of 'Tosa-buntan' without formation of nuclear fruit. 1. We evaluated the germination rate of pollen that had been irradiated with soft X-ray (500 or 1,000 Gy) and stored at 3 deg C, -20 deg C, and -40 deg C. The germination rate was the same as that of unirradiated pollen, even after storage for 1 year. Soft X-ray irradiation did not influence the storage attributes of pollen. 2. In unirradiated pollen and pollen that had been irradiated with soft X-ray (500 or 1,000 Gy), temperature conditions necessary for storing from 3 months to 1 year were -20 deg C or less, and pollen stored at -40 deg C had a higher germination rate after 1 year. 3. The germination rate was 1% or less in 4 months if silica gel was sealed into a gas barrier bag with 1,000 Gy-irradiated pollen at a rate of 10:1 (w/w). The ability to germinate was completely lost after 1 year in these conditions. 4. We evaluated the effect of sealing methods on 1,000 Gy-irradiated pollen stored at -20 deg C. There was no difference in germination rates among pollen stored in gas-barrier bags, vacuum-packaged pollen, and pollen stored with nitrogen in gas-barrier bags. Moreover, the germination rate of 750 Gy-irradiated pollen stored at -20 deg C decreased from 3 months onwards when pollen was stored with a free-oxygen absorber (Ageless ZP). 5. Pollen that was treated with acetone before or after soft X-ray irradiation (750 Gy) withstood long-term storage of 1 year. Long-term storage was possible if pollen was stored at -20 deg C, as is the case for rough pollen

  11. Data collection and storage in long-term ecological and evolutionary studies: The Mongoose 2000 system.

    Science.gov (United States)

    Marshall, Harry H; Griffiths, David J; Mwanguhya, Francis; Businge, Robert; Griffiths, Amber G F; Kyabulima, Solomon; Mwesige, Kenneth; Sanderson, Jennifer L; Thompson, Faye J; Vitikainen, Emma I K; Cant, Michael A

    2018-01-01

    Studying ecological and evolutionary processes in the natural world often requires research projects to follow multiple individuals in the wild over many years. These projects have provided significant advances but may also be hampered by needing to accurately and efficiently collect and store multiple streams of the data from multiple individuals concurrently. The increase in the availability and sophistication of portable computers (smartphones and tablets) and the applications that run on them has the potential to address many of these data collection and storage issues. In this paper we describe the challenges faced by one such long-term, individual-based research project: the Banded Mongoose Research Project in Uganda. We describe a system we have developed called Mongoose 2000 that utilises the potential of apps and portable computers to meet these challenges. We discuss the benefits and limitations of employing such a system in a long-term research project. The app and source code for the Mongoose 2000 system are freely available and we detail how it might be used to aid data collection and storage in other long-term individual-based projects.

  12. Using electrophysiology to demonstrate that cueing affects long-term memory storage over the short term.

    Science.gov (United States)

    Maxcey, Ashleigh M; Fukuda, Keisuke; Song, Won S; Woodman, Geoffrey F

    2015-10-01

    As researchers who study working memory, we often assume that participants keep a representation of an object in working memory when we present a cue that indicates that the object will be tested in a couple of seconds. This intuitively accounts for how well people can remember a cued object, relative to their memory for that same object presented without a cue. However, it is possible that this superior memory does not purely reflect storage of the cued object in working memory. We tested the hypothesis that cues presented during a stream of objects, followed by a short retention interval and immediate memory test, can change how information is handled by long-term memory. We tested this hypothesis by using a family of frontal event-related potentials believed to reflect long-term memory storage. We found that these frontal indices of long-term memory were sensitive to the task relevance of objects signaled by auditory cues, even when the objects repeated frequently, such that proactive interference was high. Our findings indicate the problematic nature of assuming process purity in the study of working memory, and demonstrate that frequent stimulus repetitions fail to isolate the role of working memory mechanisms.

  13. Winery wastewater treatment by a combined process: long term aerated storage and Fenton's reagent.

    Science.gov (United States)

    Lucas, Marco S; Mouta, Maria; Pirra, António; Peres, José A

    2009-01-01

    The degradation of the organic pollutants present in winery wastewater was carried out by the combination of two successive steps: an aerobic biological process followed by a chemical oxidation process using Fenton's reagent. The main goal of this study was to evaluate the temporal characteristics of solids and chemical oxygen demand (COD) present in winery wastewater in a long term aerated storage bioreactor. The performance of different air dosage daily supplied to the biologic reactor, in laboratory and pilot scale, were examined. The long term hydraulic retention time, 11 weeks, contributed remarkably to the reduction of COD (about 90%) and the combination with the Fenton's reagent led to a high overall COD reduction that reached 99.5% when the mass ratio (R = H(2)O(2)/COD) used was equal to 2.5, maintaining constant the molar ratio H(2)O(2)/Fe(2+)=15.

  14. Long-term sera storage does not significantly modify the interpretation of toxoplasmosis serologies.

    Science.gov (United States)

    Dard, C; Bailly, S; Drouet, T; Fricker-Hidalgo, H; Brenier-Pinchart, M P; Pelloux, H

    2017-03-01

    Serological investigation of Toxoplasma gondii can answer many questions about toxoplasmosis in human pathology. Along these lines, studies on serum storage in biobanks need to be performed especially in terms of determining the impact of storage on relevance of sera analysis after freezing. This study assessed the impact of long-term sera storage on the stability of anti-Toxoplasma immunoglobulins. The stability of anti-Toxoplasma IgG and IgM was studied in 244 and 242 sera respectively, stored at -20°C from one month to ten years. ELISA-immunoassay (Vidas®, bioMérieux) was used for initial and post-storage analyses. Linear models for repeated measures and subgroup analyses were performed to assess the effect of storage duration and sample characteristics on immunoglobulins stability. Until ten years, the variability attributed to storage (maximum 8.07% for IgG, 13.17% for IgM) was below the variations inherent to the serological technique and allowed by quality assurance systems (15%). Subgroup analysis reported no variation attributed to sera storage. Serological interpretation was modified for 3 sera (1.2%) tested for IgM, all stored more than seven years. Anti-Toxoplasma immunoglobulins can reliably be measured for at least up to six years of storage with no modification of interpretation of toxoplasmosis serologies. Copyright © 2017 Elsevier B.V. All rights reserved.

  15. Summary report of the screening process to determine reasonable alternatives for long-term storage and disposition of weapons-usable fissile materials

    International Nuclear Information System (INIS)

    1995-01-01

    Significant quantities of weapons-usable fissile materials (primarily plutonium and highly enriched uranium) have become surplus to national defense needs both in the US and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety and health consequences if surplus fissile materials are not properly managed. As announced in the Notice of Intent (NOI) to prepare a Programmatic Environmental Impact Statement (PEIS), the Department of Energy is currently conducting an evaluation process for disposition of surplus weapons-usable fissile materials determined surplus to National Security needs, and long-term storage of national security and programmatic inventories, and surplus weapons-usable fissile materials that are not able to go directly from interim storage to disposition. An extensive set of long-term storage and disposition options was compiled. Five broad long-term storage options were identified; thirty-seven options were considered for plutonium disposition; nine options were considered for HEU disposition; and eight options were identified for Uranium-233 disposition. Section 2 discusses the criteria used in the screening process. Section 3 describes the options considered, and Section 4 provides a detailed summary discussions of the screening results

  16. Summary report of the screening process to determine reasonable alternatives for long-term storage and disposition of weapons-usable fissile materials

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-29

    Significant quantities of weapons-usable fissile materials (primarily plutonium and highly enriched uranium) have become surplus to national defense needs both in the US and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety and health consequences if surplus fissile materials are not properly managed. As announced in the Notice of Intent (NOI) to prepare a Programmatic Environmental Impact Statement (PEIS), the Department of Energy is currently conducting an evaluation process for disposition of surplus weapons-usable fissile materials determined surplus to National Security needs, and long-term storage of national security and programmatic inventories, and surplus weapons-usable fissile materials that are not able to go directly from interim storage to disposition. An extensive set of long-term storage and disposition options was compiled. Five broad long-term storage options were identified; thirty-seven options were considered for plutonium disposition; nine options were considered for HEU disposition; and eight options were identified for Uranium-233 disposition. Section 2 discusses the criteria used in the screening process. Section 3 describes the options considered, and Section 4 provides a detailed summary discussions of the screening results.

  17. Qualification of polysiloxanes for long-term storage of radioactive waste; Qualifizierung von Polysiloxanen fuer die langzeitstabile Konditionierung radioaktiver Abfaelle

    Energy Technology Data Exchange (ETDEWEB)

    Kucharczyk, P.

    2005-12-15

    At present German policy envisages interim storage of all radioactive waste (for approximately 30 years) until a final repository is available. This therefore leads to higher standards for storage containers. Silicone elastomers (polysiloxanes), materials on the basis of silicon and oxygen with organic substituents, have various physical and chemical properties and seem to be suitable for the long-term storage of low- and intermediate-level radioactive waste. The aim of the present work is the qualification of a new coating material for storage containers. The use of polysiloxanes in other applications was also investigated. An important criterion for the coating is the simplicity of its application. Moreover, it should also have a high adhesion on steel as well as providing protection against corrosion. These properties were investigated for different polysiloxanes. The spraying tests showed that polysiloxane material with a viscosity of up to 45 000 mPas could be applied by the airless spraying method. An elastic coating was produced which could ensure protection against mechanical impacts. In the framework of water vapour experiments, a very high diffusion constant was determined. The corrosion test confirmed that the polysiloxane coating provided only insufficient corrosion protection if the sample was in contact with water and water vapour at the same time. This problem was solved by using an additional priming coat of 60 {mu}m zinc paint. The adhesion test showed that polysiloxanes have different levels of adhesion. The best adhesion was determined for condensation-cured silicones. The addition-cured materials had a lower adhesion, which was improved by the application of a priming coat. The outcome of these investigations is a wide spectrum of applications for polysiloxanes which can be used as firmly adhering coatings or removable decontamination layers. (orig.)

  18. Advances in Large-Scale Solar Heating and Long Term Storage in Denmark

    DEFF Research Database (Denmark)

    Heller, Alfred

    2000-01-01

    According to (the) information from the European Large-Scale Solar Heating Network, (See http://www.hvac.chalmers.se/cshp/), the area of installed solar collectors for large-scale application is in Europe, approximately 8 mill m2, corresponding to about 4000 MW thermal power. The 11 plants...... the last 10 years and the corresponding cost per collector area for the final installed plant is kept constant, even so the solar production is increased. Unfortunately large-scale seasonal storage was not able to keep up with the advances in solar technology, at least for pit water and gravel storage...... of the total 51 plants are equipped with long-term storage. In Denmark, 7 plants are installed, comprising of approx. 18,000-m2 collector area with new plants planned. The development of these plants and the involved technologies will be presented in this paper, with a focus on the improvements for Danish...

  19. A long-term analysis of pumped hydro storage to firm wind power

    International Nuclear Information System (INIS)

    Foley, A.M.; Leahy, P.G.; Li, K.; McKeogh, E.J.; Morrison, A.P.

    2015-01-01

    Highlights: • This is a long term generation analysis of a high wind power system. • A high CO 2 and fossil fuel price is closest to Ireland’s EU ETS 2020 target. • New pumped storage to firm wind is limited unless strong market costs exist. • Reserve for wind power show that ancillary services are relevant for balancing. - Abstract: Although pumped hydro storage is seen as a strategic key asset by grid operators, financing it is complicated in new liberalised markets. It could be argued that the optimum generation portfolio is now determined by the economic viability of generators based on a short to medium term return on investment. This has meant that capital intensive projects such as pumped hydro storage are less attractive for wholesale electricity companies because the payback periods are too long. In tandem a significant amount of wind power has entered the generation mix, which has resulted in operating and planning integration issues due to wind’s inherent uncertain, varying spatial and temporal nature. These integration issues can be overcome using fast acting gas peaking plant or energy storage. Most analysis of wind power integration using storage to date has used stochastic optimisation for power system balancing or arbitrage modelling to examine techno-economic viability. In this research a deterministic dynamic programming long term generation expansion model is employed to optimise the generation mix, total system costs and total carbon dioxide emissions, and unlike other studies calculates reserve to firm wind power. The key finding of this study is that the incentive to build capital-intensive pumped hydro storage to firm wind power is limited unless exogenous market costs come very strongly into play. Furthermore it was demonstrated that reserve increases with increasing wind power showing the importance of ancillary services in future power systems

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

    Directory of Open Access Journals (Sweden)

    B. Yolanda Moratilla Soria

    2013-01-01

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

  1. Interim Storage of Spent Nuclear Fuel before Final Disposal in Germany - Regulator's view

    International Nuclear Information System (INIS)

    Arens, G.; Goetz, Ch.; Geupel, Sandra; Gmal, B.; Mester, W.

    2014-01-01

    For spent nuclear fuel management in Germany the concept of dry interim storage in dual purpose casks before direct disposal is applied. The Federal Office for Radiation Protection (BfS) is the competent authority for licensing of interim storage facilities. The competent authority for surveillance of operation is the responsible authority of the respective federal state (Land). Currently operation licenses for storage facilities have been granted for a storage time of 40 years and are based on safety demonstrations for all safety issues as safe enclosure, shielding, sub-criticality and decay heat removal under consideration of operation conditions. In addition, transportability of the casks for the whole storage period has to be provided. Due to current delay in site selection and exploration of a disposal site, an extension of the storage time beyond 40 years could be needed. This will cause appropriate actions by the licensee and the competent authorities as well. A brief description of the regulatory base of licensing and surveillance of interim storage is given from the regulators view. Furthermore the current planning for final disposal of spent nuclear fuel and high level waste and its interconnections between storage and disposal concepts are shortly explained. Finally the relevant aspects for licensing of extended storage time beyond 40 years will be discussed. Current activities on this issue, which have been initiated by the Federal Government, will be addressed. On the regulatory side a review and amendment of the safety guideline for interim storage of spent fuel has been performed and the procedure of periodic safety review is being implemented. A guideline for implementing an ageing management programme is available in a draft version. Regarding safety of long term storage a study focussing on the identification and evaluation of long term effects as well as gaps of knowledge has been finished in 2010. A continuation and update is currently underway

  2. Safety issues in construction of facilities for long-term storage of radioactive waste at vector site

    Energy Technology Data Exchange (ETDEWEB)

    Tokarevskyi, O.; Alekseeva, Z.; Kondratiev, S. [State Scientific and Technical Center for Nuclear and Radiation Safety, Kyiv (Ukraine); Rybalka, N. [State Nuclear Regulatory Inspectorate of Ukraine, Kyiv (Ukraine)

    2013-07-01

    In Ukraine, it is planned to create a number of near-surface facilities for disposal of short-lived RW and long-term (up to 100 years) storage of long-lived RW at the Vector site in the Chernobyl exclusion zone. The expected streams of long-lived RW are analyzed in the paper. According to the analysis of RW streams, in particular, issues are considered on development of RW acceptance criteria, admissible radiological impacts during preparation of RW for long-term storage, reliability of barriers (RW packages, modules and structures, etc.) during long-term storage of RW. (orig.)

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  4. Materials behavior in interim storage of spent fuel

    International Nuclear Information System (INIS)

    Johnson, A.B. Jr.; Bailey, W.J.; Gilbert, E.R.; Inman, S.C.

    1982-01-01

    Interim storage has emerged as the only current spent-fuel management method in the US and is essential in all countries with nuclear reactors. Materials behavior is a key aspect in licensing interim-storage facilities for several decades of spent-fuel storage. This paper reviews materials behavior in wet storage, which is licensed for light-water reactor (LWR) fuel, and dry storage, for which a licensing position for LWR fuel is developing

  5. Thermal behavior of neutron shielding material, NS-4-FR, under long term storage conditions

    International Nuclear Information System (INIS)

    Yamada, N.; O-iwa, A.; Asano, R.; Horita, R.; Kusunoki, K.

    2004-01-01

    NS-4-FR, Epoxy-Resin, has been widely used as a neutron shielding material for casks. It is recognized that the resin will degrade during storage and loose weight under high temperature conditions. Most of the examinations for the resin degrading behavior were conducted with rather small bare resin specimens. However, the actual quantity of neutron shielding is quite large and is covered by the cask body. To confirm the degrading behavior of the resin under the long-term storage conditions, we performed the test on the specimen with the same cross-section as the actual design, Hitz B69. The resin test vessels were made out of stainless steel and equipped with flange

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  7. Radiolytic gas production during long-term storage of nuclear wastes

    International Nuclear Information System (INIS)

    Bibler, N.E.

    1976-01-01

    Gases produced by in situ radiolysis of sealed solidified nuclear wastes during long-term storage could conceivably breach containment. Therefore, candidate waste forms (matrices containing simulated nuclear wastes) were irradiated with 60 Co-γ and 244 Cm-α radiation. These forms were: cement containing simulated fission product sludges, vermiculite containing organic liquids, and cellulosics contaminated with α-emitting transuranic isotopes. For cement waste forms exposed to γ-radiolysis, an equilibrium hydrogen pressure was reached that was dose rate dependent. For α-radiolysis, equilibrium was not reached. With organic wastes (n-octane on vermiculite), H 2 and traces of CO 2 and CH 4 were produced, and O 2 was consumed with both radiations. Only energy absorbed by the organic material was effective in producing H 2 . At low dose rates with both α- and γ-irradiations, G(H 2 ) was 4.5 and G(-O 2 ) was 5.0. Also, equilibrium was not obtained. For cellulosic material, H 2 , CO 2 , and CO were produced in the ratio of 1.0:0.7:0.3, and O 2 was consumed. With α-radiolysis, G(gas) was dose dependent; measured values ranged from 2.2 to 0.6 as the dose increased. Implications of all these results on long-term storage of radioactive waste are discussed. Some data from an actual nuclear wasteform are also presented

  8. Using zeolites for fixation and long-term storage of krypton

    International Nuclear Information System (INIS)

    Pirogova, G.N.; Voronin, Yu.V.; Pribylov, A.A.; Serpinskii, V.V.; Mirskii, Ya.V.; Almazova, B.B.; Golitsina, V.V.

    1993-01-01

    It is known that large quantities of 85 Kr are liberated during the operation of nuclear power plants and, in particular, during the processing of nuclear fuel. At the present time, there are several methods of its fixation (accumulation), viz., storage in high-pressure gas balloons, adsorption, plasma-aided implantation into metals, introduction into clathrate compounds, and obtaining kryptonates. Encapsulation in zeolites is one of the most promising methods. The merits of this method include safety during storage, a favorable volume-to-mass ratio, the possibility of separating krypton from a mixture of different gases, and purity of the encapsulated gas. The encapsulation technique has been developed quite recently. Several recent reports established the possibility of encapsulating krypton in the 3A-type zeolites. However, most of the investigators observed leakage during the storage of the zeolite-gas system and complete liberation of krypton from the zeolite during prolonged storage. This paper deals with a study of the encapsulation process of krypton in the zeolites obtained by cation exchange from NaA. The experimental specimens were characterized by the degree of exchange of sodium into potassium and cesium. It is known that the introduction of cesium into the structure (body) of a zeolite reduces the size of the window of entrance. All the synthesized specimens were used in their granulated form. The aim of this study was to develop zeolite specimens for carrying out long-term storage of krypton

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

    International Nuclear Information System (INIS)

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

    2017-01-01

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

  10. Conceptual design of interim storage facility for CNAI

    International Nuclear Information System (INIS)

    Fuenzalida Troyano, Carlos S.; Bergallo, Juan E.; Nassini, Horacio E.P.; Blanco, Anibal; Delmastro, Dario F.

    2007-01-01

    The reduced storage capacity available in the two spent fuel pools of argentine PHWR Atucha-1 power plant, the current plans for extending the reactor operation beyond its design lifetime, and the government decision on Atucha-2 NPP construction ending, have motivated the evaluation of a dry storage option for the interim management of spent fuel assemblies. Two different designs are presently being analyzed by an expert working group, from both technical and economical points of views. Authors are proposing a modular system consisting of an arrangement of reinforced concrete structures into which welded metallic canisters loaded with 37 spent fuel assemblies each stored in horizontal position. The reinforced concrete module is designed to provide the necessary physical protection and biological shielding to the loaded canisters during long-term storage, as well as passive means to remove the spent fuel decay heat by a combination of radiation, conduction and natural air convection. In this works are presented advances in the conceptual designs for a spent nuclear fuel system to Atucha I nuclear power plant. (author) [es

  11. Long-term stable, long-term safe storage of residues and radioactive waste. Contribution to discussion to the storage (final storage); Langzeitstabile, langzeitsichere Verwahrung von Rueckstaenden und radioaktiven Abfaellen. Beitrag zur Diskussion um Lagerung (Endlagerung)

    Energy Technology Data Exchange (ETDEWEB)

    Lersow, Michael [DGGT e.V., Breitenbrunn/Erzgeb. (Germany). Ak 5.5 Tailings; Gellermann, Rainer [Nuclear Control and Consulting GmbH, Braunschweig (Germany)

    2015-09-15

    In this paper it is presented, where radioactive waste and residues occur, how these materials can be classified, which rules and regulations have to be complied with regarding the disposal and which geotechnical environmental constructions (final repositories) are suitable to guarantee a safe long-term disposal of these materials. Primary protection objective is ''to permanently prevent the transfer of toxic, radioactive contaminations into the biosphere by air, water or rock path or to keep the amount of contamination within a commonly accepted range''. Radionuclide inventories and the given time period considered for long-term safety are compared with. It is shown, that the site-specific disposal solutions cannot be justified by the radioactive inventory deposited there. The given period of 10{sup 6} years is critically evaluated. Based on this it is suggested to subdivide this period into two time periods with different prognosis reliabilities. Results of a specially designed long-term monitoring as part of the site-specific waste disposal solution should be considered for the long-term safety proof. A modular concept for the final storage of High Active Waste (HAW) is derived based on the critical evaluation of the long-term safety, including transmutation, provisional storage and monitoring module. A foundation model is proposed to guarantee the financial resources required for the disposal of HAW.

  12. Long-term heat storage in calcium sulfoaluminate cement (CSA) based concrete

    Energy Technology Data Exchange (ETDEWEB)

    Kaufmann, Josef P.; Winnefeld, Frank [Empa Swiss Federal Laboratories for Materials Science and Technology, Duebendorf (Switzerland). Lab. for Concrete and Construction Chemistry

    2011-07-01

    in (long-term) storage of process heat. Any temperature source above about 80 C may be used.

  13. Development of long term storage technique for recovered Kr-85, (1)

    International Nuclear Information System (INIS)

    Inada, Eiichi; Motoyama, Shigeji; Tsunoda, Naomi; Yamamoto, Keizo; Hirano, Seiji.

    1979-01-01

    The adsorption storage method of radioactive krypton Kr-85 using a double cylinder packed with activated charcoal is expected to be put into practical use as an intermediate storing method until the immobilization technique for long term storage is established. In this paper, the conceptual design of an intermediate, remote-controlled Kr-85 storage facility is presented. The features of this system are double containment, low pressure storage, and remote control. Kr-85 is at first filled into a double cylinder by the adsorbing effect of activated charcoal at low temperature (-196 deg C) by cooling with liquid nitrogen. Then, the unwelded portion of the outer cylinder containing the inner cylinder is welded and inspected to make double containment. The double cylinders are cooled by ventilation to remove the decay heat of Kr-85, and krypton leakage is always monitored. If any leakage is detected, the double cylinder is transferred to the cutting cell for the re-encapsulation of Kr-85 in a safe double cylinder. All operations are performed by remote control because of a high radiation field. The expected amount and composition of Kr-85 to be recovered from the reprocessing plant are also given as the design conditions. (Wakatsuki, Y.)

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

    International Nuclear Information System (INIS)

    Bergelson, Boris R.; Gerasimov, Aleksander S.

    1999-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-07-01

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

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

    International Nuclear Information System (INIS)

    Rashid, J.; Machiels, A.

    2001-01-01

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

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

    International Nuclear Information System (INIS)

    2006-12-01

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

  18. Developing new transportable storage casks for interim dry storage

    Energy Technology Data Exchange (ETDEWEB)

    Hayashi, K.; Iwasa, K.; Araki, K.; Asano, R. [Hitachi Zosen Diesel and Engineering Co., Ltd., Tokyo (Japan)

    2004-07-01

    Transportable storage metal casks are to be consistently used during transport and storage for AFR interim dry storage facilities planning in Japan. The casks are required to comply with the technical standards of regulations for both transport (hereinafter called ''transport regulation'') and storage (hereafter called ''storage regulation'') to maintain safety functions (heat transfer, containment, shielding and sub-critical control). In addition to these requirements, it is not planned in normal state to change the seal materials during storage at the storage facility, therefore it is requested to use same seal materials when the casks are transported after storage period. The dry transportable storage metal casks that satisfy the requirements have been developed to meet the needs of the dry storage facilities. The basic policy of this development is to utilize proven technology achieved from our design and fabrication experience, to carry out necessary verification for new designs and to realize a safe and rational design with higher capacity and efficient fabrication.

  19. Image storage and permanence considerations in the long-term preservation of photographic images - update 2010

    International Nuclear Information System (INIS)

    LaBarca, Joseph E

    2010-01-01

    Archivists and consumers, alike, need to become aware of long-term storage and preservation issues that relate to the preservation of the data behind digital photographic images. The more obvious issues, such as accidental or catastrophic data loss and hardware format evolution, are only now being recognized in the archiving community. Consumers need to be alerted to these issues and be prepared to develop preservation strategies as well. However, longer-term issues beyond routine backup and migration of data need to be considered. The very basic solution of preservation via hardcopy images stored in shoeboxes or albums is one option, but this raises a fundamental question regarding image preservation that transcends even the more complex solutions-the long-term stability of the chosen media, whether digital or analog. This paper discusses archiving and preservation as it relates to images, and the data behind those images, along with historical perspectives and an overview of possible longer-term preservation strategies. The importance of image permanence standards, as they relate to overall selection of preservation strategies, will also be discussed.

  20. Long-term assessment of the oil spill at Bahia Las Minas, Panama. Interim report. Volume 2: Technical report

    International Nuclear Information System (INIS)

    Keller, B.D.; Jackson, J.B.C.

    1991-10-01

    On April 27, 1986, at least 8 million liters of medium-weight crude oil spilled from a ruptured storage tank into the Bahia Las Minas on the Caribbean Coast of Panama. Coral reefs, seagrass communities, and mangroves were affected. The area of the spill was also the location of the Smithsonian Tropical Research Institute's Galeta Laboratory where resident and visiting scientists have been studying the ecology of the Bahia Las Minas and the adjacent areas for over 15 years. Because this was a unique opportunity to assess the immediate biological effects following a major spill in the Caribbean region and to monitor the subsequent recovery, the U.S. Department of the Interior Minerals Management Service supported a 5-year environmental study. The objectives of the study are to identify any long-term changes in the marine environment that may have resulted from the spill and to understand the ecological processes causing such changes. This is the first report from the study and addresses the effects observed during the first two years of the effort

  1. Long-term assessment of the oil spill at Bahia Las Minas, Panama. Interim report. Volume 1: Executive summary

    International Nuclear Information System (INIS)

    Keller, B.D.; Jackson, J.B.C.

    1991-10-01

    On April 27, 1986, at least 8 million liters of medium-weight crude oil spilled from a ruptured storage tank into the Bahia Las Minas on the Caribbean Coast of Panama. Coral reefs, seagrass communities, and mangroves were affected. The area of the spill was also the location of the Smithsonian Tropical Research Institute's Galeta Laboratory where resident and visiting scientists have been studying the ecology of the Bahia Las Minas and the adjacent areas for over 15 years. Because this was a unique opportunity to assess the immediate biological effects following a major spill in the Caribbean region and to monitor the subsequent recovery, the U.S. Department of the Interior Minerals Management Service supported a 5-year environmental study. The objectives of the study are to identify any long-term changes in the marine environment that may have resulted from the spill and to understand the ecological processes causing such changes. This is the first report from the study and addresses the effects observed during the first two years of the effort

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

    Energy Technology Data Exchange (ETDEWEB)

    Standring, P [Sellafield Limited (United Kingdom)

    2012-07-01

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

  3. Investigation on polyetheretherketone composite for long term storage of nuclear waste

    Science.gov (United States)

    Ajeesh, G.; Bhowmik, Shantanu; Sivakumar, Venugopal; Varshney, Lalit; Kumar, Virendra; Abraham, Mathew

    2015-12-01

    This investigation highlights the effect of radiation, chemical and thermal environments on mechanical and thermal properties of Polyetheretherketone (PEEK) composites, which could prove to be an alternative material for long term storage of nuclear wastes. The tests are conducted on specimens made from PEEK and PEEK reinforced with carbon short fiber. The specimens are subjected to radiation doses, equivalent to the cumulative dosage for 500 years followed by exposure under highly corrosive and thermal environments. Studies under optical microscopy reveal that the dispersion of carbon short fiber in the PEEK Composites is significantly uniform. Differential scanning calorimeter (DSC) and thermo gravimetric analysis (TGA) indicates that there are no significant changes in thermal properties of PEEK composite when exposed to aggressive environments. It is further observed that there are no significant changes in mechanical properties of the composite after exposure to radiation and thermo-chemical environment.

  4. Investigation on polyetheretherketone composite for long term storage of nuclear waste

    International Nuclear Information System (INIS)

    Ajeesh, G.; Bhowmik, Shantanu; Sivakumar, Venugopal; Varshney, Lalit; Kumar, Virendra; Abraham, Mathew

    2015-01-01

    This investigation highlights the effect of radiation, chemical and thermal environments on mechanical and thermal properties of Polyetheretherketone (PEEK) composites, which could prove to be an alternative material for long term storage of nuclear wastes. The tests are conducted on specimens made from PEEK and PEEK reinforced with carbon short fiber. The specimens are subjected to radiation doses, equivalent to the cumulative dosage for 500 years followed by exposure under highly corrosive and thermal environments. Studies under optical microscopy reveal that the dispersion of carbon short fiber in the PEEK Composites is significantly uniform. Differential scanning calorimeter (DSC) and thermo gravimetric analysis (TGA) indicates that there are no significant changes in thermal properties of PEEK composite when exposed to aggressive environments. It is further observed that there are no significant changes in mechanical properties of the composite after exposure to radiation and thermo-chemical environment.

  5. Formation and Maintenance of Robust Long-Term Information Storage in the Presence of Synaptic Turnover.

    Directory of Open Access Journals (Sweden)

    Michael Fauth

    2015-12-01

    Full Text Available A long-standing problem is how memories can be stored for very long times despite the volatility of the underlying neural substrate, most notably the high turnover of dendritic spines and synapses. To address this problem, here we are using a generic and simple probabilistic model for the creation and removal of synapses. We show that information can be stored for several months when utilizing the intrinsic dynamics of multi-synapse connections. In such systems, single synapses can still show high turnover, which enables fast learning of new information, but this will not perturb prior stored information (slow forgetting, which is represented by the compound state of the connections. The model matches the time course of recent experimental spine data during learning and memory in mice supporting the assumption of multi-synapse connections as the basis for long-term storage.

  6. Colour changes in prints during long-term dark storage of prints

    International Nuclear Information System (INIS)

    Parraman, Carinna

    2010-01-01

    The most significant impact on colour fading in prints is exposure to light and air. However what happens to coloured prints during long-term storage in boxes, drawers and on shelves? Measurements of samples, printed in July 2005, stored in a range of light and darkened storage conditions have shown some interesting initial results. As more emphasis is placed on the effects of light, the dark stability of inkjet prints is relatively overlooked when considering how to preserve or store coloured prints. This study and presentation builds on previous research [1] and has concentrated on the changes to colour during storage. With reference to ASTM F2035 - 00(2006) Standard Practice for Measuring the Dark Stability of Ink Jet Prints, the Standards outline points out that whilst natural aging is the most reliable method of assessing image stability, materials and inks any data that is produced quickly becomes redundant; therefore accelerated aging is more preferred. However, the fine art materials in this study are still very much in circulation. The leading fine art papers, and pigmented ink-sets used in these trials are still being used by artists. We can therefore demonstrate the characteristics of colour changes and the impact of ink on paper that utilises natural aging methods.

  7. An experimental study on the long-term stability of particle motion in hadron storage rings

    International Nuclear Information System (INIS)

    Fischer, W.

    1995-12-01

    Nonlinear magnetic fields in conjunction with tune modulation may lead to chaotic particle motion and thereby limit the dynamic aperture in hadron storage rings. This is on particular interest for high energy storage rings with superconducting magnets at injection energy where magnetic field errors and the beam size have their maximum values. At the CERN SPS a dynamic aperture experiment was performed with the aim of finding the relevant effects for the stability of single particle motion in hadron storage rings. Experimental results are compared to long-term particle tracking to test to which extent computer programs can predict the dynamic aperture under well known conditions. In addition, detailed investigations of the loss mechanisms were pursued to improve the phenomenological understanding of the intricate details of particle motion in phase space. In a complementary experiment at the HERA proton ring at injection energy the dynamic aperture was measured under normal operating conditions. The computer simulations for these measurements included a very detailed model of the nonlinear fields which were measured for each individual magnet. Simulation results for the LHC are shown that estimate the effect of tune ripple of different strength on the dynamic aperture for different sets of random nonlinear field errors. (orig.)

  8. Long-term storage life of light source modules by temperature cycling accelerated life test

    International Nuclear Information System (INIS)

    Sun Ningning; Tan Manqing; Li Ping; Jiao Jian; Guo Xiaofeng; Guo Wentao

    2014-01-01

    Light source modules are the most crucial and fragile devices that affect the life and reliability of the interferometric fiber optic gyroscope (IFOG). While the light emitting chips were stable in most cases, the module packaging proved to be less satisfactory. In long-term storage or the working environment, the ambient temperature changes constantly and thus the packaging and coupling performance of light source modules are more likely to degrade slowly due to different materials with different coefficients of thermal expansion in the bonding interface. A constant temperature accelerated life test cannot evaluate the impact of temperature variation on the performance of a module package, so the temperature cycling accelerated life test was studied. The main failure mechanism affecting light source modules is package failure due to solder fatigue failure including a fiber coupling shift, loss of cooling efficiency and thermal resistor degradation, so the Norris-Landzberg model was used to model solder fatigue life and determine the activation energy related to solder fatigue failure mechanism. By analyzing the test data, activation energy was determined and then the mean life of light source modules in different storage environments with a continuously changing temperature was simulated, which has provided direct reference data for the storage life prediction of IFOG. (semiconductor devices)

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

    International Nuclear Information System (INIS)

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

    2014-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Kamimura, K [JNES (Japan)

    2012-07-01

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

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

    International Nuclear Information System (INIS)

    Bevilacqua, Arturo

    2014-01-01

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

  12. German Approach for the Transport of Spent Fuel Packages after Interim Storage

    International Nuclear Information System (INIS)

    Wille, Frank; Wolff, Dietmar; Droste, Bernhard; Voelzke, Holger

    2014-01-01

    In Germany the concept of dry interim storage of spent nuclear fuel in dual purpose metal casks is implemented, currently for periods of up to 40 years. The casks being used have an approved package design in accordance with the international transport regulations. The license for dry storage is granted on the German Atomic Energy Act with respect to the recently (in 2012) revised 'Guidelines for dry cask storage of spent nuclear fuel and heat-generating waste' by the German Waste management Commission (ESK) which are very similar to the former RSK (reactor safety commission) guidelines. For transport on public routes between or after long term interim storage periods, it has to be ensured that the transport and storage casks fulfil the specifications of the transport approval or other sufficient properties which satisfy the proofs for the compliance of the safety objectives at that time. In recent years the validation period of transport approval certificates for manufactured, loaded and stored packages were discussed among authorities and applicants. A case dependent system of 3, 5 and 10 years was established. There are consequences for the safety cases in the Package Design Safety Report including evaluation of long term behavior of components and specific operating procedures of the package. Present research and knowledge concerning the long term behavior of transport and storage cask components have to be consulted as well as experiences from interim cask storage operations. Challenges in the safety assessment are e.g. the behavior of aged metal and elastomeric seals under IAEA test conditions to ensure that the results of drop tests can be transferred to the compliance of the safety objectives at the time of transport after the interim storage period (aged package). Assessment methods for the material compatibility, the behavior of fuel assemblies and the aging behavior of shielding parts are issues as well. This paper describes the state

  13. INAA applied to halogen (Br and I) stability in long-term storage of lyophilized biological materials

    International Nuclear Information System (INIS)

    Zaichick, V.; Zaichick, S.

    2000-01-01

    Instrumental neutron activation analysis (INAA) was used to determine the Br and I concentration in the same ten lyophilized and homogenized human thyroid samples prior and after a 20-year storage at room temperature. It was found that long-term storage had no effect on the iodine content. At the same time, the bromine content was about 2-fold lower (p<0.01). It was assumed that possible losses of other halogens can occur under long-term storage of lyophilized biological materials at room temperature. (author)

  14. Options for the interim storage of spent fuel

    International Nuclear Information System (INIS)

    Kromar, M.; Kurincic, B.

    1995-01-01

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

  15. New a-Si:H photo-detectors for long-term charge storage

    International Nuclear Information System (INIS)

    Lee, H.; Cho, G.; Drewery, J.S.; Hong, W.S.; Jing, T.; Kaplan, S.N.; Mireshghi, A.; Perez-Mendez, V.; Wildermuth, D.

    1993-04-01

    Using the high light absorption properties of amorphous silicon, we developed a new device configuration that can detect photons and store the induced charges for relatively long time. This device, coupled to a scintillator such as CsI(Tl) in an array form, could be used as a scintillation camera, or for long-term photo-detection such as radionuclide labeled chromatography. The detector has a simple sandwich structure consisting of a scintillator followed by a top metal layer, p-i-n layers of hydrogenated amorphous silicon (a-Si:H), a second metal layer, a thin insulating layer and a bottom metal layer. The electron-hole pairs generated in the i-layer by the interaction with the incident light will be separated by the imposed electric field and be stored in the central metal-insulator interface. Readout will be done by switching the external bias to ground after the storage time, which depends on the needs for the specific application. Prototype devices were fabricated and tested. The performances of the devices were analyzed in connection with the storage time and the background signal produced by the thermally generated charges

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  17. Optimization of conditions for long-term prefreezing storage of brown bear sperm before cryopreservation.

    Science.gov (United States)

    López-Urueña, E; Alvarez, M; Gomes-Alves, S; Anel-López, L; Martínez-Rodríguez, C; Manrique, P; Borragan, S; Anel, L; de Paz, P

    2015-10-15

    Brown bear ejaculates are usually collected in field conditions and may need to be shipped to a laboratory for the application of reproductive biotechnologies before cryopreservation. The aim of this study was to extend the prefreezing step to 48 hours (1 hour vs. long-term storage [LS] to 24 and 48 hours) to enable the sample to be transported. The effects of storage temperature (experiment 1), glycerol concentration (experiment 2), and dilution rate (experiment 3) on sperm were evaluated. Electroejaculates from brown bears were stored under different experimental conditions and cryopreserved. The sperm motility and viability, apoptotic status, and acrosomal status of sperm were assessed before freezing (prefreezing), after thawing, and after 2-hour incubation at 37 °C (thermal stress test). In all experiments, one control sample was frozen using a standard protocol (control). In experiment 1, three temperatures during LS with 6% glycerol were tested: 5 °C (T5), 15 °C (T15), and room temperature (RT). The LS-T5 sample yielded the highest postthawing results for viability (42.4%), progressive motility (15.6%), and intact acrosome (83.1%) after 24 hours in comparison with the other temperatures (P bear electroejaculates are at 5 °C, at a concentration of 100 × 10(6) sperm/mL, and with 6% glycerol. Copyright © 2015 Elsevier Inc. All rights reserved.

  18. Visual long-term memory has a massive storage capacity for object details.

    Science.gov (United States)

    Brady, Timothy F; Konkle, Talia; Alvarez, George A; Oliva, Aude

    2008-09-23

    One of the major lessons of memory research has been that human memory is fallible, imprecise, and subject to interference. Thus, although observers can remember thousands of images, it is widely assumed that these memories lack detail. Contrary to this assumption, here we show that long-term memory is capable of storing a massive number of objects with details from the image. Participants viewed pictures of 2,500 objects over the course of 5.5 h. Afterward, they were shown pairs of images and indicated which of the two they had seen. The previously viewed item could be paired with either an object from a novel category, an object of the same basic-level category, or the same object in a different state or pose. Performance in each of these conditions was remarkably high (92%, 88%, and 87%, respectively), suggesting that participants successfully maintained detailed representations of thousands of images. These results have implications for cognitive models, in which capacity limitations impose a primary computational constraint (e.g., models of object recognition), and pose a challenge to neural models of memory storage and retrieval, which must be able to account for such a large and detailed storage capacity.

  19. Long-term storage and safe retrieval of human papillomavirus DNA using FTA elute cards.

    Science.gov (United States)

    Barth, Heidi; Morel, Adrien; Mougin, Christiane; Averous, Gerlinde; Legrain, Michèle; Fender, Muriel; Risch, Simone; Fafi-Kremer, Samira; Velten, Michel; Oudet, Pierre; Baldauf, Jean-Jacques; Stoll-Keller, Françoise

    2016-03-01

    Biobanking or collection and storage of specimens for future research purposes have become an essential tool in many fields of biomedical research and aims to provide a better understanding of disease mechanisms as well as the identification of disease-specific biomarkers that can navigate in complex diseases. In this study, we assessed the use of Flinders Technology Associates (FTA) cards as a long-term storage device for cervical specimens with suspected human papillomavirus (HPV) infections. HPV detection and genotyping results in liquid-based transport media were compared to HPV results from FTA cards. The overall agreement for the presence of any HPV infection between liquid-based medium and FTA cards stored for 1 year at ambient temperature was 100%. Reproducibility analysis of HPV detection and genotyping from FTA cards demonstrated that FTA cards are a reliable medium to store and preserve viral nucleic acids. Biobanking of cervical cells on FTA cards may provide a key resource for epidemiological and retrospective HPV studies. Copyright © 2015 Elsevier B.V. All rights reserved.

  20. Long-term storage of irradiated potatoes for use in processed products, (2)

    International Nuclear Information System (INIS)

    Aoki, Shohei; Umeda, Keiji; Kameyama, Keiji.

    1982-01-01

    Effect of reconditioning of irradiated potatoes on the decrease of reducing sugar was studied. As a result, a suitable storage condition to maintain the desirable processing properties is proposed. The reducing sugar content was temporarily increased by irradiation at the early or last period of dormancy. The increase of reducing sugar was easily suppressed at the early period of dormancy by reconditioning immediately after irradiation. Reducing sugar did not decrease by the reconditioning when the irraditaion was carried out the early period of dormancy, but decreased when carried out at the last period of dormancy. A desirable procedure to maintain the processing properties of irradiated potatoes is as follows: Harvest the potatoes, store in bulk or containers and cure for 10 days at 10 0 C, RH90%. Irradiate the cured potatoes and recondition for 2 weeks under 15 0 C and RH80%. Long-term storage is then carried out at 7 - 8 0 C. Before processing, recondition the stored potatoes for 2 to 4 weeks at 15 0 C and RH 80%. (author)

  1. Safety research activities for Japanese regulations of spent fuel interim storage facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Japan Nuclear Energy Safety Organization (JNES) carries out (a) preparation of technical documents, (b) technical evaluations of standards (prepared by academic societies), etc. and (c) other R and D activities, to support Nuclear Regulation Authority (NRA: which controls the regulations for Spent Fuel Interim Storage Facilities). In 2012 fiscal year, JNES carried out dynamic test of spent fuel to examine the integrity of spent fuel under cask drop accidents, and preparation for PWR spent fuel storage test to prove long term integrity of spent fuel and cask itself. Some of these tests will be also carried out in 2013 fiscal year and after. (author)

  2. Long-term management of the existing radioactive wastes and residues at the Niagara Falls Storage Site. Draft Environmental Impact Statement

    International Nuclear Information System (INIS)

    1984-08-01

    The statement assesses and compares several alternatives for long-term management of the existing radioactive wastes and residues at the Niagara Falls Storage Site (NFSS), Lewiston, New York. The alternatives include: (1) no action (continued interim storage at NFSS within a diked and capped containment area), (2) long-term management at NFSS (improved containment, with or without modified form of the residues), (3) long-term management at other DOE sites (Hanford, Washington, or Oak Ridge, Tennessee), and (4) offsite management of the residues at Hanford or Oak Ridge and either leaving the wastes at NFSS or removing them for disposal in the ocean. In addition to alternatives analyzed in depth, several options are also considered, including: other modifications of residue form, modification of the basic conceptual designs, other containment design options, transportation routes, and transportation modes. The radiological health effects (primarily increased risk of cancer) associated with long-term management of the wastes and residues are expected to be smaller than the nonradiological risks of occupational and transportation-related injuries and deaths. During the action period, the risk is highest for workers if all wastes and residues are moved to Hanford. The risk is highest for the general public if the residues are moved to Hanford and the wastes are moved to the ocean. Dispersal of the slightly contaminated wastes in the ocean is not expected to result in any significant impacts on the ocean environment or pose any significant radiological risk to humans. For all alternatives, if controls ceased, there would be eventual dispersion of the radioactive materials to the environment. If it is assumed that all controls cease, predicted time for loss of covers over the buried materials ranges from several hundred years to more than two million years, depending on the use of the land surface

  3. The Behaviours of Cementitious Materials in Long Term Storage and Disposal of Radioactive Waste. Results of a Coordinated Research Project

    International Nuclear Information System (INIS)

    2013-09-01

    Radioactive waste with widely varying characteristics is generated from the operation and maintenance of nuclear power plants, nuclear fuel cycle facilities, research laboratories and medical facilities. This waste must be treated and conditioned, as necessary, to provide waste forms acceptable for safe storage and disposal. Many countries use cementitious materials (concrete, mortar, etc.) as a containment matrix for immobilization, as well as for engineered structures of disposal facilities. Radionuclide release is dependent on the physicochemical properties of the waste forms and packages, and on environmental conditions. In the use of cement, the diffusion process and metallic corrosion can induce radionuclide release. The advantage of cementitious materials is the added stability and mechanical support during storage and disposal of waste. Long interim storage is becoming an important issue in countries where it is difficult to implement low level waste and intermediate level waste disposal facilities, and in countries where cement is used in the packaging of waste that is not suitable for shallow land disposal. This coordinated research project (CRP), involving 24 research organizations from 21 Member States, investigated the behaviour and performance of cementitious materials used in an overall waste conditioning system based on the use of cement - including waste packaging (containers), waste immobilization (waste form) and waste backfilling - during long term storage and disposal. It also considered the interactions and interdependencies of these individual elements (containers, waste, form, backfill) to understand the processes that may result in degradation of their physical and chemical properties. The main research outcomes of the CRP are summarized in this report under four topical sections: (i) conventional cementitious systems; (ii) novel cementitious materials and technologies; (iii) testing and waste acceptance criteria; and (iv) modelling long

  4. The Behaviours of Cementitious Materials in Long Term Storage and Disposal of Radioactive Waste. Results of a Coordinated Research Project

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-09-15

    Radioactive waste with widely varying characteristics is generated from the operation and maintenance of nuclear power plants, nuclear fuel cycle facilities, research laboratories and medical facilities. This waste must be treated and conditioned, as necessary, to provide waste forms acceptable for safe storage and disposal. Many countries use cementitious materials (concrete, mortar, etc.) as a containment matrix for immobilization, as well as for engineered structures of disposal facilities. Radionuclide release is dependent on the physicochemical properties of the waste forms and packages, and on environmental conditions. In the use of cement, the diffusion process and metallic corrosion can induce radionuclide release. The advantage of cementitious materials is the added stability and mechanical support during storage and disposal of waste. Long interim storage is becoming an important issue in countries where it is difficult to implement low level waste and intermediate level waste disposal facilities, and in countries where cement is used in the packaging of waste that is not suitable for shallow land disposal. This coordinated research project (CRP), involving 24 research organizations from 21 Member States, investigated the behaviour and performance of cementitious materials used in an overall waste conditioning system based on the use of cement - including waste packaging (containers), waste immobilization (waste form) and waste backfilling - during long term storage and disposal. It also considered the interactions and interdependencies of these individual elements (containers, waste, form, backfill) to understand the processes that may result in degradation of their physical and chemical properties. The main research outcomes of the CRP are summarized in this report under four topical sections: (i) conventional cementitious systems; (ii) novel cementitious materials and technologies; (iii) testing and waste acceptance criteria; and (iv) modelling long

  5. Safety relevant aspects of the long-term intermediate storage of spent fuel elements and vitrified high-level radioactive wastes; Sicherheitstechnische Aspekte der langfristigen Zwischenlagerung von bestrahlten Brennelementen und verglastem HAW

    Energy Technology Data Exchange (ETDEWEB)

    Ellinger, A.; Geupel, S.; Gewehr, K.; Gmal, B.; Hannstein, V.; Hummelsheim, K.; Kilger, R.; Wagner, M. [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), Koeln (Germany); Schmidt, G.; Spieth-Achtnich, A. [Oeko-Institut e.V. - Institut fuer angewandte Oekolgie (Germany)

    2010-04-15

    The currently in Germany pursued concept for management of spent fuel from nuclear power plants provides intermediate dry cask storage at the NPP sites until direct disposal in a deep geologic repository. In addition the earlier commissioned centralized dry storage facilities are being used for storage of high level radioactive waste returned from foreign reprocessing of German spent fuel performed so far. The dry interim storage facilities are licensed for 40 years of operation time. According to the German regulations a full scope periodic safety review is not required so far, neither practical experience on dry storage for this period of time is available. With regard to this background the report at hand is dealing with long term effects, which may affect safety of the interim storage during the 40 years period or beyond if appropriate, and with the question, whether additional analyses or monitoring measures may be required. Therefore relevant publications have been evaluated, calculations have been performed as well as a systematic screening with regard to loads and possible ageing effects has been applied to structures and components important for safety of the storage, in order to identify relevant long term effects, which may not have been considered sufficiently so far and to provide proposals for an improved ageing management. The report firstly provides an overview on the current state of technology describing shortly the national and international practice and experience. In the following chapters safety aspects of interim storage with regard to time dependent effects and variations are being analyzed and discussed. Among this not only technical aspects like the long term behavior of fuel elements, canisters and storage systems are addressed, but also operational long term aspects regarding personnel planning, know how conservation, documentation and quality management are taken into account. A separate chapter is dedicated to developing and describing

  6. Fire Hazards Analysis for the 200 Area Interim Storage Area

    International Nuclear Information System (INIS)

    JOHNSON, D.M.

    2000-01-01

    This documents the Fire Hazards Analysis (FHA) for the 200 Area Interim Storage Area. The Interim Storage Cask, Rad-Vault, and NAC-1 Cask are analyzed for fire hazards and the 200 Area Interim Storage Area is assessed according to HNF-PRO-350 and the objectives of DOE Order 5480 7A. This FHA addresses the potential fire hazards associated with the Interim Storage Area (ISA) facility in accordance with the requirements of DOE Order 5480 7A. It is intended to assess the risk from fire to ensure there are no undue fire hazards to site personnel and the public and to ensure property damage potential from fire is within acceptable limits. This FHA will be in the form of a graded approach commensurate with the complexity of the structure or area and the associated fire hazards

  7. The design, fabrication, and testing of WETF high-quality, long-term-storage, secondary containment vessels

    International Nuclear Information System (INIS)

    Fisher, Kane J.

    2000-01-01

    Los Alamos National Laboratory's Weapons Engineering Tritium Facility (WETF) requires secondary containment vessels to store primary tritium containment vessels. The primary containment vessel provides the first boundary for tritium containment. The primary containment vessel is stored within a secondary containment vessel that provides the secondary boundary for tritium containment. WETF requires high-quality, long-term-storage, secondary tritium containment vessels that fit within a Mound-designed calorimeter. In order to qualify the WETF high-quality, long-term-storage, secondary containment vessels for use at WETF, steps have been taken to ensure the appropriate design, adequate testing, quality in fabrication, and acceptable documentation

  8. TWRS HLW interim storage facility search and evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Calmus, R.B., Westinghouse Hanford

    1996-05-16

    The purpose of this study was to identify and provide an evaluation of interim storage facilities and potential facility locations for the vitrified high-level waste (HLW) from the Phase I demonstration plant and Phase II production plant. In addition, interim storage facilities for solidified separated radionuclides (Cesium and Technetium) generated during pretreatment of Phase I Low-Level Waste Vitrification Plant feed was evaluated.

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-06-05

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

  11. Analysis of long-term terrestrial water storage variations in Yangtze River basin

    NARCIS (Netherlands)

    Huang, Ying; Salama, M.S.; Krol, Martinus S.; van der Velde, R.; Hoekstra, Arjen Ysbert; Zhou, Y.; Su, Zhongbo

    2012-01-01

    In this study, we analyze 32 yr of TWS data obtained from Interim Reanalysis Data (ERA-Interim) and Noah model from Global Land Data Assimilation System (GLDAS-Noah) for the period between 1979 and 2010. The accuracy of these datasets is validated against 26 yr (1979–2004) of runoff dataset from

  12. The TDR: A Repository for Long Term Storage of Geophysical Data and Metadata

    Science.gov (United States)

    Wilson, A.; Baltzer, T.; Caron, J.

    2006-12-01

    support storage of many large data products, the LEAD implementation of the TDR will provide a variety of data movement options, including gridftp. It will have a web service interface and will be callable programmatically as well as via interactive user requests. Future plans include the use of a mass storage device to provide robust long term storage. This talk will present the current state of the TDR effort.

  13. Guidelines for interim storage of low level waste

    International Nuclear Information System (INIS)

    Hornibrook, C.; Castagnacci, A.; Clymer, G.; Kelly, J.; Naughton, M.; Saunders, P.; Stoner, P.; Walker, N.; Cazzolli, R.; Dettenmeier, R.; Loucks, L.; Rigsby, M.; Spall, M.; Strum, M.

    1992-12-01

    This report presents an overview of on-site storage of Low Level Waste while providing guidelines for using the complete Interim On-Site Storage of Low Level Waste report series. Overall, this report provides a methodology for planning and implementing on-site storage

  14. Predicting long-term performance of engineered geologic carbon dioxide storage systems to inform decisions amidst uncertainty

    Science.gov (United States)

    Pawar, R.

    2016-12-01

    Risk assessment and risk management of engineered geologic CO2 storage systems is an area of active investigation. The potential geologic CO2 storage systems currently under consideration are inherently heterogeneous and have limited to no characterization data. Effective risk management decisions to ensure safe, long-term CO2 storage requires assessing and quantifying risks while taking into account the uncertainties in a storage site's characteristics. The key decisions are typically related to definition of area of review, effective monitoring strategy and monitoring duration, potential of leakage and associated impacts, etc. A quantitative methodology for predicting a sequestration site's long-term performance is critical for making key decisions necessary for successful deployment of commercial scale geologic storage projects where projects will require quantitative assessments of potential long-term liabilities. An integrated assessment modeling (IAM) paradigm which treats a geologic CO2 storage site as a system made up of various linked subsystems can be used to predict long-term performance. The subsystems include storage reservoir, seals, potential leakage pathways (such as wellbores, natural fractures/faults) and receptors (such as shallow groundwater aquifers). CO2 movement within each of the subsystems and resulting interactions are captured through reduced order models (ROMs). The ROMs capture the complex physical/chemical interactions resulting due to CO2 movement and interactions but are computationally extremely efficient. The computational efficiency allows for performing Monte Carlo simulations necessary for quantitative probabilistic risk assessment. We have used the IAM to predict long-term performance of geologic CO2 sequestration systems and to answer questions related to probability of leakage of CO2 through wellbores, impact of CO2/brine leakage into shallow aquifer, etc. Answers to such questions are critical in making key risk management

  15. Diverse perspectives on governance on the very long term. Biodiversity, climatic change, CO2 storage, radioactive wastes, space wastes

    International Nuclear Information System (INIS)

    Boeuf, Gilles; Gouyon, Pierre Henry; Rollinger, Francois; Besnus, Francois; Heriard Dubreuil, Gilles; Dahan, Amy; Alby, Fernand; Arnould, Jacques; Fabriol, Hubert; Hoummady, Moussa; Demarcq, Francois; Farret, Regis; Hubert, Philippe; Weber, Jacques; Charton, Patrick; Boissier, Fabrice; Lopez, Mirelle; Devisse, Jean-Jacques; Mathy, Sandrine; Hourcade, Jean-Charles; Le Roux, Xavier; Bourcier, Danielle; Roure, Francoise; Henry, Claude; Bartet, Jean Hughes; Calame, Mathieu; Biteau, Benoit; Kastler, Guy; Ducret, Pierre; Berest, Pierre; Charron, Sylvie; Clin, Francois; Gadbois, Serge; Gueritte, Michel; Heriard-Dubreuil, Bertrand; Laville, Bettina; Marie, Michel; Marignac, Yves; Ollagnon, Henry; Pelegrin, Flora; Roure, Francoise; Rouyer, Michel; Schellenberger, Thomas; Toussaint, Jean-Francois

    2013-03-01

    This bibliographical note contains the program of a workshop and a presentation of a book based on the contributions to this workshop proposed by experts, representatives of institutional bodies and associations, or local representatives. This workshop addressed the issue of the governance on the very long term with respect to the management of resources such as climate, geology, biodiversity or space. How to make a possible usage of these resources while ensuring their protection and durability? What are the solutions or new challenges are raising these usages on the very long term? The first part addresses the main challenges and ethical issues for governance on the very long term for each of the examined topics: biodiversity, climatic change, CO 2 storage, radioactive waste storage, and space debris). The next parts propose contributions from different origins and disciplines, present relevant data, and report evidences

  16. Transport casks help solve spent fuel interim storage problems

    International Nuclear Information System (INIS)

    Dierkes, P.; Janberg, K.; Baatz, H.; Weinhold, G.

    1980-01-01

    Transport casks can be used as storage modules, combining the inherent safety of passive cooling with the absence of secondary radioactive waste and the flexibility to build up storage capacity according to actual requirements. In the Federal Republic of Germany, transport casks are being developed as a solution to its interim storage problems. Criteria for their design and licensing are outlined. Details are given of the casks and the storage facility. Tests are illustrated. (U.K.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Broadhead, B.L.

    1995-01-01

    The radionuclide characteristics of light-water-reactor (LWR) spent fuel play key roles in the design and licensing activities for radioactive waste transportation systems, interim storage facilities, and the final repository site. Several areas of analysis require detailed information concerning the time-dependent behavior of radioactive nuclides including (1) neutron/gamma-ray sources for shielding studies, (2) fissile/absorber concentrations for criticality safety determinations, (3) residual decay heat predictions for thermal considerations, and (4) curie and/or radiological toxicity levels for materials assumed to be released into the ground/environment after long periods of time. The crucial nature of the radionuclide predictions over both short and long periods of time has resulted in an increased emphasis on thorough validation for radionuclide generation/depletion codes. Current radionuclide generation/depletion codes have the capability to follow the evolution of some 1600 isotopes during both irradiation and decay time periods. Of these, typically only 10 to 20 nuclides dominate contributions to each analysis area. Thus a quantitative ranking of nuclides over various time periods is desired for each of the analysis areas of shielding, criticality, heat transfer, and environmental dose (radiological toxicity). These rankings should allow for validation and data improvement efforts to be focused only on the most important nuclides. This study investigates the relative importances of the various actinide, fission-product, and light-element isotopes associated with LWR spent fuel with respect to five analysis areas: criticality safety (absorption fractions), shielding (dose rate fractions), curies (fractional curies levels), decay heat (fraction of total watts), and radiological toxicity (fraction of potential committed effective dose equivalent). These rankings are presented for up to six different burnup/enrichment scenarios and at decay times from 2 to

  18. System Specification for Immobilized High-Level Waste Interim Storage

    International Nuclear Information System (INIS)

    CALMUS, R.B.

    2000-01-01

    This specification establishes the system-level functional, performance, design, interface, and test requirements for Phase 1 of the IHLW Interim Storage System, located at the Hanford Site in Washington State. The IHLW canisters will be produced at the Hanford Site by a Selected DOE contractor. Subsequent to storage the canisters will be shipped to a federal geologic repository

  19. Long Term Storage with Surveillance of Canadian Prototype Nuclear Power Reactors

    International Nuclear Information System (INIS)

    Janzen, Rick

    2008-01-01

    Atomic Energy of Canada (AECL) was originally formed by the government of Canada in 1952 to perform research in radiation and nuclear areas. In the mid 1950's Canada decided to limit itself to peaceful uses of nuclear energy and AECL embarked on several research and development programs, one of them being the development of nuclear power plants. This led to the development of the CANDU TM design of heavy water power reactors, of which there are now 29 operating around the world. This presentation discusses the present state of the first two CANDU TM prototype reactors and a prototype boiling light water reactor and lessons learnt after being in a long-term storage with surveillance state for more than 20 years. AECL facilities undergo decommissioning by either a prompt or a deferred removal approach. Both approaches are initiated after an operating facility has been declared redundant and gone through final operational shutdown. For the deferred approach, initial decommissioning activities are performed to put the facility into a sustainable, safe, shutdown state to minimize the hazards and costs of the ensuing extended storage with surveillance (SWS) or Safestor phase. At the appropriate time, the facility is dismantled and removed, or put into a suitable condition for re-use. AECL has a number of facilities that were built during its history, and some of these are now redundant or will become redundant in the near future. The deferred removal approach is part of AECL's decommissioning strategy for several reasons: 1. Reduction in radiation doses to workers during the final dismantling, 2. No facilities are available yet in Canada for the management of quantity of wastes arising from decommissioning, 3. Financial constraints presented by the number of facilities that will undergo decommissioning, compared to the availability of funds to carry out the work. This has led to the development of a comprehensive decommissioning plan that includes all of AECL's redundant

  20. Permitting plan for the high-level waste interim storage

    International Nuclear Information System (INIS)

    Deffenbaugh, M.L.

    1997-01-01

    This document addresses the environmental permitting requirements for the transportation and interim storage of solidified high-level waste (HLW) produced during Phase 1 of the Hanford Site privatization effort. Solidified HLW consists of canisters containing vitrified HLW (glass) and containers that hold cesium separated during low-level waste pretreatment. The glass canisters and cesium containers will be transported to the Canister Storage Building (CSB) in a U.S. Department of Energy (DOE)-provided transportation cask via diesel-powered tractor trailer. Tri-Party Agreement (TPA) Milestone M-90 establishes a new major milestone, and associated interim milestones and target dates, governing acquisition and/or modification of facilities necessary for: (1) interim storage of Tank Waste Remediation Systems (TWRS) immobilized HLW (IHLW) and other canistered high-level waste forms; and (2) interim storage and disposal of TWRS immobilized low-activity tank waste (ILAW). An environmental requirements checklist and narrative was developed to identify the permitting path forward for the HLW interim storage (HLWIS) project (See Appendix B). This permitting plan will follow the permitting logic developed in that checklist

  1. Final Long-Term Management and Storage of Elemental Mercury Environmental Impact Statement Summary and Guide for Stakeholders

    Energy Technology Data Exchange (ETDEWEB)

    2011-01-01

    Pursuant to the Mercury Export Ban Act of 2008 (P.L. 110-414), DOE was directed to designate a facility or facilities for the long-term management and storage of elemental mercury generated within the United States. Therefore, DOE has analyzed the storage of up to 10,000 metric tons (11,000 tons) of elemental mercury in a facility(ies) constructed and operated in accordance with the Solid Waste Disposal Act, as amended by the Resource Conservation and Recovery Act (74 FR 31723). DOE prepared this Final Mercury Storage EIS in accordance with the National Environmental Policy Act of 1969 (NEPA), as amended (42 U.S.C. 4321 et seq.), the Council on Environmental Quality (CEQ) implementing regulations (40 CFR 1500–1508), and DOE’s NEPA implementing procedures (10 CFR 1021) to evaluate reasonable alternatives for a facility(ies) for the long-term management and storage of elemental mercury. This Final Mercury Storage EIS analyzes the potential environmental, human health, and socioeconomic impacts of elemental mercury storage at seven candidate locations: Grand Junction Disposal Site near Grand Junction, Colorado; Hanford Site near Richland, Washington; Hawthorne Army Depot near Hawthorne, Nevada; Idaho National Laboratory near Idaho Falls, Idaho; Kansas City Plant in Kansas City, Missouri; Savannah River Site near Aiken, South Carolina; and Waste Control Specialists, LLC, site near Andrews, Texas. As required by CEQ NEPA regulations, the No Action Alternative was also analyzed as a basis for comparison. DOE intends to decide (1) where to locate the elemental mercury storage facility(ies) and (2) whether to use existing buildings, new buildings, or a combination of existing and new buildings. DOE’s Preferred Alternative for the long-term management and storage of mercury is the Waste Control Specialists, LLC, site near Andrews, Texas.

  2. How much suspended particulate matter enters long-term in-channel storage?

    Science.gov (United States)

    Dietrich, Stephan; Kleisinger, Carmen; Kehl, Nora; Schubert, Birgit; Hillebrand, Gudrun

    2017-04-01

    The route of suspended particulate matter (SPM) downstream rivers strongly depends on discharge conditions and involves transport times and periods with resting times in deposits e.g. at areas with low-flow conditions near the channel bed. It is, however, difficult to estimate the contribution of SPM on the bed load. In this study, particle-bound polychlorinated biphenyls (PCB), which were released by an incident in the Elbe river (Central Europe) in spring 2015, could be used as unique tracer for transport pathways of SPM along the whole river stretch (over 700 km length), including low mountain ranges, lowlands, and the estuary. In 2015 the Elbe River was characterized by low-discharge conditions. Thus, the export of SPM on flood plains was strongly limited. The incident was monitored by concentration measurements of seven indicator PCB congeners along the inland part of the Elbe River as well as in the Elbe estuary. Data from ten monitoring stations (settling tanks) are considered. The total PCB load is calculated for all stations on the basis of monthly contaminant concentrations and daily suspended sediment concentrations. Monte-Carlo simulations assess the uncertainties of the calculated load. It is shown that the ratio of high versus low chlorinated PCB congeners is a suitable tracer to distinguish the PCB load of the incident from the long-term background signal (hereafter PCB6 ratio). We demonstrate that both the load of PCB as well as its chemical fingerprint allows the estimation of transport durations for the transport processes involved. Only a little part of the suspension has been transported via wash load. The PCB6 ratio is used to estimate mean transport velocities of the wash load fraction. A direct transport of wash load via the mean flow velocity of the water was not observed. Shortly after the incident, the PCB6 ratio was monitored 257 km downstream of the incident site in April 2015, in May first occurrence was monitored 514 km downstream of

  3. Changes in microbial populations of WPC34 and WPC80 whey protein during long term storage

    Science.gov (United States)

    The use of whey protein (WPC34 and WPC80) as a food ingredient and as a base for making biodegradable products is increasing. The need to alleviate world hunger in arid and semi-arid regions demands that we investigate the behavior of native bacteria in these products, especially during long term st...

  4. Massive Memory Revisited: Limitations on Storage Capacity for Object Details in Visual Long-Term Memory

    Science.gov (United States)

    Cunningham, Corbin A.; Yassa, Michael A.; Egeth, Howard E.

    2015-01-01

    Previous work suggests that visual long-term memory (VLTM) is highly detailed and has a massive capacity. However, memory performance is subject to the effects of the type of testing procedure used. The current study examines detail memory performance by probing the same memories within the same subjects, but using divergent probing methods. The…

  5. Oral features and computerized rehabilitation of a young patient with CHARGE syndrome using minimally invasive long-term interim CAD-CAM restorations.

    Science.gov (United States)

    Liebermann, Anja; Rafael, Caroline Freitas; Edelhoff, Daniel; Ramberger, Marc; Schweiger, Josef; Maziero Volpato, Claudia Angela; Saeidi Pour, Reza

    2017-04-01

    Patients with CHARGE syndrome (where CHARGE stands for coloboma of the iris or retina, heart defects or cardiac malformations, atresia/stenosis of the choanae, retardation of growth and development, genital anomalies, and ear abnormalities) present several orofacial anomalies. Their treatment depends on the specific type of manifestation. To perform the complex oral rehabilitation and achieve a conservative, esthetic, and functional exploration of the definitive treatment goal, computer-aided design and computer-aided manufacturing (CAD-CAM) polymers can be used as long-term interim restorations. This article reports the treatment of a young patient with CHARGE syndrome combined with oral alterations. CAD-CAM polymers offer an intermediate treatment with satisfying esthetics and function at low biological cost until bone growth is completed. This period facilitates additional planning for the definitive restoration. Copyright © 2016 Editorial Council for the Journal of Prosthetic Dentistry. Published by Elsevier Inc. All rights reserved.

  6. The essential conditions for the choice of location for a long-term storage of radioactive wastes

    International Nuclear Information System (INIS)

    Markovic, V.

    1964-10-01

    The paper deals with a long-term storage of radioactive wastes with a special reference to the parameters to be considered in choosing the location. It gives a short account of methods for disposal of radioactive liquid and solid wastes used in nuclear centers in the world. The possibilities of radioactive wastes disposal in our country using the methods investigated are also presented (author)

  7. Regulatory issues related to long-term storage and disposal of radioactive wastes in Kazakhstan

    International Nuclear Information System (INIS)

    Kim, A.; Romanenko, O.; Tazhibayeva, I.; Zhunussova, T.

    2012-01-01

    Full text: Reported material is a result of activity accomplished in the framework of cooperation program between Kazakhstan and Norway within 2009-2012. This work was divided into three distinctive parts, as follows: 1. Analysis of existing threats associated with radioactive wastes in the Republic of Kazakhstan. The objective of this part of the work was to reveal the most important threats in the sphere of radioactive waste management in the Republic of Kazakhstan, which require an increased regulatory attention. Threat assessment needed to identify: main radiological threats both for people who work with radioactive wastes and for population living near the radioactive waste storage places now and in the long term which require an increased regulatory attention; problems that need urgent and detailed analysis; and main problems in the realization of regulatory process in Kazakhstan including weakness in the regulatory and legal framework. Threat assessment analysis showed that in order to reduce the level of threats it was necessary to begin developing a national policy and strategy for radioactive waste management which need to be approved by the Government, to develop proposals for Radioactive Wastes new classification, including identification of relevant categories of Radioactive Wastes, as well as criteria for their disposal in accordance with IAEA recommendations and experience from other countries. 2. Development of new classification system for radioactive wastes in Kazakhstan. Following the results of threat assessment performed within the first stage, the objective of the second part of work was to develop a proposal to adopt a new Radioactive Wastes classification in Kazakhstan in accordance with the IAEA recommendations, including implementation of new categories, taking into account international experience and current situation in Kazakhstan. The result of this stage of work was a proposal for a new Radioactive Wastes classification and

  8. Effects of marrow storage at 4 degrees C on the subsequent generation of long-term marrow cultures

    International Nuclear Information System (INIS)

    Takahashi, M.; Singer, J.W.

    1985-01-01

    The present study was undertaken to examine the effect of marrow preservation at 4 degrees C on subsequent long-term culture, which evaluates both hematopoietic precursor cells and hematopoietic microenvironmental cells. Storage of unfractionated marrow was superior to storage of buffy-coat cells in tissue culture medium with 20% fetal calf serum. CFU-C recovery in unfractionated marrow was 48.4% at four days and 21.4% at seven days. Long-term marrow cultures from cells stored at 4 degrees C for up to seven days produced CFU-C for up to seven weeks and established confluent marrow stromal cell layers. Suspension cultures of marrow cells preserved at 4 degrees C for seven days cultured with irradiated allogeneic marrow stromal cell layers from normal long-term marrow cultures showed significantly increased CFU-C production from week 2 to week 5 when compared with the control cultures without adherent cell layers. These data suggest that marrow storage at 4 degrees C for up to seven days preserves early hematopoietic precursor cells and microenvironmental cells and may be used for autologous rescue from marrow ablative therapy

  9. Verification of geomechanical integrity and prediction of long-term mineral trapping for the Ketzin CO2 storage pilot site

    Science.gov (United States)

    Kempka, Thomas; De Lucia, Marco; Kühn, Michael

    2014-05-01

    Static and dynamic numerical modelling generally accompany the entire CO2 storage site life cycle. Thereto, it is required to match the employed models with field observations on a regular basis in order to predict future site behaviour. We investigated the coupled processes at the Ketzin CO2 storage pilot site [1] using a model coupling concept focusing on the temporal relevance of processes involved (hydraulic, chemical and mechanical) at given time-scales (site operation, abandonment and long-term stabilization). For that purpose, long-term dynamic multi-phase flow simulations [2], [3] established the basis for all simulations discussed in the following. Hereby, pressure changes resulting in geomechanical effects are largest during site operation, whereas geochemical reactions are governed by slow kinetics resulting in a long-term stabilization. To account for mechanical integrity, which may be mainly affected during site operation, we incorporated a regional-scale coupled hydro-mechanical model. Our simulation results show maximum ground surface displacements of about 4 mm, whereas shear and tensile failure are not observed. Consequently, the CO2 storage operation at the Ketzin pilot site does not compromise reservoir, caprock and fault integrity. Chemical processes responsible for mineral trapping are expected to mainly occur during long-term stabilization at the Ketzin pilot site [4]. Hence, our previous assessment [3] was extended by integrating two long-term mineral trapping scenarios. Thereby, mineral trapping contributes to the trapping mechanisms with 11.7 % after 16,000 years of simulation in our conservative and with 30.9 % in our maximum reactivity scenarios. Dynamic flow simulations indicate that only 0.2 % of the CO2 injected (about 67,270 t CO2 in total) is in gaseous state, but structurally trapped after 16,000 years. Depending on the studied long-term scenario, CO2 dissolution is the dominating trapping mechanism with 68.9 % and 88

  10. Radiation analysis for a generic centralized interim storage facility

    International Nuclear Information System (INIS)

    Gillespie, S.G.; Lopez, P.; Eble, R.G.

    1997-01-01

    This paper documents the radiation analysis performed for the storage area of a generic Centralized Interim Storage Facility (CISF) for commercial spent nuclear fuel (SNF). The purpose of the analysis is to establish the CISF Protected Area and Restricted Area boundaries by modeling a representative SNF storage array, calculating the radiation dose at selected locations outside the storage area, and comparing the results with regulatory radiation dose limits. The particular challenge for this analysis is to adequately model a large (6000 cask) storage array with a reasonable amount of analysis time and effort. Previous analyses of SNF storage systems for Independent Spent Fuel Storage Installations at nuclear plant sites (for example in References 5.1 and 5.2) had only considered small arrays of storage casks. For such analyses, the dose contribution from each storage cask can be modeled individually. Since the large number of casks in the CISF storage array make such an approach unrealistic, a simplified model is required

  11. Long term storage of virus templated fluorescent materials for sensing applications

    Energy Technology Data Exchange (ETDEWEB)

    Seetharam, Raviraja N; Guerra, Charles; Satir, Peter [Department of Anatomy and Structural Biology, Albert Einstein College of Medicine, 1300 Morris Park Avenue, Bronx, NY 10461 (United States); Blum, Amy Szuchmacher; Soto, Carissa M; Ratna, Banahalli R [Center for Bio/Molecular Science and Engineering, Naval Research Laboratory, 4555 Overlook Avenue SW, Washington, DC 20375 (United States); Whitley, Jessica L [Geo-Centers, Incorporated, Newton, MA 02459 (United States); Sapsford, Kim E [George Mason University, 10910 University Boulevard, Manassas, VA 20110 (United States); Chatterji, Anju; Lin Tianwei; Johnson, John E [Department of Molecular Biology, The Scripps Research Institute, 10550 North Torrey Pines Road, La Jolla, CA 92037 (United States)], E-mail: amy.blum@nrl.navy.mil

    2008-03-12

    Wild type, mutant, and chemically modified Cowpea mosaic viruses (CPMV) were studied for long term preservation in the presence and absence of cryoprotectants. Viral complexes were reconstituted and tested via fluorescence spectroscopy and a UV/vis-based RNase assay for structural integrity. When viruses lyophilized in the absence of cryoprotectant were rehydrated and RNase treated, UV absorption increased, indicating that the capsids were damaged. The addition of trehalose during lyophilization protected capsid integrity for at least 7 weeks. Measurements of the fluorescence peak maximum of CPMV lyophilized with trehalose and reconstituted also indicate that the virus remained intact. Microarray binding assays indicated that CPMV particles chemically modified for use as a fluorescent tracer were intact and retained binding specificity after lyophilization in the presence of trehalose. Thus, we demonstrate that functionalized CPMV nanostructures can be stored for the long term, enabling their use in practical sensing applications.

  12. Long-term retrievability and safeguards for immobilized weapons plutonium in geologic storage

    International Nuclear Information System (INIS)

    Peterson, P.F.

    1996-01-01

    If plutonium is not ultimately used as an energy source, the quantity of excess weapons plutonium (w-Pu) that would go into a US repository will be small compared to the quantity of plutonium contained in the commercial spent fuel in the repository, and the US repository(ies) will likely be only one (or two) locations out of many around the world where commercial spent fuel will be stored. Therefore excess weapons plutonium creates a small perturbation to the long-term (over 200,000 yr) global safeguard requirements for spent fuel. There are details in the differences between spent fuel and immobilized w-Pu waste forms (i.e. chemical separation methods, utility for weapons, nuclear testing requirements), but these are sufficiently small to be unlikely to play a significant role in any US political decision to rebuild weapons inventories, or to change the long-term risks of theft by subnational groups

  13. Long-term retrievability and safeguards for immobilized weapons plutonium in geologic storage

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, P.F. [Univ. of California, Berkeley, CA (United States)

    1996-05-01

    If plutonium is not ultimately used as an energy source, the quantity of excess weapons plutonium (w-Pu) that would go into a US repository will be small compared to the quantity of plutonium contained in the commercial spent fuel in the repository, and the US repository(ies) will likely be only one (or two) locations out of many around the world where commercial spent fuel will be stored. Therefore excess weapons plutonium creates a small perturbation to the long-term (over 200,000 yr) global safeguard requirements for spent fuel. There are details in the differences between spent fuel and immobilized w-Pu waste forms (i.e. chemical separation methods, utility for weapons, nuclear testing requirements), but these are sufficiently small to be unlikely to play a significant role in any US political decision to rebuild weapons inventories, or to change the long-term risks of theft by subnational groups.

  14. Long term storage of virus templated fluorescent materials for sensing applications

    International Nuclear Information System (INIS)

    Seetharam, Raviraja N; Guerra, Charles; Satir, Peter; Blum, Amy Szuchmacher; Soto, Carissa M; Ratna, Banahalli R; Whitley, Jessica L; Sapsford, Kim E; Chatterji, Anju; Lin Tianwei; Johnson, John E

    2008-01-01

    Wild type, mutant, and chemically modified Cowpea mosaic viruses (CPMV) were studied for long term preservation in the presence and absence of cryoprotectants. Viral complexes were reconstituted and tested via fluorescence spectroscopy and a UV/vis-based RNase assay for structural integrity. When viruses lyophilized in the absence of cryoprotectant were rehydrated and RNase treated, UV absorption increased, indicating that the capsids were damaged. The addition of trehalose during lyophilization protected capsid integrity for at least 7 weeks. Measurements of the fluorescence peak maximum of CPMV lyophilized with trehalose and reconstituted also indicate that the virus remained intact. Microarray binding assays indicated that CPMV particles chemically modified for use as a fluorescent tracer were intact and retained binding specificity after lyophilization in the presence of trehalose. Thus, we demonstrate that functionalized CPMV nanostructures can be stored for the long term, enabling their use in practical sensing applications

  15. Massive memory revisited: Limitations on storage capacity for object details in visual long-term memory

    OpenAIRE

    Cunningham, Corbin A.; Yassa, Michael A.; Egeth, Howard E.

    2015-01-01

    Previous work suggests that visual long-term memory (VLTM) is highly detailed and has a massive capacity. However, memory performance is subject to the effects of the type of testing procedure used. The current study examines detail memory performance by probing the same memories within the same subjects, but using divergent probing methods. The results reveal that while VLTM representations are typically sufficient to support performance when the procedure probes gist-based information, they...

  16. Cost Analysis and Long Term Planning Over the Lifecycle of an Enterprise Storage Solution

    Directory of Open Access Journals (Sweden)

    Christopher J. McKnight

    2006-12-01

    Full Text Available This document will cover the basics of Storage Area Networks (SAN, IP-Based Storage Networks such as NAS, and the basics of choosing a technology for an Enterprise Storage infrastructure. This document will focus on SAS (Serial Attached Storage and SATA (Serial ATA disk drive technologies. The primary focus for this document will be to aid a manager in making a purchasing decision for the selection of storage technologies. I will cover purchase options such as buy, lease, and lease-to-buy. This document will cover the basic costs associated with maintenance and upgrades over the lifetime of different storage technologies.

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

    Science.gov (United States)

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

    2017-09-01

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

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

    Directory of Open Access Journals (Sweden)

    Ternovykh Mikhail

    2017-01-01

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

  19. Engineering and planning for reactor 105-C interim safe storage project subcontract no. 0100C-SC-G0001 conceptual design report. Volume 1

    International Nuclear Information System (INIS)

    1996-04-01

    The 105-C Reactor, one of eight surplus production reactors at the Hanford Site, has been proposed by the U.S. Department of Energy, Richland, Operations Office to be the first large-scale technology demonstration project in the decontamination and decommissioning (D ampersand D) focus area as part of the project for dismantlement and interim safe storage. The 105-C Reactor will be placed in an interim safe storage condition, then undergo the decontamination and decommissioning phase. After D ampersand D, the reactor will be placed in long- term safe storage. This report provides the conceptual design for these activities

  20. Studies on the long-term characteristics of HLW glass under ultimate storage conditions

    International Nuclear Information System (INIS)

    Roggendorf, H.; Conradt, R.; Ostertag, R.

    1987-01-01

    This interim report deals with first results of corrosion investigations of HLW simulation glass (COGEMA glass SON 68) in quinary salt solutions of different concentrations; the aim of these investigations was to find out about the corrosion mechanism at the surface of the glass and the quantitative registration of the corrosion products. It became obvious that the surface layers developed can be easily removed and that a determination of weight losses becomes possible thereby. The corrosion rates for a test period of 30 days were determined. (RB) [de

  1. Woody debris along an upland chromosequence in boreal Manitoba and its impact on long-term carbon storage

    Energy Technology Data Exchange (ETDEWEB)

    Manies, K. L.; Harden, J. W. [US Geological Survey, Menlo Park, CA (United States); Bond-Lamberty, B. P. [University of Wisconsin, Dept. of Forest Ecology and Management, Madison, WI (United States); O' Neill, K. P. [USDA Agricultural Research Service, Appalachian Farming Systems Research Center, Beaver, WV (United States)

    2005-02-01

    The amount of standing dead and downed woody debris along an upland chromosequence was measured in an effort to investigate the role of fire-killed woody debris as a source of soil carbon in black spruce stands in Manitoba. Based on the measurement data and existing primary production values, a mass balance model was used to assess the potential impact of fire-killed wood on long-term carbon storage at this site. Long-term carbon was represented by the amount of carbon stored in deeper soil organic layers, persisting over millenia. Between 10 and 60 per cent of the deep-soil carbon was estimated to have been derived from wood biomass. The actual amount appears to be most affected by fire return interval, decay rate of wood, the amount of net primary production, and the decay rate of the post-fire carbon pool. Although the model was less sensitive to fire consumption rates and to rates at which standing dead wood becomes woody debris, all model runs clearly established that woody debris plays an important role in long-term carbon storage in this area. 53 refs., 4 tabs., 4 figs.

  2. Visual long-term memory has a massive storage capacity for object details

    OpenAIRE

    Brady, Timothy F.; Konkle, Talia; Alvarez, George A.; Oliva, Aude

    2008-01-01

    One of the major lessons of memory research has been that human memory is fallible, imprecise, and subject to interference. Thus, although observers can remember thousands of images, it is widely assumed that these memories lack detail. Contrary to this assumption, here we show that long-term memory is capable of storing a massive number of objects with details from the image. Participants viewed pictures of 2,500 objects over the course of 5.5 h. Afterward, they were shown pairs of images an...

  3. 105-H Reactor Interim Safe Storage Project Final Report

    International Nuclear Information System (INIS)

    Ison, E.G.

    2008-01-01

    The following information documents the decontamination and decommissioning of the 105-H Reactor facility, and placement of the reactor core into interim safe storage. The D and D of the facility included characterization, engineering, removal of hazardous and radiologically contaminated materials, equipment removal, decontamination, demolition of the structure, and restoration of the site. The ISS work also included construction of the safe storage enclosure, which required the installation of a new roofing system, power and lighting, a remote monitoring system, and ventilation components.

  4. Dry storage of spent fuel elements: interim facility

    International Nuclear Information System (INIS)

    Quihillalt, O.J.

    1993-01-01

    Apart from the existing facilities to storage nuclear fuel elements at Argentina's nuclear power stations, a new interim storage facility has been planned and projected by the Argentinean Atomic Energy Commission (CNEA) that will be constructed by private group. This article presents the developments and describes the activities undertaken until the national policy approach to the final decision for the most suitable alternative to be adopted. (B.C.A.). 09 refs, 01 fig, 09 tabs

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

    International Nuclear Information System (INIS)

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

    2010-05-01

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

  6. University of Minnesota Aquifer Thermal Energy Storage (ATES) project report on the first long-term cycle

    Science.gov (United States)

    Walton, M.

    1991-10-01

    The technical feasibility of high-temperature (greater than 100 C) aquifer thermal energy storage (IOTAS) in a deep, confined aquifer was tested in a series of experimental cycles at the University of Minnesota's St. Paul field test facility (FTF). This report describes the additions to the FTF for the long-term cycles and the details of the first long-term cycle (LT1) that was conducted from November 1984 through May 1985. Heat recovery; operational experience; and thermal, chemical, hydrologic, and geologic aspects of LT1 are reported. The permits for long-term cycles required the addition of a monitoring well 30.5 m from the storage well for monitoring near the edge of the thermally affected area and allowed the addition of a cation-exchange water softener to enable continuous operation during the injection phase. Approximately 62 percent of the 9.47 GWh of energy added to the 9.21 x 10(exp 4) cu m of ground water stored in the aquifer LT1 was recovered. Ion-exchange water softening of the heated and stored ground water prevented scaling in the system heat exchangers and the storage well and changed the major-ion chemistry of the stored water. Temperatures at the storage horizons in site monitoring wells reached as high as 108 C during the injection phase of LT1. Following heat recovery, temperatures were less than 30 C at the same locations. Less permeable horizons underwent slow temperature changes. No thermal or chemical effects were observed at the remote monitoring site.

  7. Effects of long-term storage on the quality of soybean, Glycine max ...

    African Journals Online (AJOL)

    Soybean, Glycine max (L.) Merrill, is one of the five most important legumes in the tropics and provides the protein eaten by most people in the region. One of the major constraints to soybean production is that the seed quality deteriorates rapidly during storage. This study was undertaken to assess the effect of some storage ...

  8. Combined Statistical Analyses for Long-Term Stability Data with Multiple Storage Conditions : A Simulation Study

    NARCIS (Netherlands)

    Almalik, Osama; Nijhuis, Michiel B.; van den Heuvel, Edwin R.

    2014-01-01

    Shelf-life estimation usually requires that at least three registration batches are tested for stability at multiple storage conditions. The shelf-life estimates are often obtained by linear regression analysis per storage condition, an approach implicitly suggested by ICH guideline Q1E. A linear

  9. Technical considerations and problems associated with long-term storage of low-level waste

    International Nuclear Information System (INIS)

    Siskind, B.

    1991-01-01

    If a state or regional compact does not have adequate disposal capacity for low-level radioactive waste (LLRW), then extended storage of certain LLRW may be necessary. The Nuclear Regulatory Commission (NRC) contracted with Brookhaven National Laboratory (BNL) several years ago (1984--86) to address the technical issues of extended storage. The dual objectives of this study were (1) to provide practical technical assessments for NRC to consider in evaluating specific proposals for extended storage and (2) to help ensure adequate consideration by NRC, Agreement States, and licensees of potential problems that may arise from existing or proposed extended storage practices. In this summary of that study, the circumstances under which extended storage of LLRW would most likely result in problems during or after the extended storage period are considered and possible mitigative measures to minimize these problems are discussed. These potential problem areas include: (1) the degradation of carbon steel and polyethylene containers during storage and the subsequent need for repackaging (resulting in increased occupational exposure), (2) the generation of hazardous gases during storage, and (3) biodegradative processes in LLRW

  10. Effects of Long-Term Storage Time and Original Sampling Month on Biobank Plasma Protein Concentrations

    Directory of Open Access Journals (Sweden)

    Stefan Enroth

    2016-10-01

    Full Text Available The quality of clinical biobank samples is crucial to their value for life sciences research. A number of factors related to the collection and storage of samples may affect the biomolecular composition. We have studied the effect of long-time freezer storage, chronological age at sampling, season and month of the year and on the abundance levels of 108 proteins in 380 plasma samples collected from 106 Swedish women. Storage time affected 18 proteins and explained 4.8–34.9% of the observed variance. Chronological age at sample collection after adjustment for storage-time affected 70 proteins and explained 1.1–33.5% of the variance. Seasonal variation had an effect on 15 proteins and month (number of sun hours affected 36 proteins and explained up to 4.5% of the variance after adjustment for storage-time and age. The results show that freezer storage time and collection date (month and season exerted similar effect sizes as age on the protein abundance levels. This implies that information on the sample handling history, in particular storage time, should be regarded as equally prominent covariates as age or gender and need to be included in epidemiological studies involving protein levels.

  11. Advantages on dry interim storage for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Romanato, L.S. [Centro Tecnologico da Marinha em Sao Paulo, Av. Professor Lineu Prestes 2468, 05508-900 Sao Paulo (Brazil); Rzyski, B.M. [IPEN/ CNEN-SP, 05508-000 Sao Paulo (Brazil)]. e-mail: romanato@ctmsp.mar.mil.br

    2006-07-01

    When the nuclear fuel lose its ability to efficiently create energy it is removed from the core reactor and moved to a storage unit waiting for a final destination. Generally, the spent nuclear fuel (SNF) remains inside concrete basins with water within the reactors facility for the radioactive activity decay. Water cools the generated heat and shields radioactivity emissions. After some period of time in water basins the SNF can be sent to a definitive deposition in a geological repository and handled as radioactive waste or to reprocessing installations, or still wait for a future solution. Meanwhile, SNF remains stored for a period of time in dry or wet installations, depending on the method adopted by the nuclear power plant or other plans of the country. In many SNF wet storage sites the capacity can be fulfilled very quickly. If so, additional area or other alternative storage system should be given. There are many options to provide capacity increase in the wet storage area, but dry storages are worldwide preferred since it reduces corrosion concerns. In the wet storage the temperature and water purity should be constantly controlled whereas in the dry storage the SNF stands protected in specially designed canisters. Dry interim storages are practical and approved in many countries especially that have the 'wait and see' philosophy (wait to see new technologies development). This paper shows the advantages of dry interim storages sites in comparison with the wet ones and the nowadays problems as terrorism. (Author)

  12. Advantages on dry interim storage for spent nuclear fuel

    International Nuclear Information System (INIS)

    Romanato, L.S.; Rzyski, B.M.

    2006-01-01

    When the nuclear fuel lose its ability to efficiently create energy it is removed from the core reactor and moved to a storage unit waiting for a final destination. Generally, the spent nuclear fuel (SNF) remains inside concrete basins with water within the reactors facility for the radioactive activity decay. Water cools the generated heat and shields radioactivity emissions. After some period of time in water basins the SNF can be sent to a definitive deposition in a geological repository and handled as radioactive waste or to reprocessing installations, or still wait for a future solution. Meanwhile, SNF remains stored for a period of time in dry or wet installations, depending on the method adopted by the nuclear power plant or other plans of the country. In many SNF wet storage sites the capacity can be fulfilled very quickly. If so, additional area or other alternative storage system should be given. There are many options to provide capacity increase in the wet storage area, but dry storages are worldwide preferred since it reduces corrosion concerns. In the wet storage the temperature and water purity should be constantly controlled whereas in the dry storage the SNF stands protected in specially designed canisters. Dry interim storages are practical and approved in many countries especially that have the 'wait and see' philosophy (wait to see new technologies development). This paper shows the advantages of dry interim storages sites in comparison with the wet ones and the nowadays problems as terrorism. (Author)

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

    International Nuclear Information System (INIS)

    Muir, D.W.

    1986-01-01

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

  14. Effect of Endodontic Irrigants on Microtensile Bond Strength to Dentin After Thermocycling and Long-Term Water Storage

    Directory of Open Access Journals (Sweden)

    Daniel Galafassi

    2013-01-01

    Full Text Available Objective: The bond strength of adhesives in irrigated dentin behaves differently over time. The aim of this study was to evaluate the influence of long-term water storage and thermocycling on the microtensile bond strength of adhesive systems to dentin irrigated with endodontic solutions.Materials and Methods: Sixty human molars were used after removal of the occlusal portion and exposure of the dentin by grinding. The specimens were irrigated with 2.5% NaOCl for 30 minutes and then 17% EDTA for 5 minutes and assigned to six groups according to the adhesive system (n=10: G1 and G2–Clearfil SE Bond; G3 and G4–Single Bond 2; and G5 and G6–XP Bond. The teeth were restored with composite and were subjected to water storage for different time periods. G1, G3 and G5 were stored for 24 h; G2, G4 and G6 were stored for 6 months and were subjected to thermocycling (12,000 cycles, 5°C to 55°C, 500 cycles per week for 6 months. After storage, the tooth/restoration assembly was sectioned to obtain four sticks of approximately 1 mm2, for microtensile bond strength testing. The results were analyzed by two-way ANOVA and Tukey’s test.Results: Significant differences were observed among the adhesives (p<0.01. No significant differences were observed in the microtensile bond strength between samples after 24 hours of storage without thermocycling and after 6-month storage with 12,000 cycles (p<0.05.Conclusion: The bond strengths of G5 and G6 after irrigation with 2.5% NaOCl and 17% EDTA were significantly different from those of other groups. Long-term water storage/thermocycling had no effect on bond strength to dentin.

  15. Effects of glucose metabolism pathways on sperm motility and oxidative status during long-term liquid storage of goat semen.

    Science.gov (United States)

    Qiu, Jian-Hua; Li, You-Wei; Xie, Hong-Li; Li, Qing; Dong, Hai-Bo; Sun, Ming-Ju; Gao, Wei-Qiang; Tan, Jing-He

    2016-08-01

    Although great efforts were made to prolong the fertility of liquid-stored semen, limited improvements have been achieved in different species. Although it is expected that energy supply and the redox potential will play an essential role in sperm function, there are few reports on the impact of specific energy substrates on spermatozoa during liquid semen storage. Furthermore, although it is accepted that glucose metabolism through glycolysis provides energy, roles of pentose phosphate pathway (PPP) and tricarboxylic acid cycle remain to be unequivocally found in spermatozoa. We have studied the pathways by which spermatozoa metabolize glucose during long-term liquid storage of goat semen. The results indicated that among the substrates tested, glucose and pyruvate were better than lactate in maintaining goat sperm motility. Although both glycolysis and PPP were essential, PPP was more important than glycolysis to maintain sperm motility. Pentose phosphate pathway reduced oxidative stress and provided glycolysis with more intermediate products such as fructose-6-phosphate. Pyruvate entered goat spermatozoa through monocarboxylate transporters and was oxidized by the tricarboxylic acid cycle and electron transfer to sustain sperm motility. Long-term liquid semen storage can be used as a good model to study sperm glucose metabolism. The data are important for an optimal control of sperm survival during semen handling and preservation not only in the goat but also in other species. Copyright © 2016 Elsevier Inc. All rights reserved.

  16. Long-term energy storage tanks for dwellings and solar house architecture. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1980-12-01

    The design and installation of hot water storage tanks as accumulators of solar energy is presented. Solar house architecture which maximizes roof, solar collector energy absorption potential is then considered. Proposals for residential areas which include solar houses are made.

  17. Improvement of hygienic quality and long-term storage of dried red pepper by gamma irradiation

    International Nuclear Information System (INIS)

    Byun, M.W.; Yook, H.S.; Kwon, J.H.; Kim, J.O.

    1996-01-01

    Dried-red pepper, whole and powdered types, was subjected to a storage-study by investigation the effects of packaging methods (polycloth & polyethylene/polycloth, whole dried-red pepper; nylon/polyethylene-lam-inated film, red pepper powder), temperature and gamma irradiation doses (0-10 kGy). After 6 months storage in polyclith sack at ambient temperature, all whole dried-red pepper showed quality deterioration, such as weight change, insect infestation, discoloration and chemical changes, After 2 years storage in combined packaging with polyethylene/polycloth sack of 5-7.5 kGy irradiated whole dried-red pepper at ambient temperature, however, quality deterioration was not observed. Gamma-irradiated red pepper powder (7.5-10kGy) showed a good quality in hygienic, physicochemical and organoleptic evaluation after 2 years of storage at ambient temperature

  18. Long-term storage of sweetpotato by small-scale farmers through ...

    African Journals Online (AJOL)

    Mo

    by high-performance liquid chromatography, HPLC (Class-. VP, LC-10ATVP, Kyoto, ... and fructose) were measured according as described by. Picha (1985) using ..... pit storage method (Figure 7b), and similarly for Naspot 1 and Ejumula ...

  19. DNA MemoChip: Long-Term and High Capacity Information Storage and Select Retrieval.

    Science.gov (United States)

    Stefano, George B; Wang, Fuzhou; Kream, Richard M

    2018-02-26

    Over the course of history, human beings have never stopped seeking effective methods for information storage. From rocks to paper, and through the past several decades of using computer disks, USB sticks, and on to the thin silicon "chips" and "cloud" storage of today, it would seem that we have reached an era of efficiency for managing innumerable and ever-expanding data. Astonishingly, when tracing this technological path, one realizes that our ancient methods of informational storage far outlast paper (10,000 vs. 1,000 years, respectively), let alone the computer-based memory devices that only last, on average, 5 to 25 years. During this time of fast-paced information generation, it becomes increasingly difficult for current storage methods to retain such massive amounts of data, and to maintain appropriate speeds with which to retrieve it, especially when in demand by a large number of users. Others have proposed that DNA-based information storage provides a way forward for information retention as a result of its temporal stability. It is now evident that DNA represents a potentially economical and sustainable mechanism for storing information, as demonstrated by its decoding from a 700,000 year-old horse genome. The fact that the human genome is present in a cell, containing also the varied mitochondrial genome, indicates DNA's great potential for large data storage in a 'smaller' space.

  20. An analysis of the long-term stability of the particle dynamics in hadron storage rings

    International Nuclear Information System (INIS)

    Bruening, O.S.

    1994-05-01

    This thesis extends the stability analysis of the particle motion in a storage ring and estimates the diffusion rates well inside the dynamic aperture. The calculation of the drift and diffusion coefficients focuses on an application to the proton storage ring in HERA, where the proton beam lifetime drops considerably after the proton and electron beams are brought to collision. The analysis shows that the combined effect of slow and fast modulation frequencies leads to an increased emittance growth in the storage ring. HERA the slow frequency components are caused by ground motion in the HERA tunnel and the fast frequency components by ripples in the power supplies. The thesis provides upper limits for the modultion depths of a fast tune modulation which result in tolerable growth rates for the proton emittance. The analytically calculated drift coefficients agree numerical simulations for the particle dynamics. A comparison of the calculated drift coefficients with those measured in the HERA proton storage ring shows that the analyzed mechanism can lead to growth rates of the same order of magnitude as the ones measured during the luminosity operation in the HERA storage ring. Analytical estimates for the proton growth rates predict a high sensitivity to the particle diffusion on the frequency components of the fast fast tune modulation. This prediction was confirmed by a subsequent modulation experiment in the proton storage ring of HERA, where an external tune modulation with fast frequency components led to a drastic increase in the growth rates

  1. Long-term storage of radioactive solid waste within disposal facilities

    International Nuclear Information System (INIS)

    Wakerley, M.W.; Edmunds, J.

    1986-05-01

    A study of the feasibility and implications of operating potential disposal facilities for low and intermediate level solid radioactive waste in a retrievable storage mode for extended periods of up to 200 years has been carried out. The arisings of conditioned UK radioactive waste up to the year 2030 have been examined. Assignments of these wastes to different types of underground disposal facilities have been made on the basis of their present activity and that which they will have in 200 years time. Five illustrative disposal concepts proposed both in the UK and overseas have been examined with a view to their suitability for adaption for storage/disposal duty. Two concepts have been judged unsuitable because either the waste form or the repository structure were considered unlikely to last the storage phase. Three of the concepts would be feasible from a construction and operational viewpoint. This suggests that with appropriate allowance for geological aspects and good repository and waste form design that storage/disposal within the same facility is achievable. The overall cost of the storage/disposal concepts is in general less than that for separate surface storage followed by land disposal, but more than that for direct disposal. (author)

  2. Use of information-retrieval languages in automated retrieval of experimental data from long-term storage

    Science.gov (United States)

    Khovanskiy, Y. D.; Kremneva, N. I.

    1975-01-01

    Problems and methods are discussed of automating information retrieval operations in a data bank used for long term storage and retrieval of data from scientific experiments. Existing information retrieval languages are analyzed along with those being developed. The results of studies discussing the application of the descriptive 'Kristall' language used in the 'ASIOR' automated information retrieval system are presented. The development and use of a specialized language of the classification-descriptive type, using universal decimal classification indices as the main descriptors, is described.

  3. Preservation of RK and M for Long Term Storage Facilities: The Results of a French Study

    International Nuclear Information System (INIS)

    Schneider, Thierry

    2012-01-01

    Due to the specific long lasting radioactivity of high level waste types, new issues may arise for radiation protection. In this perspective, technical, societal and organizational aspects have to be considered. For the two latter aspects, it is interesting to analyse the efficiency of protection systems available in other fields than nuclear waste management, in order either to protect society from specific risk or to preserve world heritage. Few years ago, CEPN together with MUTADIS have performed a specific study, commissioned by CEA (Commissariat a l'Energie Atomique). The presentation briefly presented the case studies performed on long term protection, as well as the key lessons related to the continuity and sustainability of the surveillance and control of radioactive waste facilities, and the effectiveness of financing schemes for the long term management of radioactive waste. This study has identified a set of performance criteria to deal with long term protection. These results were notably discussed within the framework of the European project COWAM 2 in a working group involving experts, authorities, waste managers, locally elected representatives and NGOs. One part of the study was to analyse the characteristics of protection systems used to manage risks associated with the presence of past underground cavities and mines. A case study presented was the following: After the closing of last mines, maintenance also ended, which, years later, caused ground collapses which led to discussions on responsibility. The connection between the safety problems and the loss of economic activities was underlined. In this context, the IGC (Inspection Generale des Carrieres) was set up. An important part of its functioning is the interaction with the building owners of Paris. The arrangement is that the current owners pay for assuring safety, even though the cause of the safety issue goes back long before owners bought the premises. It was pointed out that market value

  4. Impact of environmental factors on PADC radon detector sensitivity during long term storage

    Science.gov (United States)

    Wasikiewicz, J. M.

    2018-01-01

    A broad set of data on poly-allyl diglycol carbonate (PADC) exposure to various environmental conditions has been collected for a period of 1 year in order to study the aging effect on the sensitivity to radon detection. Aging is a phenomenon that occurs during long PADC storage resulting in a loss of sensitivity and/or creation of false tracks. Conditions under investigation were storages under pure nitrogen or air atmospheres, in water solutions of different pHs, in a range of temperatures, humidity and exposure to UV, gamma and neutron radiations. It was found that PADC strongly responds to some external conditions through physical changes in the polymer material; for example, etching of UV exposed detectors led to 10% loss of their thickness and the removal of the tracks layer. Performance of detectors was compared with a control that was the sensitivity of detectors from the same sheet at the time of primary calibration - within 1 month of each sheet being manufactured. Substantial difference in performance was found between storage under pure, dry nitrogen and in the presence of water. The former preserves PADC radon detection properties for the period of one year without noticeable change. The latter, on the other hand significantly reduces its performance even after 3 months' storage. It was also established that storage under low temperature is not a suitable means to preserve PADC sensitivity to radon detection due to significant loss in the detector sensitivity.

  5. Long term, non-anthropogenic groundwater storage changes simulated by a global land surface model

    Science.gov (United States)

    Li, B.; Rodell, M.; Sheffield, J.; Wood, E. F.

    2017-12-01

    Groundwater is crucial for meeting agricultural, industrial and municipal water needs, especially in arid, semi-arid and drought impacted regions. Yet, knowledge on groundwater response to climate variability is not well understood due to lack of systematic and continuous in situ measurements. In this study, we investigate global non-anthropogenic groundwater storage variations with a land surface model driven by a 67-year (1948-204) meteorological forcing data set. Model estimates were evaluated using in situ groundwater data from the central and northeastern U.S. and terrestrial water storage derived from the Gravity Recovery and Climate Experiment (GRACE) satellites and found to be reasonable. Empirical orthogonal function (EOF) analysis was employed to examine modes of variability of groundwater storage and their relationship with atmospheric effects such as precipitation and evapotranspiration. The result shows that the leading mode in global groundwater storage reflects the influence of the El Niño Southern Oscillation (ENSO). Consistent with the EOF analysis, global total groundwater storage reflected the low frequency variability of ENSO and decreased significantly over 1948-2014 while global ET and precipitation did not exhibit statistically significant trends. This study suggests that while precipitation and ET are the primary drivers of climate related groundwater variability, changes in other forcing fields than precipitation and temperature are also important because of their influence on ET. We discuss the need to improve model physics and to continuously validate model estimates and forcing data for future studies.

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

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  7. Stabilization of Neem Oil Biodiesel with Corn Silk Extract during Long-term Storage.

    Science.gov (United States)

    Ali, Rehab Farouk M; El-Anany, Ayman M

    2017-02-01

    The current study aimed to evaluate the antioxidant efficiency of different extracts of corn silk. In addition, the impact of corn silk extract on oxidative stability of neem biodiesel during storage was studied. The highest phenolics, DPPH radical scavenging and reducing power activities were recorded for methanol-water extract. The longest oxidation stability (10 h) was observed for biodiesel samples blended with 1000 ppm of corn silk extract (CSE). At the end of storage period the induction time of biodiesel samples mixed with 1000 ppm of CSE or butylated hydroxytoluene (BHT) were about 6.72 and 5.63 times as high as in biodiesel samples without antioxidants. Biodiesel samples blended with 1000 ppm of CSE had the lowest acidity at the end of storage period. Peroxide value of biodiesel samples containing 1000 ppm of CSE was about 4.28 times as low as in control sample without antioxidants.

  8. Long term thermal energy storage with stable supercooled sodium acetate trihydrate

    DEFF Research Database (Denmark)

    Dannemand, Mark; Schultz, Jørgen M.; Johansen, Jakob Berg

    2015-01-01

    Utilizing stable supercooling of sodium acetate trihydrate makes it possible to store thermal energy partly loss free. This principle makes seasonal heat storage in compact systems possible. To keep high and stable energy content and cycling stability phase separation of the storage material must...... it expands and will cause a pressure built up in a closed chamber which might compromise stability of the supercooling. This can be avoided by having an air volume above the phase change material connected to an external pressure less expansion tank. Supercooled sodium acetate trihydrate at 20 °C stores up...

  9. Concept study for interim storage of research reactor fuel elements in transport and storage casks. Transport and storage licensing procedure for the CASTOR MTR 2 cask. Final report

    International Nuclear Information System (INIS)

    Weiss, M.

    2001-01-01

    As a result of the project, a concept was to be developed for managing spent fuel elements from research reactors on the basis of the interim storage technology existing in Germany, in order to make the transition to direct disposal possible in the long term. This final report describes the studies for the spent fuel management concept as well as the development of a transport and storage cask for spent fuel elements from research reactors. The concept analyses were based on data of the fuel to be disposed of, as well as the handling conditions for casks at the German research reactors. Due to the quite different conditions for handling of casks at the individual reactors, it was necessary to examine different cask concepts as well as special solutions for loading the casks outside of the spent fuel pools. As a result of these analyses, a concept was elaborated on the basis of a newly developed transport and storage cask as well as a mobile fuel transfer system for the reactor stations, at which a direct loading of the cask is not possible, as the optimal variant. The cask necessary for this concept with the designation CASTOR trademark MTR 2 follows in ist design the tried and tested principles of the CASTOR trademark casks for transport and interim storage of spent LWR fuel. With the CASTOR trademark MTR 2, it is possible to transport and to place into long term interim storage various fuel element types, which have been and are currently used in German research reactors. The technical development of the cask has been completed, the documents for the transport license as type B(U)F package design and for obtaining the storage license at the interim storage facility of Ahaus have been prepared, submitted to the licensing authorities and to a large degree already evaluated positively. The transport license of the CASTOR trademark MTR 2 has been issued for the shipment of VKTA-contents and FRM II compact fuel elements. (orig.)

  10. Viability loss and oxidative stress in Lily bulbs during long-term cold storage.

    NARCIS (Netherlands)

    Bonnier, J.F.M.; Hoekstra, F.A.; Vos, de C.H.R.; Tuyl, van J.M.

    1997-01-01

    The regeneration ability of bulb scales of the Asiatic hybrid lily (Lilium hybrids L.) ‘Enchantment’ was monitored for bulbs stored for 0 to 5 years at −2°C in moist peat. Regeneration ability decreased after more than 1 year of storage and was completely lost after 5 years. Possible involvement of

  11. Optimal sizing and operation of energy storage systems considering long term assessment

    Directory of Open Access Journals (Sweden)

    Gerardo Guerra

    2018-01-01

    Full Text Available This paper proposes a procedure for estimating the optimal sizing of Photovoltaic Generators and Energy Storage units when they are operated from the utility’s perspective. The goal is to explore the potential improvement on the overall operating conditions of the distribution system to which the Generators and Storage units will be connected. Optimization is conducted by means of a General Parallel Genetic Algorithm that seeks to maximize the technical benefits for the distribution system. The paper proposes an operation strategy for Energy Storage units based on the daily variation of load and generation; the operation strategy is optimized for an evaluation period of one year using hourly power curves. The construction of the yearly Storage operation curve results in a high-dimension optimization problem; as a result, different day-classification methods are applied in order to reduce the dimension of the optimization. Results show that the proposed approach is capable of producing significant improvements in system operating conditions and that the best performance is obtained when the day-classification is based on the similarity among daily power curves.

  12. Long-term storage of samples for flow cytometric DNA analysis

    DEFF Research Database (Denmark)

    Vindeløv, L L; Christensen, I J; Keiding, N

    1983-01-01

    estimation by deconvolution, there was significant intraday and interday variation. Hence the most accurate results are obtained if different aliquots of a sample are measured on different days rather than on the same day. Use of the storage method thus has the potential of increasing the accuracy...

  13. Long-term frozen storage of urine samples: a trouble to get PCR results in Schistosoma spp. DNA detection?

    Science.gov (United States)

    Fernández-Soto, Pedro; Velasco Tirado, Virginia; Carranza Rodríguez, Cristina; Pérez-Arellano, José Luis; Muro, Antonio

    2013-01-01

    Human schistosomiasis remains a serious worldwide public health problem. At present, a sensitive and specific assay for routine diagnosis of schistosome infection is not yet available. The potential for detecting schistosome-derived DNA by PCR-based methods in human clinical samples is currently being investigated as a diagnostic tool with potential application in routine schistosomiasis diagnosis. Collection of diagnostic samples such as stool or blood is usually difficult in some populations. However, urine is a biological sample that can be collected in a non-invasive method, easy to get from people of all ages and easy in management, but as a sample for PCR diagnosis is still not widely used. This could be due to the high variability in the reported efficiency of detection as a result of the high variation in urine samples' storage or conditions for handling and DNA preservation and extraction methods. We evaluate different commercial DNA extraction methods from a series of long-term frozen storage human urine samples from patients with parasitological confirmed schistosomiasis in order to assess the PCR effectiveness for Schistosoma spp. detection. Patients urine samples were frozen for 18 months up to 7 years until use. Results were compared with those obtained in PCR assays using fresh healthy human urine artificially contaminated with Schistosoma mansoni DNA and urine samples from mice experimentally infected with S. mansoni cercariae stored frozen for at least 12 months before use. PCR results in fresh human artificial urine samples using different DNA based extraction methods were much more effective than those obtained when long-term frozen human urine samples were used as the source of DNA template. Long-term frozen human urine samples are probably not a good source for DNA extraction for use as a template in PCR detection of Schistosoma spp., regardless of the DNA method of extraction used.

  14. Long-term frozen storage of urine samples: a trouble to get PCR results in Schistosoma spp. DNA detection?

    Directory of Open Access Journals (Sweden)

    Pedro Fernández-Soto

    Full Text Available BACKGROUND: Human schistosomiasis remains a serious worldwide public health problem. At present, a sensitive and specific assay for routine diagnosis of schistosome infection is not yet available. The potential for detecting schistosome-derived DNA by PCR-based methods in human clinical samples is currently being investigated as a diagnostic tool with potential application in routine schistosomiasis diagnosis. Collection of diagnostic samples such as stool or blood is usually difficult in some populations. However, urine is a biological sample that can be collected in a non-invasive method, easy to get from people of all ages and easy in management, but as a sample for PCR diagnosis is still not widely used. This could be due to the high variability in the reported efficiency of detection as a result of the high variation in urine samples' storage or conditions for handling and DNA preservation and extraction methods. METHODOLOGY/PRINCIPAL FINDINGS: We evaluate different commercial DNA extraction methods from a series of long-term frozen storage human urine samples from patients with parasitological confirmed schistosomiasis in order to assess the PCR effectiveness for Schistosoma spp. detection. Patients urine samples were frozen for 18 months up to 7 years until use. Results were compared with those obtained in PCR assays using fresh healthy human urine artificially contaminated with Schistosoma mansoni DNA and urine samples from mice experimentally infected with S. mansoni cercariae stored frozen for at least 12 months before use. PCR results in fresh human artificial urine samples using different DNA based extraction methods were much more effective than those obtained when long-term frozen human urine samples were used as the source of DNA template. CONCLUSIONS/SIGNIFICANCE: Long-term frozen human urine samples are probably not a good source for DNA extraction for use as a template in PCR detection of Schistosoma spp., regardless of the DNA

  15. Nanodefects of membranes cause destruction of packed red blood cells during long-term storage

    International Nuclear Information System (INIS)

    Kozlova, Elena; Chernysh, Aleksandr; Moroz, Victor; Sergunova, Victoria; Gudkova, Olga; Kuzovlev, Artem

    2015-01-01

    Packed red blood cells (PRBC) are used for blood transfusion. PRBC were stored for 30 days under 4 °C in hermetic blood bags with CPD anticoagulant-preservative solution. Hematocrit was 50–55%. The distortions of PRBC membranes nanostructure and cells morphology during storage were studied by atomic force microscopy. Basic measurements were performed at the day 2, 6, 9, 16, 23 and 30 of storage and additionally 2–3 days after it. Topological defects occurred on RBC membranes by day 9. They appeared as domains with grain-like structures (“grains”) sized up to 200 nm. These domains were appeared in almost all cells. Later these domains merged and formed large defects on cells. It was the formation of domains with the “grains” which was onset process leading eventually to destruction of PRBC. Possible mechanisms of transformation of PRBC and their membrane are related to the alterations of spectrin cytoskeleton. During this storage period potassium ions and lactat concentrations increased, pH decreased, intracellular concentration of reduced glutathione diminished in the preservative solution. Changes of PRBC morphology were detected within the entire period of PRBC storage. Discocytes predominated at the days 1 and 2. By day 30 PRBC transformed into irreversible echinocytes and spheroechinocytes. Study of defects of membranes nanostructure may form the basis of assessing the quality of the stored PRBC. This method may allow to work out the best recommendations for blood transfusion. - Highlights: • Domains with “grains” are formed on membranes surface on 9–16 days of PRBC storage. • The development of domains is the reason of irreversible changes of PRBC structure. • The origin of domains is the consequence of alterations of spectrin cytoskeleton. • Study of nanostructure may form basis of assessing the quality of the stored PRBC

  16. Nanodefects of membranes cause destruction of packed red blood cells during long-term storage

    Energy Technology Data Exchange (ETDEWEB)

    Kozlova, Elena, E-mail: waterlake@mail.ru [V.A. Negovsky Scientific Research Institute of General Reanimatology, Moscow (Russian Federation); I.M. Sechenov First Moscow State Medical University, Moscow (Russian Federation); Chernysh, Aleksandr [V.A. Negovsky Scientific Research Institute of General Reanimatology, Moscow (Russian Federation); I.M. Sechenov First Moscow State Medical University, Moscow (Russian Federation); Moroz, Victor; Sergunova, Victoria; Gudkova, Olga; Kuzovlev, Artem [V.A. Negovsky Scientific Research Institute of General Reanimatology, Moscow (Russian Federation)

    2015-10-01

    Packed red blood cells (PRBC) are used for blood transfusion. PRBC were stored for 30 days under 4 °C in hermetic blood bags with CPD anticoagulant-preservative solution. Hematocrit was 50–55%. The distortions of PRBC membranes nanostructure and cells morphology during storage were studied by atomic force microscopy. Basic measurements were performed at the day 2, 6, 9, 16, 23 and 30 of storage and additionally 2–3 days after it. Topological defects occurred on RBC membranes by day 9. They appeared as domains with grain-like structures (“grains”) sized up to 200 nm. These domains were appeared in almost all cells. Later these domains merged and formed large defects on cells. It was the formation of domains with the “grains” which was onset process leading eventually to destruction of PRBC. Possible mechanisms of transformation of PRBC and their membrane are related to the alterations of spectrin cytoskeleton. During this storage period potassium ions and lactat concentrations increased, pH decreased, intracellular concentration of reduced glutathione diminished in the preservative solution. Changes of PRBC morphology were detected within the entire period of PRBC storage. Discocytes predominated at the days 1 and 2. By day 30 PRBC transformed into irreversible echinocytes and spheroechinocytes. Study of defects of membranes nanostructure may form the basis of assessing the quality of the stored PRBC. This method may allow to work out the best recommendations for blood transfusion. - Highlights: • Domains with “grains” are formed on membranes surface on 9–16 days of PRBC storage. • The development of domains is the reason of irreversible changes of PRBC structure. • The origin of domains is the consequence of alterations of spectrin cytoskeleton. • Study of nanostructure may form basis of assessing the quality of the stored PRBC.

  17. Long-term urine biobanking: storage stability of clinical chemical parameters under moderate freezing conditions without use of preservatives.

    Science.gov (United States)

    Remer, Thomas; Montenegro-Bethancourt, Gabriela; Shi, Lijie

    2014-12-01

    To examine the long-term stability and validity of analyte concentrations of 21 clinical biochemistry parameters in 24-h urine samples stored for 12 or 15 yr at -22°C and preservative free. Healthy children's 24-h urine samples in which the respective analytes had been measured shortly after sample collection (baseline) were reanalyzed. Second measurement was performed after 12 yr (organic acids) and 15 yr (creatinine, urea, osmolality, iodine, nitrogen, anions, cations, acid-base parameters) with the same analytical methodology. Paired comparisons and correlations between the baseline and repeated measurements were done. Recovery rates were calculated. More than half of the analytes (creatinine, urea, iodine, nitrogen, sodium, potassium, magnesium, calcium, ammonium, bicarbonate, citric & uric acid) showed measurement values after >10 yr of storage not significantly different from baseline. 15 of the 21 parameters were highly correlated (r=0.99) between baseline and second measurement. Poorest correlation was r=0.77 for oxalate. Recovery ranged from 73% (oxalate) to 105% (phosphate). Our results suggest high long-term stability and measurement validity for numerous clinical chemistry parameters stored at -22°C without addition of any urine preservative. Prospective storage of urine aliquots at -22°C for periods even exceeding 10 yr, appears to be an acceptable and valid tool in epidemiological settings for later quantification of several urine analytes. Copyright © 2014 The Canadian Society of Clinical Chemists. Published by Elsevier Inc. All rights reserved.

  18. High resolution numerical investigation on the effect of convective instability on long term CO2 storage in saline aquifers

    International Nuclear Information System (INIS)

    Lu, C; Lichtner, P C

    2007-01-01

    CO 2 sequestration (capture, separation, and long term storage) in various geologic media including depleted oil reservoirs, saline aquifers, and oceanic sediments is being considered as a possible solution to reduce green house gas emissions. Dissolution of supercritical CO 2 in formation brines is considered an important storage mechanism to prevent possible leakage. Accurate prediction of the plume dissolution rate and migration is essential. Analytical analysis and numerical experiments have demonstrated that convective instability (Rayleigh instability) has a crucial effect on the dissolution behavior and subsequent mineralization reactions. Global stability analysis indicates that a certain grid resolution is needed to capture the features of density-driven fingering phenomena. For 3-D field scale simulations, high resolution leads to large numbers of grid nodes, unfeasible for a single workstation. In this study, we investigate the effects of convective instability on geologic sequestration of CO 2 by taking advantage of parallel computing using the code PFLOTRAN, a massively parallel 3-D reservoir simulator for modeling subsurface multiphase, multicomponent reactive flow and transport based on continuum scale mass and energy conservation equations. The onset, development and long-term fate of a supercritical CO 2 plume will be resolved with high resolution numerical simulations to investigate the rate of plume dissolution caused by fingering phenomena

  19. Soil charcoal as long-term pyrogenic carbon storage in Amazonian seasonal forests.

    Science.gov (United States)

    Turcios, Maryory M; Jaramillo, Margarita M A; do Vale, José F; Fearnside, Philip M; Barbosa, Reinaldo Imbrozio

    2016-01-01

    Forest fires (paleo + modern) have caused charcoal particles to accumulate in the soil vertical profile in Amazonia. This forest compartment is a long-term carbon reservoir with an important role in global carbon balance. Estimates of stocks remain uncertain in forests that have not been altered by deforestation but that have been impacted by understory fires and selective logging. We estimated the stock of pyrogenic carbon derived from charcoal accumulated in the soil profile of seasonal forest fragments impacted by fire and selective logging in the northern portion of Brazilian Amazonia. Sixty-nine soil cores to 1-m depth were collected in 12 forest fragments of different sizes. Charcoal stocks averaged 3.45 ± 2.17 Mg ha(-1) (2.24 ± 1.41 Mg C ha(-1) ). Pyrogenic carbon was not directly related to the size of the forest fragments. This carbon is equivalent to 1.40% (0.25% to 4.04%) of the carbon stocked in aboveground live tree biomass in these fragments. The vertical distribution of pyrogenic carbon indicates an exponential model, where the 0-30 cm depth range has 60% of the total stored. The total area of Brazil's Amazonian seasonal forests and ecotones not altered by deforestation implies 65-286 Tg of pyrogenic carbon accumulated along the soil vertical profile. This is 1.2-2.3 times the total amount of residual pyrogenic carbon formed by biomass burning worldwide in 1 year. Our analysis suggests that the accumulated charcoal in the soil vertical profile in Amazonian forests is a substantial pyrogenic carbon pool that needs to be considered in global carbon models. © 2015 John Wiley & Sons Ltd.

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

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  1. Stability of selected serum hormones and lipids after long-term storage in the Janus Serum Bank.

    Science.gov (United States)

    Gislefoss, Randi E; Grimsrud, Tom K; Mørkrid, Lars

    2015-04-01

    The potential value of a biobank depends on the quality of the samples, i.e. how well they reflect the biological or biochemical state of the donors at the time of sampling. Documentation of sample quality has become a particularly important issue for researchers and users of biobank studies. The aim of this study was to investigate the long-term stability of selected components: cholesterol, high density cholesterol (HDLC), low density cholesterol (LDLC), apolipoprotein A1 (apo-A1), apolipoprotein B (apo B), follicle stimulating hormone (FSH), luteinizing hormone (LH), prolactin (PRL), thyroid stimulating hormone (TSH) and free thyroxin (FT4). Samples, stored at -25°C, from 520 men aged 40-49 years at blood sampling distributed in equally sized groups (n=130) according to length of storage, 0, 4, 17 and 29 years, respectively, were used in a cross sectional design. The freshly collected serum samples were used as a reference group to calculate storage related changes. The differences between fresh samples and samples stored for 29 years were substantial for apo-A1 (+12%), apo-B (+22.3%), HDLC (-69.2%), LDLC (+31.3%), and PRL (-33.5%), while total cholesterol, FSH, LH, TSH and FT4 did not show any significant difference. The study showed large differences in serum level of the selected components. The lipids and apolipoproteins were all changed except for total cholesterol. Most hormones investigated (FSH, LH, TSH and FT4) proved to be stable after 29 years of storage while PRL showed sign of degradation. The observed differences are probably due to long-term storage effects and/or external factors (i.e. diet and smoking). Copyright © 2014 The Canadian Society of Clinical Chemists. Published by Elsevier Inc. All rights reserved.

  2. Issues at stake when considering long term storage of HLW. A comprehensive approach to designing the facility

    International Nuclear Information System (INIS)

    Marvy, A.; Ochem, D.

    2002-01-01

    CEA has been conducting a comprehensive R and D program to identify and study key HLW storage design criteria to possibly meet the lifetime goal of a century and beyond. A novel approach is being used since such installations must be understood as a global system comprised of various materials and hardware components, canisters, concrete and steel structures and specific procedures covering engineering steps from construction to operation including monitoring, care and maintenance as well as licensing. The challenge set by such a lifetime design goal made the R and D people focus on issues at stake and relevant to long term HLW storage in particular heat management, the effect of time on materials and the sustainability of care and maintenance. This opened up the R and D field from fundamental research areas to more conventional and technical aspects. Two major guiding principles have been devised as key design goals for the storage concepts under consideration. One is the paramount function of retrievability, which must allow the safe retrieval of any HLW package from the facility at any given time. Next is the passive containment philosophy requiring that a two-barrier system be considered. In the case of spent fuel, CEA's early assessment of the long-term behaviour of cladding shows that it cannot qualify as a reliable barrier over a long period of time. Therefore, the overriding strategy of preventing corrosion and material degradation to achieve canister protection, and therefore containment of radioactive material throughout the time of period envisaged, is at the heart of the R and D program and several design alternatives are being studied to meet that objective. For instance available thermal power from SF is used to establish dry corrosion conditions within the storage facility. The paper reviews all of these different R and D and engineering aspects. (author)

  3. Seed quality preservation advantage of gamma irradiation seed pre-treatment during long term storage in soybean

    International Nuclear Information System (INIS)

    Guha, Sameer Kumar; Sumedha; Singh, Bhupinder

    2014-01-01

    The experiment was conducted to analyse the effect of gamma irradiation seed pre-treatment on insect damage and quality preservation of soybean seeds during long term storage at ambient temperature (27-42 ℃) and relative humidity (50-95%). Freshly harvested seeds of soybean (cv. Pusa-9814) were treated with control (0), 0.01, 0.05, 0.5, 1.0, 3.0, 5.0 kGy gamma radiation on a Gamma irradiator (Gamma Chamber 5000, 60 Co source, activity 12000 Ci, BRIT, Mumbai, India) at the Nuclear Research Laboratory, IARI, New Delhi and were stored over one year in cotton cloth bags under ambient conditions. Protein and oil per cent and fatty acid profile was measured in freshly harvested zero time unirradiated control, aged unirradiated control and other treatments of ionizing radiation. Seed oil was extracted through the soxhlet extraction method and oil profiling was done by gas chromatography. Change in saturated and unsaturated fatty acids like palmitic, stearic, oleic, linolic, linolenic acid and oleic to linoleic ratio was measured. Oil content of unirradiated stored seeds compared to that of the freshly harvested control was lower. However, radiation in general, helped in maintaining a higher seed oil during storage when compared with that of the aged unirradiated control and was insignificantly reduced over the fresh unirrradiated control. Further, gamma irradiation treatment did not yield any adverse affect on the seed protein even after prolonged storage. The results reveal a reduced rate of lipid degradation and improved seed hardness over untreated control with no significant change in fatty acid profile of the irradiated and the unirradiated seeds over a long term storage period. (author)

  4. Examination of the rheological properties of stirred joghurt during the long-term storage by using dynamic oscillation method

    Directory of Open Access Journals (Sweden)

    Milica Vilušić

    2003-07-01

    Full Text Available In this work the rheological properties of stirred yoghurt during the longterm storage at 4 and 8°C were investigated. The optimal quantity of additives, in order to increase dry matter content (whole milk powder and whey protein-lactalbumin, was preliminary determined and the fermentation was performed. During 42 days, i.e., 1st, 7th, 14th, 21st, 28th, 35th and 42nd day of storage of stirred yoghurt, in refrigerator at 4 and 8°C, the changes of pH value, acidity and rheological properties by using of dynamic oscillation method were observed. Results of this work indicated that an addition of whole milk powder and whey protein have an influence on rheological properties of stirred yoghurt. The long-term storage of stirred yoghurt and the results of dynamic oscilations showed permanently higher G’storage (elasticity modulus, where elastic properties of viscoelastic products dominate, in comparison with the G” loss (viscosity modulus. Increased moduls of elasticy and viscosity, as function of time, permanently occurs at pH value 4.00 and lower, as an indication of alteration of long casein chains in the coagulum structure. Different temperatures of storage had no influence on changes of rheological properties of examinated types of stirred yoghur. The relation of above mentioned moduls of elasticy and viscosity kept the same increasing tendency.

  5. High density FTA plates serve as efficient long-term sample storage for HLA genotyping.

    Science.gov (United States)

    Lange, V; Arndt, K; Schwarzelt, C; Boehme, I; Giani, A S; Schmidt, A H; Ehninger, G; Wassmuth, R

    2014-02-01

    Storage of dried blood spots (DBS) on high-density FTA(®) plates could constitute an appealing alternative to frozen storage. However, it remains controversial whether DBS are suitable for high-resolution sequencing of human leukocyte antigen (HLA) alleles. Therefore, we extracted DNA from DBS that had been stored for up to 4 years, using six different methods. We identified those extraction methods that recovered sufficient high-quality DNA for reliable high-resolution HLA sequencing. Further, we confirmed that frozen whole blood samples that had been stored for several years can be transferred to filter paper without compromising HLA genotyping upon extraction. Concluding, DNA derived from high-density FTA(®) plates is suitable for high-resolution HLA sequencing, provided that appropriate extraction protocols are employed. © 2014 John Wiley & Sons A/S. Published by John Wiley & Sons Ltd.

  6. Dry interim storage of radioactive material in Germany

    International Nuclear Information System (INIS)

    Drobniewski, Christian; Palmes, Julia

    2013-01-01

    In accordance with the waste management concept in Germany, spent fuel is stored in interim storage facilities for a period of up to 40 years until deposition in a geological repository. In twelve on-site interim storages in the vicinity or directly on the sites of the nuclear power plants, spent fuel elements from reactor operation are stored after the necessary period of decay in wet storage basins inside the reactors. Additionally, three central interim storage facilities for storage of spent fuel of different origin are in operation. The German facilities realize the concept of dry interim storage in metallic transport and storage casks. The confinement of the radioactive material is ensured by the double lid system of the casks, of which the leak tightness is monitored constantly. The casks are constructed to provide adequate heat removal and shielding of gamma and neutron radiation. Usually the storage facilities are halls of thick concrete structures, which ensure the removal of the decay heat by natural convection. The main safety goal of the storage concept is to prevent unnecessary exposure of persons, material goods and environment to ionizing radiation. Moreover any exposure should be kept as low as reasonable achievable. To reach this goal the containment of the radioactive materials, the disposal of decay heat, the sub criticality and the shielding of ionizing radiation has to be demonstrated by the applicant and verified by the licensing authority. In particular accidents, incidents and disasters have to be considered in the facility and cask design. This includes mechanical impacts onto the cask, internal and external fire, and environmental effects like wind, rain, snowfall, flood, earthquakes and landslides. In addition civilizatoric influences like plane crashes and explosions have to be taken into account. In all mentioned cases the secure confinement of the radioactive materials has to be ensured. On-site storage facilities have to consider the

  7. [Properties of live antibiotics-resistant anthrax vaccine STI-PR after long-term storage].

    Science.gov (United States)

    Aksenova, L Iu; Buravtseva, N P; Kogotkova, O I; Eremenko, E I; Tsygankova, O I

    2007-01-01

    Study showed that cultural, morphologic, genetic, immunologic characteristics, and resistance to antibiotics of STI-PR anthrax vaccine did not change after storage during 20 years in lyophilized condition. It has been shown that medium for lyophilization plays important role in preservation of vitality of anthrax spores. Optimal preservative properties have been observed for thioureal and sucrose-gelatinous media for lyophilization. Obtained results give reasons for prolongation of shelf live of STI-PR vaccine from 2 - 3 to 5 - 8 years.

  8. Rejuvenation capacity of red blood cells in additive solutions over long-term storage.

    Science.gov (United States)

    Meyer, Erin K; Dumont, Deborah F; Baker, Sharry; Dumont, Larry J

    2011-07-01

    Red blood cells (RBCs) are Food and Drug Administration (FDA)-approved for 42-day storage with the use of additive solutions (ASs). However, adenosine triphosphate (ATP) and 2,3-diphosphoglycerate (2,3-DPG) levels in the RBCs decline over this time. These constituents may be restored by treatment with rejuvenation (REJ) solutions. This study was done to assess the response capability of RBCs from 30 to 120 days of storage in three FDA-licensed RBC storage solutions after incubation with a rejuvenating solution of pyruvate, inosine, phosphate, and adenine. Three units each of RBCs in approved AS (AS-1 [Adsol, Fenwal, Inc.], AS-3 [Nutricel, Medsep Corp.], and AS-5 [Optisol, Terumo Corp.]) were stored under standard conditions at 1 to 6°C for up to 120 days. Aliquots (4 mL) on Days 30, 42, 60, 80, 100, and 120 (± 2 days) were REJ by incubating with Rejuvesol (Encyte Corp.). Control untreated and REJ aliquots were extracted using perchloric acid and stored at -80°C until assayed for 2,3-DPG and ATP. RBCs responded to REJ by increasing DPG and ATP contents. The response declined linearly at 0.070 ± 0.008 µmol DPG/g hemoglobin (Hb)/day and 0.035 ± 0.004 µmol ATP/g Hb/day with no differences between ASs. We conclude that Rejuvesol is able to restore ATP and 2,3-DPG levels in RBCs stored up to 120 days in AS. The response diminishes as storage time increases. This rejuvenation (REJ) capability does not seem useful for routine assessment of RBC anabolic capacity in research programs, but may be useful to the investigator when studying unique and novel treatment methods. © 2011 American Association of Blood Banks.

  9. Long-term storage of irradiated potatoes for processing use, 4

    International Nuclear Information System (INIS)

    Aoki, Shohei; Umeda, Keiji; Kameyama, Kenji.

    1984-01-01

    In order to develop suitable storage conditions in potatoes for processing use, non-irradiated and irradiated potatoes var. Norin No. 1 were stored in containers and in bulk. The contents of reducing sugars were determined and the properties of potato chips were analysed. Reconditioning at 10 deg C and RH 90 % for 4 weeks during an early period of dormancy lowered the content of reducing sugars remarkably in both the non-irradiated and irradiated potatoes which were either stored in containers or in bulk. The optimum conditions for the storage of potatoes were 8 deg C and RH 90 %, which enabled the potatoes to retain their hardness while the content reducing sugars decreased. The potatoes stored under the above conditions gave chips with a fairly good color. In contrast, the non-irradiated potatoes stored for a period of 6 months or longer sprouted and aged, resulting in chips with unsatisfactory color. It was found necessary to use potatoes with low contents of both amino acids and reducing sugars to avoid the browning of chips. Bulk storage which was found to be effective for air circulation through potatoes caused creeping phenomenon. (author)

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

    International Nuclear Information System (INIS)

    Dehaudt, Ph.

    2000-01-01

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

  11. 105-C Reactor interim safe storage project technology integration plan

    International Nuclear Information System (INIS)

    Pulsford, S.K.

    1997-01-01

    The 105-C Reactor Interim Safe Storage Project Technology Integration Plan involves the decontamination, dismantlement, and interim safe storage of a surplus production reactor. A major goal is to identify and demonstrate new and innovative D and D technologies that will reduce costs, shorten schedules, enhance safety, and have the potential for general use across the RL complex. Innovative technologies are to be demonstrated in the following areas: Characterization; Decontamination; Waste Disposition; Dismantlement, Segmentation, and Demolition; Facility Stabilization; and Health and Safety. The evaluation and ranking of innovative technologies has been completed. Demonstrations will be selected from the ranked technologies according to priority. The contractor team members will review and evaluate the demonstration performances and make final recommendations to DOE

  12. Interim dry storage system technologies and innovations VARNA 2002

    International Nuclear Information System (INIS)

    Chollet, P.; Guenon, Y.

    2002-01-01

    The main concepts of the TN24 Family and NUHOMS System are explained in the paper. It is discussed how the NPPs specific requirements and economics trends contributes to the growing families of interim dry storage systems delivered under COGEMA LOGICTICS license. It is concluded that modular solutions are currently dominating because they are derived from main concepts evolved over time, benefited from both the transport aspects with internationally recognised stringent regulations, and various specific ISFSI requirements and economic trends

  13. Waste Encapsulation and Storage Facility interim operational safety requirements

    CERN Document Server

    Covey, L I

    2000-01-01

    The Interim Operational Safety Requirements (IOSRs) for the Waste Encapsulation and Storage Facility (WESF) define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation during receipt and inspection of cesium and strontium capsules from private irradiators; decontamination of the capsules and equipment; surveillance of the stored capsules; and maintenance activities. Controls required for public safety, significant defense-in-depth, significant worker safety, and for maintaining radiological consequences below risk evaluation guidelines (EGs) are included.

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

    International Nuclear Information System (INIS)

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

    1997-04-01

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

  15. Concepts for the interim storage of spent fuel elements from research reactors in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Niephaus, D.; Bensch, D.; Quaassdorff, P.; Plaetzer, S.

    1997-01-01

    Research reactors have been operated in the Federal Republic of Germany since the late fifties. These are Material Test Reactors (MTR) and training, Research and Isotope Facilities of General Atomic (TRIGA). A total of seven research reactors, i.e. three TRIGA and four MTR facilities were still in operation at the beginning of 1996. Provisions to apply to the back-end of the fuel cycle are required for their continued operation and for already decommissioned plants. This was ensured until the end of the eighties by the reprocessing of spent fuel elements abroad. In view of impeding uncertainties in connection with waste management through reprocessing abroad, the development of a national back-end fuel cycle concept was commissioned by the Federal Minister of Education, Science, Research and Technology in early 1990. Development work was oriented along the lines of the disposal concept for irradiated light-water reactor fuel elements from nuclear power plants. Analogously, the fuel elements from research reactors are to be interim-stored on a long-term basis in adequately designed transport and storage casks and then be directly finally disposed without reprocessing after up to forty years of interim storage. As a first step in the development of a concept for interim storage, several sites with nuclear infrastructure were examined and assessed with respect to their suitability for interim storage. A reasonably feasible reference concept for storing the research reactor fuel elements in CASTOR MTR 2 transport and storage casks at the Ahaus interim storage facility (BZA) was evaluated and the hot cell facility and AVR store of Forschungszentrum Juelich (KFA) were proposed as an optional contingency concept for casks that cannot be repaired at Ahaus. Development work was continued with detailed studies on these two conceptual variants and the results are presented in this paper. (author)

  16. Mineral-modeled ceramics for long-term storage of high-level nuclear wastes

    International Nuclear Information System (INIS)

    Vance, E.R.

    1980-01-01

    Over the past ten years, Penn State's Materials Research Laboratory has done extensive work on mineral-modeled ceramics for high-level nuclear waste storage. These ceramics are composed of several mineral analogues that form a monolithic polycrystalline aggregate. Mineral-modeling can be made in a similar fashion to nuclear waste glasses, and their naturally occurring analogues are known to last millions, and even billions, of years in hot, wet conditions. It is believed that such ceramics could reduce dispersal of radionuclides by leaching to a minimum

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

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

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  19. 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

  20. Using electrophysiology to demonstrate that cuing affects long-term memory storage over the short term

    OpenAIRE

    Maxcey, Ashleigh M.; Fukuda, Keisuke; Song, Won S.; Woodman, Geoffrey F.

    2015-01-01

    As researchers who study working memory, we often assume that participants keep a representation of an object in working memory when we present a cue that indicates that object will be tested in a couple of seconds. This intuitively accounts for how well people can remember a cued object relative to their memory for that same object presented without a cue. However, it is possible that this superior memory does not purely reflect storage of the cued object in working memory. We tested the hyp...

  1. Mathematical models as tools for probing long-term safety of CO2 storage

    Energy Technology Data Exchange (ETDEWEB)

    Pruess, Karsten; Birkholzer, Jens; Zhou, Quanlin

    2009-02-01

    Subsurface reservoirs being considered for storing CO{sub 2} include saline aquifers, oil and gas reservoirs, and unmineable coal seams (Baines and Worden, 2004; IPCC, 2005). By far the greatest storage capacity is in saline aquifers (Dooley et al., 2004), and our discussion will focus primarily on CO{sub 2} storage in saline formations. Most issues for safety and security of CO{sub 2} storage arise from the fact that, at typical temperature and pressure conditions encountered in terrestrial crust, CO{sub 2} is less dense than aqueous fluids. Accordingly, CO{sub 2} will experience an upward buoyancy force in most subsurface environments, and will tend to migrate upwards whenever (sub-)vertical permeable pathways are available, such as fracture zones, faults, or improperly abandoned wells (Bachu, 2008; Pruess, 2008a, b; Tsang et al., 2008). CO{sub 2} injection will increase fluid pressures in the target formation, thereby altering effective stress distributions, and potentially triggering movement along fractures and faults that could increase their permeability and reduce the effectiveness of a caprock in containing CO{sub 2} (Rutqvist et al., 2008; Chiaramonte et al., 2008). Induced seismicity as a consequence of fluid injection is also a concern (Healy et al., 1968; Raleigh et al., 1976; Majer et al., 2007). Dissolution of CO{sub 2} in the aqueous phase generates carbonic acid, which may induce chemical corrosion (dissolution) of minerals with associated increase in formation porosity and permeability, and may also mediate sequestration of CO{sub 2} as solid carbonate (Gaus et al., 2008). Chemical dissolution of caprock minerals could promote leakage of CO{sub 2} from a storage reservoir (Gherardi et al., 2007). Chemical dissolution and geomechanical effects could reinforce one another in compromising CO{sub 2} containment. Additional issues arise from the potential of CO{sub 2} to mobilize hazardous chemical species (Kharaka et al., 2006), and from migration of

  2. Harvest Date Influences Superficial Scald Development in Granny Smith Apples During Long Term Storage

    OpenAIRE

    ERKAN, Mustafa; PEKMEZCİ, Mustafa

    2014-01-01

    The effects of harvest dates on superficial scald development and postharvest quality in 'Granny Smith' apples (Malus domestica Borkh.) were investigated. Apples were harvested at 15-day intervals during 2 consecutive years (2000-2001) and stored at 0 °C with 90% relative humidity for 8 months. At the end of the 8 - month storage period plus an additional 1 week at 20 °C the percentage of superficial scald was lower (24.4%) in late harvested (November 15) apples than in ap...

  3. Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 3. Alternatives for interim storage and transportation

    International Nuclear Information System (INIS)

    1976-05-01

    Volume III of the five-volume report contains information on alternatives for interim storage and transportation. Section titles are: interim storage of spent fuel elements; interim storage of chop-leach fuel bundle residues; tank storage of high-level liquid waste; interim storage of solid non-high-level wastes; interim storage of solidified high-level waste; and, transportation alternatives

  4. The role of reconsolidation and the dynamic process of long-term memory formation and storage

    Directory of Open Access Journals (Sweden)

    Cristina M Alberini

    2011-03-01

    Full Text Available It is becoming increasingly clear that the processes of memory formation and storage are exquisitely dynamic. Elucidating the nature and temporal evolution of the biological changes that accompany encoding, storage and retrieval is key to understand memory formation. For explicit or medial temporal lobe-dependent memories that form after a discrete event and are stored for a long time, the physical changes underlying the encoding and processing of the information (memory trace or engram remain in a fragile state for some time. However, over time, the new memory becomes increasingly resistant to disruption until it is consolidated. Retrieval or reactivation of an apparently consolidated memory can render the memory labile again, and reconsolidation is the process that occurs to mediate its restabilization. Reconsolidation also evolves with the age of the memory: Young memories are sensitive to postreactivation disruption, but older memories are more resistant. Why does a memory become labile again if it is retrieved or reactivated? Here I suggest that the main function of reconsolidation is to contribute to the lingering consolidation process and mediate memory strengthening. I also discuss the literature and results regarding the influence of the passage of time on the reconsolidation of memory. These points have important implications for the use of reconsolidation in therapeutic settings.

  5. Long term storage of dry versus frozen RNA for next generation molecular studies.

    Directory of Open Access Journals (Sweden)

    Eric Seelenfreund

    Full Text Available The standard method for the storage and preservation of RNA has been at ultra-low temperatures. However, reliance on liquid nitrogen and freezers for storage of RNA has multiple downsides. Recently new techniques have been developed for storing RNA at room temperature utilizing desiccation and are reported to be an effective alternative for preserving RNA integrity. In this study we compared frozen RNA samples stored for up to one year to those which had been desiccated using RNAstable (Biomatrica, Inc., San Diego, CA and stored at room temperature. RNA samples were placed in aliquots and stored after desiccation or frozen (at -80°C, and were analyzed for RNA Integrity Number (RIN, and by qPCR, and RNA sequencing. Our study shows that RNAstable is able to preserve desiccated RNA samples at room temperature for up to one year, and that RNA preserved by desiccation is comparable to cryopreserved RNA for downstream analyses including real-time-PCR and RNA sequencing.

  6. Long-term storage of 85Kr in amorphous zeolite 5A

    International Nuclear Information System (INIS)

    Penzhorn, R.D.; Noppel, H.E.; Dorea, A.; Guenther, K.; Leitzig, H.; Schuster, P.

    1984-01-01

    Ar, Kr and Xe can be immobilized in type A zeolites as well as in mordenite and chabazite, when the original crystal structure is hydrothermally vitrified in the presence of the densified gas. Zeolites containing a high percentage of earth alcali metals yield encapsulates that are thermally very stable. Gas fixation conditions are essentially independent of the form of aggregation of the matrix. Noble gas encapsulates were characterized by their specific surface area as well as by microprobe analysis, X-ray analysis and electron diffraction. The results indicate that Kr is immobilized in units smaller than the size of a zeolite crystal. The thermal conductivity of zeolites was determined experimentally in various fluid media. With the data obtained the heat transport through a final storage vessel cooled by natural air convection was calculated. The estimated temperature profiles correlate well with those obtained in experiments simulating a storage containment. To verify the process, active samples having specific activities up to 30 mCi/g have been prepared. Leaching results demonstrate the chemical stability of the Kr/5A encapsulates. A semi-pilot facility based on the one-way autoclave concept has been constructed and demonstrated in operation

  7. Interim Storage of Plutonium in Existing Facilities

    International Nuclear Information System (INIS)

    Woodsmall, T.D.

    1999-01-01

    'In this era of nuclear weapons disarmament and nonproliferation treaties, among many problems being faced by the Department of Energy is the safe disposal of plutonium. There is a large stockpile of plutonium at the Rocky Flats Environmental Technology Center and it remains politically and environmentally strategic to relocate the inventory closer to a processing facility. Savannah River Site has been chosen as the final storage location, and the Actinide Packaging and Storage Facility (APSF) is currently under construction for this purpose. With the ability of APSF to receive Rocky Flats material an estimated ten years away, DOE has decided to use the existing reactor building in K-Area of SRS as temporary storage to accelerate the removal of plutonium from Rocky Flats. There are enormous cost savings to the government that serve as incentive to start this removal as soon as possible, and the KAMS project is scheduled to receive the first shipment of plutonium in January 2000. The reactor building in K-Area was chosen for its hardened structure and upgraded seismic qualification, both resulting from an effort to restart the reactor in 1991. The KAMS project has faced unique challenges from Authorization Basis and Safety Analysis perspectives. Although modifying a reactor building from a production facility to a storage shelter is not technically difficult, the nature of plutonium has caused design and safety analysis engineers to make certain that the design of systems, structures and components included will protect the public, SRS workers, and the environment. A basic overview of the KAMS project follows. Plutonium will be measured and loaded into DOT Type-B shipping packages at Rocky Flats. The packages are 35-gallon stainless steel drums with multiple internal containment boundaries. DOE transportation vehicles will be used to ship the drums to the KAMS facility at SRS. They will then be unloaded, stacked and stored in specific locations throughout the

  8. Sheet GT3-2. General approach of life phases on a long term for uranium mining residues storages and comparison with other storages

    International Nuclear Information System (INIS)

    2009-01-01

    This document aims at specifying the short term, middle term and long term boundaries for a sustainable management and rehabilitated ancient uranium mining sites and of uranium mining residue storage sites. It presents a general overview of site evolution in time, and then, more precisely, the different functions (rehabilitation management, corrective actions, control and monitoring, and so on) and equipment (confinement works, measurement system) at stake in the management of these sites and the control of their impacts. Functions and equipment implemented on such a site, as well as time scales corresponding to different approaches are compared with those of other types of storage. The peculiarity of ancient uranium mining sites and its implications in terms of management on a long term are discussed

  9. Long-term storage and safe retrieval of DNA from microorganisms for molecular analysis using FTA matrix cards.

    Science.gov (United States)

    Rajendram, D; Ayenza, R; Holder, F M; Moran, B; Long, T; Shah, H N

    2006-12-01

    We assessed the potential use of Whatman FTA paper as a device for archiving and long-term storage of bacterial cell suspensions of over 400 bacterial strains representing 61 genera, the molecular applications of immobilised DNA on FTA paper, and tested its microbial inactivation properties. The FTA paper extracted bacterial DNA is of sufficiently high quality to successfully carryout the molecular detection of several key genes including 16S rRNA, esp (Enterococcus surface protein), Bft (Bacteroides fragilis enterotoxin) and por (porin protein) by PCR and for DNA fingerprinting by random amplified polymorphic DNA-PCR (RAPD-PCR). To test the long-term stability of the FTA immobilised DNA, 100 of the 400 archived bacterial samples were randomly selected following 3 years of storage at ambient temperature and PCR amplification was used to monitor its success. All of the 100 samples were successfully amplified using the 16S rDNA gene as a target and confirmed by DNA sequencing. Furthermore, the DNA was eluted into solution from the FTA cards using a new alkaline elution procedure for evaluation by real-time PCR-based assays. The viability of cells retained on the FTA cards varied among broad groups of bacteria. For the more fragile gram-negative species, no viable cells were retained even at high cell densities of between 10(7) and 10(8) colony forming units (cfu) ml(-1), and for the most robust species such as spore-formers and acid-fast bacteria, complete inactivation was achieved at cell densities ranging between 10(1) and 10(4) cfu ml(-1). The inactivation of bacterial cells on FTA cards suggest that this is a safe medium for the storage and transport of bacterial nucleic acids.

  10. Long-term preservation of Tetraselmis indica (Chlorodendrophyceae, Chlorophyta) for flow cytometric analysis: Influence of fixative and storage temperature.

    Science.gov (United States)

    Naik, Sangeeta Mahableshwar; Anil, Arga Chandrashekar

    2017-08-01

    Immediate enumeration of phytoplankton is seldom possible. Therefore, fixation and subsequent storage are required for delayed analysis. This study investigated the influence of glutaraldehyde (GA) concentrations (0.25%, 0.5%, and 1%) and storage temperatures (-80°C LN2 , -80°C, -20°C, and 5°C) on Tetraselmis indica for flow cytometric analysis. Cell recovery, granularity, and membrane permeability were independent of GA concentration whereas cell size and chlorophyll autofluorescence were concentration dependent. After an initial cell loss (16-19%), no cell loss was observed when samples were stored at 5°C. Cell recovery was not influenced by storage temperature until 4months but later samples preserved at -80°C LN2 , -80°C, and -20°C resulted in ~41% cell loss. Although maximum cell recovery with minimal effect on cell integrity was obtained at 5°C, autofluorescence was retained better at -80°C LN2 and -80°C. This suggests that in addition to fixative, the choice of storage temperature is equally important. Thus for long-term preservation, especially to retain autofluorescence, the use of lower concentration (0.25%) of GA when stored at a lower temperature (-80°C LN2 and -80°C) while a higher concentration (1%) of GA when stored at a higher temperature (5°C) is recommended. Copyright © 2017 Elsevier B.V. All rights reserved.

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

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  12. The British Library Newspaper Collection: Long Term Storage, Preservation and Access

    Directory of Open Access Journals (Sweden)

    Patrick Fleming

    2008-11-01

    Full Text Available The British Library has recently unveiled plans for improving the collection care of, and digital access to, one of the world's greatest newspaper collections. The collection, which dates from the 16th century, contains UK titles as well as 200 overseas titles and is at risk. 15% of the collection is unusable because of its deterioration, and there are pressures on space and a need to develop greater digital content for access. The solution is to place all of the physical newspapers into a new, state of the art Newspaper Storage Building at Boston Spa, the British Library's main storage and logistics site, and home to its document delivery service. The building will comprise of 160 km of high density shelf space, fully automated under special environmental conditions including low oxygen, regulated 16 degree Celsius temperature, and 52% humidity. Future access to the collection will be at the BL's main Library site at St Pancras, in a specially equipped reading room, so that researchers can integrate other collection items into their studies. However, access will be by surrogate means, initially microfilm, stored in London, and then, increasingly, digital access. By March 2009, the British Library will have digitised 3 million historic newspapers with JISC funds, and this content will be available to readers for free in reading rooms and on a paid for basis online, or via subscriptions. The Library is investigating a similar model going forward with a private sector partner who is willing to digitise and sell online out of copyright newspapers from the BL's collection for a fixed period. This will provide digital content for customers in reading rooms, free at the point of access.

  13. Retrievable surface storage: interim storage of solidified high-level waste

    International Nuclear Information System (INIS)

    LaRiviere, J.R.; Nelson, D.C.

    1976-01-01

    Studies have been conducted on retrievable-surface-storage concepts for the interim storage of solidified high-level wastes. These studies have been reviewed by the Panel on Engineered Storage, convened by the Committee on Radioactive Waste Management of the National Research Council-National Academy of Sciences. The Panel has concluded that ''retrievable surface storage is an acceptable interim stage in a comprehensive system for managing high-level radioactive wastes.'' The scaled storage cask concept, which was recommended by the Panel on Engineered Storage, consists of placing a canister of waste inside a carbon-steel cask, which in turn is placed inside a thick concrete cylinder. The waste is cooled by natural convection air flow through an annulus between the cask and the inner wall of the concrete cylinder. The complete assembly is placed above ground in an outdoor storage area

  14. Nuclear waste: Is there a need for federal interim storage

    International Nuclear Information System (INIS)

    1989-01-01

    The Congress created the Monitored Retrievable Storage Review Commission to provide a report on the need for a Federal monitored retrievable storage facility (MRS) as part of the Nation's nuclear waste management system. The Commission concludes that the MRS as presently described in the law, which links the capacity and schedule of operation of the MRS to a permanent geologic repository, cannot be justified. The Commission finds, however, that while no single factor would favor an MRS over the No-MRS option, cumulatively the advantages of an MRS would justify the building of an MRS if: there were no linkages between the MRS and the repository; the MRS could be constructed at an early date; and the opening of the repository were delayed considerably beyond its presently scheduled date of operation. The Commission therefore recommends that the Congress take the following actions: Authorize construction of a Federal Emergency Storage facility with a capacity limit of 2,000 metric tons of uranium; Authorize construction of a User-Funded Interim Storage facility with a capacity limit of 5,000 metric tons of uranium; Reconsider the subject of interim storage by the year 2000

  15. The long term storage of radioactive waste: Safety and sustainability. A position paper of international experts

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-06-01

    The purpose of the report is to reflect the currently prevailing views among experts in the field of radioactive waste storage and disposal. It is intended for use as a central and authoritative reference point for national discussions and policy papers. It is therefore potentially useful to national committees and bodies concerned with the management of radioactive waste. It may also be of value to concerned members of the public since it is written in language that should be comprehensible to the informed lay person. It was produced as a result of several meetings of experts in the first part of 2002. Since then, it has been reviewed by the international Waste Safety Standards Committee (WASSC), by the WASSC Subgroup on Principles and Criteria for the Disposal of Radioactive Waste at its meeting in October 2000 and by a technical committee convened specifically to review the paper at a meeting held in November 2002. Finally, the essential conclusions of the paper were presented to and discussed with participants to the International Conference on Issues and Trends in Radioactive Waste Management, held in Vienna in December 2002.

  16. The long term storage of radioactive waste: Safety and sustainability. A position paper of international experts

    International Nuclear Information System (INIS)

    2003-06-01

    The purpose of the report is to reflect the currently prevailing views among experts in the field of radioactive waste storage and disposal. It is intended for use as a central and authoritative reference point for national discussions and policy papers. It is therefore potentially useful to national committees and bodies concerned with the management of radioactive waste. It may also be of value to concerned members of the public since it is written in language that should be comprehensible to the informed lay person. It was produced as a result of several meetings of experts in the first part of 2002. Since then, it has been reviewed by the international Waste Safety Standards Committee (WASSC), by the WASSC Subgroup on Principles and Criteria for the Disposal of Radioactive Waste at its meeting in October 2000 and by a technical committee convened specifically to review the paper at a meeting held in November 2002. Finally, the essential conclusions of the paper were presented to and discussed with participants to the International Conference on Issues and Trends in Radioactive Waste Management, held in Vienna in December 2002

  17. Non-stationarity driven by long-term change in catchment storage: possibilities and implications

    Directory of Open Access Journals (Sweden)

    J. D. Hughes

    2015-06-01

    Full Text Available "Non-stationarity" with reference to hydrology is a term applied to many situations (Milly et al., 2008. While climate change non-stationarity is often examined, these effects can provide a test for assumptions of runoff generation process impliedin rainfall–runoff (RR models. Observations from South-western Australia (SWA over the past 40 years show a decline in rainfall and reductions in runoff. Runoff and rainfall relationships in SWA show a significant shift over the past 40 years suggesting a change in runoff generation and catchment state. This has challenged the nature of assumed runoff generation process in SWA as well as the veracity of conceptual RR model structure. We expand on some of the lessons learned from SWA and discuss the climatic and geomorphic conditions that may make reasonable predictions of runoff very difficult with RR models calibrated in traditional ways. Catchment storage has a significant interaction with runoff generation and we examine the situations where these may change in the longer term. We suggest some strategies in terms of model structure and calibration that may improve predictive performance in such situations.

  18. Modernization and refurbishment of the Central Interim Storage

    International Nuclear Information System (INIS)

    Mele, I.; Zeleznik, N.

    2002-01-01

    The Central Interim Storage for radioactive waste in Brinje, being put into operation in 1986, needs refurbishment and modernization in order to meet the up-to-date operational and safety requirements and to ensure the normal and undisturbed acceptance of radioactive waste from small producers in the future. Because of the waste, being already stored in the storage, the lack of reprocessing capacities and the lack of auxiliary room, the refurbishment and modernization is a complex problem, which needs to be addressed with care. The plan of refurbishment and modernization requires an integral approach, covering all different aspects of renewal and reconstruction. The implementation plan, however, must be based on the actual state of the storage and real conditions for the implementations: from technical to financial. In this paper the project for refurbishment and modernization of the storage, and some activities that have already been implemented, are presented.(author)

  19. Changes in chemical quality indices during long-term storage of palm-olein oil under heated storage and transport-type conditions

    CSIR Research Space (South Africa)

    Van der Merwe, GH

    2004-01-15

    Full Text Available of Food and Agriculture J Sci Food Agric 84:52?58 (online: 2003) DOI: 10.1002/jsfa.1609 Changes in chemical quality indices during long-term storage of palm-olein oil under heated storage and transport-type conditions Gretel H van der Merwe,1asteriskmath... Lourens M du Plessis1 and John RN Taylor2 1CSIR Bio/Chemtek, PO Box 395, Pretoria 0001, South Africa 2Department of Food Science, University of Pretoria, Pretoria 0002, South Africa Abstract: Six quality indices, namely free fatty acids (FFA), peroxide...

  20. Radiolysis of Salts and Long-Term Storage Issues for Both Pure and Impure PuO{sub 2} Materials in Plutonium Storage Containers

    Energy Technology Data Exchange (ETDEWEB)

    Lav Tandon

    2000-05-01

    The Material Identification and Surveillance (MIS) project sponsored a literature search on the effects of radiation on salts, with focus on alkali chlorides. The goal of the survey was to provide a basis for estimating the magnitude of {alpha} radiation effects on alkali chlorides that can accompany plutonium oxide (PuO{sub 2}) into storage. Chloride radiolysis can yield potentially corrosive gases in plutonium storage containers that can adversely affect long-term stability. This literature search was primarily done to provide a tutorial on this topic, especially for personnel with nonradiation chemistry backgrounds.

  1. Long-Term Fungal Inhibition by Pisum sativum Flour Hydrolysate during Storage of Wheat Flour Bread

    Science.gov (United States)

    Lavecchia, Anna; Gramaglia, Valerio; Gobbetti, Marco

    2015-01-01

    In order to identify antifungal compounds from natural sources to be used as ingredients in the bakery industry, water/salt-soluble extracts (WSE) from different legume flour hydrolysates obtained by the use of a fungal protease were assayed against Penicillium roqueforti DPPMAF1. The agar diffusion assays allowed the selection of the pea (Pisum sativum) hydrolysate as the most active. As shown by the hyphal radial growth rate, the WSE had inhibitory activity towards several fungi isolated from bakeries. The MIC of the WSE was 9.0 mg/ml. Fungal inhibition was slightly affected by heating and variations in pH. The antifungal activity was attributed to three native proteins (pea defensins 1 and 2 and a nonspecific lipid transfer protein [nsLTP]) and a mixture of peptides released during hydrolysis. The three proteins have been reported previously as components of the defense system of the plant. Five peptides were purified from WSE and were identified as sequences encrypted in leginsulin A, vicilin, provicilin, and the nsLTP. To confirm antifungal activity, the peptides were chemically synthesized and tested. Freeze-dried WSE were used as ingredients in leavened baked goods. In particular, breads made by the addition of 1.6% (wt/wt) of the extract and fermented by baker's yeast or sourdough were characterized for their main chemical, structural, and sensory features, packed in polyethylene bags, stored at room temperature, and compared to controls prepared without pea hydrolysate. Artificially inoculated slices of a bread containing the WSE did not show contamination by fungi until at least 21 days of storage and behaved like the bread prepared with calcium propionate (0.3%, wt/wt). PMID:25862230

  2. Integrity of the Human Faecal Microbiota following Long-Term Sample Storage.

    Directory of Open Access Journals (Sweden)

    Elahe Kia

    Full Text Available In studies of the human microbiome, faecal samples are frequently used as a non-invasive proxy for the study of the intestinal microbiota. To obtain reliable insights, the need for bacterial DNA of high quality and integrity following appropriate faecal sample collection and preservation steps is paramount. In a study of dietary mineral balance in the context of type 2 diabetes (T2D, faecal samples were collected from healthy and T2D individuals throughout a 13-day residential trial. These samples were freeze-dried, then stored mostly at -20°C from the trial date in 2000/2001 until the current research in 2014. Given the relative antiquity of these samples (~14 years, we sought to evaluate DNA quality and comparability to freshly collected human faecal samples. Following the extraction of bacterial DNA, gel electrophoresis indicated that our DNA extracts were more sheared than extracts made from freshly collected faecal samples, but still of sufficiently high molecular weight to support amplicon-based studies. Likewise, spectrophotometric assessment of extracts revealed that they were of high quality and quantity. A subset of bacterial 16S rRNA gene amplicons were sequenced using Illumina MiSeq and compared against publicly available sequence data representing a similar cohort analysed by the American Gut Project (AGP. Notably, our bacterial community profiles were highly consistent with those from the AGP data. Our results suggest that when faecal specimens are stored appropriately, the microbial profiles are preserved and robust to extended storage periods.

  3. Drought-induced recharge promotes long-term storage of porewater salinity beneath a prairie wetland

    Science.gov (United States)

    Levy, Zeno F.; Rosenberry, Donald O.; Moucha, Robert; Mushet, David M.; Goldhaber, Martin B.; LaBaugh, James W.; Fiorentino, Anthony J.; Siegel, Donald I.

    2018-02-01

    Subsurface storage of sulfate salts allows closed-basin wetlands in the semiarid Prairie Pothole Region (PPR) of North America to maintain moderate surface water salinity (total dissolved solids [TDS] from 1 to 10 g L-1), which provides critical habitat for communities of aquatic biota. However, it is unclear how the salinity of wetland ponds will respond to a recent shift in mid-continental climate to wetter conditions. To understand better the mechanisms that control surface-subsurface salinity exchanges during regional dry-wet climate cycles, we made a detailed geoelectrical study of a closed-basin prairie wetland (P1 in the Cottonwood Lake Study Area, North Dakota) that is currently experiencing record wet conditions. We found saline lenses of sulfate-rich porewater (TDS > 10 g L-1) contained in fine-grained wetland sediments 2-4 m beneath the bathymetric low of the wetland and within the currently ponded area along the shoreline of a prior pond stand (c. 1983). During the most recent drought (1988-1993), the wetland switched from a groundwater discharge to recharge function, allowing salts dissolved in surface runoff to move into wetland sediments beneath the bathymetric low of the basin. However, groundwater levels during this time did not decline to the elevation of the saline lenses, suggesting these features formed during more extended paleo-droughts and are stable in the subsurface on at least centennial timescales. We hypothesize a "drought-induced recharge" mechanism that allows wetland ponds to maintain moderate salinity under semiarid climate. Discharge of drought-derived saline groundwater has the potential to increase the salinity of wetland ponds during wet climate.

  4. Structural Changes in the Surface of Red Blood Cell Membranes during Long-Term Donor Blood Storage

    Directory of Open Access Journals (Sweden)

    V. V. Moroz

    2012-01-01

    Full Text Available Objective: to study changes in the surface of red blood cell membranes of donor blood at the macro- and ultrastructural level during its storage for 30 days and to evaluate the functional state of the red blood cell membrane during the whole storage period. Material and methods. The investigation was conducted on human whole blood and packed red blood cells placed in the specialized packs containing the preservative CPDA-1, by using calibrated electroporation and atomic force microscopy and measuring plasma pH. Conclusion. The long-term, up to 30-day, storage of whole blood and packed red blood cells at 4°C was attended by lower plasma pH and increased hemolysis rate constant during calibrated electroporation and by the development of oxidative processes. The hemolysis rate constant was also higher in the packed red blood cells than that in the whole blood. On days 5—6, the membrane structure showed defects that developed, as the blood was stored, and caused irreversible cell membrane damage by day 30. Key words: donor blood, red blood cell membranes, atomic force microscopy.

  5. Long-term evolution of radio-active waste storage in geological formations: analogy with the weathering of mineral deposits

    International Nuclear Information System (INIS)

    Cantinolle, P.; Griffault, L.; Jebrak, M.

    1986-01-01

    The aim of this study was to select examples of mineral deposits and their weathering environment, showing the long-term behaviour, in geological time, measuring (area, volume) some constituent elements of radio-active waste storage subject to the hazards of hydrogeochemical weathering. Initially, a feasibility study was made to collate data available within the BRGM (mining group and public service) and from literature dealing with weathering of deposits. It was thus discovered that the analogy between radio-active waste storage and mineral deposits could be approached in two different yet complementary ways: - one approach is to observe the behaviour of a mineral deposit in relation to the country rocks. For this a bibliographic metallogenic study was made. The other approach is to observe the behaviour of chemical elements during deposition of a mineral deposit whose genesis is similar to the spatial and thermal environment of a deposit of radio-active waste in a geological formation. For this two sites were selected corresponding to hydrothermal systems showing strong analogies to those expected in the neighbourhood of the storage sites. These two sites, Langenberg in the Vosges and La Telhaie in Brittany, were the subject of complementary analytical work [fr

  6. Analysis of long-term impacts of TRU waste remaining at generator/storage sites for No Action Alternative 2

    International Nuclear Information System (INIS)

    Buck, J.W.; Bagaasen, L.M.; Bergeron, M.P.; Streile, G.P.

    1997-09-01

    This report is a supplement to the Waste Isolation Pilot Plant Disposal-Phase Final Supplemental Environmental Impact Statement (SEIS-II). Described herein are the underlying information, data, and assumptions used to estimate the long-term human-health impacts from exposure to radionuclides and hazardous chemicals in transuranic (TRU) waste remaining at major generator/storage sites after loss of institutional control under No Action Alternative 2. Under No Action Alternative 2, TRU wastes would not be emplaced at the Waste Isolation Pilot Plant (WIPP) but would remain at generator/storage sites in surface or near-surface storage. Waste generated at smaller sites would be consolidated at the major generator/storage sites. Current TRU waste management practices would continue, but newly generated waste would be treated to meet the WIPP waste acceptance criteria. For this alternative, institutional control was assumed to be lost 100 years after the end of the waste generation period, with exposure to radionuclides and hazardous chemicals in the TRU waste possible from direct intrusion and release to the surrounding environment. The potential human-health impacts from exposure to radionuclides and hazardous chemicals in TRU waste were analyzed for two different types of scenarios. Both analyses estimated site-specific, human-health impacts at seven major generator/storage sites: the Hanford Site (Hanford), Idaho National Engineering and Environmental Laboratory (INEEL), Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Rocky Flats Environmental Technology Site (RFETS), and Savannah River Site (SRS). The analysis focused on these seven sites because 99 % of the estimated TRU waste volume and inventory would remain there under the assumptions of No Action Alternative 2

  7. Immobilized high-level waste interim storage alternatives generation and analysis and decision report

    International Nuclear Information System (INIS)

    CALMUS, R.B.

    1999-01-01

    This report presents a study of alternative system architectures to provide onsite interim storage for the immobilized high-level waste produced by the Tank Waste Remediation System (TWRS) privatization vendor. It examines the contract and program changes that have occurred and evaluates their impacts on the baseline immobilized high-level waste (IHLW) interim storage strategy. In addition, this report documents the recommended initial interim storage architecture and implementation path forward

  8. Tolerance of Ruppia sinensis Seeds to Desiccation, Low Temperature, and High Salinity With Special Reference to Long-Term Seed Storage.

    Science.gov (United States)

    Gu, Ruiting; Zhou, Yi; Song, Xiaoyue; Xu, Shaochun; Zhang, Xiaomei; Lin, Haiying; Xu, Shuai; Yue, Shidong; Zhu, Shuyu

    2018-01-01

    Seeds are important materials for the restoration of globally-threatened marine angiosperm (seagrass) populations. In this study, we investigated the differences between different Ruppia sinensis seed types and developed two feasible long-term R. sinensis seed storage methods. The ability of R. sinensis seeds to tolerate the short-term desiccation and extreme cold had been investigated. The tolerance of R. sinensis seeds to long-term exposure of high salinity, cold temperature, and desiccation had been considered as potential methods for long-term seed storage. Also, three morphological and nine physiological indices were measured and compared between two types of seeds: Shape L and Shape S. We found that: (1) wet storage at a salinity of 30-40 psu and 0°C were the optimal long-term storage conditions, and the proportion of viable seeds reached over 90% after a storage period of 11 months since the seeds were collected from the reproductive shoots; (2) dry condition was not the optimal choice for long-term storage of R. sinensis seeds; however, storing seeds in a dry condition at 5°C and 33 ± 10% relative humidity for 9 months had a relatively high percentage (74.44 ± 2.22%) of viable seeds, consequently desiccation exposure could also be an acceptable seed storage method; (3) R. sinensis seeds would lose vigor in the interaction of extreme cold (-27°C) and desiccation; (4) there were significant differences in seed weight, seed curvature, and endocarp thickness between the two types of seeds. These findings provided fundamental physiological information for R. sinensis seeds and supported the long-term storage of its seeds. Our results may also serve as useful reference for seed storage of other threatened seagrass species and facilitate their ex situ conservation and habitat restoration.

  9. Tolerance of Ruppia sinensis Seeds to Desiccation, Low Temperature, and High Salinity With Special Reference to Long-Term Seed Storage

    Directory of Open Access Journals (Sweden)

    Ruiting Gu

    2018-03-01

    Full Text Available Seeds are important materials for the restoration of globally-threatened marine angiosperm (seagrass populations. In this study, we investigated the differences between different Ruppia sinensis seed types and developed two feasible long-term R. sinensis seed storage methods. The ability of R. sinensis seeds to tolerate the short-term desiccation and extreme cold had been investigated. The tolerance of R. sinensis seeds to long-term exposure of high salinity, cold temperature, and desiccation had been considered as potential methods for long-term seed storage. Also, three morphological and nine physiological indices were measured and compared between two types of seeds: Shape L and Shape S. We found that: (1 wet storage at a salinity of 30–40 psu and 0°C were the optimal long-term storage conditions, and the proportion of viable seeds reached over 90% after a storage period of 11 months since the seeds were collected from the reproductive shoots; (2 dry condition was not the optimal choice for long-term storage of R. sinensis seeds; however, storing seeds in a dry condition at 5°C and 33 ± 10% relative humidity for 9 months had a relatively high percentage (74.44 ± 2.22% of viable seeds, consequently desiccation exposure could also be an acceptable seed storage method; (3 R. sinensis seeds would lose vigor in the interaction of extreme cold (-27°C and desiccation; (4 there were significant differences in seed weight, seed curvature, and endocarp thickness between the two types of seeds. These findings provided fundamental physiological information for R. sinensis seeds and supported the long-term storage of its seeds. Our results may also serve as useful reference for seed storage of other threatened seagrass species and facilitate their ex situ conservation and habitat restoration.

  10. Management and storage of spent fuel from CEA research reactors

    International Nuclear Information System (INIS)

    Merchie, F.

    1996-01-01

    CEA research reactors and their interim spent fuel storage facilities are described. Long-term solutions for spent fuel storage problems, involving wet storage at PEGASE or dry storage at CASCAD, are outlined in some detail. (author)

  11. Sorption heat storage for long-term low-temperature applications: A review on the advancements at material and prototype scale

    NARCIS (Netherlands)

    Scapino, L.; Zondag, H.A.; Van Bael, J.; Diriken, J.; Rindt, C.C.M.

    2017-01-01

    Sorption heat storage has the potential to store large amounts of thermal energy from renewables and other distributed energy sources. This article provides an overview on the recent advancements on long-term sorption heat storage at material- and prototype- scales. The focus is on applications

  12. Desorption behaviour of polycyclic aromatic hydrocarbons after long-term storage of two harbour sludges from the port of Rotterdam, The Netherlands

    KAUST Repository

    Heister, Katja; Pols, Sabine; Loch, J. P. Gustav; Bosma, Tom N. P.

    2013-01-01

    storage time of 14 years at 4 °C under anaerobic conditions in the dark, mimicking depository conditions. Such long-term storage is believed to effect the desorption of the PAHs. Materials and methods: Batch desorption experiments over a time period of 130

  13. Centralized interim storage facility for radioactive wastes at Wuerenlingen (ZWILAG)

    International Nuclear Information System (INIS)

    Lutz, H.R.; Schnetzler, U.

    1994-01-01

    Radioactive waste management in Switzerland is the responsibility of the waste producers; in this respect, the law requires permanent, safe management of the wastes by means of final disposal. Nagra is responsible for the research and development work associated with final disposal. Processing of the wastes into a form suitable for disposal, as well as interim storage, remain the responsibility of the waste producers. In order to supplement the existing conditioning and storage facilities at the nuclear power plants and to replace the outdated waste treatment plant at the Paul Scherrer Institute (PSI) at Wuerenlingen, the operators of the Swiss nuclear power plants are planning a joint treatment and storage facility at the PSI-East site. The organisation ''Zwischenlager Wuerenlingen AG'', which was set up at the beginning of 1990, has been entrusted with this task. (author) 4 figs

  14. Evaluation of the Universal Viral Transport system for long-term storage of virus specimens for microbial forensics.

    Science.gov (United States)

    Hosokawa-Muto, Junji; Fujinami, Yoshihito; Mizuno, Natsuko

    2015-08-01

    Forensic microbial specimens, including bacteria and viruses, are collected at biocrime and bioterrorism scenes. Although it is preferable that the pathogens in these samples are alive and kept in a steady state, the samples may be stored for prolonged periods before analysis. Therefore, it is important to understand the effects of storage conditions on the pathogens contained within such samples. To evaluate the capacity to preserve viable virus and the viral genome, influenza virus was added to the transport medium of the Universal Viral Transport system and stored for over 3 months at various temperatures, after which virus titrations and quantitative analysis of the influenza hemagglutinin gene were performed. Although viable viruses became undetectable 29 days after the medium was stored at room temperature, viruses in the medium stored at 4°C were viable even after 99 days. A quantitative PCR analysis indicated that the hemagglutinin gene was maintained for 99 days at both 4°C and room temperature. Therefore, long-term storage at 4°C has little effect on viable virus and viral genes, so the Universal Viral Transport system can be useful for microbial forensics. This study provides important information for the handling of forensic virus specimens. Copyright © 2015 Elsevier Ltd and Faculty of Forensic and Legal Medicine. All rights reserved.

  15. R and D applied to the non-destructive characterization of waste packages for long term storage or deep disposal

    Energy Technology Data Exchange (ETDEWEB)

    Malvache, P.; Perot, B.; Ma, J.L.; Pettier, J.L. [CEA Cadarache, Dept. d' Etudes des Dechets, DED, 13 - Saint Paul lez Durance (France); Capdevila, J.M.; Huot, N. [CEA Saclay, Dir. du Developpement et de l' Innovation Nucleares DDIN, 91 - Gif Sur Yvette (France); Moulin, V. [CEA Grenoble, Lab. d' Electronique, de Technologie de l' Information LETI, DSYS, 38 (France)

    2001-07-01

    To ensure the quality and traceability of waste package management in the long term, knowledge on these packages is necessary so as to confirm their compliance to storage or disposal specifications. Research is focused on the management of the knowledge on these packages (fabrication means, materials contained,...) and on the acquisition, through measurement, of their characteristics. Within this context, many studies are underway at the CEA in the field of measurements so as to obtain non- destructive tools to access the parameters which allow the waste packages to be characterized. The two main R and D investigations concern: the nuclear measurement methods for the detection and quantification of radionuclides and of chemical elements considered as important for storage or disposal safety ; the measurement methods for the physical characteristics of the packages by high energy photon imaging, thus allowing pictures of the contents of large, high density and sometimes irradiating packages to be known. During the last five years, the research at the CEA focused on these two areas and resulted in a significant evolution in the non-destructive characterization means for long lived waste packages. (author)

  16. R and D applied to the non-destructive characterization of waste packages for long term storage or deep disposal

    International Nuclear Information System (INIS)

    Malvache, P.; Perot, B.; Ma, J.L.; Pettier, J.L.; Capdevila, J.M.; Huot, N.; Moulin, V.

    2001-01-01

    To ensure the quality and traceability of waste package management in the long term, knowledge on these packages is necessary so as to confirm their compliance to storage or disposal specifications. Research is focused on the management of the knowledge on these packages (fabrication means, materials contained,...) and on the acquisition, through measurement, of their characteristics. Within this context, many studies are underway at the CEA in the field of measurements so as to obtain non- destructive tools to access the parameters which allow the waste packages to be characterized. The two main R and D investigations concern: the nuclear measurement methods for the detection and quantification of radionuclides and of chemical elements considered as important for storage or disposal safety ; the measurement methods for the physical characteristics of the packages by high energy photon imaging, thus allowing pictures of the contents of large, high density and sometimes irradiating packages to be known. During the last five years, the research at the CEA focused on these two areas and resulted in a significant evolution in the non-destructive characterization means for long lived waste packages. (author)

  17. Cost estimation of interim dry storage for Atucha I NPP

    International Nuclear Information System (INIS)

    Bergallo, Juan E.; Fuenzalida Troyano, Carlos S.

    2007-01-01

    A joint effort between NASA and CNEA has been performed in order to evaluate and fix the strategy of interim spent fuel storage for Atucha I nuclear power plant. In this work the cost estimation on the proposed system was performed in order to fix the parameter and design criteria for the next engineering step. The main results achieved show that both alternatives are all in the same range of costs per unit of mass to be stored, the impact on electricity cost is less than 1 US mills/KWh and the scaling factor achieved is 0.85. (author) [es

  18. 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

  19. RADIATION SAFETY JUSTIFICATION FOR THE LONG-TERM STORAGE OF GAS CONDENSATE IN THE UNDERGROUND RESERVOURS FORMED BY THE NUCLEAR EXPLOSION TECHNOLOGY

    Directory of Open Access Journals (Sweden)

    I. K. Romanovich

    2010-01-01

    Full Text Available The paper presents approaches to the safety justification of the gas condensate and brine long-term storage in the underground reservoirs formed by the nuclear explosion technology. Gas condensate and brine are the intermediate level liquid radioactive waste containing isotopes: 3Н, 137Cs and 90Sr, in traces - 239Pu, 235U, 241Am.Safety of the gas condensate and brine long-term storage in the underground reservoirs is assessed on the base of the multi-barrier principle implementation, used during radioactive waste disposal. It is shown that the gas condensate and brine long-term storage in the sealed underground reservoirs formed by nuclear explosion technologies in salt domes does not lead to the surface radioactive contamination and population exposure.

  20. Glass packages in interim storage; Les verres dans les stockages

    Energy Technology Data Exchange (ETDEWEB)

    Jacquet-Francillon, N

    1994-10-01

    This report summarize the current state of knowledge concerning the behavior of type C waste packages consisting of vitrified high-level solutions produced by reprocessing spent fuel. The composition and the physical and chemical properties of the feed solutions are reviewed, and the vitrification process is described. Sodium alumino-borosilicate glass compositions are generally employed - the glass used at la Hague for LWR fuel solutions, for example, contains 45 % SiO{sub 2}. The major physical, chemical, mechanical and thermal properties of the glass are reviewed. In order to allow their thermal power to diminish, the 3630 glass packages produced (as of January 1993) in the vitrification facilities at Marcoule and La Hague are placed in interim storage for several decades. The actual interim storage period has not been defined, as it is closely related to the concept and organization selected for the final destination of the packages: a geological repository. The glass behavior under irradiation is described. Considerable basic and applied research has been conducted to assess the aqueous leaching behavior of nuclear containment glass. The effects of various repository parameters (temperature, flow rate, nature of the environmental materials) have been investigated. The experimental findings have been used to specify a model describing the kinetics of aqueous corrosion of the glass. More generally all the ``source term`` models developed in France by the CEA or by ANDRA are summarized. (author). 152 refs., 33 figs.

  1. Using optimization to improve radioactive waste interim storage

    International Nuclear Information System (INIS)

    Dellamano, J.C.; Sordi, G.M.

    2006-01-01

    In several countries where repository for final disposal is not constructed and in operation, the low level radioactive wastes are treated and stored. In some cases, interim storage can be extended for decades demanding special attention regarding security aspects. On the other hand, some packages contains very small quantities of radioactive material either by the long period of storage or by the rudimental segregation carried out when the radioactive waste were collected. This paper discuss the use of cost-benefit analysis as technique to aid decision making in order to evaluate the feasibility of to open the packages containing compactable solid radioactive wastes and to segregate these waste according to the classification that consider the recent clearance levels and exemption limits recommended by international organisms. (authors)

  2. SNF Interim Storage Canister Corrosion and Surface Environment Investigations

    International Nuclear Information System (INIS)

    Bryan, Charles R.; Enos, David G.

    2015-01-01

    This progress report describes work being done at Sandia National Laboratories (SNL) to assess the localized corrosion performance of container/cask materials used in the interim storage of spent nuclear fuel (SNF). Of particular concern is stress corrosion cracking (SCC), by which a through-wall crack could potentially form in a canister outer wall over time intervals that are shorter than possible dry storage times. In order for SCC to occur, three criteria must be met. A corrosive environment must be present on the canister surface, the metal must susceptible to SCC, and sufficient tensile stress to support SCC must be present through the entire thickness of the canister wall. SNL is currently evaluating the potential for each of these criteria to be met.

  3. SNF Interim Storage Canister Corrosion and Surface Environment Investigations

    Energy Technology Data Exchange (ETDEWEB)

    Bryan, Charles R. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Enos, David G. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

    2015-09-01

    This progress report describes work being done at Sandia National Laboratories (SNL) to assess the localized corrosion performance of container/cask materials used in the interim storage of spent nuclear fuel (SNF). Of particular concern is stress corrosion cracking (SCC), by which a through-wall crack could potentially form in a canister outer wall over time intervals that are shorter than possible dry storage times. In order for SCC to occur, three criteria must be met. A corrosive environment must be present on the canister surface, the metal must susceptible to SCC, and sufficient tensile stress to support SCC must be present through the entire thickness of the canister wall. SNL is currently evaluating the potential for each of these criteria to be met.

  4. Sacramento Municipal Utility district's interim onsite storage building for low level radioactive waste

    International Nuclear Information System (INIS)

    Gillis, E.

    1986-01-01

    In order to meet current and anticipated needs for the low level radwaste management program at the Rancho Seco Nuclear Generating Station, the Sacramento Municipal Utility District has a design and construction program underway which will provide an onsite interim storage facility that can be expanded in two and one-half year increments. The design approach utilized allows capital investment to be minimized and still provides radwaste management flexibility in anticipation of delays in resolution of the nationwide long term radwaste disposal situation. The facility provides storage and material accountability for all low level radwastes generated by the plant. Wastes are segregated by radioactivity level and are stored in two separate storage areas located within one facility. Lower activity wastes are stored in a lightly shielded structure and handled by lift trucks, while the higher activity wastes are stored in a highly shielded structure and handled remotely by manual bridge crane. The layout of the structure provides for economy of operation and minimizes personnel radiation exposure. Design philosophy and criteria, building layout and systems, estimated costs and construction schedule are discussed

  5. Engineering study: disposition of terminal liquors for interim storage

    International Nuclear Information System (INIS)

    Metz, W.P.; Ogren, W.E.

    1975-02-01

    Eight alternative processes were chosen as being technologically feasible within the time frame dictated by budgeting procedures and terminal liquor availability. Solidified waste products acceptable for single-shell tank storage were assumed to be placed in available single-shell tanks. Double-shell tanks were used only for the more mobile terminal liquors or semi-solid mush products. The mush, chemical neutralization, and clay in-tank processes offer potential savings of tens of millions of dollars over double-shell tank storage of terminal liquors. In order to achieve this cost savings, the process development and demonstration must be completed prior to the beginning of double-shell tank construction (Dec. 1976) expected to be funded from a fiscal year 1977 line item. Budgeting for these additional double-shell tanks must proceed since the processing options discussed here are not yet available and may not prove to be available at the required time. This study indicates the following topics for additional study: Process technology development to achieve interim storage of terminal liquor products receives the greatest emphasis as a means of reducing capital expenditures. Interim storage product criteria, waste inventory, and conversion to final form require definition to allow comparison of the alternatives for disposition of terminal liquors. The pseudotechnical nature of product acceptability criteria is important to the evaluation of the partial neutralization and aluminum removal alternatives. More accurate estimates of terminal liquor quantity and composition are required to give a sound technical basis for choosing the appropriate processing alternative. Retrieval and reprocessing operations may affect the comparisons presented by this study

  6. Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

    International Nuclear Information System (INIS)

    Burgard, K.C.

    1998-01-01

    The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis

  7. Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

    Energy Technology Data Exchange (ETDEWEB)

    Burgard, K.C.

    1998-04-09

    The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

  8. Chemical and proteolysis-derived changes during long-term storage of lactose-hydrolyzed ultrahigh-temperature (UHT) milk.

    Science.gov (United States)

    Jansson, Therese; Jensen, Hanne B; Sundekilde, Ulrik K; Clausen, Morten R; Eggers, Nina; Larsen, Lotte B; Ray, Colin; Andersen, Henrik J; Bertram, Hanne C

    2014-11-19

    Proteolytic activity in milk may release bitter-tasting peptides and generate free amino terminals that react with carbohydrates, which initiate Maillard reaction. Ultrahigh temperature (UHT) heat treatment inactivates the majority of proteolytic enzymes in milk. In lactose-hydrolyzed milk a β-galactosidase preparation is applied to the milk after heat treatment, which has proteolytic side activities that may induce quality deterioration of long-term-stored milk. In the present study proteolysis, glycation, and volatile compound formation were investigated in conventional (100% lactose), filtered (60% lactose), and lactose-hydrolyzed (<1% lactose) UHT milk using reverse phase high-pressure liquid chromatography-mass spectrometry, proton nuclear magnetic resonance, and gas chromatography-mass spectrometry. Proteolysis was observed in all milk types. However, the degree of proteolysis was significantly higher in the lactose-hydrolyzed milk compared to the conventional and filtered milk. The proteins most prone to proteolysis were β-CN and αs1-CN, which were clearly hydrolyzed after approximately 90 days of storage in the lactose-hydrolyzed milk.

  9. Safety aspects of spent nuclear fuel interim storage installations

    Energy Technology Data Exchange (ETDEWEB)

    Romanato, Luiz Sergio [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), Sao Paulo, SP (Brazil). Dept. da Qualidade. Div. de Sistemas da Qualidade]. E-mail: romanato@ctmsp.mar.mil.br; Rzyski, Barbara Maria [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil). Div. de Ensino]. E-mail: bmrzyski@ipen.br

    2007-07-01

    Nowadays safety and security of spent nuclear fuel (SNF) interim storage installations are very important, due to a great concentration of fission products, actinides and activation products. In this kind of storage it is necessary to consider the physical security. Nuclear installations have become more vulnerable. New types of accidents must be considered in the design of these installations, which in the early days were not considered like: fissile material stolen, terrorists' acts and war conflicts, and traditional accidents concerning the transport of the spent fuel from the reactor to the storage location, earthquakes occurrence, airplanes crash, etc. Studies related to airplane falling had showed that a collision of big commercials airplanes at velocity of 800 km/h against SNF storage and specially designed concrete casks, do not result in serious structural injury to the casks, and not even radionuclides liberation to the environment. However, it was demonstrated that attacks with modern military ammunitions, against metallic casks, are calamitous. The casks could not support a direct impact of this ammo and the released radioactive materials can expose the workers and public as well the local environment to harmful radiation. This paper deals about the main basic aspects of a dry SNF storage installation, that must be physically well protected, getting barriers that difficult the access of unauthorized persons or vehicles, as well as, must structurally resist to incidents or accidents caused by unauthorized intrusion. (author)

  10. Safety aspects of spent nuclear fuel interim storage installations

    International Nuclear Information System (INIS)

    Romanato, Luiz Sergio

    2007-01-01

    Nowadays safety and security of spent nuclear fuel (SNF) interim storage installations are very important, due to a great concentration of fission products, actinides and activation products. In this kind of storage it is necessary to consider the physical security. Nuclear installations have become more vulnerable. New types of accidents must be considered in the design of these installations, which in the early days were not considered like: fissile material stolen, terrorists' acts and war conflicts, and traditional accidents concerning the transport of the spent fuel from the reactor to the storage location, earthquakes occurrence, airplanes crash, etc. Studies related to airplane falling had showed that a collision of big commercials airplanes at velocity of 800 km/h against SNF storage and specially designed concrete casks, do not result in serious structural injury to the casks, and not even radionuclides liberation to the environment. However, it was demonstrated that attacks with modern military ammunitions, against metallic casks, are calamitous. The casks could not support a direct impact of this ammo and the released radioactive materials can expose the workers and public as well the local environment to harmful radiation. This paper deals about the main basic aspects of a dry SNF storage installation, that must be physically well protected, getting barriers that difficult the access of unauthorized persons or vehicles, as well as, must structurally resist to incidents or accidents caused by unauthorized intrusion. (author)

  11. Numerical modelling of the long term mechanical behaviour of a storage cell for high level nuclear wastes

    International Nuclear Information System (INIS)

    Bian, H.B.; Jia, Y.; Duveau, G.; Shao, J.F.; Poutrel, A.

    2010-01-01

    the various important processes in the storage structures, the coupling between the corrosion/strain processes and the Callovo-Oxfordian clay formation is death with in this study. The principal objective is to establish a numerical method capable to reproduce correctly the evolutionary interface between the metallic container and clay formation taking into account the decrease of mechanical resistance and the generated supplementary volume. Special attention is paid on the evolution of the interface of steel and rock, the amplitude of possible overpressure and stress and the evolution of the EDZ (Excavation Damaged Zone). In the numerical analyses, different materials are taken into account: limestone, argillite, steel and air. Firstly, a brief presentation of the constitutive models for the Callovo-Oxfordian clay is given. For the sake of simplicity, a poro-elastic model is used for limestone and an elasto-plasticity model using a Mises type criterion is applied to the steel. Then a series of parametric studies is performed in order to study the mechanical resistance of corroded steel.. Finally, a storage cell of High-Level Wastes is simulated. In the numerical model, the wastes cell is taken as a circular borehole. The loading path is composed of the following three steps: the excavation phase, the waiting phase for the installation of waste package, and the evolution phase after the backfilling of the storage cell. The proposed model is able to describe the main features of poro-mechanical behaviour for the clay formation: such as plastic deformation, material damage by microcracks, transition of volumetric compressibility/dilatancy and the viscoplastic strain. In spite of the simplifications used, the numerical results allow us to obtain some quantitative results describing the mechanical behaviour and the coupled thermo-hydro-mechanical processes for a short and long-term in the storage cell. (authors)

  12. Modelling the long-term isolation performance of natural and engineered geologic CO{sub 2} storage sites

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, J.W.; Nitao, J.J.; Morris, J.P. [California Univ., Livermore, CA (United States). Lawrence Livermore National Laboratory

    2005-07-01

    Caprock integrity is an important constraint on the long-term performance of natural and engineered carbon dioxide (CO{sub 2}) sequestration sites. Influxes of CO{sub 2} can lead to concomitant geochemical alteration and geomechanical deformation of the caprock and degrade seal integrity. In this study, reactive transport modelling was used to assess the evolution of caprock permeability. The model was based on mathematical models of the coupled physical and chemical processes catalyzed by an influx event, along with supporting geochemical databases and a distinct-element geomechanical model. Geomechanical contribution was evaluated within a full system analysis of coupled hydrological and geochemical processes for Sleipner-like settings, and then analyzed as a function of hydrological processes, key reservoir properties, and CO{sub 2} influx parameters. The net effect of the geomechanical and geomechanical contributions on caprock integrity was then evaluated for both natural and engineered storage scenarios. Results of the study showed that CO{sub 2} influx-triggered geochemical and geomechanical processes act in opposition to enhance and degrade hydrodynamic seal capacity through aperture narrowing and widening of microfractures. The extent of geochemical enhancement was independent of the reservoir characteristics that distinguished saline-aquifer from enhanced oil recovery and CO{sub 2} sequestration settings. However, while the extent of geochemical alteration was nearly independent of the filling mode, geomechanical deformation processes were more pronounced in engineered storage scenarios. Results suggested that the secure caprocks of natural CO{sub 2} accumulation settings may be incapable of providing effective seals for engineered injection processes. The pressure increase associated with CO{sub 2} accumulation in any compartmentalized system resulted in the net geomechanical aperture widening of caprock microfractures. It was concluded that the

  13. Coccidian oöcysts as type-specimens: long-term storage in aqueous potassium dichromate solution preserves DNA.

    Science.gov (United States)

    Williams, R B; Thebo, P; Marshall, R N; Marshall, J A

    2010-05-01

    Preservation of the exogenous oöcyst stage of coccidian parasites (phylum Apicomplexa N.D. Levine, 1970) as type-specimens of newly described species has long been problematical. Conventional fixatives have proved unsatisfactory, and compromises such as embedding oöcysts in resin or photographing them are not entirely appropriate for various reasons. As an alternative, chilled potassium dichromate solution (normally used in the laboratory to prevent putrefaction of temporary preparations of live oöcysts) has been tested as a long-term preservative of sporulated oöcysts of Eimeria brunetti P.P. Levine, 1942, E. maxima Tyzzer, 1929, E. mitis Tyzzer, 1929, E. necatrix Johnson, 1930, E. praecox Johnson, 1930 and E. tenella (Railliet & Lucet, 1891) (suborder Eimeriorina Léger, 1911; family Eimeriidae Minchin, 1903). Oöcysts from faeces of chickens Gallus gallus (Linnaeus) were placed in 2.5% w/v aqueous potassium dichromate solution (PDS) and stored in the dark at 4 +/- 2 degrees C. After 23 years in storage, oöcysts of each species were administered orally to chickens and failed to initiate infections, indicating that the oöcysts were dead. Nevertheless, after about 24 years, DNA was still recoverable from the oöcysts, and the original species identifications made by classic parasitological methods were confirmed by polymerase chain reaction assays. Furthermore, after almost 25 years, microscopical examination revealed that the walls and internal structures remained well preserved in 83-98% of the oöcysts of the six species investigated. Hence, PDS is potentially suitable for the long-term preservation of sporulated coccidian oöcysts as type-specimens for taxonomic purposes. The samples used in this study are now in the care of the Natural History Museum, London, UK. It is recommended that they be monitored in like manner, by suitably qualified scientists, at intervals of about 5 years to assess their state of preservation and the recoverability of DNA

  14. Waste Encapsulation and Storage Facility (WESF) Interim Status Closure Plan

    International Nuclear Information System (INIS)

    SIMMONS, F.M.

    2000-01-01

    This document describes the planned activities and performance standards for closing the Waste Encapsulation and Storage Facility (WESF). WESF is located within the 225B Facility in the 200 East Area on the Hanford Facility. Although this document is prepared based on Title 40 Code of Federal Regulations (CFR), Part 265, Subpart G requirements, closure of the storage unit will comply with Washington Administrative Code (WAC) 173-303-610 regulations pursuant to Section 5.3 of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Action Plan (Ecology et al. 1996). Because the intention is to clean close WESF, postclosure activities are not applicable to this interim status closure plan. To clean close the storage unit, it will be demonstrated that dangerous waste has not been left onsite at levels above the closure performance standard for removal and decontamination. If it is determined that clean closure is not possible or environmentally is impracticable, the interim status closure plan will be modified to address required postclosure activities. WESF stores cesium and strontium encapsulated salts. The encapsulated salts are stored in the pool cells or process cells located within 225B Facility. The dangerous waste is contained within a double containment system to preclude spills to the environment. In the unlikely event that a waste spill does occur outside the capsules, operating methods and administrative controls require that waste spills be cleaned up promptly and completely, and a notation made in the operating record. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

  15. Stability of Folate and Vitamin B 12 in Human Serum after Long-Term Storage: A Follow-Up after 13 Years

    NARCIS (Netherlands)

    Jansen, Eugène H. J. M.; Beekhof, Piet K.; Centre for Health Protection, National Institute of Public Health and the Environment, P.O. Box 1, 3720 BA Bilthoven, Netherlands; Centre for Health Protection, National Institute of Public Health and the Environment, P.O. Box 1, 3720 BA Bilthoven, Netherlands

    2018-01-01

    In epidemiological and nutrition research, it is very important to evaluate the stability of biomarkers as function of both storage time and temperature. In this study, the stability of folate and vitamin B 12 in human serum samples has been tested after long-term

  16. Long-term safety and efficacy of AAV gene therapy in the canine model of glycogen storage disease type Ia.

    Science.gov (United States)

    Lee, Young Mok; Conlon, Thomas J; Specht, Andrew; Coleman, Kirsten E; Brown, Laurie M; Estrella, Ana M; Dambska, Monika; Dahlberg, Kathryn R; Weinstein, David A

    2018-05-25

    Viral mediated gene therapy has progressed after overcoming early failures, and gene therapy has now been approved for several conditions in Europe and the USA. Glycogen storage disease (GSD) type Ia, caused by a deficiency of glucose-6-phosphatase-α, has been viewed as an outstanding candidate for gene therapy. This follow-up report describes the long-term outcome for the naturally occurring GSD-Ia dogs treated with rAAV-GPE-hG6PC-mediated gene therapy. A total of seven dogs were treated with rAAV-GPE-hG6PC-mediated gene therapy. The first four dogs were treated at birth, and three dogs were treated between 2 and 6 months of age to assess the efficacy and safety in animals with mature livers. Blood and urine samples, radiographic studies, histological evaluation, and biodistribution were assessed. Gene therapy improved survival in the GSD-Ia dogs. With treatment, the biochemical studies normalized for the duration of the study (up to 7 years). None of the rAAV-GPE-hG6PC-treated dogs had focal hepatic lesions or renal abnormalities. Dogs treated at birth required a second dose of rAAV after 2-4 months; gene therapy after hepatic maturation resulted in improved efficacy after a single dose. rAAV-GPE-hG6PC treatment in GSD-Ia dogs was found to be safe and efficacious. GSD-Ia is an attractive target for human gene therapy since it is a monogenic disorder with limited tissue involvement. Blood glucose and lactate monitoring can be used to assess effectiveness and as a biomarker of success. GSD-Ia can also serve as a model for other hepatic monogenic disorders.

  17. Monosynaptic connections made by the sensory neurons of the gill- and siphon-withdrawal reflex in Aplysia participate in the storage of long-term memory for sensitization

    OpenAIRE

    Frost, William N.; Castellucci, Vincent F.; Hawkins, Robert D.; Kandel, Eric R.

    1985-01-01

    We have found that in the gill- and siphon- withdrawal reflex of Aplysia, the memory for short-term sensitization grades smoothly into long-term memory with increased amounts of sensitization training. One cellular locus for the storage of the memory underlying short-term sensitization is the set of monosynaptic connections between the siphon sensory cells and the gill and siphon motor neurons. We have now also found that these same monosynaptic connections participate in the storage of the m...

  18. Integrated system of safety features for spent fuel interim storage

    International Nuclear Information System (INIS)

    Pantazi, Doina; Stanciu, Marcela; Mateescu, Silvia; Marin, Ion

    1999-01-01

    The design of the spent fuel interim storage facility (SFISF) must meet the applicable safety requirements in order to ensure radiological protection of the personnel, public and environment during all phases of the facility. To elaborate the safety documentation necessary for licensing, we were trying to chose the most appropriate approach related to safety features for SFISF, based on national and international regulations, standards and recommendations, as well as on the experience of other countries with similar facilities and finally, on our own experience in designing other nuclear objectives in Romania. The paper presents the issues that we consider important for the safety evaluation and are developed as a detailed diagram. The diagram contains in a logical succession the following issues: - fundamental principles of radioprotection; - fundamental safety principles of radioactive waste management; - safety objectives of SFISF; - safety criteria for SFISF; - safety requirements for SFISF; - siting criteria for SFISF; - siting requirements for SFISF. (authors)

  19. Fabrication and operational experience with the interim storage cask

    International Nuclear Information System (INIS)

    Scott, P.L.

    1998-01-01

    This paper discusses the fabrication and operational experience of the Interim Storage Cask (ISC). The ISC is a dry storage cask which is used to safely store a Core Component Container (CCC) containing up to seven Fast Flux Test Facility (FFTF) spent fuel assemblies at the US Department of Energy's Hanford Site. Under contract to B and W Hanford Company (BWHC), General Atomics (GA) designed and fabricated thirty ISC casks which BWHC is remotely loading at the FFTF facility. BWHC designed and fabricated the CCCS. As of December 1997, thirty ISCs have been fabricated, of which eighteen have been loaded and moved to a storage site adjacent to the FFTF facility. Fabrication consisted of three sets of casks. The first unit was completed and acceptance tested before any other units were fabricated. After the first unit passed all acceptance tests, nine more units were fabricated in the first production run. Before those nine units were completed, GA began a production run of twenty more units. The paper provides an overview of the cask design and discusses the problems encountered in fabrication, their resolution, and changes made in the fabrication processes to improve the quality of the casks. The paper also discusses the loading process and operational experiences with loading and handling of the casks. Information on loading times, worker dose exposure, and total dose for loading are presented

  20. Dry corrosion prediction of radioactive waste containers in long term interim storage: mechanisms of low temperature oxidation of pure iron and numerical simulation of an oxide scale growth; Prevision de la corrosion seche des conteneurs de dechets radioactifs en condition d'entreposage: etude des mecanismes d'oxydation du fer a basse temperature et simulation numerique de la croissance d'une couche d'oxyde

    Energy Technology Data Exchange (ETDEWEB)

    Bertrand, N

    2006-10-15

    In the framework of research on long term behaviour of radioactive waste containers, this work consists on the one hand in the study of low temperature oxidation of iron and on the other hand in the development of a numerical model of oxide scale growth. Isothermal oxidation experiments are performed on pure iron at 300 and 400 C in dry and humid air at atmospheric pressure. Oxide scales formed in these conditions are characterized. They are composed of a duplex magnetite scale under a thin hematite scale. The inner layer of the duplex scale is thinner than the outer one. Both are composed of columnar grains, that are smaller in the inner part. The outer hematite layer is made of very small equiaxed grains. Markers and tracers experiments show that a part of the scale grows at metal/oxide interface thanks to short-circuits diffusion of oxygen. A model for iron oxide scale growth at low temperature is then deduced. Besides this experimental study, the numerical model EKINOX (Estimation Kinetics Oxidation) is developed. It allows to simulate the growth of an oxide scale controlled by mixed mechanisms, such as anionic and cationic vacancies diffusion through the scale, as well as metal transfer at metal/oxide interface. It is based on the calculation of concentration profiles of chemical species and also point defects in the oxide scale and in the substrate. This numerical model does not use the classical quasi-steady-state approximation and calculates the future of cationic vacancies at metal/oxide interface. Indeed, these point defects can either be eliminated by interface motion or injected in the substrate, where they can be annihilated, considering sinks as the climb of dislocations. Hence, the influence of substrate cold-work can be investigated. The EKINOX model is validated in the conditions of Wagner's theory and is confronted with experimental results by its application to the case of high temperature oxidation of nickel. (author)

  1. Interim storage of spent fuel elements in the Paks Nuclear Power Plant, Hungary

    International Nuclear Information System (INIS)

    Szabo, B.

    1998-01-01

    The interim storage of spent fuel cassettes of the Paks NPP provides storage for 50 years at the Paks NPP site. The modular dry storage technology is presented. The technological design and the licensing of the facility has been made by the GEC Alsthom ESL firm. This storage facility can accommodate 450 fuel cassettes until their final disposal. (R.P.)

  2. Alternatives generation and analysis report for immobilized low-level waste interim storage architecture

    Energy Technology Data Exchange (ETDEWEB)

    Burbank, D.A., Westinghouse Hanford

    1996-09-01

    The Immobilized Low-Level Waste Interim Storage subproject will provide storage capacity for immobilized low-level waste product sold to the U.S. Department of Energy by the privatization contractor. This report describes alternative Immobilized Low-Level Waste storage system architectures, evaluation criteria, and evaluation results to support the Immobilized Low-Level Waste storage system architecture selection decision process.

  3. Comparison of cask and drywell storage concepts for a monitored retrievable storage/interim storage system

    International Nuclear Information System (INIS)

    Rasmussen, D.E.

    1982-12-01

    The Department of Energy, through its Richland Operations Office is evaluating the feasibility, timing, and cost of providing a federal capability for storing the spent fuel, high-level wastes, and transuranic wastes that DOE may be obligated by law to manage until permanent waste disposal facilities are available. Three concepts utilizing a monitored retrievable storage/interim storage (MRS/IS) facility have been developed and analyzed. The first concept, co-location with a reprocessing plant, has been developed by staff of Allied General Nuclear Services. the second concept, a stand-alone facility, has been developed by staff of the General Atomic Company. The third concept, co-location with a deep geologic repository, has been developed by the Pacific Northwest Laboratory with the assistance of the Westinghouse Hanford Company and Kaiser Engineers. The objectives of this study are: to develop preconceptual designs for MRS/IS facilities: to examine various issues such as transportation of wastes, licensing of the facilities, and environmental concerns associated with operation of such facilities; and to estimate the life-cycle costs of the facilities when operated in response to a set of scenarios that define the quantities and types of waste requiring storage in specific time periods, generally spanning the years 1989 to 2037. Three scenarios are examined to develop estimates of life-cycle costs for the MRS/IS facilities. In the first scenario, the reprocessing plant is placed in service in 1989 and HLW canisters are stored until a repository is opened in the year 1998. Additional reprocessing plants and repositories are placed in service at intervals as needed to meet the demand. In the second scenario, the reprocessing plants are delayed in starting operations by 10 years, but the repositories open on schedule. In the third scenario, the repositories are delayed 10 years, but the reprocessing plants open on schedule

  4. Comparison of cask and drywell storage concepts for a monitored retrievable storage/interim storage system

    Energy Technology Data Exchange (ETDEWEB)

    Rasmussen, D.E.

    1982-12-01

    The Department of Energy, through its Richland Operations Office is evaluating the feasibility, timing, and cost of providing a federal capability for storing the spent fuel, high-level wastes, and transuranic wastes that DOE may be obligated by law to manage until permanent waste disposal facilities are available. Three concepts utilizing a monitored retrievable storage/interim storage (MRS/IS) facility have been developed and analyzed. The first concept, co-location with a reprocessing plant, has been developed by staff of Allied General Nuclear Services. the second concept, a stand-alone facility, has been developed by staff of the General Atomic Company. The third concept, co-location with a deep geologic repository, has been developed by the Pacific Northwest Laboratory with the assistance of the Westinghouse Hanford Company and Kaiser Engineers. The objectives of this study are: to develop preconceptual designs for MRS/IS facilities: to examine various issues such as transportation of wastes, licensing of the facilities, and environmental concerns associated with operation of such facilities; and to estimate the life-cycle costs of the facilities when operated in response to a set of scenarios that define the quantities and types of waste requiring storage in specific time periods, generally spanning the years 1989 to 2037. Three scenarios are examined to develop estimates of life-cycle costs for the MRS/IS facilities. In the first scenario, the reprocessing plant is placed in service in 1989 and HLW canisters are stored until a repository is opened in the year 1998. Additional reprocessing plants and repositories are placed in service at intervals as needed to meet the demand. In the second scenario, the reprocessing plants are delayed in starting operations by 10 years, but the repositories open on schedule. In the third scenario, the repositories are delayed 10 years, but the reprocessing plants open on schedule.

  5. ULTimateCO2 - State of the art report. Dealing with uncertainty associated with long-term CO2 geological storage

    International Nuclear Information System (INIS)

    2014-01-01

    ULTimateCO2, a four-year collaborative project financed by the 7. Framework Programme and coordinated by BRGM, aims to shed more light on the long-term processes associated with the geological storage of CO 2 . ULTimateCO2 unites 12 partners (research institutes, universities, industrialists) and a varied panel of experts (NGOs, national authority representatives, IEAGHG,...). Based on a multidisciplinary approach, and bringing together laboratory experiments, numerical modelling and natural analogue field studies, ULTimateCO2 will increase our understanding of the long-term effects of CO 2 Capture and Storage (CCS) in terms of hydrodynamics, geochemistry, mechanics of the storage formations and their vicinity. The report contains the partners' pooled knowledge and provides a view of the current state-of-the-art for the issues addressed by this project: - The long-term reservoir trapping efficiency (WP3); - The long-term sealing integrity of faulted and fractured cap-rock (WP4); - The near-well leakage characterisation and chemical processes (WP5); - The long-term behavior of stored CO 2 looking at the basin scale (WP2); - Uncertainty assessment (WP6). Each chapter is divided into two sections: (i) a summary which explains in 'simple words' the main issues and objectives of the WP, and (ii) a current state of the art section which provides a more sound review on the specific studied processes. The aim is to provide answers to pertinent questions from a variety of users, particularly project owners, site operators and national authorities, about their exposure to uncertainty downstream of closure of a CO 2 geological storage site

  6. Project management plan for Reactor 105-C Interim Safe Storage project

    International Nuclear Information System (INIS)

    Plagge, H.A.

    1996-09-01

    Reactor 105-C (located on the Hanford Site in Richland, Washington) will be placed into an interim safe storage condition such that (1) interim inspection can be limited to a 5-year frequency; (2) containment ensures that releases to the environmental are not credible under design basis conditions; and (3) final safe storage configuration shall not preclude or significantly increase the cost for any decommissioning alternatives for the reactor assembly.This project management plan establishes plans, organizational responsibilities, control systems, and procedures for managing the execution of Reactor 105-C interim safe storage activities to meet programmatic requirements within authorized funding and approved schedules

  7. Expansion of storage capacity of interim spent fuel storage (MSVP) Bohunice

    International Nuclear Information System (INIS)

    Pilat, P.; Fridrich, V.

    2005-01-01

    This article describes modifications of Interim spent fuel storage, performed with aim of storage capacity expansion, seismic stability enhancement, and overall increase of service life as well as assuring of MSVP safe operation. Uniqueness of adopted technical solutions is based upon the fact that mentioned innovations and modifications were performed without any changes, neither in ground plan nor architecture of MSVP structure. It also important to mention that all modifications were performed during continual operation of MSVP without any breaks of limits or operational regulations. Reconstruction and innovation of existing construction and technological systems of MSVP has assured required quality standard comparable with actual trends. (authors)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-07-06

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

  9. Dry Cask Storage Inspection and Monitoring. Interim Report.

    Energy Technology Data Exchange (ETDEWEB)

    Bakhtiari, Susan [Argonne National Lab. (ANL), Argonne, IL (United States); Elmer, Thomas W. [Argonne National Lab. (ANL), Argonne, IL (United States); Koehl, Eugene R. [Argonne National Lab. (ANL), Argonne, IL (United States); Wang, Ke [Argonne National Lab. (ANL), Argonne, IL (United States); Raptis, Apostolos C. [Argonne National Lab. (ANL), Argonne, IL (United States); Kunerth, Dennis C. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Birk, Sandra M. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-03-04

    Recently, the U.S. Nuclear Regulatory Commission (NRC) issued the guidance on the aging management of dry storage facilities that indicates the necessity to monitor the conditions of dry cask storage systems (DCSSs) over extended periods of time.1 Part of the justification of the aging management plans is the requirement for inspection and monitoring to verify whether continued monitoring, inspection or mitigation are necessary. To meet this challenge Argonne National Laboratory (ANL) in collaboration with Idaho National Laboratory (INL) is conducting scoping studies on current and emerging nondestructive evaluation/examination (NDE) and online monitoring (OLM) technologies for DCSS integrity assessments. The scope of work plan includes identification and verification of technologies for long-term online monitoring of DCSSs’ crucial physical parameters such as temperature, pressure, leakage and structural integrity in general. Modifications have been made to the current technologies to accommodate field inspections and monitoring. A summary of the scoping studies and experimental efforts conducted to date as well as plans for future activities is provided below.

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

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  11. Development of Accident Scenario for Interim Spent Fuel Storage Facility Based on Fukushima Accident

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dongjin; Choi, Kwangsoon; Yoon, Hyungjoon; Park, Jungsu [KEPCO-E and C, Yongin (Korea, Republic of)

    2014-05-15

    700 MTU of spent nuclear fuel is discharged from nuclear fleet every year and spent fuel storage is currently 70.9% full. The on-site wet type spent fuel storage pool of each NPP(nuclear power plants) in Korea will shortly exceed its storage limit. Backdrop, the Korean government has rolled out a plan to construct an interim spent fuel storage facility by 2024. However, the type of interim spent fuel storage facility has not been decided yet in detail. The Fukushima accident has resulted in more stringent requirements for nuclear facilities in case of beyond design basis accidents. Therefore, there has been growing demand for developing scenario on interim storage facility to prepare for beyond design basis accidents and conducting dose assessment based on the scenario to verify the safety of each type of storage.

  12. Carbon storage and long-term rate of accumulation in high-altitude Andean peatlands of Bolivia

    Science.gov (United States)

    J.A. Hribljan; D.J. Cooper; J. Sueltenfuss; E.C. Wolf; K.A. Heckman; Erik Lilleskov; R.A. Chimner

    2015-01-01

    The high-altitude (4,500+ m) Andean mountain range of north-western Bolivia contains many peatlands. Despite heavy grazing pressure and potential damage from climate change, little is known about these peatlands. Our objective was to quantify carbon pools, basal ages and long-term peat accumulation rates in peatlands in two areas of the arid puna ecoregion of Bolivia:...

  13. Long-term ecosystem nitrogen storage and soil nitrogen availability in post-fire lodgepole pine ecosystems

    Science.gov (United States)

    Erica A. H. Smithwick; Daniel M. Kashian; Michael G. Ryan; Monica G.  Turner

    2009-01-01

    Long-term, landscape patterns in inorganic nitrogen (N) availability and N stocks following infrequent, stand-replacing fire are unknown but are important for interpreting the effect of disturbances on ecosystem function. Here, we present results from a replicated chronosequence study in the Greater Yellowstone Ecosystem (Wyoming, USA) directed at measuring inorganic N...

  14. DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

    Energy Technology Data Exchange (ETDEWEB)

    T. A. Lee

    2005-09-15

    The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

  15. Application of dose evaluation of the MCNP code for interim spent fuel cask storage facility

    International Nuclear Information System (INIS)

    Kosako, Toshiso; Iimoto, Takeshi; Ishikawa, Satoshi; Tsuboi, Takafumi; Teramura, Masahiro; Okamura, Tomomi; Narumiya, Yoshiyuki

    2007-01-01

    The interim storage facility for spent fuel metallic cask is designed as a concrete building structure with air inlet and outlet for circulating the natural cooling. The feature of the interim storage facility is big capacity of spent fuel at several thousands MTU and restricted site usage. It is important to evaluate realistic dose rate in shielding design of the interim storage facility, therefore the three-dimensional continuous-energy Monte Carlo radiation transport code MCNP that exactly treating the complicated geometry was applied. The validation of dose evaluation for interim storage facility by MCNP code were performed by three kinds of neutron shielding benchmark experiments; cask shadow shielding experiment, duct streaming experiment and concrete deep penetration experiment. Dose rate distributions at each benchmark were measured and compared with the calculated results. The comparison showed a good consistency between calculation and experiment results. (author)

  16. DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

    International Nuclear Information System (INIS)

    Lee, T.A.

    2005-01-01

    The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

  17. Final hazard classification and auditable safety analysis for the 105-C Reactor Interim Safe Storage Project

    International Nuclear Information System (INIS)

    Rodovsky, T.J.; Larson, A.R.; Dexheimer, D.

    1996-12-01

    This document summarizes the inventories of radioactive and hazardous materials present in the 105-C Reactor Facility and the operations associated with the Interim Safe Storage Project which includes decontamination and demolition and interim safe storage of the remaining facility. This document also establishes a final hazard classification and verifies that appropriate and adequate safety functions and controls are in place to reduce or mitigate the risk associated with those operations

  18. Acceptable TRU packaging for interim storage and/or terminal isolation: FY-1977 final report

    International Nuclear Information System (INIS)

    Doty, J.W.; Peterson, J.B.

    1978-01-01

    A program was conducted for the definition and demonstration of acceptable waste packages for defense transuranic waste for interim storage and terminal isolation. During FY-1977, a Contractor Questionnaire was used to gather pertinent data and to assess contractor concerns. This information was integrated into basic application data in the form of a checklist. Conceptual Container Design Specifications were developed by analyzing and evaluating the application data against Federal Regulations and interim/terminal storage constraints

  19. Review of the seismic risk in the design of civil engineering of nuclear installations excepted the long term storage of radioactive wastes

    International Nuclear Information System (INIS)

    2006-01-01

    This guide aims to define, for the nuclear installations excepted the long term storage of radioactive wastes, from site data, the design specifications of earthquake resistant civil engineering and the possible methods for: the determination of the seismic response of the buildings, taking into account the interactions with the materials and the evaluation of the associated strains to size the installation; the determination of seismic displacements to be considered to size the materials. (A.L.B.)

  20. Identification and understanding the factors affecting the public and political acceptance of long term storage of spent fuel and high-level radioactive wastes

    International Nuclear Information System (INIS)

    Gorea, Valica

    2006-01-01

    In the end of 2004, according to the information available to the IAEA, there were 440 nuclear reactors operating worldwide, with a total net capacity of 366.3 GW(e), 6 of them being connected to the grid in 2004 ( 2 in Ukraine, one each in China, Japan and the Russian Federation and a reconnection in Canada) by comparison with 2 connections and 2 re-connections in 2003. Also, in the end of 2004, 26 nuclear power plants were under construction with a total net capacity of 20.8 GW(e). The conclusion accepted by common consent is that the nuclear power is still in progress and represents one of the options for power security on long and middle term. If we refer to the nuclear fusion which will produce commercial electric power, over 30 - 40 years, in practically unlimited quantities, the above underlining becomes even more evident. Fortunately, besides the beneficent characteristics, such as: clean, stable as engendering and price, has also a negative characteristic, which generally breathes fear into the people: radioactive waste. A classification of the radioactive waste is not the target of this presentation. I just want to point that a nuclear power plant produces during the time spent fuel - long life high radioactive, generating heat. Another high radioactive waste have similar characteristics (HLW = High Level Waste) for which reason these two categories of wastes are treated together. The spent fuel and the High Level Waste are interim stored for cooling, for around 50 years, afterwards it is transferred to the final repository where it will be kept for hundreds of years, in the case of an open fuel cycle and this is also the case of Cernavoda NPP. Taking into consideration that the Cernavoda Unit 1 reaches the age of 10 years of commercial running during December 2006, it results that the issue of the final disposal is not such urgent as it looks. The objectives of long term management of radioactive waste are public health and protection of the environment

  1. Effect of Gaseous Impurities on Long-Term Thermal Cycling and Aging Properties of Complex Hydrides for Hydrogen Storage

    Energy Technology Data Exchange (ETDEWEB)

    Chandra, Dhanesh [Primary Contact; Lamb, Joshua; Chien, Wen-Ming; Talekar, Anjali; and Pal, Narendra

    2011-03-28

    This program was dedicated to understanding the effect of impurities on Long-Term Thermal Cycling and aging properties of Complex Hydrides for Hydrogen Storage. At the start of the program we found reversibility between Li2NH+LiH LiH+LiNH2 (yielding ~5.8 wt.%H capacity). Then we tested the effect of impurity in H2 gas by pressure cycling at 255°C; first with industrial gas containing ppm levels of O2 and H2O as major impurities. Both these impurities had a significant impact on the reversibility and decreased the capacity by 2.65 wt.%H. Further increase in number of cycles from 500 to 1100 showed only a 0.2 wt%H more weight loss, showing some capacity is still maintained after a significant number of cycles. The loss of capacity is attributed to the formation of ~55 wt% LiH and ~30% Li2O, as major contaminant phases, along with the hydride Li2NH phase; suggesting loss of nitrogen during cycling. The effect of 100 ppm H2O in H2 also showed a decrease of ~2.5 wt.%H (after 560 cycles), and 100ppm O2 in H2; a loss of ~4.1 wt.%. Methane impurity (100 ppm, 100cycles), showed a very small capacity loss of 0.9 wt.%H under similar conditions. However, when Li3N was pressure cycled with 100ppmN2-H2 there were beneficial effects were observed (255oC); the reversible capacity increased to 8.4wt.%H after 853 cycles. Furthermore, with 20 mol.%N2-H2 capacity increased to ~10 wt.%H after 516 cycles. We attribute this enhancement to the reaction of nitrogen with liquid lithium during cycling as the Gibbs free energy of formation of Li3N (Go = -98.7 kJ/mol) is more negative than that of LiH (Go = -50.3 kJ/mol). We propose that the mitigation of hydrogen capacity losses is due to the destabilization of the LiH phase that tends to accumulate during cycling. Also more Li2NH phase was found in the cycled product. Mixed Alanates (3LiNH2:Li3AlH6) showed that 7 wt% hydrogen desorbed under dynamic vacuum. Equilibrium experiments (maximum 12 bar H2) showed up to 4wt% hydrogen reversibly

  2. Behavior of spent nuclear fuel and storage system components in dry interim storage.

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, A.B. Jr.; Gilbert, E.R.; Guenther, R.J.

    1982-08-01

    Irradiated nuclear fuel has been handled under dry conditions since the early days of nuclear reactor operation, and use of dry storage facilities for extended management of irradiated fuel began in 1964. Irradiated fuel is currently being stored dry in four types of facilities: dry wells, vaults, silos, and metal casks. Essentially all types of irradiated nuclear fuel are currently stored under dry conditions. Gas-cooled reactor (GCR) and liquid metal fast breeder reactor (LMFBR) fuels are stored in vaults and dry wells. Certain types of fuel are being stored in licensed dry storage facilities: Magnox fuel in vaults in the United Kingdom and organic-cooled reactor (OCR) fuel in silos in Canada. Dry storage demonstrations are under way for Zircaloy-clad fuel from boiling water reactors BWR's, pressurized heavy-water reactors (PHWRs), and pressurized water reactors (PWRs) in all four types of dry storage facilities. The demonstrations and related hot cell and laboratory tests are directed toward expanding the data base and establishing a licensing basis for dry storage of water reactor fuel. This report reviews the scope of dry interim storage technology, the performance of fuel and facility materials, the status of programs in several countries to license dry storage of water reactor fuel, and the characteristics of water reactor fuel that relate to dry storage conditions.

  3. Behavior of spent nuclear fuel and storage-system components in dry interim storage

    International Nuclear Information System (INIS)

    Johnson, A.B. Jr.; Gilbert, E.R.; Guenther, R.J.

    1982-08-01

    Irradiated nuclear fuel has been handled under dry conditions since the early days of nuclear reactor operation, and use of dry storage facilities for extended management of irradiated fuel began in 1964. Irradiated fuel is currently being stored dry in four types of facilities: dry wells, vaults, silos, and metal casks. Essentially all types of irradiated nuclear fuel are currently stored under dry conditions. Gas-cooled reactor (GCR) and liquid metal fast breeder reactor (LMFBR) fuels are stored in vaults and dry wells. Certain types of fuel are being stored in licensed dry storage facilities: Magnox fuel in vaults in the United Kingdom and organic-cooled reactor (OCR) fuel in silos in Canada. Dry storage demonstrations are under way for Zircaloy-clad fuel from boiling water reactors BWR's, pressurized heavy-water reactors (PHWRs), and pressurized water reactors (PWRs) in all four types of dry storage facilities. The demonstrations and related hot cell and laboratory tests are directed toward expanding the data base and establishing a licensing basis for dry storage of water reactor fuel. This report reviews the scope of dry interim storage technology, the performance of fuel and facility materials, the status of programs in several countries to license dry storage of water reactor fuel, and the characteristics of water reactor fuel that relate to dry storage conditions

  4. Transuranic waste storage and assay facility (TRUSAF) interim safety basis

    International Nuclear Information System (INIS)

    Gibson, K.D.

    1995-09-01

    The TRUSAF ISB is based upon current facility configuration and procedures. The purpose of the document is to provide the basis for interim operation or restrictions on interim operations and the authorization basis for the TRUSAF at the Hanford Site. The previous safety analysis document TRUSAF hazards Identification and Evaluation (WHC 1977) is superseded by this document

  5. Interim Storage Facility for LLW of Decommissioning Nuclear Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Amato, S.; Ugolini, D.; Basile, F. [European Commission, Joint Research Centre, Nuclear Decommissioning and Facility Management Unit, TP 800, Via E. Fermi 2749, 21027 Ispra - VA (Italy)

    2009-06-15

    JRC-Ispra has initiated a Decommissioning and Waste Management (D and WM) Programme of all its nuclear facilities. In the frame of this programme, it has been decided to build an interim storage facility to host conditioned low level waste (LLW) that had been produced during the operation of JRC-Ispra nuclear research reactors and laboratories and that will be produced from their decommissioning. This paper presents the main characteristics of the facility. The storage ISFISF has a rectangular shape with uniform height and it is about 128 m long, 41 m wide and 9 m high. The entire surface affected by the facility, including screening area and access roads, is about 27.000 m{sup 2}. It is divided in three sectors, a central one, about 16 m long, for loading/unloading operations and operational services and two lateral sectors, each about 55 m long, for the conditioned LLW storage. Each storage sector is divided by a concrete wall in two transversal compartments. The ISFISF, whose operational lifetime is 50 years, is designed to host the conditioned LLW boxed in UNI CP-5.2 packages, 2,5 m long, 1.65 m wide, and 1,25 m high. The expected nominal inventory of waste is about 2100 packages, while the maximum storage is 2540 packages, thus a considerably large reserve capacity is available. The packages will be piled in stacks of maximum number of five. The LLW is going to be conditioned with a cement matrix. The maximum weight allowed for each package has been fixed at 16.000 kg. The total radioactivity inventory of waste to be hosted in the facility is about 30 TBq (mainly {beta}/{gamma} emitters). In order to satisfy the structural, seismic, and, most of all, radiological requirements, the external walls of the ISFISF are made of pre-fabricated panels, 32 cm thick, consisting of, from inside to outside, 20 cm of reinforced concrete, 7 cm of insulating material, and again 5 cm of reinforced concrete. For the same reason the roof is made with pre-fabricated panels in

  6. Wayne Interim Storage Site annual environmental report for calendar year 1991, Wayne, New Jersey. [Wayne Interim Storage Site

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-09-01

    This document describes the envirormental monitoring program at the Wayne Interim Storage Site (WISS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring of WISS and surrounding area began in 1984 when Congress added the site to the US Department of Energy's (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. WISS is a National Priorities List site. The environmental monitoring program at WISS includes sampling networks for radon and thoron concentrations in air; external gamma radiation exposure; and radium-226, radium-228, thorium-232, and total uranium concentrations in surface water, sediment, and groundwater. Several nonradiological parameters are also measured in groundwater. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides, dose limits, and other requirements in DOE orders. Environmental standards are established to protect public health and the environment.

  7. Maywood Interim Storage Site annual environmental report for calendar year 1991, Maywood, New Jersey. [Maywood Interim Storage Site

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-09-01

    This document describes the environmental monitoring program at the Maywood Interim Storage Site (MISS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring of MISS began in 1984 when congress added the site to the US Department of Energy's (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a DOE program to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental monitoring program at MISS includes sampling networks for radon and thoron concentrations in air; external gamma radiation-exposure; and total uranium, radium-226, radium-228, thorium-232, and thorium-230 concentrations in surface water, sediment, and groundwater. Additionally, several nonradiological parameters are measured in surface water, sediment, and groundwater. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides (DCGs), dose limits, and other requirements in DOE orders. Environmental standards are established to protect public health and the environment.

  8. Annex D-200 Area Interim Storage Area Final Safety Analysis Report [FSAR] [Section 1 and 2

    International Nuclear Information System (INIS)

    CARRELL, R.D.

    2002-01-01

    The 200 Area Interim Storage Area (200 Area ISA) at the Hanford Site provides for the interim storage of non-defense reactor spent nuclear fuel (SNF) housed in aboveground dry cask storage systems. The 200 Area ISA is a relatively simple facility consisting of a boundary fence with gates, perimeter lighting, and concrete and gravel pads on which to place the dry storage casks. The fence supports safeguards and security and establishes a radiation protection buffer zone. The 200 Area ISA is nominally 200,000 ft 2 and is located west of the Canister Storage Building (CSB). Interim storage at the 200 Area ISA is intended for a period of up to 40 years until the materials are shipped off-site to a disposal facility. This Final Safety Analysis Report (FSAR) does not address removal from storage or shipment from the 200 Area ISA. Three different SNF types contained in three different dry cask storage systems are to be stored at the 200 Area ISA, as follows: (1) Fast Flux Test Facility Fuel--Fifty-three interim storage casks (ISC), each holding a core component container (CCC), will be used to store the Fast Flux Test Facility (FFTF) SNF currently in the 400 Area. (2) Neutron Radiography Facility (NRF) TRIGA'--One Rad-Vault' container will store two DOT-6M3 containers and six NRF TRIGA casks currently stored in the 400 Area. (3) Commercial Light Water Reactor Fuel--Six International Standards Organization (ISO) containers, each holding a NAC-I cask4 with an inner commercial light water reactor (LWR) canister, will be used for commercial LWR SNF from the 300 Area. An aboveground dry cask storage location is necessary for the spent fuel because the current storage facilities are being shut down and deactivated. The spent fuel is being transferred to interim storage because there is no permanent repository storage currently available

  9. Annex D-200 Area Interim Storage Area Final Safety Analysis Report [FSAR] [Section 1 & 2

    Energy Technology Data Exchange (ETDEWEB)

    CARRELL, R D

    2002-07-16

    The 200 Area Interim Storage Area (200 Area ISA) at the Hanford Site provides for the interim storage of non-defense reactor spent nuclear fuel (SNF) housed in aboveground dry cask storage systems. The 200 Area ISA is a relatively simple facility consisting of a boundary fence with gates, perimeter lighting, and concrete and gravel pads on which to place the dry storage casks. The fence supports safeguards and security and establishes a radiation protection buffer zone. The 200 Area ISA is nominally 200,000 ft{sup 2} and is located west of the Canister Storage Building (CSB). Interim storage at the 200 Area ISA is intended for a period of up to 40 years until the materials are shipped off-site to a disposal facility. This Final Safety Analysis Report (FSAR) does not address removal from storage or shipment from the 200 Area ISA. Three different SNF types contained in three different dry cask storage systems are to be stored at the 200 Area ISA, as follows: (1) Fast Flux Test Facility Fuel--Fifty-three interim storage casks (ISC), each holding a core component container (CCC), will be used to store the Fast Flux Test Facility (FFTF) SNF currently in the 400 Area. (2) Neutron Radiography Facility (NRF) TRIGA'--One Rad-Vault' container will store two DOT-6M3 containers and six NRF TRIGA casks currently stored in the 400 Area. (3) Commercial Light Water Reactor Fuel--Six International Standards Organization (ISO) containers, each holding a NAC-I cask4 with an inner commercial light water reactor (LWR) canister, will be used for commercial LWR SNF from the 300 Area. An aboveground dry cask storage location is necessary for the spent fuel because the current storage facilities are being shut down and deactivated. The spent fuel is being transferred to interim storage because there is no permanent repository storage currently available.

  10. Multi-period MINLP model for optimising operation and structural changes to CHP plants in district heating networks with long-term thermal storage

    International Nuclear Information System (INIS)

    Tveit, Tor-Martin; Savola, Tuula; Gebremedhin, Alemayehu; Fogelholm, Carl-Johan

    2009-01-01

    By using thermal storages it is possible to decouple the generation of power and heat, and it can also lead to an reduction in investments, as the storage can be used to cover the peak load periods. This work presents a MINLP model that can be used for analysing new investments and the long-term operation of CHP plants in a district heating network with long-term thermal storage. The model presented in this work includes the non-linear off-design behaviour of the CHP plants as well as a generic mathematical model of the thermal storage, without the need to fix temperatures and pressure. The model is formulated in such a way that it is suitable for deterministic MINLP solvers. The model is non-convex, and subsequently global optimality cannot be guaranteed with local solvers. In order to reduce the chance of obtaining a poor local optimum compared to the global optimum, the model should be solved many times with the initial values varying randomly. It is possible to extract a lot of results from the model, for instance total annual profit, the optimal selection of process options, mass flow through the plant, and generated power from each plant. The formulation of the model makes it suitable for deterministic MINLP solvers

  11. Optically-controlled long-term storage and release of thermal energy in phase-change materials

    OpenAIRE

    Han, Grace G. D.; Li, Huashan; Grossman, Jeffrey C.

    2017-01-01

    Thermal energy storage offers enormous potential for a wide range of energy technologies. Phase-change materials offer state-of-the-art thermal storage due to high latent heat. However, spontaneous heat loss from thermally charged phase-change materials to cooler surroundings occurs due to the absence of a significant energy barrier for the liquid–solid transition. This prevents control over the thermal storage, and developing effective methods to address this problem has remained an elusive ...

  12. Long-Term Safety and Effectiveness of Adalimumab for Moderate to Severe Psoriasis: Results from 7-Year Interim Analysis of the ESPRIT Registry.

    Science.gov (United States)

    Menter, Alan; Thaçi, Diamant; Wu, Jashin J; Abramovits, William; Kerdel, Francisco; Arikan, Dilek; Guo, Dianlin; Ganguli, Arijit; Bereswill, Mareike; Camez, Anne; Valdecantos, Wendell C

    2017-09-01

    ESPRIT (NCT00799877) is an ongoing 10-year international prospective observational registry evaluating the long-term safety and effectiveness of originator adalimumab in routine clinical practice for adult patients with chronic plaque psoriasis. Herein, we report the long-term safety, effectiveness, and patient-reported outcomes (PROs) following adalimumab treatment over the first 7 years of the ESPRIT registry. All treatment-emergent (All-TE) adverse events (AE) since the initial (first ever) dose of adalimumab were assessed. Physician Global Assessment (PGA) and PROs (PROs for US patients only) were evaluated during registry participation. As of 30 November 2015, 6051 patients in the ESPRIT registry were analyzed, representing 23,660.1 patient-years (PY) of overall adalimumab exposure. The incidence rates for All-TE serious AEs, serious infections, and malignancies were 4.4, 1.0, and 1.0 events per 100 PY (E/100PY), respectively. The standardized mortality ratio for TE deaths in the registry was 0.27 (95% CI 0.18-0.38). During the registry's first 7 years, PGA "clear" or "minimal" was achieved by >50% of patients at each annual visit, and among US patients, the mean improvement from baseline in different PROs was maintained. No new safety signals were identified during the first 7 years of the registry, and safety was consistent with the known safety profile of adalimumab. The number of TE deaths was below the expected rate. During the registry's first 7 years, most of the patients remained free of All-TE cardiovascular events, serious infections, and malignancy. As-observed effectiveness of adalimumab and improvements from baseline in PROs were maintained through 7 years of registry participation. Abbvie. ClinicalTrials.gov identifier, NCT00799877.

  13. Assessment of Shelf-Life Ability of Apples cv. ‘Auksis’ after Long-term Storage Under Different Conditions

    OpenAIRE

    Juhņeviča-Radenkova Karina; Radenkovs Vitalijs

    2016-01-01

    The objective of the current research was to ascertain the shelf-life ability of apple ‘Auksis’ after 6 months of cold storage under different conditions. The effect of storage conditions such as: cold storage under normal atmosphere (NA), 1-methylcyclopropene (1-MCP) + cold storage, and ultra-low oxygen (ULO)-controlled atmosphere (CA) [2.0% CO2 and 1.0% O2 (ULO1) and 2.5% CO2 and 1.5% O2 (ULO2)] on the quality of apples during shelf-life was evaluated. Apple fruits immediately after cold st...

  14. Carbon storage and long-term rate of accumulation in high-altitude Andean peatlands of Bolivia

    Directory of Open Access Journals (Sweden)

    J.A. Hribljan

    2015-11-01

    Full Text Available (1 The high-altitude (4,500+ m Andean mountain range of north-western Bolivia contains many peatlands. Despite heavy grazing pressure and potential damage from climate change, little is known about these peatlands. Our objective was to quantify carbon pools, basal ages and long-term peat accumulation rates in peatlands in two areas of the arid puna ecoregion of Bolivia: near the village of Manasaya in the Sajama National Park (Cordillera Occidentale, and in the Tuni Condoriri National Park (Cordillera Real. (2 We cored to 5 m depth in the Manasaya peatland, whose age at 5 m was ca. 3,675 yr. BP with a LARCA of 47 g m-2 yr-1. However, probing indicated that the maximum depth was 7–10 m with a total estimated (by extrapolation carbon stock of 1,040 Mg ha-1. The Tuni peat body was 5.5 m thick and initiated ca. 2,560 cal. yr. BP. The peatland carbon stock was 572 Mg ha-1 with a long-term rate of carbon accumulation (LARCA of 37 g m-2 yr-1. (3 Despite the dry environment of the Bolivian puna, the region contains numerous peatlands with high carbon stocks and rapid carbon accumulation rates. These peatlands are heavily used for llama and alpaca grazing.

  15. Key Performance Criteria Affecting the Most the Safety of a Nuclear Waste Long Term Storage : A Case Study Commissioned by CEA

    International Nuclear Information System (INIS)

    Marvy, A.; Lioure, A; Heriard-Dubreuil, G.; Gadbois, S.; Schneider, T.; Schieber, C.

    2003-01-01

    As part of the work scope set in the French law on high level long lived waste R and D passed in 1991, CEA is conducting a research program to establish the scientific basis and assess the feasibility of long term storage as an option for the safe management of nuclear waste for periods as long as centuries. This goal is a significant departure from the current industrial practice where storage facilities are usually built to last only a few decades. From a technical viewpoint such an extension in time seems feasible provided care and maintenance is exercised. Considering such long periods of time, the risk for Society of loosing oversight and control of such a facility is real, which triggers the question of whether and how long term storage safety can be actually achieved. Therefore CEA commissioned a study (1) in which MUTADIS Consultants (2) and CEPN (3) were both involved. The case study looks into several past and actual human enterprises conducted over significant periods o f time, one of them dating back to the end of the 18th century, and all identified out of the nuclear field. Then-prevailing societal behavior and organizational structures are screened out to show how they were or are still able to cope with similar oversight and control goals. As a result, the study group formulated a set of performance criteria relating to issues like responsibility, securing funds, legal and legislative implications, economic sustainable development, all being areas which are not traditionally considered as far as technical studies are concerned. These criteria can be most useful from the design stage onward, first in an attempt to define the facility construction and operating guiding principles, and thereafter to substantiate the safety case for long term storage and get geared to the public dialogue on that undertaking should it become a reality

  16. Key Performance Criteria Affecting the Most the Safety of a Nuclear Waste Long Term Storage : A Case Study Commissioned by CEA

    Energy Technology Data Exchange (ETDEWEB)

    Marvy, A.; Lioure, A; Heriard-Dubreuil, G.; Gadbois, S.; Schneider, T.; Schieber, C.

    2003-02-24

    As part of the work scope set in the French law on high level long lived waste R&D passed in 1991, CEA is conducting a research program to establish the scientific basis and assess the feasibility of long term storage as an option for the safe management of nuclear waste for periods as long as centuries. This goal is a significant departure from the current industrial practice where storage facilities are usually built to last only a few decades. From a technical viewpoint such an extension in time seems feasible provided care and maintenance is exercised. Considering such long periods of time, the risk for Society of loosing oversight and control of such a facility is real, which triggers the question of whether and how long term storage safety can be actually achieved. Therefore CEA commissioned a study (1) in which MUTADIS Consultants (2) and CEPN (3) were both involved. The case study looks into several past and actual human enterprises conducted over significant periods o f time, one of them dating back to the end of the 18th century, and all identified out of the nuclear field. Then-prevailing societal behavior and organizational structures are screened out to show how they were or are still able to cope with similar oversight and control goals. As a result, the study group formulated a set of performance criteria relating to issues like responsibility, securing funds, legal and legislative implications, economic sustainable development, all being areas which are not traditionally considered as far as technical studies are concerned. These criteria can be most useful from the design stage onward, first in an attempt to define the facility construction and operating guiding principles, and thereafter to substantiate the safety case for long term storage and get geared to the public dialogue on that undertaking should it become a reality.

  17. A look at new key performance criteria that could most affect the safety of long term storage of nuclear waste. A case study commissioned by CEA

    International Nuclear Information System (INIS)

    Marvy, A.; Lioure, A.; Heriard-Dubreuil, G.; Gadbois, S.; Schneider, T.; Schieber, C

    2002-01-01

    As part of the work scope set in the French law on high level long lived waste R and D passed in 1991, CEA is conducting research work to establish the scientific basis and assess the feasibility of long term storage as an option for the safe management of nuclear waste for periods as long as a few centuries. This goal is a significant departure from current industrial practice where storage facilities are usually built to last only a few decades. From a technical viewpoint such an extension in time seems feasible provided care and maintenance is exercised. Considering such long periods of time risk for Society of loosing oversight and control of such a facility is real which triggers the question of whether and how long term storage safety can be actually achieved. Therefore CEA commissioned a study in which MUTADIS Consultants and CEPN were both involved. The case study looks into several past and actual human enterprises conducted over significant periods of time - one dating back to the end of the 18th century - and identified off the nuclear field. Then-prevailing societal behaviour and organizational structures are screened out to show how they were and are still able to cope with similar oversight and control goals. As a result the study group obtained a set of performance criteria relating to issues like responsibility, securing funds, legal and legislative implications, economic sustainable development, all being areas which are not traditionally considered when technical studies are conducted. These criteria can be most useful from the design stage onward, first in an attempt to define the facility construction and operating guiding principles, and thereafter to substantiate the safety case for long term storage and get geared to the public dialogue on that undertaking should it become a reality. (author)

  18. Long-term experience in salt mining and experience in salt mine decommissioning - a chance for ultimate storage?

    International Nuclear Information System (INIS)

    Sitz, P.; Rauche, H.

    2003-01-01

    The author discusses similarities between salt mining and ultimate storage and the possibility of using abandoned salt mines as ultimate storage site. He states that with all the numeric prediction tools now available, expert knowledge of mining engineers is still indispensable [de

  19. Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage.

  20. Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

    International Nuclear Information System (INIS)

    1995-06-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage

  1. Long-term modelling of Carbon Capture and Storage, Nuclear Fusion, and large-scale District Heating

    DEFF Research Database (Denmark)

    Grohnheit, Poul Erik; Korsholm, Søren Bang; Lüthje, Mikael

    2011-01-01

    before 2050. The modelling tools developed by the International Energy Agency (IEA) Implementing Agreement ETSAP include both multi-regional global and long-term energy models till 2100, as well as national or regional models with shorter time horizons. Examples are the EFDA-TIMES model, focusing...... on nuclear fusion and the Pan European TIMES model, respectively. In the next decades CCS can be a driver for the development and expansion of large-scale district heating systems, which are currently widespread in Europe, Korea and China, and with large potentials in North America. If fusion will replace...... fossil fuel power plants with CCS in the second half of the century, the same infrastructure for heat distribution can be used which will support the penetration of both technologies. This paper will address the issue of infrastructure development and the use of CCS and fusion technologies using...

  2. Safety and efficacy of ipragliflozin in Japanese patients with type 2 diabetes in real-world clinical practice: interim results of the STELLA-LONG TERM post-marketing surveillance study.

    Science.gov (United States)

    Nakamura, Ichiro; Maegawa, Hiroshi; Tobe, Kazuyuki; Tabuchi, Hiromi; Uno, Satoshi

    2018-02-01

    Data regarding the efficacy and safety of sodium-glucose cotransporter 2 inhibitors in the real-world setting in Japan are limited. The STELLA-LONG TERM study is an ongoing 3-year post-marketing surveillance study of ipragliflozin in type 2 diabetes (T2D) patients. Here, we report the interim results (including 3-, 12-, and 24-month data). All Japanese patients with T2D who were first prescribed ipragliflozin between 17 July 2014 and 16 October 2015 at participating centers in Japan were registered in STELLA-LONG TERM. At 3, 12, and 24 months, the safety analysis set comprised 11,053, 5475, and 138 patients, respectively; the efficacy analysis set comprised 8757 patients. Ipragliflozin treatment resulted in statistically significant improvements versus baseline in hemoglobin A1c, fasting plasma glucose concentration, body weight, blood pressure, heart rate, and serum concentrations of low-density lipoprotein cholesterol and triglycerides. The adverse drug reaction incidence rate was 10.71%, the most common reactions being renal and urinary disorders (5.06%), infections and infestations (1.24%), and skin and subcutaneous tissue disorders (1.14%). Ipragliflozin was well tolerated and effective in Japanese patients with T2D; no new safety issues were identified.

  3. Effect of storage in short--and long-term commercial semen extenders on the motility, plasma membrane and chromatin integrity of boar spermatozoa.

    Science.gov (United States)

    De Ambrogi, Marco; Ballester, Juan; Saravia, Fernando; Caballero, Ignacio; Johannisson, Anders; Wallgren, Margareta; Andersson, Magnus; Rodriguez-Martinez, Heriberto

    2006-10-01

    For artificial insemination (AI) in pigs, preservation of liquid boar semen at 16-20 degrees C is still common practice as sperm cryopreservation remains suboptimal in this species. To meet the different needs of the swine industry, several extenders have been developed to preserve semen in liquid form for short--and long-term storage. In the present study, three different commercial extenders devised for short-term (BTS+) or long-term preservation (MR-A and X-Cell), were used to test whether storage of semen from four mature, fertile boars at 17 degrees C for 96 h would affect sperm characteristics relevant for fertility, such as motility, membrane integrity and chromatin stability. Computer-assisted sperm analysis, and stainings with the acylated membrane dye SYBR-14/propidium iodide, and acridine orange in connection with flow cytometry were used to evaluate these variables. Percentages of total motile spermatozoa decreased slightly, but significantly, after 72-96 h. While membrane integrity values varied during the period of study, no significant changes in either membrane integrity or chromatin stability were, however, registered. This suggests a customary 96-day storage at 17 degrees C in these extenders was too short an interval to cause losses of integrity in nuclear DNA in the boar population studied.

  4. Assessment of Shelf-Life Ability of Apples cv. ‘Auksis’ after Long-term Storage Under Different Conditions

    Directory of Open Access Journals (Sweden)

    Juhņeviča-Radenkova Karina

    2016-12-01

    Full Text Available The objective of the current research was to ascertain the shelf-life ability of apple ‘Auksis’ after 6 months of cold storage under different conditions. The effect of storage conditions such as: cold storage under normal atmosphere (NA, 1-methylcyclopropene (1-MCP + cold storage, and ultra-low oxygen (ULO-controlled atmosphere (CA [2.0% CO2 and 1.0% O2 (ULO1 and 2.5% CO2 and 1.5% O2 (ULO2] on the quality of apples during shelf-life was evaluated. Apple fruits immediately after cold storage and after 25 days of maintaining at market condition had been evaluated. The physical (firmness, weight losses, chemical (total soluble solids and acid contents, and sensory (aroma, taste, acidity, sweetness, juiciness, and color characteristics of apples had been evaluated after 5, 10, 15, 20, and 25 days to ascertain maximal shelf-life. Results from sensory evaluation indicated that apples treated with 1-MCP and stored at NA were characterized with distinctive aroma, whereas apples stored under CA were poor in sweetness and had remarkable acidity and juiciness. Apples that were stored in cold had pronounced aroma and color but without taste. Based on the evaluation by panelist, maximum shelf-life of apples that were kept under cold storage and ULO1 was 15 days, whereas that of apples that had been treated with 1-MCP and stored at NA and those stored in ULO2 was 25 days.

  5. Transitioning aluminum clad spent fuels from wet to interim dry storage

    International Nuclear Information System (INIS)

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

    1994-01-01

    The United States Department of Energy (DOE) currently owns several hundred metric tons of aluminum clad, spent nuclear fuel and target assemblies. The vast majority of these irradiated assemblies are currently stored in water basins that were designed and operated for short term fuel cooling prior to fuel reprocessing. Recent DOE decisions to severely limit the reprocessing option have significantly lengthened the time of storage, thus increasing the tendency for corrosion induced degradation of the fuel cladding and the underlying core material. The portent of continued corrosion, coupled with the age of existing wet storage facilities and the cost of continuing basin operations, including necessary upgrades to meet current facility standards, may force the DOE to transition these wet stored, aluminum clad spent fuels to interim dry storage. The facilities for interim dry storage have not been developed, partially because fuel storage requirements and specifications for acceptable fuel forms are lacking. In spite of the lack of both facilities and specifications, current plans are to dry store fuels for approximately 40 to 60 years or until firm decisions are developed for final fuel disposition. The transition of the aluminum clad fuels from wet to interim dry storage will require a sequence of drying and canning operations which will include selected fuel preparations such as vacuum drying and conditioning of the storage atmosphere. Laboratory experiments and review of the available literature have demonstrated that successful interim dry storage may also require the use of fuel and canister cleaning or rinsing techniques that preclude, or at least minimize, the potential for the accumulation of chloride and other potentially deleterious ions in the dry storage environment. This paper summarizes an evaluation of the impact of fuel transitioning techniques on the potential for corrosion induced degradation of fuel forms during interim dry storage

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

    International Nuclear Information System (INIS)

    Marino, Armando C

    2009-01-01

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

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

    International Nuclear Information System (INIS)

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

    1995-06-01

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

  8. Modeling the long-term durability of concrete barriers in the context of low-activity waste storage

    Directory of Open Access Journals (Sweden)

    Samson E.

    2013-07-01

    Full Text Available The paper investigates the long-term durability of concrete barriers in contact with a cementitious wasteform designed to immobilize low-activity nuclear waste. The high-pH pore solution of the wasteform contains high concentration level of sulfate, nitrate, nitrite and alkalis. The multilayer concrete/wasteform system was modeled using a multiionic reactive transport model accounting for coupling between species, dissolution/ precipitation reactions, and feedback effect. One of the primary objectives was to investigate the risk associated with the presence of sulfate in the wasteform on the durability of concrete. Simulation results showed that formation of expansive phases, such as gypsum and ettringite, into the concrete barrier was not extensive. Based on those results, it was not possible to conclude that concrete would be severely damaged, even after 5,000 years. Lab work was performed to provide data to validate the modeling results. Paste samples were immersed in sulfate contact solutions and analyzed to measure the impact of the aggressive environment on the material. The results obtained so far tend to confirm the numerical simulations.

  9. Administrative Court Stade, decision of March 22, 1985 (interim storage facility at Gorleben)

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    This decision deals with the planned interim storage facility of Gorleben (F.R.G.). The provisions introduced by the 4th ammendment to sec. 5 para. 6 and 9a to 9c of the German Atomic Energy Act might contain a definite regulation of the 'Entsorgung' of nuclear power stations. Sec. 6 of the Atomic Energy Act is not applicable to interim storage facilities because irradiated nuclear fuel has a double nature: It is spent fuel and nuclear waste as well. Considering current licensing procedures of construction and operation of nuclear installations in the field of 'Entsorgung', special legal regulations for the construction and operation of an interim storage facility have to be required. (CW)

  10. An allowable cladding peak temperature for spent nuclear fuels in interim dry storage

    Science.gov (United States)

    Cha, Hyun-Jin; Jang, Ki-Nam; Kim, Kyu-Tae

    2018-01-01

    Allowable cladding peak temperatures for spent fuel cladding integrity in interim dry storage were investigated, considering hydride reorientation and mechanical property degradation behaviors of unirradiated and neutron irradiated Zr-Nb cladding tubes. Cladding tube specimens were heated up to various temperatures and then cooled down under tensile hoop stresses. Cool-down specimens indicate that higher heat-up temperature and larger tensile hoop stress generated larger radial hydride precipitation and smaller tensile strength and plastic hoop strain. Unirradiated specimens generated relatively larger radial hydride precipitation and plastic strain than did neutron irradiated specimens. Assuming a minimum plastic strain requirement of 5% for cladding integrity maintenance in interim dry storage, it is proposed that a cladding peak temperature during the interim dry storage is to keep below 250 °C if cladding tubes are cooled down to room temperature.

  11. Optically-controlled long-term storage and release of thermal energy in phase-change materials.

    Science.gov (United States)

    Han, Grace G D; Li, Huashan; Grossman, Jeffrey C

    2017-11-13

    Thermal energy storage offers enormous potential for a wide range of energy technologies. Phase-change materials offer state-of-the-art thermal storage due to high latent heat. However, spontaneous heat loss from thermally charged phase-change materials to cooler surroundings occurs due to the absence of a significant energy barrier for the liquid-solid transition. This prevents control over the thermal storage, and developing effective methods to address this problem has remained an elusive goal. Herein, we report a combination of photo-switching dopants and organic phase-change materials as a way to introduce an activation energy barrier for phase-change materials solidification and to conserve thermal energy in the materials, allowing them to be triggered optically to release their stored latent heat. This approach enables the retention of thermal energy (about 200 J g -1 ) in the materials for at least 10 h at temperatures lower than the original crystallization point, unlocking opportunities for portable thermal energy storage systems.

  12. A coupled geochemical-transport-geomechanical model to address caprock integrity during long-term CO2 storage

    NARCIS (Netherlands)

    Veer, E.F. van der; Waldmann, S.; Fokker, P.A.

    2015-01-01

    Underground storage of CO2 will lead to chemical fluid-rock interactions which may potentially alter the porosity and the flow patterns in faults. In this study, we present a coupled numerical model combining chemical fluid-rock interactions, aqueous diffusion, fluid flow, and mechanical processes,

  13. Cold storage as a method for the long-term preservation of tropical dissolved organic carbon (DOC

    Directory of Open Access Journals (Sweden)

    S. Cook

    2016-11-01

    Full Text Available Fluvial fluxes of dissolved organic carbon (DOC may represent an important loss for terrestrial carbon stores in the tropics. However, there is currently limited guidance on the preservation of tropical water samples for DOC analysis. Commonly employed preservation techniques such as freezing or acidification can limit degradation but may also alter sample properties, complicating DOC analysis. We examined the effects of cold storage at 4 °C on DOC concentration and quality in water samples collected from a tropical peat catchment. Samples were stored in the dark at 4 °C for periods of 6–12 weeks. Freeze/thaw experiments were also made. Mean DOC concentrations in samples stored for six weeks at 4 °C were 6.1 % greater than in samples stored at ambient room temperature (33 °C over the same period. Changes in DOC concentrations, in two sample sets, during cold storage were 2.25 ± 2.9 mg L-1 (8 % to 2.69 ± 1.4 mg L-1 (11 % over a 12-week period. Freeze/thaw resulted in alterations in the optical properties of samples, and this in turn altered the calculated DOC concentrations by an average of 10.9 %. We conclude that cold storage at 4 °C is an acceptable preservation method for tropical DOC water samples, for moderate time periods, and is preferable to freezing or storage at ambient temperatures.

  14. Long-term effects of drying conditions on the essential oil and color of tarragon leaves during storage

    NARCIS (Netherlands)

    ArabHosseini, A.; Boxtel, van A.J.B.; Huisman, W.; Muller, J.

    2007-01-01

    The effect of storage on the essential oil content and color of French Tarragon (Artemisia dracunculus L.) leaves is studied. Tarragon leaves were dried at temperatures 45, 60 and 90 °C with, respectively, the relative humidity levels 17%, 7% and 2.5%. At 60 °C also a relative humidity level of 18%

  15. The effect of long-term storage on the physiochemical and bactericidal properties of electrochemically activated solutions.

    Science.gov (United States)

    Robinson, Gareth; Thorn, Robin; Reynolds, Darren

    2012-12-24

    Electrochemically activated solutions (ECAS) are generated by electrolysis of NaCl solutions, and demonstrate broad spectrum antimicrobial activity and high environmental compatibility. The biocidal efficacy of ECAS at the point of production is widely reported in the literature, as are its credentials as a "green biocide." Acidic ECAS are considered most effective as biocides at the point of production and ill suited for extended storage. Acidic ECAS samples were stored at 4 °C and 20 °C in glass and polystyrene containers for 398 days, and tested for free chlorine, pH, ORP and bactericidal activity throughout. ORP and free chlorine (mg/L) in stored ECAS declined over time, declining at the fastest rate when stored at 20 °C in polystyrene and at the slowest rate when stored at 4 °C in glass. Bactericidal efficacy was also affected by storage and ECAS failed to produce a 5 log(10) reduction on five occasions when stored at 20 °C. pH remained stable throughout the storage period. This study represents the longest storage evaluation of the physiochemical parameters and bactericidal efficacy of acidic ECAS within the published literature and reveals that acidic ECAS retain useful bactericidal activity for in excess of 12 months, widening potential applications.

  16. The Effect of Long-Term Storage on the Physiochemical and Bactericidal Properties of Electrochemically Activated Solutions

    Directory of Open Access Journals (Sweden)

    Gareth Robinson

    2012-12-01

    Full Text Available Electrochemically activated solutions (ECAS are generated by electrolysis of NaCl solutions, and demonstrate broad spectrum antimicrobial activity and high environmental compatibility. The biocidal efficacy of ECAS at the point of production is widely reported in the literature, as are its credentials as a “green biocide.” Acidic ECAS are considered most effective as biocides at the point of production and ill suited for extended storage. Acidic ECAS samples were stored at 4 °C and 20 °C in glass and polystyrene containers for 398 days, and tested for free chlorine, pH, ORP and bactericidal activity throughout. ORP and free chlorine (mg/L in stored ECAS declined over time, declining at the fastest rate when stored at 20 °C in polystyrene and at the slowest rate when stored at 4 °C in glass. Bactericidal efficacy was also affected by storage and ECAS failed to produce a 5 log10 reduction on five occasions when stored at 20 °C. pH remained stable throughout the storage period. This study represents the longest storage evaluation of the physiochemical parameters and bactericidal efficacy of acidic ECAS within the published literature and reveals that acidic ECAS retain useful bactericidal activity for in excess of 12 months, widening potential applications.

  17. A DFT based equilibrium study of a chemical mixture Tachyhydrite and their lower hydrates for long term heat storage

    NARCIS (Netherlands)

    Pathak, A.D.; Gaastra - Nedea, S.V.; Zondag, H.A.; Rindt, C.C.M.; Smeulders, D.M.J.

    2016-01-01

    Chloride based salt hydrates are promising materials for seasonal heat storage. However, hydrolysis, a side reaction, deteriorates, their cycle stability. To improve the kinetics and durability, we have investigated the optimum operating conditions of a chemical mixture of CaCl2 and MgCl2 hydrates.

  18. Assessment of sperm viability, mitochondrial activity, capacitation and acrosome intactness in extended boar semen during long-term storage.

    Science.gov (United States)

    Huo, Li-Jun; Ma, Xing-Hong; Yang, Zeng-Ming

    2002-10-15

    The purpose of this study was to assess sperm quality in extended boar semen during in vitro storage in order to determine which extender should be used and how long boar semen can be stored. Freshly ejaculated boar semen was diluted with equal volumes of Beltsville thaw solution (BTS), Androhep, KIEV or Zorlesco extenders and stored at 17 degrees C for up to 15 days. Sperm quality was evaluated by examining viability using SYBR-14/PI and Hoechst 33258 staining, mitochondrial activity using 5,5',6,6'-tetrachloro-1,1',3,3'-tetraethylbenzimidazolyl-carbocyanine iodide (JC-1) staining, acrosome intactness by Coomassie blue staining, and capacitation status by chlortetracycline (CTC) staining. There were over 50% viable spermatozoa in boar semen extended with Zorlesco and Androhep extenders on Day 13 of storage. The percentage of JC-1-stained spermatozoa was 53.8 +/- 2.1% for Zorlesco and 57.7 +/- 1.60% for Androhep extenders on Day 13 of storage. The percentage of acrosome-intact spermatozoa detected by Coomassie blue staining was higher than that in the SYBR-14PI-, Hoechst 33258-, and JC-1-stained samples in our study. The results from SYBR-14/PI, Hoechst 33258, JC-1, and Coomassie blue staining were highly correlated (r > or = 0.9461). There were less than 15% capacitated spermatozoa in the semen extended with BTS, Androhep and Zorlesco extenders during 9 days of storage. However, most viable boar spermatozoa became capacitated by Day 13 of storage. The rank order of four extenders for maintaining sperm viability and mitochondrial activity was as follows: Androhep, Zorlesco, BTS, KIEV.

  19. Co-ensiling as a new technique for long-term storage of agro-industrial waste with low sugar content prior to anaerobic digestion.

    Science.gov (United States)

    Hillion, Marie-Lou; Moscoviz, Roman; Trably, Eric; Leblanc, Yoann; Bernet, Nicolas; Torrijos, Michel; Escudié, Renaud

    2018-01-01

    Biodegradable wastes produced seasonally need an upstream storage, because of the requirement for a constant feeding of anaerobic digesters. In the present article, the potential of co-ensiling biodegradable agro-industrial waste (sugar beet leaves) and lignocellulosic agricultural residue (wheat straw) to obtain a mixture with low soluble sugar content was evaluated for long-term storage prior to anaerobic digestion. The aim is to store agro-industrial waste while pretreating lignocellulosic biomass. The dynamics of co-ensiling was evaluated in vacuum-packed bags at lab-scale during 180 days. Characterization of the reaction by-products and microbial communities showed a succession of metabolic pathways. Even though the low initial sugars content was not sufficient to lower the pH under 4.5 and avoid undesirable fermentations, the methane potential was not substantially impacted all along the experiment. No lignocellulosic damages were observed during the silage process. Overall, it was shown that co-ensiling was effective to store highly fermentable fresh waste evenly with low sugar content and offers new promising possibilities for constant long-term supply of industrial anaerobic digesters. Copyright © 2017 Elsevier Ltd. All rights reserved.

  20. Current status of the first interim spent fuel storage facility in Japan

    International Nuclear Information System (INIS)

    Shinbo, Hitoshi; Kondo, Mitsuru

    2008-01-01

    In Japan, storage of spent fuels outside nuclear power plants was enabled as a result of partial amendments to the Nuclear Reactor Regulation Law in June 2000. Five months later, Mutsu City in Aomori Prefecture asked the Tokyo Electric Power Company (TEPCO) to conduct technical surveys on siting of the interim spent fuel storage facility (we call it 'Recyclable-Fuel Storage Center'). In April 2003, TEPCO submitted the report on siting feasibility examination, concluded that no improper engineering data for siting, construction of the facility will be possible from engineering viewpoint. Siting Activities for publicity and public acceptance have been continued since then. After these activities, Aomori Prefecture and Mutsu City approved siting of the Recyclable Fuel Storage Center in October 2005. Aomori Prefecture, Mutsu City, TEPCO and Japan Atomic Power Company (JAPC) signed an agreement on the interim spent fuel storage Facility. A month later, TEPCO and JAPC established Recyclable-Fuel Storage Company (RFS) in Mutsu City through joint capital investment, specialized in the first interim spent fuel storage Facility in Japan. In May 2007, we made an application for establishment permit, following safety review by regulatory authorities. In March 2008, we started the preparatory construction. RFS will safely store of spent fuels of TEPCO and JAPC until they will be reprocessed. Final storage capacity will be 5,000 ton-U. First we will construct the storage building of 3,000 ton-U to be followed by second building. We aim to start operation by 2010. (author)

  1. Safety of interim storage solutions of used nuclear fuel during extended term

    Energy Technology Data Exchange (ETDEWEB)

    Shelton, C.; Bader, S.; Issard, H.; Arslan, M. [AREVA, 7135 Minstrel Way, Suite 300 Columbia, MD 21045 (United States)

    2013-07-01

    In 2013, the total amount of stored used nuclear fuel (UNF) in the world will reach 225,000 T HM. The UNF inventory in wet storage will take up over 80% of the available total spent fuel pool (SFP) capacity. Interim storage solutions are needed. They give flexibility to the nuclear operators and ensure that nuclear reactors continue to operate. However, we need to keep in mind that they are also an easy way to differ final decision and implementation of a UNF management approach (recycling or final disposal). In term of public perception, they can have a negative impact overtime as it may appear that nuclear industry may have significant issues to resolve. In countries lacking an integrated UNF management approach, the UNF are being discharged from the SFPs to interim storage (mostly to dry storage) at the same rate as UNF is being discharged from reactors, as the SFPs at the reactor sites are becoming full. This is now the case in USA, Taiwan, Switzerland, Spain, South Africa and Germany. For interim storage, AREVA has developed different solutions in order to allow the continued operation of reactors while meeting the current requirements of Safety Authorities: -) Dry storage canisters on pads, -) Dual-purpose casks (dry storage and transportation), -) Vault dry storage, and -) Centralized pool storage.

  2. Geothermal long-term modelling of a solar coupled geothermal probe heat storage in Crailsheim; Geothermische Langzeitmodellierung eines solargekoppelten Erdsonden-Waermespeichers in Crailsheim

    Energy Technology Data Exchange (ETDEWEB)

    Homuth, Sebastian; Mikisek, Philipp; Goetz, Annette E.; Sass, Ingo [Technische Univ. Darmstadt (Germany). Fachgebiet Angewandte Geothermie

    2011-10-24

    The thermal variations of the subsurface in the vicinity of a seasonal solar coupled geothermal probe heat storage were modeled using FEFLOW {sup registered} over a period of thirty years. The geothermal probe heat storage consists of eighty boreholes in an area of 85 square meters. The geothermal probes have a depth of 55 m and are mainly located in limestones of the Upper Muschelkalk (Triassic). The geothermal probe heat storage is thermally loaded from April to September. The thermal discharge takes place from October to March. The thermal and hydraulic input data of the model are based on three 80 meter deep geothermal probes (GWM 1-3) in the vicinity of the storage. The cores were completely lithologically, facially and finely stratigraphically affiliated. Measurements of thermal conductivity, permeability, porosity and density of 76 representative samples from the geothermal probe GWM 3 and measurements of the main fracture directions in two reference digestions at Crailsheim enabled a most realistic modeling of the storage. The results of the long-term modeling can be used for a detailed forecasting of the thermal alterations in the subsurface.

  3. The Effect of Long-Term Storage on the Physiochemical and Bactericidal Properties of Electrochemically Activated Solutions

    OpenAIRE

    Robinson, Gareth; Thorn, Robin; Reynolds, Darren

    2012-01-01

    Electrochemically activated solutions (ECAS) are generated by electrolysis of NaCl solutions, and demonstrate broad spectrum antimicrobial activity and high environmental compatibility. The biocidal efficacy of ECAS at the point of production is widely reported in the literature, as are its credentials as a “green biocide.” Acidic ECAS are considered most effective as biocides at the point of production and ill suited for extended storage. Acidic ECAS samples were stored a...

  4. 1987 Federal interim storage fee study: A technical and economic analysis

    Energy Technology Data Exchange (ETDEWEB)

    1987-09-01

    This document is the latest in a series of reports that are published annually by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE). This information in the report, which was prepared by E.R. Johnson Associates under subcontract to PNL, will be used by the DOE to establish a payment schedule for interim storage of spent nuclear fuel under the Federal Interim Storage (FIS) Program, which was mandated by the Nuclear Waste Policy Act of 1982. The information in this report will be used to establish the schedule of charges for FIS services for the year commencing January 1, 1988. 13 tabs.

  5. 1987 Federal interim storage fee study: A technical and economic analysis

    International Nuclear Information System (INIS)

    1987-09-01

    This document is the latest in a series of reports that are published annually by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE). This information in the report, which was prepared by E.R. Johnson Associates under subcontract to PNL, will be used by the DOE to establish a payment schedule for interim storage of spent nuclear fuel under the Federal Interim Storage (FIS) Program, which was mandated by the Nuclear Waste Policy Act of 1982. The information in this report will be used to establish the schedule of charges for FIS services for the year commencing January 1, 1988. 13 tabs

  6. Immobilized High-Level Waste (HLW) Interim Storage Alternative Generation and analysis and Decision Report - second Generation Implementing Architecture

    International Nuclear Information System (INIS)

    CALMUS, R.B.

    2000-01-01

    Two alternative approaches were previously identified to provide second-generation interim storage of Immobilized High-Level Waste (IHLW). One approach was retrofit modification of the Fuel and Materials Examination Facility (FMEF) to accommodate IHLW. The results of the evaluation of the FMEF as the second-generation IHLW interim storage facility and subsequent decision process are provided in this document

  7. Final Report on "Rising CO2 and Long-term Carbon Storage in Terrestrial Ecosystems: An Empirical Carbon Budget Validation"

    Energy Technology Data Exchange (ETDEWEB)

    J. Patrick Megonigal; Bert G. Drake

    2010-08-27

    The primary goal of this report is to report the results of Grant DE-FG02-97ER62458, which began in 1997 as Grant DOE-98-59-MP-4 funded through the TECO program. However, this project has a longer history because DOE also funded this study from its inception in 1985 through 1997. The original grant was focused on plant responses to elevated CO2 in an intact ecosystem, while the latter grant was focused on belowground responses. Here we summarize the major findings across the 25 years this study has operated, and note that the experiment will continue to run through 2020 with NSF support. The major conclusions of the study to date are: (1 Elevated CO2 stimulated plant productivity in the C3 plant community by ~30% during the 25 year study. The magnitude of the increase in productivity varied interannually and was sometime absent altogether. There is some evidence of down-regulation at the ecosystem level across the 25 year record that may be due to interactions with other factors such as sea-level rise or long-term changes in N supply; (2) Elevated CO2 stimulated C4 productivity by <10%, perhaps due to more efficient water use, but C3 plants at elevated CO2 did not displace C4 plants as predicted; (3) Increased primary production caused a general stimulation of microbial processes, but there were both increases and decreases in activity depending on the specific organisms considered. An increase in methanogenesis and methane emissions implies elevated CO2 may amplify radiative forcing in the case of wetland ecosystems; (4) Elevated CO2 stimulated soil carbon sequestration in the form of an increase in elevation. The increase in elevation is 50-100% of the increase in net ecosystem production caused by elevated CO2 (still under analysis). The increase in soil elevation suggests the elevated CO2 may have a positive outcome for the ability of coastal wetlands to persist despite accelerated sea level rise; (5) Crossing elevated CO2 with elevated N causes the elevated CO

  8. The European FP7 ULTimateCO2 project: A comprehensive approach to study the long term fate of CO2 geological storage sites

    Science.gov (United States)

    Audigane, P.; Brown, S.; Dimier, A.; Pearce, J.; Frykman, P.; Maurand, N.; Le Gallo, Y.; Spiers, C. J.; Cremer, H.; Rutters, H.; Yalamas, T.

    2013-12-01

    The European FP7 ULTimateCO2 project aims at significantly advance our knowledge of specific processes that could influence the long-term fate of geologically stored CO2: i) trapping mechanisms, ii) fluid-rock interactions and effects on mechanical integrity of fractured caprock and faulted systems and iii) leakage due to mechanical and chemical damage in the well vicinity, iv) brine displacement and fluid mixing at regional scale. A realistic framework is ensured through collaboration with two demonstration sites in deep saline sandstone formations: the onshore former NER300 West Lorraine candidate in France (ArcelorMittal GeoLorraine) and the offshore EEPR Don Valley (former Hatfield) site in UK operated by National Grid. Static earth models have been generated at reservoir and basin scale to evaluate both trapping mechanisms and fluid displacement at short (injection) and long (post injection) time scales. Geochemical trapping and reservoir behaviour is addressed through experimental approaches using sandstone core materials in batch reactive mode with CO2 and impurities at reservoir pressure and temperature conditions and through geochemical simulations. Collection of data has been generated from natural and industrial (oil industry) analogues on the fluid flow and mechanical properties, structure, and mineralogy of faults and fractures that could affect the long-term storage capacity of underground CO2 storage sites. Three inter-related lines of laboratory experiments investigate the long-term evolution of the mechanical properties and sealing integrity of fractured and faulted caprocks using Opalinus clay of Mont Terri Gallery (Switzerland) (OPA), an analogue for caprock well investigated in the past for nuclear waste disposal purpose: - Characterization of elastic parameters in intact samples by measuring strain during an axial experiment, - A recording of hydraulic fracture flow properties by loading and shearing samples in order to create a 'realistic

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

    Energy Technology Data Exchange (ETDEWEB)

    Orban, G.; Shelton, C.

    2015-07-01

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

  10. Experimentation of a LiBr–H2O absorption process for long-term solar thermal storage: Prototype design and first results

    International Nuclear Information System (INIS)

    N'Tsoukpoe, K.E.; Le Pierrès, N.; Luo, L.

    2013-01-01

    The long-term thermal storage by absorption process studied in this paper is devoted to building heating. A demonstrative prototype that can store 8 kWh of heat and produce a heating power of 1 kW has been designed and built. It has been tested in static and dynamic operating conditions, which are compatible with domestic solar thermal and heating plants. The process operating principle, the prototype design and first experimental results are presented and discussed in this contribution. The charging process has been proved successful. The observed power during the charging phases is satisfactory, according to the process design for a real plant (2–5 kW). Absorption during discharging phase is also verified. Discharging tests show that absorption operates in conditions that could allow house heating as the absorber outlet solution temperature can reach 40 °C. However, some problems related to the absorber design have not allowed observing the heat recovery by the heat transfer fluid as expected. Some avenues are explored prior to a new and more appropriate design and eventually a new operating mode. Various aspects such as the use of a heat and mass transfer enhancement additive and stratification in the solution storage tank have also been addressed. - Highlights: ► A long-term thermal storage prototype is tested under practical conditions. ► For the prototype design, a separate reactor is used with integrated components. ► The observed powers during the charging phases are satisfactory (2–5 kW). ► Following crystallisation phases, discharging tests enabled the crystal dissolution. ► Absorber temperature that could allow house heating (up to 40°C) has been observed

  11. Safety, Efficacy, and Persistence of Long-Term Mirabegron Treatment for Overactive Bladder in the Daily Clinical Setting: Interim (1-Year) Report from a Japanese Post-Marketing Surveillance Study.

    Science.gov (United States)

    Kato, Daisuke; Tabuchi, Hiromi; Uno, Satoshi

    2017-08-01

    To report interim 1-year results from a 3-year surveillance study evaluating safety, efficacy, and persistence of long-term mirabegron for overactive bladder (OAB). Patients starting treatment with mirabegron for urinary urgency, daytime frequency, and urgency incontinence associated with OAB were registered and followed up for 3 years. Data were collected on adverse drug reactions (ADR), changes in OAB symptoms, changes in Overactive Bladder Symptom Score (OABSS), and treatment discontinuations. Treatment persistence rates were calculated by Kaplan-Meier analysis. Eighty-one ADR were observed in 72/1139 patients (6.3%) through 1 year of mirabegron treatment, with the incidence highest during the first month. No significant change in residual urine volume was observed at any observation point up to 1 year of mirabegron treatment. Mirabegron was deemed "effective" in 883/1091 patients (80.9%) at 1 year/discontinuation. Total OABSS was decreased with statistical significance at 3 months, 6 months, and 1 year, or at discontinuation (P similar for male and female patients but significantly higher for patients aged ≥65 years (67.3%; n = 908) compared with those aged <65 years (59.8%; n = 231; log-rank test: P = 0.032). Long-term OAB treatment with mirabegron was well-tolerated, with effectiveness maintained through 1 year. Mirabegron treatment persistence was higher than has been previously reported, and was greater in patients aged ≥65 years compared with those aged <65 years. © 2017 John Wiley & Sons Australia, Ltd.

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

    International Nuclear Information System (INIS)

    Hwang, Yong Soo

    2008-12-01

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

  13. Long-term energy and climate implications of carbon capture and storage deployment strategies in the US coal-fired electricity fleet.

    Science.gov (United States)

    Sathre, Roger; Masanet, Eric

    2012-09-04

    To understand the long-term energy and climate implications of different implementation strategies for carbon capture and storage (CCS) in the US coal-fired electricity fleet, we integrate three analytical elements: scenario projection of energy supply systems, temporally explicit life cycle modeling, and time-dependent calculation of radiative forcing. Assuming continued large-scale use of coal for electricity generation, we find that aggressive implementation of CCS could reduce cumulative greenhouse gas emissions (CO(2), CH(4), and N(2)O) from the US coal-fired power fleet through 2100 by 37-58%. Cumulative radiative forcing through 2100 would be reduced by only 24-46%, due to the front-loaded time profile of the emissions and the long atmospheric residence time of CO(2). The efficiency of energy conversion and carbon capture technologies strongly affects the amount of primary energy used but has little effect on greenhouse gas emissions or radiative forcing. Delaying implementation of CCS deployment significantly increases long-term radiative forcing. This study highlights the time-dynamic nature of potential climate benefits and energy costs of different CCS deployment pathways and identifies opportunities and constraints of successful CCS implementation.

  14. Plutonium storage criteria

    Energy Technology Data Exchange (ETDEWEB)

    Chung, D. [Scientech, Inc., Germantown, MD (United States); Ascanio, X. [Dept. of Energy, Germantown, MD (United States)

    1996-05-01

    The Department of Energy has issued a technical standard for long-term (>50 years) storage and will soon issue a criteria document for interim (<20 years) storage of plutonium materials. The long-term technical standard, {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides,{close_quotes} addresses the requirements for storing metals and oxides with greater than 50 wt % plutonium. It calls for a standardized package that meets both off-site transportation requirements, as well as remote handling requirements from future storage facilities. The interim criteria document, {open_quotes}Criteria for Interim Safe Storage of Plutonium-Bearing Solid Materials{close_quotes}, addresses requirements for storing materials with less than 50 wt% plutonium. The interim criteria document assumes the materials will be stored on existing sites, and existing facilities and equipment will be used for repackaging to improve the margin of safety.

  15. Conceptual design report for regional low-level waste interim storage site

    International Nuclear Information System (INIS)

    Bird, M.V.; Thompson, J.D.

    1981-08-01

    An interim storage site design concept was developed for receiving 100,000 ft 3 low-level waste per year, in the form of solidified wastes in 55-gallon drums with a dose rate of < 200 mrem per hour at contact

  16. Cost Implications of an Interim Storage Facility in the Waste Management System

    Energy Technology Data Exchange (ETDEWEB)

    Jarrell, Joshua J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Joseph, III, Robert Anthony [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Howard, Rob L [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Petersen, Gordon M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Nutt, Mark [Argonne National Lab. (ANL), Argonne, IL (United States); Carter, Joe [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Cotton, Thomas [Complex Systems Group, Bozeman, MT (United States)

    2016-09-01

    This report provides an evaluation of the cost implications of incorporating a consolidated interim storage facility (ISF) into the waste management system (WMS). Specifically, the impacts of the timing of opening an ISF relative to opening a repository were analyzed to understand the potential effects on total system costs.

  17. Introduction: Long term prediction

    International Nuclear Information System (INIS)

    Beranger, G.

    2003-01-01

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

  18. Repacking of Cobalt 60 spent sources in the central interim storage

    International Nuclear Information System (INIS)

    Zeleznik, N.

    2003-01-01

    After the transfer of the responsibility for the management of the Central interim storage for waste from small producers, located at the reactor centre in Brinje near Ljubljana, Slovenia, the national Agency for radwaste management (ARAO) started with most urgent activities to improve the utilization of the storage facility. One of the main tasks has also been the rearrangement of the already stored radioactive waste in order to reduce volume of the waste and to collect same radioisotopes in the containers. The latest campaign, performed in 2002/2003, was repacking of all Co-60 spent sealed sources in the storage facility and also at the producer's premises which were after conditioning put into two drums with concrete matrix and stored back to the Central interim storage. The preparation works together with the implementation are described in the paper. (author)

  19. Effect of the long-term memory on the beam break-up instability of a single bunch in storage rings

    International Nuclear Information System (INIS)

    Pestrikov, D.V.

    2009-01-01

    We study modifications of the beam break-up instability of transverse coherent oscillations of a single bunch which occur in storage rings due to weak wakefields decaying longer than the revolution period of particles. The long-term part of the wake results in the eigenmode spectra of coherent oscillations. Both stable and unstable modes are found for coherent oscillations of a monochromatic bunch. The single turn wakefields result in the beam break-up coherent oscillations of the bunch. The found eigenmode spectrum does not contain a leading unstable mode. Despite the exponential increase in time of the eigenmodes, both self-consistent and the beam break-up parts of the coherent oscillations indicate similar and non-exponential time dependencies. The beam break-up behavior dominates, if the wake memory is weak.

  20. Financing long term liabilities (Germany)

    International Nuclear Information System (INIS)

    2003-01-01

    charges and fees levied from the waste producers. Altogether, financial resources for decommissioning are needed for the following steps: the post-operational phase in which the facility is prepared for dismantling after its final shut-down, dismantling of the radioactive part of the facility, management, storage and disposal of the radioactive waste, restoration of the site, licensing and regulatory supervision of all these steps. Additional means are necessary for the management, storage and disposal of the spent fuel. The way in which the availability of financial resources is secured differs between public owned installations and installations of the private power utilities. In Germany, past practices has resulted in singular contaminated sites of limited extent, mainly during the first half of the 20. century. Those contaminated sites have been or are being cleaned up and redeveloped. In large areas of Saxony and Thuringia, the geological formations permitted the surface and underground mining of Uranium ore. Facilities of the former Soviet-German WISMUT Ltd. where ore was mined and processed from 1946 until the early 1990's can be found at numerous sites. In the course of the re-unification of Germany, the soviet shares of the WISMUT were taken over by the Federal Republic of Germany and the closure of the WISMUT facilities was initiated. In that phase the extent of the damages to the environment and of the necessary remediation work became clear. All mining and milling sites are now closed and are under decommissioning. A comprehensive remediation concept covers all WISMUT sites. Heaps and mill-tailing ponds are transferred into a long-term stable condition. The area of the facilities to be remediated amounts to more than 30 km 2 . Heaps cover a total area of ca. 15,5 km 2 , tailing ponds in which the tailings resulting from the Uranium production are stored as sludges cover 6,3 km 2 ). In total, the remediation issues are very complex and without precedent. The

  1. Effect of different bulking agents on water variation and thermal balance and their respective contribution to bio-generated heat during long-term storage sludge biodrying process.

    Science.gov (United States)

    Liu, Tiantian; Cui, Chongwei; He, Junguo; Tang, Jian

    2018-04-17

    Biodrying was first used for the post-treatment of long-term storage sludge with vinasse as bulking agents. The effect of different bulking agents on water and heat variation and their respective contributions to bio-generated heat during storage sludge biodrying were investigated. Three different bulking agents (beer lees and distillers grains, with conventional straw used for comparison) were mixed with storage sludge for biodrying for an 18-day period. The results revealed the treatment with beer lees as bulking agent achieved the best performance with the highest water removal capacity (658 g kg -1 initial water). The extent of organic degradation in the mixture was related to the degradation ability of the bulking agents. The degradation of C- and H-containing materials (e.g., carboxylic acid) accounted for volatile solids (VS) loss. Water and thermal analyses showed that evaporation was the main way of water loss (accounting for 90%), while evaporation heat was the main component of heat consumption (accounting for 56.67-60.62%).The biodegradation of bulking agents contributed a high proportion of the bio-generated heat consumed by water evaporation (82.35-86.67%).

  2. Long-term effects of climate change on carbon storage and tree species composition in a dry deciduous forest.

    Science.gov (United States)

    Fekete, István; Lajtha, Kate; Kotroczó, Zsolt; Várbíró, Gábor; Varga, Csaba; Tóth, János Attila; Demeter, Ibolya; Veperdi, Gábor; Berki, Imre

    2017-08-01

    Forest vegetation and soils have been suggested as potentially important sinks for carbon (C) with appropriate management and thus are implicated as effective tools in stabilizing climate even with increasing anthropogenic release of CO 2 . Drought, however, which is often predicted to increase in models of future climate change, may limit net primary productio (NPP) of dry forest types, with unknown effects on soil C storage. We studied C dynamics of a deciduous temperate forest of Hungary that has been subject to significant decreases in precipitation and increases in temperature in recent decades. We resampled plots that were established in 1972 and repeated the full C inventory by analyzing more than 4 decades of data on the number of living trees, biomass of trees and shrubs, and soil C content. Our analyses show that the decline in number and biomass of oaks started around the end of the 1970s with a 71% reduction in the number of sessile oak stems by 2014. Projected growth in this forest, based on the yield table's data for Hungary, was 4.6 kg C/m 2 . Although new species emerged, this new growth and small increases in oak biomass resulted in only 1.9 kg C/m 2 increase over 41 years. The death of oaks increased inputs of coarse woody debris to the surface of the soil, much of which is still identifiable, and caused an increase of 15.5%, or 2.6 kg C/m 2 , in the top 1 m of soil. Stability of this fresh organic matter input to surface soil is unknown, but is likely to be low based on the results of a colocated woody litter decomposition study. The effects of a warmer and drier climate on the C balance of forests in this region will be felt for decades to come as woody litter inputs decay, and forest growth remains impeded. © 2017 John Wiley & Sons Ltd.

  3. Technical and economic assessments of storage techniques for long-term retention of industrial-beet sugar for non-food industrial fermentations

    Science.gov (United States)

    Vargas-Ramirez, Juan Manuel

    Industrial beets may compete against corn grain as an important source of sugars for non-food industrial fermentations. However, dependable and energy-efficient systems for beet sugar storage and processing are necessary to help establish industrial beets as a viable sugar feedstock. Therefore, technical and economic aspects of beet sugar storage and processing were evaluated. First, sugar retention was evaluated in whole beets treated externally with either one of two antimicrobials or a senescence inhibitor and stored for 36 wk at different temperature and atmosphere combinations. Although surface treatment did not improve sugar retention, full retention was enabled by beet dehydration caused by ambient air at 25 °C and with a relative humidity of 37%. This insight led to the evaluation of sugar retention in ground-beet tissue ensiled for 8 wk at different combinations of acidic pH, moisture content (MC), and sugar:solids. Some combinations of pH ≤ 4.0 and MC ≤ 67.5% enabled retentions of at least 90%. Yeast fermentability was also evaluated in non-purified beet juice acidified to enable long-term storage and partially neutralized before fermentation. None of the salts synthesized through juice acidification and partial neutralization inhibited yeast fermentation at the levels evaluated in that work. Conversely, yeast fermentation rates significantly improved in the presence of ammonium salts, which appeared to compensate for nitrogen deficiencies. Capital and operating costs for production and storage of concentrated beet juice for an ethanol plant with a production capacity of 76 x 106 L y-1 were estimated on a dry-sugar basis as U.S. ¢34.0 kg-1 and ¢2.2 kg-1, respectively. Storage and processing techniques evaluated thus far prove that industrial beets are a technically-feasible sugar feedstock for ethanol production.

  4. Design analysis of various transportation package options for BN-350 SNF in terms of nuclear radiation safety in planning for long-terms dry storage

    International Nuclear Information System (INIS)

    Aisabekov, A.Z.; Mukenova, S.A.; Tur, E.S.; Tsyngaev, V.M.

    2004-01-01

    Full text: This effort is performed under the BN-350 reactor facility decommissioning project. One of the project tasks - spent nuclear fuel handling - includes the following: fuel packaging into sealed canisters, transportation of the canisters in multi-seat metallo-concrete containers and placement of the containers for a long-term dry storage. The goal of this effort is to computationally validate nuclear and radiation safety of the SNF containers placed for storage both under normal storage conditions and probable accident situations. The basic unit structure and design configurations are presented: assemblies, canisters, transportation containers. The major factors influencing nuclear and radiation safety are presented: fuel burn-up, enrichment, fabrication tolerance, types of fuel assemblies, configuration of assemblies in the canister and canisters in the container, background of assemblies placed in the reactor and cooling pool. Conditions under which the SNF containers will be stored are described and probable accident situations are listed. Proceeding from the conservatism principle, selection of the assemblies posing the greatest nuclear hazard is validated. A neutron effective multiplication factor is calculated for the SNF containers under the normal storage conditions and for the case of emergency. The effective multiplication factor is shown to be within a standard value of 0.95 in any situation. Based on the experimental data on assembly and canister dose rates, canisters posing the highest radiation threat are selected. Activities of sources and gamma-radiation spectral composition are calculated. Distribution of the dose rate outside the containers both under the normal storage conditions and accident situations are calculated. The results obtained are analyzed

  5. Interim storage packagings for spent fuels : how to optimize an universal design to local needs

    International Nuclear Information System (INIS)

    Konirsch, O.; Kawabata, T.; Hunter, I.

    2003-01-01

    For the last ten years, the interim storage market for spent fuels issued from Nuclear Power Plants has significantly increased all over the world: there are presently many storage projects either in Asia, in North America and in Europe. Even if there is no international regulation on that field, there is a big concern from all the nuclear industry to try to harmonise the specification for the definition of the Interim Storage Systems. One example of this harmonisation is the common and general wish to develop systems, which allow to be easily transportable either to a final repository or to a reprocessing plant. As this destination is generally not yet known, the storage system should be able to be transported all over the world. On the other hand, the specific requirement for the storage facility and its associated equipment are subject to local and/or national regulation. COGEMA LOGISTICS Group has developed two different technologies which are compatible with this principle of harmonisation: dual purpose metallic cask represented by the TN24 family and the concrete storage system NUHOMS(R). For both technologies, basic designs can be adapted to the local needs in term of performance and of national regulation. To cover all the world, COGEMA LOGISTICS Group has its own subsidiaries, in Asia, in North America and in Europe with their own autonomous engineers teams for designing, licensing, manufacturing and delivering the transport/storage products. COGEMA LOGISTICS Group is presently the leader on the dry interim storage market. The purpose of the present paper is to show how it is possible to optimise a basic existing design of a dual purpose metallic cask for a local need of storage. Taking into account the national rules for storage and the international regulation for transport, the designer shall minimise the development cost for a completely new design and maximise the capacity of the packaging regarding the allowable limits in the Nuclear Power Plant, in

  6. Development of dual-purpose metal cask for interim storage of spent nuclear fuel (1). Outline of cask structure

    International Nuclear Information System (INIS)

    Shimizu, Masashi; Hayashi, Makoto; Kashiwakura, Jun

    2003-01-01

    Spent fuels discharged from nuclear power plants in Japan are planed to be reprocessed at the nuclear fuel recycle plant under construction at Rokkasho-mura. Since the amount of the spent fuels exceeds that of recycled fuel, the spent fuels have to be properly stored and maintained as recycle fuel resource until the beginning of the reprocessing. For that sake, interim storage installations are being constructed outside the nuclear power plants by 2010. The storage dry casks have been practically used as the interim storage in the nuclear power plants. From this reason, the storage system using the storage dry casks is promising as the interim storage installations away form the reactors, which are under discussion. In the interim storage facilities, the storage using the dry cask of the storage metal cask with business showings, having the function of transportation is now under discussion. By employing transportation and storage dual-purpose cask, the repack equipments can be exhausted, and the reliability of the interim storage installations can be increased. Hitachi, Ltd. has been developing the high reliable and economical transportation and storage dry metal cask. In this report, the outline of our developing transportation and storage dry cask is described. (author)

  7. Desorption behaviour of polycyclic aromatic hydrocarbons after long-term storage of two harbour sludges from the port of Rotterdam, The Netherlands

    KAUST Repository

    Heister, Katja

    2013-04-12

    Purpose: The desorption behaviour of 16 polycyclic aromatic hydrocarbons (PAHs) in sludges from two sites of the port of Rotterdam, The Netherlands, which are designated to be stored in a subaqueous sludge depository, was investigated after a storage time of 14 years at 4 °C under anaerobic conditions in the dark, mimicking depository conditions. Such long-term storage is believed to effect the desorption of the PAHs. Materials and methods: Batch desorption experiments over a time period of 130 days were performed with the brackish Beerkanaal (BK) sludge and the freshwater Beneden Merwede River (BMR) sludge. The organic carbon-water partitioning coefficient (K OC) values were calculated and compared to values of a previous study on the same sludges after a storage time of 3 years and to values obtained from calculations based on octanol-water partitioning coefficient (K OW) values. Additionally, the organic matter of the sludges was characterised by C and N elemental analysis and solid-state 13C nuclear magnetic resonance spectroscopy. Results and discussion: Only desorption of low molecular weight PAHs up to pyrene was detected. Several K OC values were higher compared to the values from the previous study, and all were increased compared to values based on K OW values. It is assumed that the increase in K OC was an effect of the prolonged contact time, causing slow intradomain diffusion of PAHs into the condensed carbon domains. Desorption was higher in BK than in BMR, which is explained by differences in organic matter composition because BMR (containing predominantly aromatic carbon) and BK (which was dominated by lipids) contained the same amount of organic carbon. It is inferred that lipids compete with PAHs for sorption sites on the aromatic carbon, so that lipids block these sorption sites, and the PAHs are adsorbed to the lipids. Conclusions: Since the amounts of PAHs desorbed from both sludges in this study were so low, it is supposed that long-term

  8. In-situ storage: An approach to interim remedial action - recent case studies in Canada

    International Nuclear Information System (INIS)

    Zelmer, R.L.

    1991-01-01

    The Low-Level Radioactive Waste Management Office (LLRWMO) acts on behalf of the federal government to manage historic low-level radioactive wastes. Recent interim remedial work in the Town of Port Hope, Ontario has included the consolidation of radium and uranium contaminated soils into temporary storage facilities on two sites to await final disposal elsewhere. Simple containments constructed and sited on already contaminated sites have been found effective as part of an interim remedial strategy. The approach has been accepted and supported by the local public. Lessons have been learned from a project management, environmental remediation and engineering design point of view

  9. Relative risk measure suitable for comparison of design alternatives of interim spent nuclear fuel storage facility

    International Nuclear Information System (INIS)

    Ferjencik, M.

    1997-01-01

    Accessible reports on risk assessment of interim spent nuclear fuel storage facilities presume that only releases of radioactive substances represent undesired consequences. However, only certain part of the undesired consequences is represented by them. Many other events are connected with safety and are able to cause losses to the operating company. The following two presumptions are pronounced based on this. 1. Any event causing a disturbance of a safety function of the storage facility is an incident event. 2. Any disturbance of a safety function is an undesired consequence. If the facility safety functions are identified and if the severity of their disturbances is quantified, then it is possible to combine consequence severity quantifications and event frequencies into a risk measure. Construction and application of such a risk measure is described in this paper. The measure is shown to be a tool suitable for comparison of interim storage technology design alternatives. (author)

  10. Central processing and interim storage of radioactive wastes

    International Nuclear Information System (INIS)

    Wenger, J.P.

    1996-01-01

    Within the ZWILAG project, the buildings for the temporary storage of all categories of radioactive wastes including the spent fuel elements are being readied at a central location. The intermediate storage installations are enhanced by a conditioning and burning plant for weak radioactive operating waste from the nuclear power plants and from the area of responsibility of the state. (author) 2 figs

  11. Development of a separate tank with an electrolysis-dependent bacteria controlling system for the long term storage of potable water.

    Science.gov (United States)

    Ishizuka, Akinori; Tanji, Masataka; Hayashi, Nobuatsu; Wakabayashi, Akihiro; Tatsumoto, Hideki; Hotta, Kunimoto

    2006-12-01

    For the long term storage of tap water, we developed a separate type of tank (5 m3) equipped with an electrolysis system to control bacterial growth. The electrolysis conditions using 20A direct current and a water flow rate of 10 L/min were capable of producing available chlorine (AC) at the rate of 5-8mg/min and raising the AC level of the stored tap water by about 0.2 mg/kg within 20-30 min The electrolyzed tap water with 0.2 mg/kg AC showed a capability per ml of killing 10(5)-10(6) cfu of bacteria such as Escherichia coli and Pseudomonas aeruginosa within 15 sec. A 6-month trial operation of the storage system with an automatic electrolysis control to keep AC level ranging 0.2-0.4 mg/kg demonstrated that the system worked well for the stored tap water in suppressing bacterial growth as well as in keeping good potable quality with reference to the 46 parameters specified for Japanese tap water. Actually, the electrolysis treatment was administered intermittently with an interval of about two weeks. Thus we believe the developed system has good potential to secure a potable water supply not only in the occasion of emergencies but also in countries having problems in the supply of safe drinking water.

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

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  13. Long-term survival of Naegleria polaris from Antarctica after 10 years of storage at 4 °C.

    Science.gov (United States)

    Matsuo, Junji; Nakamura, Shinji; Okubo, Torahiko; Fukui, Manabu; Yamaguchi, Hiroyuki

    2018-03-01

    A free-living amoeba, Naegleria is ubiquitously distributed in various natural environments. Since some Naegleria spp. are exclusively distributed in the Arctic and sub-Antarctic regions, we hypothesized that the amoeba may be useful to determine long-term survival of Naegleria in laboratory conditions at 4 °C. The main objective of the study is to determine that a species of an environmental amoebal isolated can live at low temperatures after a long time. Here, we therefore show long-term survival of an amoeba, Naegleria polaris isolated from a sediment sample, which was collected from Antarctica 10 years ago, and since stored at 4 °C. The sample was put on non-nutrient agar plates with heat-killed Escherichia coli, and then the plate was incubated at 4, 15, or 30 °C. Motile amoebae were seen only when the plate was incubated at 15 °C. The sequencing of ribosomal DNA including internal transcribed spacers (ITS) 1, 5.8S rDNA, and ITS2 region revealed the amoebae to be N. polaris, which is exclusively distributed in the Arctic and sub-Antarctic regions. Scanning electron microscopic observation showed that no typical sucker-like structure was seen on the surface of N. polaris, but the cysts were similar to those of Naegleria fowleri. Thus, our result shows, for the first time, that N. polaris can survive after 10 years of storage at 4 °C. This finding may help us understand the still undescribed effects of environmental samples on viability of amoebae.

  14. 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)

  15. 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)

  16. Assessment of Hanford burial grounds and interim TRU storage

    International Nuclear Information System (INIS)

    Geiger, J.F.; Brown, D.J.; Isaacson, R.E.

    1977-08-01

    A review and assessment is made of the Hanford low level solid radioactive waste management sites and facilities. Site factors considered favorable for waste storage and disposal are (1) limited precipitation, (2) a high deficiency of moisture in the underlying sediments (3) great depth to water table, all of which minimize radionuclide migration by water transport, and (4) high sorbtive capacity of the sediments. Facilities are in place for 20 year retrievable storage of transuranic (TRU) wastes and for disposal of nontransuranic radioactive wastes. Auxiliary facilities and services (utilities, roads, fire protection, shops, etc.) are considered adequate. Support staffs such as engineering, radiation monitoring, personnel services, etc., are available and are shared with other operational programs. The site and associated facilities are considered well suited for solid radioactive waste storage operations. However, recommendations are made for study programs to improve containment, waste package storage life, land use economy, retrievability and security of TRU wastes

  17. Long term storage in liquid nitrogen leads to only minor phenotypic and gene expression changes in the mammary carcinoma model cell line BT474.

    Science.gov (United States)

    Fazekas, Judit; Grunt, Thomas W; Jensen-Jarolim, Erika; Singer, Josef

    2017-05-23

    Cancer cell lines are indispensible surrogate models in cancer research, as they can be used off-the-shelf, expanded to the desired extent, easily modified and exchanged between research groups for affirmation, reproduction or follow-up experiments.As malignant cells are prone to genomic instability, phenotypical changes may occur after certain passages in culture. Thus, cell lines have to be regularly authenticated to ensure data quality. In between experiments these cell lines are often stored in liquid nitrogen for extended time periods.Although freezing of cells is a necessary evil, little research is performed on how long-term storage affects cancer cell lines. Therefore, this study investigated the effects of a 28-year long liquid nitrogen storage period on BT474 cells with regard to phenotypical changes, differences in cell-surface receptor expression as well as cytokine and gene expressional variations. Two batches of BT474 cells, one frozen in 1986, the other directly purchased from ATCC were investigated by light microscopy, cell growth analysis, flow cytometry and cytokine as well as whole-transcriptome expression profiling. The cell lines were morphologically indifferent and showed similar growth rates and similar cell-surface receptor expression. Transcriptome analysis revealed significant differences in only 26 of 40,716 investigated RefSeq transcripts with 4 of them being up-regulated and 22 down-regulated. This study demonstrates that even after very long periods of storage in liquid nitrogen, cancer cell lines display only minimal changes in their gene expression profiles. However, also such minor changes should be carefully assessed before continuation of experiments, especially if phenotypic alterations can be additionally observed.

  18. Rapid fabrication of superhydrophobic Al/Fe{sub 2}O{sub 3} nanothermite film with excellent energy-release characteristics and long-term storage stability

    Energy Technology Data Exchange (ETDEWEB)

    Ke, Xiang; Zhou, Xiang, E-mail: zhouxiang@njust.edu.cn; Hao, Gaozi; Xiao, Lei; Liu, Jie; Jiang, Wei, E-mail: superfine_jw@126.com

    2017-06-15

    Highlights: • Superhydrophobic Al/Fe{sub 2}O{sub 3} nanothermite film is prepared by combining electrophoretic deposition and surface modification technologies. • The deposition system and kinetics of electrophoretic deposition process are investigated to optimize parameters to obtain smooth films. • Energy-release characteristics of superhydrophobic films are significantly improved for both fresh and aged samples. • Superhydrophobic films exhibit excellent long-time storage stability both in natural and accelerated aging test. • A preignition reaction is found to enhance the energy-release characteristics of superhydrophobic nanothermite film. - Abstract: One of the challenges for the application of energetic materials is their energy-retaining capabilities after long-term storage. In this study, we report a facile method to fabricate superhydrophobic Al/Fe{sub 2}O{sub 3} nanothermite film by combining electrophoretic deposition and surface modification technologies. Different concentrations of dispersion solvents and additives are investigated to optimize the deposition parameters. Meanwhile, the dependence of deposition rates on nanoparticle concentrations is also studied. The surface morphology and chemical composition are characterized by field-emission scanning electron microscopy, X-ray diffraction, X-ray energy-dispersive spectroscopy, and X-ray photoelectron spectroscopy. A static contact angles as high as 156° shows the superhydrophobicity of the nanothermite film. Natural and accelerated aging tests are performed and the thermal behavior is analyzed. Thermal analysis shows that the surface modification contributes to significantly improved energy-release characteristics for both fresh and aged samples, which is supposed to be attributed to the preignition reaction between Al{sub 2}O{sub 3} shell and FAS-17. Superhydrophobic Al/Fe{sub 2}O{sub 3} nanothermite film exhibits excellent long-time storage stability with 83.4% of energy left in

  19. Interim licensing criteria for physical protection of certain storage of spent fuel

    International Nuclear Information System (INIS)

    Dwyer, P.A.

    1994-11-01

    This document presents interim criteria to be used in the physical protection licensing of certain spent fuel storage installations. Installations that will be reviewed under this criteria are those that store power reactor spent fuel at decommissioned power reactor sites; independent spent fuel storage installations located outside of the owner controlled area of operating nuclear power reactors; monitored retrievable storage installations owned by the Department of Energy, designed and constructed specifically for the storage, of spent fuel; the proposed geologic repository operations area; or permanently shutdown power reactors still holding a Part 50 license. This criteria applies to both dry cask and pool storage. However, the criteria in this document does not apply to the storage of spent fuel within the owner-controlled area of operating nuclear power reactors

  20. Safety report for Central Interim Storage facility for radioactive waste from small producers

    International Nuclear Information System (INIS)

    Zeleznik, N.; Mele, I.

    2004-01-01

    In 1999 the Agency for Radwaste Management took over the management of the Central Interim Storage (CIS) in Brinje, intended only for radioactive waste from industrial, medical and research applications. With the transfer of the responsibilities for the storage operation, ARAO, the new operator of the facility, received also the request from the Slovenian Nuclear Safety Administration for refurbishment and reconstruction of the storage and for preparation of the safety report for the storage with the operational conditions and limitations. In order to fulfill these requirements ARAO first thoroughly reviewed the existing documentation on the facility, the facility itself and the stored inventory. Based on the findings of this review ARAO prepared several basic documents for improvement of the current conditions in the storage facility. In October 2000 the Plan for refurbishment and modernization of the CIS was prepared, providing an integral approach towards remediation and refurbishment of the facility, optimization of the inventory arrangement and modernization of the storage and storing utilization. In October 2001 project documentation for renewal of electric installations, water supply and sewage system, ventilation system, the improvements of the fire protection and remediation of minor defects discovered in building were completed according to the Act on Construction. In July 2003 the safety report was prepared, based on the facility status after the completion of the reconstruction works. It takes into account all improvements and changes introduced by the refurbishment and reconstruction of the facility according to project documentation. Besides the basic characteristics of the location and its surrounding, it also gives the technical description of the facility together with proposed solutions for the renewal of electric installations, renovation of water supply and sewage system, refurbishment of the ventilation system, the improvement of fire

  1. Criteria for designing an interim waste storage facility

    International Nuclear Information System (INIS)

    Vicente, Roberto

    2011-01-01

    The long-lived radioactive wastes with activity above clearance levels generated by radioisotope users in Brazil are collected into centralized waste storage facilities under overview of the National Commission on Nuclear Energy (CNEN). One of these centers is the Radioactive Waste Management Department (GRR) at the Nuclear and Energy Research Institute (IPEN), in Sao Paulo, which since 1978 also manages the wastes generated by IPEN itself. Present inventory of stored wastes includes about 160 tons of treated wastes, distributed in 1290 steel, 200-liters drums, and 52 steel, 1.6 m 3 -boxes, with an estimated total activity of 0.8 TBq. Radionuclides present in these wastes are fission and activation products, transuranium elements, and isotopes from the uranium and thorium decay series. The capacity and quality of the storage rooms at GRR evolved along the last decades to meet the requirements set forth by the Brazilian regulatory authorities.From a mere outdoor concrete platform over which drums were simply stacked and covered with canvas to the present day building, a great progress was made in the storage method. In this paper we present the results of a study in the criteria that were meant to guide the design of the storage building, many of which were eventually adopted in the final concept, and are now built-in features of the facility. We also present some landmarks in the GRR's activities related to waste management in general and waste storage in particular, until the treated wastes of IPEN found their way into the recently licensed new storage facility. (author)

  2. Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

    Energy Technology Data Exchange (ETDEWEB)

    Pickett, W.W.

    1997-12-30

    This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations.

  3. Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

    International Nuclear Information System (INIS)

    Pickett, W.W.

    1997-01-01

    This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations

  4. Experience with the licensing of the interim spent fuel storage facility modification

    International Nuclear Information System (INIS)

    Bezak, S.; Beres, J.

    1999-01-01

    After political and economical changes in the end of eighties, the utility operating the nuclear power plants in the Slovak Republic (SE, a.s.) decided to change the original scheme of the back-end of the nuclear fuel cycle; instead of reprocessing in the USSR/Russian Federation spent fuel will be stored in an interim spent fuel storage facility until the time of the final decision. As the best solution, a modification of the existing interim spent fuel storage facility has been proposed. Due to lack of legal documents for this area, the Regulatory Authority of the Slovak Republic (UJD SR) performed licensing procedures of the modification on the basis of recommendations by the IAEA, the US NRC and the relevant parts of the US CFR Title 10. (author)

  5. Federal interim storage fee study for civilian spent nuclear fuel: a technical and economical analysis

    International Nuclear Information System (INIS)

    1983-07-01

    This report describes the study conducted by the Department of Energy (the Department) regarding payment charges for the federal interim storage (FIS) of spent fuel and presents the details of the study results. It describes the selection of a methodology for calculating a FIS fee schedule, sets forth the estimates of cost for construction and operation of FIS facilities, provides a range of estimates for the fee for FIS services, and identifies special contractual considerations associated with providing FIS services to authorized users. The fee is structured for a range of spent fuel capacities because of uncertainties regarding the schedule of availability and amount of spent fuel that may require and qualify for FIS. The results set forth in the report were used as a basis for development of the report entitled Payment Charges for Federal Interim Storage of Spent Nuclear Fuel from Civilian Nuclear Power Plants in the United States, dated July 1983

  6. Operations and Maintenance Concept Plan for the Immobilized High Level Waste (IHLW) Interim Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    JANIN, L.F.

    2000-08-30

    This O&M Concept looks at the future operations and maintenance of the IHLW/CSB interim storage facility. It defines the overall strategy, objectives, and functional requirements for the portion of the building to be utilized by Project W-464. The concept supports the tasks of safety basis planning, risk mitigation, alternative analysis, decision making, etc. and will be updated as required to support the evolving design.

  7. Implementation plan for deployment of Federal Interim Storage facilities for commercial spent nuclear fuel

    International Nuclear Information System (INIS)

    1986-12-01

    This document is the third annual report on plans for providing Federal Interim Storage (FIS) capacity. References are made to the first and second annual reports, as necessary. Background factors and aspects that were considered in the development of this deployment plan and activities and interactions considered to be required to implement an FIS program are discussed. A generic description of the approach that the Department plans to follow in deploying FIS facilities is also described

  8. Implementation plan for deployment of Federal Interim Storage facilities for commercial spent nuclear fuel

    International Nuclear Information System (INIS)

    1985-01-01

    This document is the second annual report on plans for providing Federal Interim Storage (FIS) capacity. References are made to the first annual report as necessary (DOE/RW-0003, 1984). Background factors and aspects that were considered in the development of this deployment plan and activities and interactions considered to be required to implement an FIS program are discussed. The generic approach that the Department plans to follow in deploying FIS facilities is also described

  9. Operations and Maintenance Concept Plan for the Immobilized High-Level Waste (IHLW) Interim Storage Facility

    International Nuclear Information System (INIS)

    JANIN, L.F.

    2000-01-01

    This OandM Concept looks at the future operations and maintenance of the IHLW/CSB interim storage facility. It defines the overall strategy, objectives, and functional requirements for the portion of the building to be utilized by Project W-464. The concept supports the tasks of safety basis planning, risk mitigation, alternative analysis, decision making, etc. and will be updated as required to support the evolving design

  10. A Tissue Retrieval and Postharvest Processing Regimen for Rodent Reproductive Tissues Compatible with Long-Term Storage on the International Space Station and Postflight Biospecimen Sharing Program

    Directory of Open Access Journals (Sweden)

    Vijayalaxmi Gupta

    2015-01-01

    Full Text Available Collection and processing of tissues to preserve space flight effects from animals after return to Earth is challenging. Specimens must be harvested with minimal time after landing to minimize postflight readaptation alterations in protein expression/translation, posttranslational modifications, and expression, as well as changes in gene expression and tissue histological degradation after euthanasia. We report the development of a widely applicable strategy for determining the window of optimal species-specific and tissue-specific posteuthanasia harvest that can be utilized to integrate into multi-investigator Biospecimen Sharing Programs. We also determined methods for ISS-compatible long-term tissue storage (10 months at −80°C that yield recovery of high quality mRNA and protein for western analysis after sample return. Our focus was reproductive tissues. The time following euthanasia where tissues could be collected and histological integrity was maintained varied with tissue and species ranging between 1 and 3 hours. RNA quality was preserved in key reproductive tissues fixed in RNAlater up to 40 min after euthanasia. Postfixation processing was also standardized for safe shipment back to our laboratory. Our strategy can be adapted for other tissues under NASA’s Biospecimen Sharing Program or similar multi-investigator tissue sharing opportunities.

  11. Evaluation of swine fertilisation medium (SFM) efficiency in preserving spermatozoa quality during long-term storage in comparison to four commercial swine extenders.

    Science.gov (United States)

    Fantinati, P; Zannoni, A; Bernardini, C; Forni, M; Tattini, A; Seren, E; Bacci, M L

    2009-02-01

    In pig production, artificial insemination is widely carried out and the use of fresh diluted semen is predominant. For this reason, there are increasing interests in developing new extenders and in establishing the optimal storage conditions for diluted spermatozoa. In the last few decades, we utilised a homemade diluent (swine fertilisation medium (SFM)) for spermatozoa manipulation and biotechnological application as the production of transgenic pigs utilising the sperm-mediated gene transfer technique. The purpose of the present study is therefore to analyse the ability of SFM, in comparison to four commercial extenders, in preserving the quality of diluted boar semen stored at 16.5°C till 15 days. We utilised some of the main predictive tests as objectively measured motility, acrosome and sperm membrane integrity, high mitochondrial membrane potential and pH. Based on our in vitro study, SFM could be declared as a good long-term extender, able to preserve spermatozoa quality as well as Androhep Enduraguard for up to 6 to 9 days and more.

  12. Transport, handling, and interim storage of intermediate-level transuranic waste at the INEL

    International Nuclear Information System (INIS)

    Metzger, J.C.; Snyder, A.M.

    1977-09-01

    The Idaho National Engineering Laboratory stores transuranic (TRU)-contaminated waste emitting significant amounts of beta-gamma radiation. This material is referred to as intermediate-level TRU waste. The Energy Research and Development Administration requires that this waste be stored retrievably during the interim before a Federal repository becomes operational. Waste form and packaging criteria for the eventual storage of this waste at a Federal repository, i.e., the Waste Isolation Pilot Plant (WIPP), have been tentatively established. The packaging and storage techniques now in use at the Idaho National Engineering Laboratory are compatible with these criteria and also meet the requirement that the waste containers remain in a readily-retrievable, contamination-free condition during the interim storage period. The Intermediate Level Transuranic Storage Facility (ILTSF) provides below-grade storage in steel pipe vaults for intermediate-level TRU waste prior to shipment to the WIPP. Designated waste generating facilities, operated for the Energy Research and Development Administration, use a variety of packaging and transportation methods to deliver this waste to the ILTSF. Transfer of the waste containers to the ILTSF storage vaults is accomplished using handling methods compatible with these waste packaging and transport methods

  13. Conceptual design of an interim dry storage system for the Atucha nuclear power plant spent fuels

    International Nuclear Information System (INIS)

    Nassini, Horacio E.P.; Fuenzalida Troyano, C.S.; Bevilacqua, Arturo M.; Bergallo, Juan E.

    2005-01-01

    The Atucha I nuclear power station, after completing the rearrangement and consolidation of the spent fuels in the two existing interim wet storage pools, will have enough room for the storage of spent fuel from the operation of the reactor till December 2014. If the operation is extended beyond 2014, or if the reactor is decommissioned, it will be necessary to empty both pools and to transfer the spent fuels to a dry storage facility. This paper shows the progress achieved in the conceptual design of a dry storage system for Atucha I spent fuels, which also has to be adequate, without modifications, for the storage of fuels from the second unity of the nuclear power station, Atucha II, that is now under construction. (author) [es

  14. A review at the role of storage in energy systems with a focus on Power to Gas and long-term storage

    NARCIS (Netherlands)

    Blanco, Herib; Faaij, André

    2018-01-01

    A review of more than 60 studies (plus more than 65 studies on P2G) on power and energy models based on simulation and optimization was done. Based on these, for power systems with up to 95% renewables, the electricity storage size is found to be below 1.5% of the annual demand (in energy terms).

  15. Lessons learned from the Siting Process of an Interim Storage Facility in Spain - 12024

    Energy Technology Data Exchange (ETDEWEB)

    Lamolla, Meritxell Martell [MERIENCE Strategic Thinking, 08734 Olerdola, Barcelona (Spain)

    2012-07-01

    On 29 December 2009, the Spanish government launched a site selection process to host a centralised interim storage facility for spent fuel and high-level radioactive waste. It was an unprecedented call for voluntarism among Spanish municipalities to site a controversial facility. Two nuclear municipalities, amongst a total of thirteen municipalities from five different regions, presented their candidatures to host the facility in their territories. For two years the government did not make a decision. Only in November 30, 2011, the new government elected on 20 November 2011 officially selected a non-nuclear municipality, Villar de Canas, for hosting this facility. This paper focuses on analysing the factors facilitating and hindering the siting of controversial facilities, in particular the interim storage facility in Spain. It demonstrates that involving all stakeholders in the decision-making process should not be underestimated. In the case of Spain, all regional governments where there were candidate municipalities willing to host the centralised interim storage facility, publicly opposed to the siting of the facility. (author)

  16. Release of radionuclides following severe accident in interim storage facility. Source term determination

    International Nuclear Information System (INIS)

    Morandi, S.; Mariani, M.; Giacobbo, F.; Covini, R.

    2006-01-01

    Among the severe accidents that can cause the release of radionuclides from an interim storage facility, with a consequent relevant radiological impact on the population, there is the impact of an aircraft on the facility. In this work, a safety assessment analysis for the case of an aircraft crash into an interim storage facility is tackled. To this aim a methodology, based upon DOE, IAEA and NUREG standard procedures and upon conservative yet realistic hypothesis, has been developed in order to evaluate the total radioactivity, source term, released to the biosphere in consequence of the impact, without recurring to the use of complicated numerical codes. The procedure consists in the identification of the accidental scenarios, in the evaluation of the consequent damage to the building structures and to the waste packages and in the determination of the total release of radionuclides through the building-atmosphere interface. The methodology here developed has been applied to the case of an aircraft crash into an interim storage facility currently under design. Results show that in case of perforation followed by a fire incident the total released activity would be greater of some orders of magnitude with respect to the case of mere perforation. (author)

  17. Quantifying the benefit of wellbore leakage potential estimates for prioritizing long-term MVA well sampling at a CO2 storage site.

    Science.gov (United States)

    Azzolina, Nicholas A; Small, Mitchell J; Nakles, David V; Glazewski, Kyle A; Peck, Wesley D; Gorecki, Charles D; Bromhal, Grant S; Dilmore, Robert M

    2015-01-20

    This work uses probabilistic methods to simulate a hypothetical geologic CO2 storage site in a depleted oil and gas field, where the large number of legacy wells would make it cost-prohibitive to sample all wells for all measurements as part of the postinjection site care. Deep well leakage potential scores were assigned to the wells using a random subsample of 100 wells from a detailed study of 826 legacy wells that penetrate the basal Cambrian formation on the U.S. side of the U.S./Canadian border. Analytical solutions and Monte Carlo simulations were used to quantify the statistical power of selecting a leaking well. Power curves were developed as a function of (1) the number of leaking wells within the Area of Review; (2) the sampling design (random or judgmental, choosing first the wells with the highest deep leakage potential scores); (3) the number of wells included in the monitoring sampling plan; and (4) the relationship between a well’s leakage potential score and its relative probability of leakage. Cases where the deep well leakage potential scores are fully or partially informative of the relative leakage probability are compared to a noninformative base case in which leakage is equiprobable across all wells in the Area of Review. The results show that accurate prior knowledge about the probability of well leakage adds measurable value to the ability to detect a leaking well during the monitoring program, and that the loss in detection ability due to imperfect knowledge of the leakage probability can be quantified. This work underscores the importance of a data-driven, risk-based monitoring program that incorporates uncertainty quantification into long-term monitoring sampling plans at geologic CO2 storage sites.

  18. Long-term liquid storage and reproductive evaluation of an innovative boar semen extender (Formula12®) containing a non-reducing disaccharide and an enzymatic agent.

    Science.gov (United States)

    Bresciani, Carla; Bianchera, Annalisa; Bettini, Ruggero; Buschini, Annamaria; Marchi, Laura; Cabassi, Clotilde Silvia; Sabbioni, Alberto; Righi, Federico; Mazzoni, Claudio; Parmigiani, Enrico

    2017-05-01

    There are no reports of saccharolytic enzymes being used in the preparation of formulations for animal semen extenders. In the present study, the use of an innovative semen extender (Formula12 ® ) in the long-term liquid storage of boar semen at 17°C was evaluated. The formulation included use of a disaccharide (sucrose) as the energy source precursor coupled to an enzymatic agent (invertase). The innovative extender was evaluated and compared in vitro to a commercial extender (Vitasem LD ® ) for the following variables: Total Motility (TM), Forward Progressive Motility (FPM), sperm morphology, membrane integrity, acrosome integrity, and chromatin instability. Boar sperm diluted in Formula12 ® and stored for 12 days at 17°C maintained a commercially acceptable FPM (>70%). Using the results from the in vitro study, an AI field trial was performed. A total of 170 females were inseminated (135 with Formula12 ® and 35 with Vitasem LD ® ). The pregnancy rates were 97.8% compared with 91.4%, and the farrowing rates were 96.3% compared with 88.6% when Formula12 ® and Vitasem LD ® were used, respectively. The mean number of piglets born/sow were 14.92±0.46 compared with 13.83±0.70, and the number of piglets born alive/sow were 14.07±0.46 compared with 12.12±0.70 (Pextender allowed for meeting the metabolic requirements of boar sperm during storage at 17°C. It is suggested that there was a beneficial effect on fertilizing capacity of boar sperm in the female reproductive tract with use of these technologies. Copyright © 2017 Elsevier B.V. All rights reserved.

  19. Interim spent-fuel storage options at commercial nuclear power plants

    International Nuclear Information System (INIS)

    Thakkar, A.R.; Hylko, J.M.

    1991-01-01

    Although spent fuel can be stored safely in waterfilled pools at reactor sites, some utilities may not possess sufficient space for life-of-plant storage capability. In-pool storage capability may be increased by reracking assemblies, rod consolidation, double tiering spent-fuel racks, and by shipping spent fuel to other utility-owned facilities. Long-term on-site storage capability for spent fuel may be provided by installing (dry-type) metal casks, storage and transportation casks, concrete casks, horizontal concrete modules, modular concrete vaults, or by constructing additional (pool-type) storage installations. Experience to date has provided valuable information regarding dry-type or pool-type installations, cask handling and staffing requirements, security features, decommissioning activities, and radiological issues

  20. Requirements for a long-term safety certification for chemotoxic substances stored in a final storage facility for high radioactive and heat-generating radioactive waste in rock salt formations

    International Nuclear Information System (INIS)

    Tholen, M.; Hippler, J.; Herzog, C.

    2007-01-01

    Within the scope of a project funded by the German Federal Ministry of Economics and Technology (Bundesministerium fuer Wirtschaft und Technologie, BMWi), a safety certification concept for a future permanent final storage for high radioactive and heat-generating radioactive waste (HAW disposal facility) in rock salt formations is being prepared. For a reference concept, compliance with safety requirements in regard to operational safety as well as radiological and non-radiological protection objectives related to long-term safety, including ground water protection, will be evaluated. This paper deals with the requirements for a long-term safety certification for the purpose of protecting ground water from chemotoxic substances. In particular, longterm safety certifications for the permanent disposal of radioactive waste in a HAW disposal facility in rock salt formations and for the dumping of hazardous waste in underground storage facilities in rock salt formations are first discussed, followed by an evaluation as to whether these methods can be applied to the long-term safety certification for chemotoxic substances. The authors find it advisable to apply the long-term safety certification for underground storage facilities to the long-term safety certification for chemotoxic substances stored in a HAW disposal facility in rock salt formations. In conclusion, a corresponding certification concept is introduced. (orig.)

  1. Czech interim spent fuel storage facility: operation experience, inspections and future plans

    International Nuclear Information System (INIS)

    Fajman, V.; Bartak, L.; Coufal, J.; Brzobohaty, K.; Kuba, S.

    1999-01-01

    The paper describes the situation in the spent fuel management in the Czech Republic. The interim Spent Fuel Storage Facility (ISFSF) at Dukovany, which was commissioned in January 1997 and is using dual transport and storage CASTOR - 440/84 casks, is briefly described. The authors deal with their experience in operating and inspecting the ISFSF Dukovany. The structure of the basic safety document 'Limits and Conditions of Normal Operation' is also mentioned, including the experience of the performance. The inspection activities focused on permanent checking of the leak tightness of the CASTOR 440/84 casks, the maximum cask temperature and inspections monitoring both the neutron and gamma dose rate as well as the surface contamination. The results of the inspections are mentioned in the presentation as well. The operator's experience with re-opening partly loaded and already dried CASTOR-440/84 cask, after its transport from NPP Jaslovske Bohunice to the NPP Dukovany is also described. The paper introduces briefly the concept of future spent fuel storage both from the NPP Dukovany and the NPP Temelin, as prepared by the CEZ. The preparatory work for the Central Interim Spent Nuclear Fuel Storage Facility (CISFSF) in the Czech Republic and the information concerning the planned storage technology for this facility is discussed in the paper as well. The authors describe the site selection process and the preparatory steps concerning new spent fuel facility construction including the Environmental Impact Assessment studies. (author)

  2. COMPLETION OF THE FIRST INTEGRATED SPENT NUCLEAR FUEL TRANSSHIPMENT/INTERIM STORAGE FACILITY IN NW RUSSIA

    International Nuclear Information System (INIS)

    Dyer, R.S.; Barnes, E.; Snipes, R.L.; Hoeibraaten, S.; Gran, H.C.; Foshaug, E.; Godunov, V.

    2003-01-01

    Northwest and Far East Russia contain large quantities of unsecured spent nuclear fuel (SNF) from decommissioned submarines that potentially threaten the fragile environments of the surrounding Arctic and North Pacific regions. The majority of the SNF from the Russian Navy, including that from decommissioned nuclear submarines, is currently stored in on-shore and floating storage facilities. Some of the SNF is damaged and stored in an unstable condition. Existing Russian transport infrastructure and reprocessing facilities cannot meet the requirements for moving and reprocessing this amount of fuel. Additional interim storage capacity is required. Most of the existing storage facilities being used in Northwest Russia do not meet health and safety, and physical security requirements. The United States and Norway are currently providing assistance to the Russian Federation (RF) in developing systems for managing these wastes. If these wastes are not properly managed, they could release significant concentrations of radioactivity to these sensitive environments and could become serious global environmental and physical security issues. There are currently three closely-linked trilateral cooperative projects: development of a prototype dual-purpose transport and storage cask for SNF, a cask transshipment interim storage facility, and a fuel drying and cask de-watering system. The prototype cask has been fabricated, successfully tested, and certified. Serial production is now underway in Russia. In addition, the U.S. and Russia are working together to improve the management strategy for nuclear submarine reactor compartments after SNF removal

  3. Review of the seismic risk in the design of civil engineering of nuclear installations excepted the long term storage of radioactive wastes; Prise en compte du risque sismique a la conception des ouvrages de genie civil d'installations nucleaires de base a l'exception des stockages a long terme des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This guide aims to define, for the nuclear installations excepted the long term storage of radioactive wastes, from site data, the design specifications of earthquake resistant civil engineering and the possible methods for: the determination of the seismic response of the buildings, taking into account the interactions with the materials and the evaluation of the associated strains to size the installation; the determination of seismic displacements to be considered to size the materials. (A.L.B.)

  4. Long-term collections

    CERN Multimedia

    Collectes à long terme

    2007-01-01

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

  5. USING POLYMERIC HYDROGEN GETTERS TO PREVENT COMBUSTIBLE ATMOSPHERES DURING INTERIM SAFE STORAGE OF PLUTONIUM OXIDE

    International Nuclear Information System (INIS)

    Woodsmall, T

    2007-01-01

    Nuclear Materials Management (NMM) of WSRC has recently installed the capability to perform both non-destructive and destructive examination of 3013 containers of Pu oxide in accordance with DOE-STD-3013. The containers will be opened and the oxide will be sampled for analysis. The remaining bulk oxide must then be safely stored in a non-3013-compliant configuration. Available processing equipment and controls cannot prevent the oxide from adsorbing moisture during this process. Subsequent radiolysis of moisture during storage may generate combustible quantities of gases while waiting final processing, and satisfying DOE Interim Safe Storage Criteria (ISSC) would require that storage containers be vented at impractical frequencies. With support from an independent National Laboratory, WSRC/NMM has demonstrated that a commercial hydrogen getter material will effectively prevent the accumulation of combustible gas concentrations. A project overview, including storage requirements and strategies, as well as getter technology, current test results, and anticipated future developments will be addressed

  6. Hanford Tank Farm interim storage phase probabilistic risk assessment outline

    International Nuclear Information System (INIS)

    1994-01-01

    This report is the second in a series examining the risks for the high level waste (HLW) storage facilities at the Hanford Site. The first phase of the HTF PSA effort addressed risks from Tank 101-SY, only. Tank 101-SY was selected as the initial focus of the PSA because of its propensity to periodically release (burp) a mixture of flammable and toxic gases. This report expands the evaluation of Tank 101-SY to all 177 storage tanks. The 177 tanks are arranged into 18 farms and contain the HLW accumulated over 50 years of weapons material production work. A centerpiece of the remediation activity is the effort toward developing a permanent method for disposing of the HLW tank's highly radioactive contents. One approach to risk based prioritization is to perform a PSA for the whole HLW tank farm complex to identify the highest risk tanks so that remediation planners and managers will have a more rational basis for allocating limited funds to the more critical areas. Section 3 presents the qualitative identification of generic initiators that could threaten to produce releases from one or more tanks. In section 4 a detailed accident sequence model is developed for each initiating event group. Section 5 defines the release categories to which the scenarios are assigned in the accident sequence model and presents analyses of the airborne and liquid source terms resulting from different release scenarios. The conditional consequences measured by worker or public exposure to radionuclides or hazardous chemicals and economic costs of cleanup and repair are analyzed in section 6. The results from all the previous sections are integrated to produce unconditional risk curves in frequency of exceedance format

  7. Hanford Tank Farm interim storage phase probabilistic risk assessment outline

    Energy Technology Data Exchange (ETDEWEB)

    1994-05-19

    This report is the second in a series examining the risks for the high level waste (HLW) storage facilities at the Hanford Site. The first phase of the HTF PSA effort addressed risks from Tank 101-SY, only. Tank 101-SY was selected as the initial focus of the PSA because of its propensity to periodically release (burp) a mixture of flammable and toxic gases. This report expands the evaluation of Tank 101-SY to all 177 storage tanks. The 177 tanks are arranged into 18 farms and contain the HLW accumulated over 50 years of weapons material production work. A centerpiece of the remediation activity is the effort toward developing a permanent method for disposing of the HLW tank`s highly radioactive contents. One approach to risk based prioritization is to perform a PSA for the whole HLW tank farm complex to identify the highest risk tanks so that remediation planners and managers will have a more rational basis for allocating limited funds to the more critical areas. Section 3 presents the qualitative identification of generic initiators that could threaten to produce releases from one or more tanks. In section 4 a detailed accident sequence model is developed for each initiating event group. Section 5 defines the release categories to which the scenarios are assigned in the accident sequence model and presents analyses of the airborne and liquid source terms resulting from different release scenarios. The conditional consequences measured by worker or public exposure to radionuclides or hazardous chemicals and economic costs of cleanup and repair are analyzed in section 6. The results from all the previous sections are integrated to produce unconditional risk curves in frequency of exceedance format.

  8. Effectiveness of interim remedial actions at the Niagara Falls Storage Site

    International Nuclear Information System (INIS)

    Devgun, J.S.; Beskid, N.J.; Seay, W.M.; McNamee, E.

    1990-01-01

    There are 190,000 m 3 of contaminated soils, wastes, and residues stored at the Niagara Falls Storage Site (NFSS). The residues have a volume of 18,000 m 3 and contain about 1,930 Ci of 226 Ra, which accounts for most of the radioactivity. Since 1980, actions have been taken to minimize potential radiological risks and prevent radionuclide migration. Interim actions included capping vents, sealing pipes, relocating the perimeter fence (to limit radon risk), transferring and consolidating wastes, upgrading storage buildings, constructing a clay cutoff wall (to limit potential ground-water transport of contaminants), treating and releasing contaminated water, using a synthetic liner, and using an interim clay cap. An interim waste containment facility was completed in 1986. Environmental monitoring showed a decrease in radon concentrations and in external gamma radiation from 1982 to 1986; levels have been stable since 1986. Uranium and radium concentrations in surface water have decreased; very low concentrations have been detected in stream sediments, and concentrations in ground water have remained stable. Recent monitoring showed that NFSS is in compliance with the U.S. Department of Energy's (DOE's) radiation protection standards

  9. Long term aspects of uranium tailings management

    International Nuclear Information System (INIS)

    Bragg, K.

    1980-05-01

    This paper sets out the background issues which lead to the development of interim close-out criteria for uranium mill tailings. It places the current state-of-the-art for tailings management into both a national and international perspective and shows why such interim criteria are needed now. There are seven specific criteria proposed dealing with the need to have: passive barriers, limits on surface water recharge, durable systems, long term performance guarantees, limits to access, controls on water and airborne releases and finally to have a knowledge of exposure pathways. This paper is intended to serve as a focus for subsequent discussions with all concerned parties. (auth)

  10. Cost comparisons of wet and dry interim storage facilities for PWR spent nuclear fuel in Korea

    International Nuclear Information System (INIS)

    Cho, Chun-Hyung; Kim, Tae-Man; Seong, Ki-Yeoul; Kim, Hyung-Jin; Yoon, Jeong-Hyoun

    2011-01-01

    Research highlights: → We compare the costs of wet and dry interim storage facilities for PWR spent fuel. → We use the parametric method and quotations to deduce unknown cost items. → Net present values and levelized unit prices are calculated for cost comparisons. → A system price is the most decisive factor in cost comparisons. - Abstract: As a part of an effort to determine the ideal storage solution for pressurized water reactor (PWR) spent nuclear fuel, a cost assessment was performed to better quantify the competitiveness of several storage types. Several storage solutions were chosen for comparison, including three dry storage concepts and a wet storage concept. The net present value (NPV) and the levelized unit cost (LUC) of each solution were calculated, taking into consideration established scenarios and facility size. Wet storage was calculated to be the most expensive solution for a 1700 MTU facility, and metal cask storage marked the highest cost for a 5000 MTU facility. Sensitivity analyses on discount rate, metal cask price, operation and maintenance cost, and facility size revealed that the system price is the most decisive factor affecting competitiveness among the storage types.

  11. Acceptance criteria for interim dry storage of aluminum-clad fuels

    International Nuclear Information System (INIS)

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

    1994-01-01

    Direct repository disposal of foreign and domestic research reactor fuels owned by the United States Department of Energy is an alternative to reprocessing (together with vitrification of the high level waste and storage in an engineered barrier) for ultimate disposition. Neither the storage systems nor the requirements and specifications for acceptable forms for direct repository disposal have been developed; therefore, an interim storage strategy is needed to safely store these fuels. Dry storage (within identified limits) of the fuels received from wet-basin storage would avoid excessive degradation to assure post-storage handleability, a full range of ultimate disposal options, criticality safety, and provide for maintaining confinement by the fuel/clad system. Dry storage requirements and technologies for US commercial fuels, specifically zircaloy-clad fuels under inert cover gas, are well established. Dry storage requirements and technologies for a system with a design life of 40 years for dry storage of aluminum-clad foreign and domestic research reactor fuels are being developed by various groups within programs sponsored by the DOE

  12. Cost comparisons of wet and dry interim storage facilities for PWR spent nuclear fuel in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Chun-Hyung, E-mail: skycho@krmc.or.kr [Korea Radioactive Waste Management Corporation, 1045 Daedeokdaero, Yuseong-Gu, Daejeon 305-353 (Korea, Republic of); Kim, Tae-Man; Seong, Ki-Yeoul; Kim, Hyung-Jin; Yoon, Jeong-Hyoun [Korea Radioactive Waste Management Corporation, 1045 Daedeokdaero, Yuseong-Gu, Daejeon 305-353 (Korea, Republic of)

    2011-05-15

    Research highlights: > We compare the costs of wet and dry interim storage facilities for PWR spent fuel. > We use the parametric method and quotations to deduce unknown cost items. > Net present values and levelized unit prices are calculated for cost comparisons. > A system price is the most decisive factor in cost comparisons. - Abstract: As a part of an effort to determine the ideal storage solution for pressurized water reactor (PWR) spent nuclear fuel, a cost assessment was performed to better quantify the competitiveness of several storage types. Several storage solutions were chosen for comparison, including three dry storage concepts and a wet storage concept. The net present value (NPV) and the levelized unit cost (LUC) of each solution were calculated, taking into consideration established scenarios and facility size. Wet storage was calculated to be the most expensive solution for a 1700 MTU facility, and metal cask storage marked the highest cost for a 5000 MTU facility. Sensitivity analyses on discount rate, metal cask price, operation and maintenance cost, and facility size revealed that the system price is the most decisive factor affecting competitiveness among the storage types.

  13. Assessment of alternatives for long-term management of uranium ore residues and contaminated soils located at DOE's Niagara Falls Storage Site

    International Nuclear Information System (INIS)

    Merry-Libby, P.

    1985-01-01

    About 11,000 m 3 of uranium ore residues and 180,000 m 3 of slightly contaminated soils (wastes) are consolidated within a diked containment area at the Niagara Falls Storage Site located about 30 km north of Buffalo, New York. The residues account for less than 6% of the total volume of contaminated materials but almost 99% of the radioactivity. The average radium-226 concentration in the residues is 67,000 pCi/g. The US Department of Energy is considering several alternatives for long-term management of the wastes and residues, including: improvement of the containment at NFSS, modification of the form of the residues, management of the residues separately from the wastes, management of the wastes and residues at another humid site (Oak Ridge, Tennessee) or an arid site (Hanford, Washington), and dispersal of the wastes in the ocean. Potential radiological risks associated with implementation of any of the alternatives are expected to be smaller than the nonradiological risks of occupational and transportation-related injuries and deaths. Dispersal of the slightly contaminated wastes in the ocean is not expected to result in any significant radiological risk to humans. The residues and wastes will remain hazardous for thousands of years. After controls cease, the radioactive materials will eventually be dispersed in the environment. Loss of the earthen covers over the buried materials is predicted to occur from several hundred to more than two million years, depending primarily on the use of the land surface. Groundwater will eventually be contaminated in all alternatives; however, the groundwater pathway is relatively insignificant with respect to radiological risks to the general population. 2 references, 2 figures, 6 tables

  14. Effect of freezing, long-term storage and microwave thawing on the stability of a mixture of diclofenac and sodium bicarbonate in glucose 5% polyolefin bags.

    Science.gov (United States)

    François, J-H; Hecq, J-D; Vanbeckbergen, D; Jamart, J; Galanti, L

    2009-11-01

    Preparation in advance of intravenous solution could be efficient to improve quality assurance, security, time management and cost saving of drug delivery. The aim of this study was to investigate the stability of a mixture of diclofenac 75 mg/100 ml and sodium bicarbonate 42 mg/100 ml in 5% glucose polyolefin bags after freezing, long-term storage, and microwave thawing. The stability of five polyolefin bags containing approximately 75 mg/100ml of diclofenac and 42 mg/100ml of sodium bicarbonate in 5% glucose prepared under aseptic conditions was studied after freezing for 2 months at -20 degrees C, thawing in a microwave oven with a validated cycle, and stored at 5 + or - 3 degrees C. Diclofenac concentrations were measured by high-pressure liquid chromatography using a reversed-phase column, a mobile phase consisting of 40% of acetonitrile (v/v) in KH(2)PO(4) buffer 0.02 M, pH 8.40 + or - 0.05, and UV detection at 276.0 nm. Visual inspection, microscope observation, spectrophotometric measurements and pH measurement were also performed. No colour change or precipitation occurred in the preparations. No microaggregate was observed with optical microscopy or revealed by a change of absorbance. Based on a shelf-life of 90% residual potency, diclofenac was stable for at least 30 days after freezing and microwave thawing, period where 95% lower confidence limit of the concentration-time profile remained superior to 90% of the initial concentration. During this period, the pH values of drug solutions have not been altered. Within these limits, diclofenac in 5% glucose infusion may be prepared and frozen in advance by a centralized intravenous admixture service, then thawed before use in clinical units.

  15. Annex D 200 Area Interim Storage Area Final Safety Analysis Report Volume 5 (FSAR) (Section 1 and 2)

    International Nuclear Information System (INIS)

    CARRELL, R.D.

    2003-01-01

    The 200 Area Interim Storage Area (200 Area ISA) at the Hanford Site provides for the interim storage of non-defense reactor spent nuclear fuel (SNF) housed in aboveground dry cask storage systems. The 200 Area ISA is a relatively simple facility consisting of a boundary fence with gates, perimeter lighting, and concrete and gravel pads on which to place the dry storage casks. The fence supports safeguards and security and establishes a radiation protection buffer zone. The 200 Area ISA is nominally 200,000 ft 2 and is located west of the Canister Storage Building (CSB). Interim storage at the 200 Area ISA is intended for a period of up to 40 years until the materials are shipped offsite to a disposal facility. This Final Safety Analysis Report (FSAR) does not address removal from storage or shipment from the 200 Area ISA. Three different SNF types contained in three different dry cask storage systems are to be stored at the 200 Area ISA, as follows: (1) Fast Flux Test Facility (FFTF) Fuel--Fifty-three interim storage casks (ISC), each holding a core component container (CCC), will be used to store the FFTF SNF currently in the 400 Area. (2) Neutron Radiography Facility (NRF)TRIGA--One Rad-Vault container stores two DOT-6M 3 containers and six NRF TRIGA casks. (3) Commercial Light Water Reactor Fuel--Six International Standards Organization (ISO) containers, each holding a NAC-1 cask with an inner commercial light water reactor (LWR) canister, are used for storing commercial LWR SNF from the 300 Area. An aboveground dry cask storage location is necessary for the spent fuel because the current storage facilities are being shut down and deactivated. The spent fuel is being transferred to interim storage because there is no permanent repository storage currently available

  16. Long-Term Outcomes of Laser Prostatectomy for Storage Symptoms: Comparison of Serial 5-Year Followup Data between High Performance System Photoselective Vaporization and Holmium Laser Enucleation of the Prostate.

    Science.gov (United States)

    Cho, Min Chul; Song, Won Hoon; Park, Juhyun; Cho, Sung Yong; Jeong, Hyeon; Oh, Seung-June; Paick, Jae-Seung; Son, Hwancheol

    2018-01-09

    We compared long-term storage symptom outcomes between photoselective laser vaporization of the prostate with a 120 W high performance system and holmium laser enucleation of the prostate. We also determined factors influencing postoperative improvement of storage symptoms in the long term. Included in our study were 266 men, including 165 treated with prostate photoselective laser vaporization using a 120 W high performance system and 101 treated with holmium laser enucleation of the prostate, on whom 60-month followup data were available. Outcomes were assessed serially 6, 12, 24, 36, 48 and 60 months postoperatively using the International Prostate Symptom Score, uroflowmetry and the serum prostate specific antigen level. Postoperative improvement in storage symptoms was defined as a 50% or greater reduction in the subtotal storage symptom score at each followup visit after surgery compared to baseline. Improvements in frequency, urgency, nocturia, subtotal storage symptom scores and the quality of life index were maintained up to 60 months after photoselective laser vaporization or holmium laser enucleation of the prostate. There was no difference in the degree of improvement in storage symptoms or the percent of patients with postoperative improvement in storage symptoms between the 2 groups throughout the long-term followup. However, the holmium laser group showed greater improvement in voiding symptoms and quality of life than the laser vaporization group. On logistic regression analysis a higher baseline subtotal storage symptom score and a higher BOOI (Bladder Outlet Obstruction Index) were the factors influencing the improvement in storage symptoms 5 years after prostate photoselective laser vaporization or holmium laser enucleation. Our serial followup data suggest that storage symptom improvement was maintained throughout the long-term postoperative period for prostate photoselective laser vaporization with a 120 W high performance system and holmium

  17. Criteria for Corrosion Protection of Aluminum-Clad Spent Nuclear Fuel in Interim Wet Storage

    International Nuclear Information System (INIS)

    Howell, J.P.

    1999-01-01

    Storage of aluminum-clad spent nuclear fuel at the Savannah River Site (SRS) and other locations in the U. S. and around the world has been a concern over the past decade because of the long time interim storage requirements in water. Pitting corrosion of production aluminum-clad fuel in the early 1990''s at SRS was attributed to less than optimum quality water and corrective action taken has resulted in no new pitting since 1994. The knowledge gained from the corrosion surveillance testing and other investigations at SRS over the past 8 years has provided an insight into factors affecting the corrosion of aluminum in relatively high purity water. This paper reviews some of the early corrosion issues related to aluminum-clad spent fuel at SRS, including fundamentals for corrosion of aluminum alloys. It updates and summarizes the corrosion surveillance activities supporting the future storage of over 15,000 research reactor fuel assemblies from countries over the world during the next 15-20 years. Criteria are presented for providing corrosion protection for aluminum-clad spent fuel in interim storage during the next few decades while plans are developed for a more permanent disposition

  18. Factors affecting the sporulation capacity during long-term storage of the aphid-pathogenic fungus Pandora neoaphidis grown on broomcorn millet.

    Science.gov (United States)

    Feng, Ming-Guang; Hua, Li

    2005-04-15

    Aphid-pathogenic fungus, Pandora neoaphidis, grown on broomcorn millet possesses greater sporulation capacity (C(s)) than aphid cadavers. The most sporulating cultures (32.0x10(4) spores millet(-1) grain) with water content (C(w)) of 48.7% were prepared by incubation at 20 degrees C for 15 days and used to study the effect of temperature and humidity on C(s) during long-term storage. Cultures were sealed with paper to retain ambient humidity, with parafilm for saturated humidity, or kept in 85% and 98% RH chambers. The C(w) and C(s) were monitored during 200-day storage at 5-20 degrees C. The paper-sealed cultures at 5 degrees C, associated with 21-25% of C(w), were best preserved and their 120-day C(s) was similar to that of the fresh cadavers. Consistently or variably high RH at 5 degrees C resulted in significantly higher C(w) and lower C(s) despite longer viability. The regimes at 10 degrees C preserved the cultures for 40 days. The observations fit well to the logistic model C(s)=35.28/{1+exp[-2.36+(-0.003C(w)+0.001C(w)T)t]} (r(2)=0.95) for all regimes of temperature (T) or C(s)=35.55/[1+exp(-2.33+0.001C(w)t)] (r(2)=0.93) at 5 degrees C only. The rate of decline of C(s) of -0.003C(w)+0.001C(w)T or 0.001 C(w) over days (t) highlights the primary effect of C(w). The daily C(s)-decline rates obtained for the best-stored cultures and air-dried cadavers stored at 5 degrees C were surprisingly identical. The results suggest a possible cheap method for preparing and storing large quantities of P. neoaphiodis inocula.

  19. Interim restorations.

    Science.gov (United States)

    Gratton, David G; Aquilino, Steven A

    2004-04-01

    Interim restorations are a critical component of fixed prosthodontic treatment, biologically and biomechanically. Interim restoration serves an important diagnostic role as a functional and esthetic try-in and as a blueprint for the design of the definitive prosthesis. When selecting materials for any interim restoration, clinicians must consider physical properties, handling properties, patient acceptance, and material cost. Although no single material meets all the requirements and material classification alone of a given product is not a predictor of clinical performance, bis-acryl materials are typically best suited to single-unit restorations, and poly(methylmethacrylate) interim materials are generally ideal for multi-unit, complex, long-term, interim fixed prostheses. As with most dental procedures, the technique used for fabrication has a greater effect on the final result than the specific material chosen.

  20. Cna 1 spent fuel element interim dry storage system thermal analysis

    International Nuclear Information System (INIS)

    Hilal, R. E; Garcia, J. C; Delmastro, D. F

    2006-01-01

    At the moment, the Atucha I Nuclear Power Plant (Cnea-I) located in the city of Lima, has enough room to store its spent fuel (Sf) in their two pools spent fuel until about 2015.In case of life extension a spend fuel element interim dry storage system is needed.Nucleolectrica Argentina S.A. (N A-S A) and the Comision Nacional de Energia Atomica (Cnea), have proposed different interim dry storage systems.These systems have to be evaluated in order to choose one of them.The present work's objective is the thermal analysis of one dry storage alternative for the Sf element of Cna 1.In this work a simple model was developed and used to perform the thermal calculations corresponding to the system proposed by Cnea.This system considers the store of sealed containers with 37 spent fuels in concrete modules.Each one of the containers is filled in the pool houses and transported to the module in a transference cask with lead walls.Fulfill the maximum cladding temperature requirement ( [es

  1. Maywood Interim Storage Site environmental report for calendar year 1989, Maywood, New Jersey

    International Nuclear Information System (INIS)

    1990-05-01

    The environmental monitoring program, which began in 1984, was continued in 1989 at the Maywood Interim Storage Site (MISS), a US Department of Energy (DOE) facility located in the Borough of Maywood and the Township of Rochelle Park, New Jersey. MISS is currently used for storage of soils contaminated with low-level radioactivity. MISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to identify and decontaminate or otherwise control sites where residual radioactive materials are present. The monitoring program at MISS measures thoron and radon concentrations in air; external gamma radiation levels; and thorium, uranium, and radium concentrations in surface water, groundwater, and sediment. Additionally, several nonradiological parameters are measured in groundwater. The radiation dose was calculated for a hypothetical maximally exposed individual to verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and to assess its potential effects on public health. This report presents the results of the environmental monitoring program conducted at the US Department of Energy's (DOE) Maywood Interim Storage Site (MISS) during calendar year 1989. Environmental monitoring began at MISS in 1984. 19 refs., 23 figs., 14 tabs

  2. Benchmarking of MCNP for calculating dose rates at an interim storage facility for nuclear waste.

    Science.gov (United States)

    Heuel-Fabianek, Burkhard; Hille, Ralf

    2005-01-01

    During the operation of research facilities at Research Centre Jülich, Germany, nuclear waste is stored in drums and other vessels in an interim storage building on-site, which has a concrete shielding at the side walls. Owing to the lack of a well-defined source, measured gamma spectra were unfolded to determine the photon flux on the surface of the containers. The dose rate simulation, including the effects of skyshine, using the Monte Carlo transport code MCNP is compared with the measured dosimetric data at some locations in the vicinity of the interim storage building. The MCNP data for direct radiation confirm the data calculated using a point-kernel method. However, a comparison of the modelled dose rates for direct radiation and skyshine with the measured data demonstrate the need for a more precise definition of the source. Both the measured and the modelled dose rates verified the fact that the legal limits (<1 mSv a(-1)) are met in the area outside the perimeter fence of the storage building to which members of the public have access. Using container surface data (gamma spectra) to define the source may be a useful tool for practical calculations and additionally for benchmarking of computer codes if the discussed critical aspects with respect to the source can be addressed adequately.

  3. Maywood Interim Storage Site environmental report for calendar year 1989, Maywood, New Jersey

    Energy Technology Data Exchange (ETDEWEB)

    1990-05-01

    The environmental monitoring program, which began in 1984, was continued in 1989 at the Maywood Interim Storage Site (MISS), a US Department of Energy (DOE) facility located in the Borough of Maywood and the Township of Rochelle Park, New Jersey. MISS is currently used for storage of soils contaminated with low-level radioactivity. MISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to identify and decontaminate or otherwise control sites where residual radioactive materials are present. The monitoring program at MISS measures thoron and radon concentrations in air; external gamma radiation levels; and thorium, uranium, and radium concentrations in surface water, groundwater, and sediment. Additionally, several nonradiological parameters are measured in groundwater. The radiation dose was calculated for a hypothetical maximally exposed individual to verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and to assess its potential effects on public health. This report presents the results of the environmental monitoring program conducted at the US Department of Energy's (DOE) Maywood Interim Storage Site (MISS) during calendar year 1989. Environmental monitoring began at MISS in 1984. 19 refs., 23 figs., 14 tabs.

  4. Analysis of the interim safe storage of reactors at the Hanford site

    International Nuclear Information System (INIS)

    Wang Hailiang

    2014-01-01

    The nine production reactors, i.e. B, C, D, DR, F, H, KE, KW and N, at the Hanford site are all water-cooled and graphite-moderated reactors with natural uranium fuel. In 1993, the U.S. Department of Energy (DOE) decided to put eight production reactors (except for B) into Interim Safe Storage (ISS) for 75 years followed by deferred one-piece removal. Reactor B will remain as a national historical landmark. By the end of 2013, six reactors C, F, D, DR, H and N had been successfully put into the ISS. Reactors KE and KW will be put into the ISS in the coming years. Taking reactor C as an example, this paper mainly talks about how to put the production reactors in the Interim Safe Storage, e.g. how to make site preparation, how to construct the safe storage enclosure (SSE) and how to perform surveillance and maintenance during the ISS period, etc. (authors)

  5. Long-term behaviour of waste-forms in the near-field environment of a deep underground storage site, overview

    International Nuclear Information System (INIS)

    Toulhoat, P.; Lassabatere, Th.; Galle, Ch.; Cranga, M.; Trotignon, L.; Maillard, S.; Iracane, D.

    1997-01-01

    CEA (French Atomic Energy Commission) is responsible for the achievement of high activity and/or long life waste conditioning processes. Various waste-forms are used (glass, bitumen, etc...). ANDRA (French National Agency for Nuclear Waste Management) has to integrate the long-term durability of such waste-forms in the conception of a deep disposal and the assessment of its long-term confinement performances. The influence of near-field and of the boundary conditions imposed by the far-field on the long-term evolution is being more and more documented. Transport properties and reactivity of silica in the near field is one of the best examples of such effects. A coherent framework with relevant successive events (site re-saturation, chemical evolution of the engineered barrier, overpack corrosion) and a thorough analysis of hierarchized couplings are necessary to evaluate the long term durability of waste-form, and finally, to deliver a near-field-integrated source-term of radionuclides versus lime. We present hereafter some preliminary results obtained in the framework of the CEA 'C3P' project - long-term behaviour of waste-forms in their near-field environment. (authors)

  6. Uses of the waste heat from the interim fuel storage facility

    International Nuclear Information System (INIS)

    Wehrum, A.

    It was the objective of this study to investigate the possibilities of a convenient use of the waste heat from the designed interim fuel storage at Ahaus. In this sense the following possibilities have been investigated: district heating, heat for industrial processes, fish-production, green house-heating, production of methane from original waste, agrotherm (agricultur field heating). It has been shown, that an economical behaviour for nearly all variations is not given without the financial help of the government, because of the high costs for heat transport and out-put. The most economical project is the intensive fish production plant. (orig.) [de

  7. Thermal analysis of the unloading cell of the Spanish centralized interim storage facility (CISF)

    International Nuclear Information System (INIS)

    Perez Dominguez, J. R.; Perez Vara, R.; Huelamo Martinez, E.

    2016-01-01

    This article deals with the thermal analysis performed for the Untoading Cell of Spain Centralized Interim Storage Facility, CISF (ATC, in Spanish). The analyses are done using computational fluid dynamics (CFD) simulation, with the aim of obtaining the air flow required to remove the residual heat of the elements stored in the cell. Compliance with the admissible heat limits is checked with the results obtained in the various operation and accident modes. The calculation model is flexible enough to allow carrying out a number of sensitivity analyses with the different parameters involved in the process. (Author)

  8. 226Ra out of use therapeutic needles and tubes interim storage

    International Nuclear Information System (INIS)

    Pavlovic, R.; Plecas, I.; Maksic, R.; Pavlovic, S.; Vukovic, S.

    1999-01-01

    When the main producers stopped production of radium in the 1960s, the total quantity of radium produced by the main refiners was estimated to be a few kg. Continuous progress concerning the knowledge of hazards associated with the use of a radioactive material, and the characteristics of most of the devices containing radium, calls for a well planned and carefully executed collection and ongoing management of those items under the direction of responsible authorities. Some aspects of the related to the packaging and interim storage of spent radium therapeutic sources are presented in this paper. (author)

  9. Environmental Impact Statement. March 2011. Interim storage, encapsulation and final disposal of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    2011-07-01

    An Environmental Impact Statement (EIS) shall be prepared and submitted along with applications for permissibility and a licence under the Environmental Code and a licence under the Nuclear Activities Act for new nuclear facilities. This Environmental Impact Statement has been prepared by Svensk Kaernbraenslehantering AB (the Swedish Nuclear Fuel and Waste Management Co, SKB) to be included in the licence applications for continued operation of Clab (central interim storage facility for spent nuclear fuel) in Simpevarp in Oskarshamn Municipality and construction and operation of facilities for encapsulation (integrated with Clab) and final disposal of spent nuclear fuel in Forsmark in Oesthammar Municipality

  10. Environmental Impact Statement. March 2011. Interim storage, encapsulation and final disposal of spent nuclear fuel

    International Nuclear Information System (INIS)

    2011-01-01

    An Environmental Impact Statement (EIS) shall be prepared and submitted along with applications for permissibility and a licence under the Environmental Code and a licence under the Nuclear Activities Act for new nuclear facilities. This Environmental Impact Statement has been prepared by Svensk Kaernbraenslehantering AB (the Swedish Nuclear Fuel and Waste Management Co, SKB) to be included in the licence applications for continued operation of Clab (central interim storage facility for spent nuclear fuel) in Simpevarp in Oskarshamn Municipality and construction and operation of facilities for encapsulation (integrated with Clab) and final disposal of spent nuclear fuel in Forsmark in Oesthammar Municipality

  11. An assessment of the potentials of nuclear power and carbon capture and storage in the long-term global warming mitigation options based on Asian Modeling Exercise scenarios

    International Nuclear Information System (INIS)

    Mori, Shunsuke

    2012-01-01

    This paper presents an evaluation of global warming mitigation options based on scenarios from the Asian Modeling Exercise. Using an extended version of the integrated assessment model MARIA-23 (Multiregional Approach for Resource and Industry Allocation), we analyze nuclear fuel recycling options, carbon capture and storage technologies (CCS), and biomass utilization. To assess the potential implications of decreased social acceptance of nuclear power in the wake of the Fukushima nuclear accident, additional scenarios including a nuclear power expansion limitation, are analyzed. We also evaluate MARIA-23 model simulation estimates of long-term contributions and interrelationships among nuclear power, biomass, and CCS. Finally, potential costs of nuclear limitation under carbon control policies are assessed. The simulation results in this paper suggest the following: (1) under the reference scenario, global GDP losses in climate limitation scenarios range from 1.3% per year to 3.9% per year in 2060, rising to between 3.5% per year and 4.5% per year in 2100; (2) the use of nuclear fuel reprocessing technologies increase rapidly in all carbon control policy scenarios; (3) under a scenario where the price of CO 2 is $30 and nuclear power expansion is strictly limited, GDP losses increase significantly—from 4.5% per year to 6.4% per year by 2100; (4) nuclear power and CCS are substitute mitigation technologies. With nuclear power technology available CCS deployment reaches approximately 15,000 Mt-CO 2 per year by 2010; without a nuclear power option, CCS deployment rises to more than 80,000 Mt-CO 2 per year; and (5) biomass utilization cannot fully compensate for limitations to nuclear power expansion in policy scenarios. In addition to examining the role of these three technologies on global scales, we report results for several major Asian regions, namely Japan, China, and India. China tends to deploy nuclear power (if available) in response to rapidly growing

  12. Long-Term Collections

    C