WorldWideScience

Sample records for tes retrievals reprocessed

  1. TES ammonia retrieval strategy and global observations of the spatial and seasonal variability of ammonia

    Directory of Open Access Journals (Sweden)

    M. W. Shephard

    2011-10-01

    Full Text Available Presently only limited sets of tropospheric ammonia (NH3 measurements in the Earth's atmosphere have been reported from satellite and surface station measurements, despite the well-documented negative impact of NH3 on the environment and human health. Presented here is a detailed description of the satellite retrieval strategy and analysis for the Tropospheric Emission Spectrometer (TES using simulations and measurements. These results show that: (i the level of detectability for a representative boundary layer TES NH3 mixing ratio value is ~0.4 ppbv, which typically corresponds to a profile that contains a maximum level value of ~1 ppbv; (ii TES NH3 retrievals generally provide at most one degree of freedom for signal (DOFS, with peak sensitivity between 700 and 900 mbar; (iii TES NH3 retrievals show significant spatial and seasonal variability of NH3 globally; (iv initial comparisons of TES observations with GEOS-CHEM estimates show TES values being higher overall. Important differences and similarities between modeled and observed seasonal and spatial trends are noted, with discrepancies indicating areas where the timing and magnitude of modeled NH3 emissions from agricultural sources, and to lesser extent biomass burning sources, need further study.

  2. Using TES retrievals to investigate PAN in North American biomass burning plumes

    Science.gov (United States)

    Fischer, Emily V.; Zhu, Liye; Payne, Vivienne H.; Worden, John R.; Jiang, Zhe; Kulawik, Susan S.; Brey, Steven; Hecobian, Arsineh; Gombos, Daniel; Cady-Pereira, Karen; Flocke, Frank

    2018-04-01

    Peroxyacyl nitrate (PAN) is a critical atmospheric reservoir for nitrogen oxide radicals, and plays a lead role in their redistribution in the troposphere. We analyze new Tropospheric Emission Spectrometer (TES) PAN observations over North America from July 2006 to July 2009. Using aircraft observations from the Colorado Front Range, we demonstrate that TES can be sensitive to elevated PAN in the boundary layer (˜ 750 hPa) even in the presence of clouds. In situ observations have shown that wildfire emissions can rapidly produce PAN, and PAN decomposition is an important component of ozone production in smoke plumes. We identify smoke-impacted TES PAN retrievals by co-location with NOAA Hazard Mapping System (HMS) smoke plumes. Depending on the year, 15-32 % of cases where elevated PAN is identified in TES observations (retrievals with degrees of freedom (DOF) > 0.6) overlap smoke plumes during July. Of all the retrievals attempted in the July 2006 to July 2009 study period, 18 % is associated with smoke . A case study of smoke transport in July 2007 illustrates that PAN enhancements associated with HMS smoke plumes can be connected to fire complexes, providing evidence that TES is sufficiently sensitive to measure elevated PAN several days downwind of major fires. Using a subset of retrievals with TES 510 hPa carbon monoxide (CO) > 150 ppbv, and multiple estimates of background PAN, we calculate enhancement ratios for tropospheric average PAN relative to CO in smoke-impacted retrievals. Most of the TES-based enhancement ratios fall within the range calculated from in situ measurements.

  3. Using TES retrievals to investigate PAN in North American biomass burning plumes

    Directory of Open Access Journals (Sweden)

    E. V. Fischer

    2018-04-01

    Full Text Available Peroxyacyl nitrate (PAN is a critical atmospheric reservoir for nitrogen oxide radicals, and plays a lead role in their redistribution in the troposphere. We analyze new Tropospheric Emission Spectrometer (TES PAN observations over North America from July 2006 to July 2009. Using aircraft observations from the Colorado Front Range, we demonstrate that TES can be sensitive to elevated PAN in the boundary layer (∼ 750 hPa even in the presence of clouds. In situ observations have shown that wildfire emissions can rapidly produce PAN, and PAN decomposition is an important component of ozone production in smoke plumes. We identify smoke-impacted TES PAN retrievals by co-location with NOAA Hazard Mapping System (HMS smoke plumes. Depending on the year, 15–32 % of cases where elevated PAN is identified in TES observations (retrievals with degrees of freedom (DOF > 0.6 overlap smoke plumes during July. Of all the retrievals attempted in the July 2006 to July 2009 study period, 18 % is associated with smoke . A case study of smoke transport in July 2007 illustrates that PAN enhancements associated with HMS smoke plumes can be connected to fire complexes, providing evidence that TES is sufficiently sensitive to measure elevated PAN several days downwind of major fires. Using a subset of retrievals with TES 510 hPa carbon monoxide (CO > 150 ppbv, and multiple estimates of background PAN, we calculate enhancement ratios for tropospheric average PAN relative to CO in smoke-impacted retrievals. Most of the TES-based enhancement ratios fall within the range calculated from in situ measurements.

  4. Methanol from TES global observations: retrieval algorithm and seasonal and spatial variability

    Directory of Open Access Journals (Sweden)

    K. E. Cady-Pereira

    2012-09-01

    Full Text Available We present a detailed description of the TES methanol (CH3OH retrieval algorithm, along with initial global results showing the seasonal and spatial distribution of methanol in the lower troposphere. The full development of the TES methanol retrieval is described, including microwindow selection, error analysis, and the utilization of a priori and initial guess information provided by the GEOS-Chem chemical transport model. Retrieval simulations and a sensitivity analysis using the developed retrieval strategy show that TES: (i generally provides less than 1.0 piece of information, (ii is sensitive in the lower troposphere with peak sensitivity typically occurring between ~900–700 hPa (~1–3 km at a vertical resolution of ~5 km, (iii has a limit of detectability between 0.5 and 1.0 ppbv Representative Volume Mixing Ratio (RVMR depending on the atmospheric conditions, corresponding roughly to a profile with a maximum concentration of at least 1 to 2 ppbv, and (iv in a simulation environment has a mean bias of 0.16 ppbv with a standard deviation of 0.34 ppbv. Applying the newly derived TES retrieval globally and comparing the results with corresponding GEOS-Chem output, we find generally consistent large-scale patterns between the two. However, TES often reveals higher methanol concentrations than simulated in the Northern Hemisphere spring, summer and fall. In the Southern Hemisphere, the TES methanol observations indicate a model overestimate over the bulk of South America from December through July, and a model underestimate during the biomass burning season.

  5. Evaluating climate model performance in the tropics with retrievals of water isotopic composition from Aura TES

    Science.gov (United States)

    Field, Robert; Kim, Daehyun; Kelley, Max; LeGrande, Allegra; Worden, John; Schmidt, Gavin

    2014-05-01

    Observational and theoretical arguments suggest that satellite retrievals of the stable isotope composition of water vapor could be useful for climate model evaluation. The isotopic composition of water vapor is controlled by the same processes that control water vapor amount, but the observed distribution of isotopic composition is distinct from amount itself . This is due to the fractionation that occurs between the abundant H216O isotopes (isotopologues) and the rare and heavy H218O and HDO isotopes during evaporation and condensation. The fractionation physics are much simpler than the underlying moist physics; discrepancies between observed and modeled isotopic fields are more likely due to problems in the latter. Isotopic measurements therefore have the potential for identifying problems that might not be apparent from more conventional measurements. Isotopic tracers have existed in climate models since the 1980s but it is only since the mid 2000s that there have been enough data for meaningful model evaluation in this sense, in the troposphere at least. We have evaluated the NASA GISS ModelE2 general circulation model over the tropics against water isotope (HDO/H2O) retrievals from the Aura Tropospheric Emission Spectrometer (TES), alongside more conventional measurements. A small ensemble of experiments was performed with physics perturbations to the cumulus and planetary boundary layer schemes, done in the context of the normal model development process. We examined the degree to which model-data agreement could be used to constrain a select group of internal processes in the model, namely condensate evaporation, entrainment strength, and moist convective air mass flux. All are difficult to parameterize, but exert strong influence over model performance. We found that the water isotope composition was significantly more sensitive to physics changes than precipitation, temperature or relative humidity through the depth of the tropical troposphere. Among the

  6. Reprocessing

    International Nuclear Information System (INIS)

    Couture, J.; Rougeau, J.-P.

    1987-01-01

    The course of development of a comprehensive nuclear power industry has its own pace which implies the timely progressive and consistent mastery of each industrial step. In the nuclear fuel it is not surprising that the back-end services have lastly reached the industrial stage. In France, we have now fully completed the industrial demonstration of the closed fuel cycle. Our experience covers all necessary steps : transportation of spent fuel, storage, reprocessing, waste conditioning, recovered uranium recycling, plutonium recycling in thermal MOX fuels, plutonium-based fuel for FBR. While FBR development is a long term target, recycling of fissile materials in present LWR reactors appears to be a source of noticable savings. In the meantime rational management of waste material is the key for increased safety and better environment protection. Reprocessing activity is certainly the major achievement of the back-end strategy. The proven efficiency of this technique as it is implemented at La Hague facility gives the full assurance of a smooth operation of the under completion UP3 unit. The base-load management system which applies during the first ten years of its operation will make possible a noticable reduction of the commercial price for reprocessing services by the end of the century. Industrial maturity being confirmed, economic maturity is now the outstanding merit of the reprocessing and recycling strategy. It is a permanent challenge, to which the response is definitely positive in the sense of reducing the nuclear KWh production cost. (author)

  7. Methane from the Tropospheric Emission Spectrometer (TES)

    Science.gov (United States)

    Payne, Vivienne; Worden, John; Kulawik, Susan; Frankenberg, Christian; Bowman, Kevin; Wecht, Kevin

    2012-01-01

    TES V5 CH4 captures latitudinal gradients, regional variability and interannual variation in the free troposphere. V5 joint retrievals offer improved sensitivity to lower troposphere. Time series extends from 2004 to present. V5 reprocessing in progress. Upper tropospheric bias. Mitigated by N2O correction. Appears largely spatially uniform, so can be corrected. How to relate free-tropospheric values to surface emissions.

  8. Processing TES Level-2 Data

    Science.gov (United States)

    Poosti, Sassaneh; Akopyan, Sirvard; Sakurai, Regina; Yun, Hyejung; Saha, Pranjit; Strickland, Irina; Croft, Kevin; Smith, Weldon; Hoffman, Rodney; Koffend, John; hide

    2006-01-01

    TES Level 2 Subsystem is a set of computer programs that performs functions complementary to those of the program summarized in the immediately preceding article. TES Level-2 data pertain to retrieved species (or temperature) profiles, and errors thereof. Geolocation, quality, and other data (e.g., surface characteristics for nadir observations) are also included. The subsystem processes gridded meteorological information and extracts parameters that can be interpolated to the appropriate latitude, longitude, and pressure level based on the date and time. Radiances are simulated using the aforementioned meteorological information for initial guesses, and spectroscopic-parameter tables are generated. At each step of the retrieval, a nonlinear-least-squares- solving routine is run over multiple iterations, retrieving a subset of atmospheric constituents, and error analysis is performed. Scientific TES Level-2 data products are written in a format known as Hierarchical Data Format Earth Observing System 5 (HDF-EOS 5) for public distribution.

  9. Why reprocess

    International Nuclear Information System (INIS)

    Greenwood, T.

    1977-01-01

    Prospective costs of reprocessing, waste management, and mixed oxide fuel fabrication have risen so much that the costs of U/P recycle and of spent fuel storage are nearly equal. This paper reviews the current state of the reprocessing industry, with a list of facilities all over the world, and examines the incentives and disincentives other than short-term economics that will affect the decision of states to acquire their own reprocessing facilities. Finally, it examines the possibility of avoiding a widespread commercial reprocessing industry

  10. Reprocessing decision

    International Nuclear Information System (INIS)

    Heising, C.D.

    1978-01-01

    The United States must decide whether to permit, delay, or prohibit the reprocessing and recycling of nuclear spent fuel. To permit reprocessing would allow recycle as early as 1985; to delay the decision for a later administration to deal with means spent fuel would mount up at nuclear reactor sites; to prohibit would eliminate recycling and mandate permanent storage. Bayesian decision analysis was used to examine reprocessing costs associated with risks and economic benefits. Three distinct categories of risk that are important in the nuclear fuel cycle are discussed. These are: health, environment, and safety risks; nuclear theft and sabotage; and nuclear weapons proliferation risks. Results are discussed from comparing nine routes to weapons-usuable mterial available to nonweapons states that desire a nuclear capability. These are: production reactor and military reporcessor; research reacotr and military reprocessor; power plant plus military reprocessor or commercial reprocessor; enrichment (centrifuge, gaseous diffusion, electromagnetic separation, or aerodynamic jet cascade); and accelerator. It was found that the commercial power reactor-commercial reprocessor route is comparatively unattractive to a nonweapons state. In summary, allowing nuclear fuel reprocessing to go forward in the United States can be expected to increase the costs to society by a maximum $360 million a year. This is approximately one-seventh of the expected benefit (reduced electricity bills) to be dderived by society from closing the fuel cycle. It appears that the permitting reprocessing now is logically preferable to delaying or prohibiting the technology, the author concludes

  11. HTGR fuel reprocessing technology

    International Nuclear Information System (INIS)

    Brooks, L.H.; Heath, C.A.; Shefcik, J.J.

    1976-01-01

    The following aspects of HTGR reprocessing technology are discussed: characteristics of HTGR fuels, criteria for a fuel reprocessing flowsheet; selection of a reference reprocessing flowsheet, and waste treatment

  12. INTENSITAS COPYING ANSWER PADA TES KEMAMPUAN MATEMATIKA

    Directory of Open Access Journals (Sweden)

    Nursalam Nursalam

    2012-07-01

    Abstrak: Seorang peserta tes akan menjawab tes dengan tiga asumsi yaitu peserta tes akan menjawab suatu butir pertanyaan karena mengetahui, peserta menjawab tes dengan menebak, dan peserta menjawab tes karena menyalin jawaban dari peserta lain (menyontek. Akan tetapi jika peserta tes tidak memiliki akses untuk menyontek maka peserta hanya akan memberikan jawaban dengan asumsi pertama dan kedua. Artikel ini membahas intensitas menyontek sebelum pelaksanaan tes, pada saat pelaksanan tes, dan ketika tes dilaksanakan secara tiba-tiba.Hasil penelitian menunjukkan bahwa intensitas menyontek paling tinggi dilakukan oleh peserta tes pada saat ujian berlansung kemudian ketika ujian dilakukan secara tiba-tiba atau mendadak dan terakhir adalah sebelum pelaksanaan tes.

  13. Why reprocess

    International Nuclear Information System (INIS)

    Hagen, M.

    1977-01-01

    The problem of whether to reprocess spent nuclear fuel elements has been studied already in the early days of the commercial utilization of nuclear power and has been answered positively. This also, and in particular, applies to the United States. Under the new American nuclear policy reprocessing is rejected only for reasons of non-proliferation. Although these are valid reasons, the effectiveness of a ban on reprocessing, as fas as the non-profileration of nuclear weapons is concerned, is not accepted worldwide because the necessary knowledge either already exists in many countries or can be obtained. Only if there had been a realistic chance to prevent the proliferation of nuclear weapons, also the other industrialized countries would have seconded the policy of the United States. A country like the Federal Republic of Germany, with a substantial long-term nuclear power program based initially on light water reactors, subsequently on advanced reactor systems, cannot do without a complete nuclear fuel cycle. This reasoning is outlined in the light of economic and radioecological aspects. Extensive experience on a technical scale is available in the reprocessing sector. The technical problems associated with this activity have been solved in principle and have largely been demonstrated to function in practice. (orig.) [de

  14. PENGEMBANGAN TES BAKAT TERPADU ONLINE

    Directory of Open Access Journals (Sweden)

    I Made Candiasa

    2016-08-01

    Full Text Available Abstrak Pengembangan tes bakat online didasari ide untuk memperluas otomasi layanan pendidikan, melengkapi e-learning yang sudah berkembang dengan baik untuk otomasi pembelajaran. Kelebihan tes bakat online yang dikembangkan adalah dapat digunakan setiap saat, dan tidak terlalu terikat tempat, serta tidak memerlukan petugas yang memahami evaluasi. Selain itu, tes bakat online dapat menyajikan variasi tes yang berbeda setiap kali diakses, serta dapat memberikan informasi hasil tes secara otomatis langsung setelah peserta tes memvalidasi jawabannya. Kata kunci: tes bakat online, otomasi layanan pendidikan Abstract Development of online aptitude test based on idea of widening automation on educational service, completing existing various e-learning model for instructional automation. There are some advantages of online aptitude test. It can be used anytime and anywhere by everyone. Furthermore, it can present various package of test every time it is accessed and automatically gives score and feedback immediately after tester finish answer the test. Keywords: online aptitude test, automation of educational service

  15. Winter- and summertime continental influences on tropospheric O3 and CO observed by TES over the western North Atlantic Ocean

    Directory of Open Access Journals (Sweden)

    R. Talbot

    2010-04-01

    Full Text Available The distributions of tropospheric ozone (O3 and carbon monoxide (CO, and the synoptic factors regulating these distributions over the western North Atlantic Ocean during winter and summer were investigated using profile retrievals from the Tropospheric Emission Spectrometer (TES for 2004–2006. Seasonal composites of TES retrievals, reprocessed to remove the influence of the a priori on geographical and seasonal structure, exhibited strong seasonal differences. At the 681 hPa level during winter months of December, January and February (DJF the composite O3 mixing ratios were uniformly low (~45 ppbv, but continental export was evident in a channel of enhanced CO (100–110 ppbv flowing eastward from the US coast. In summer months June, July, and August (JJA O3 mixing ratios were variable (45–65 ppbv and generally higher due to increased photochemical production. The summer distribution also featured a channel of enhanced CO (95–105 ppbv flowing northeastward around an anticyclone and exiting the continent over the Canadian Maritimes around 50° N. Offshore O3-CO slopes were generally 0.15–0.20 mol mol−1 in JJA, indicative of photochemical O3 production. Composites for 4 predominant synoptic patterns or map types in DJF suggested that export to the lower free troposphere (681 hPa level was enhanced by the warm conveyor belt airstream of mid-latitude cyclones while stratospheric intrusions increased TES O3 levels at 316 hPa. A major finding in the DJF data was that offshore 681 hPa CO mixing ratios behind cold fronts could be enhanced up to >150 ppbv likely by lofting from the surface via shallow convection resulting from rapid destabilization of cold air flowing over much warmer ocean waters. In JJA composites for 3 map types showed that the general export pattern of the seasonal composites was associated with a synoptic pattern featuring the Bermuda High. However, weak cyclones and frontal troughs could enhance offshore 681 hPa CO

  16. Reprocessing business in the UK

    Energy Technology Data Exchange (ETDEWEB)

    Wilkinson, W L

    1985-01-01

    The development of the process for separating uranium, plutonium and fission products from irradiated fuel began in Britain in late 1940s, and the first separation plant was operated at Sellafield in 1952. This plant was operated very well for more than 12 years with the overall availability over 95%. The second separation plant to meet the needs of the growing nuclear power program became operational in 1964. This plant has been extremely successful, but the significant improvement was made to extend the operating life of the key items. In mid 1970s, by the introduction of uranium oxide fuel reactors, significant reprocessing capacity became to be required. Therefore, it was decided to embark upon the development of a thermal oxide reprocessing plant (THORP) to complement the existing facilities at Sellafield. The THORP is a very large complex of plants. The first duty for the THORP is to reprocess 6,000 t U of oxide fuel in 10 years. But the plant is designed for the life of 25 years. The plant has the capacity of 1200 tes/year. The scope covered by the THORP, the plant processes and the wastes produced from the THORP are described. (Kako, I.).

  17. Tropospheric Emission Spectrometer (TES) Data

    Data.gov (United States)

    National Aeronautics and Space Administration — TES focuses on the troposphere, the layer of atmosphere that stretches from the ground to the altitude at which airplanes fly. With very high spectral resolution,...

  18. Tropospheric Emission Spectrometer (TES) Satellite Validations of Ammonia, Methanol, Formic Acid, and Carbon Monoxide over the Canadian Oil Sands

    Data.gov (United States)

    U.S. Environmental Protection Agency — The URLs link to the data archive of the Troposphere Emission Spectrometer (TES) retrievals. These include the transects included in the Canadian Tar Sands study. A...

  19. Long-term stability of TES satellite radiance measurements

    Directory of Open Access Journals (Sweden)

    T. C. Connor

    2011-07-01

    Full Text Available The utilization of Tropospheric Emission Spectrometer (TES Level 2 (L2 retrieval products for the purpose of assessing long term changes in atmospheric trace gas composition requires knowledge of the overall radiometric stability of the Level 1B (L1B radiances. The purpose of this study is to evaluate the stability of the radiometric calibration of the TES instrument by analyzing the difference between measured and calculated brightness temperatures in selected window regions of the spectrum. The Global Modeling and Assimilation Office (GMAO profiles for temperature and water vapor and the Real-Time Global Sea Surface Temperature (RTGSST are used as input to the Optimal Spectral Sampling (OSS radiative transfer model to calculate the simulated spectra. The TES reference measurements selected cover a 4-year period of time from mid 2005 through mid 2009 with the selection criteria being; observation latitudes greater than −30° and less than 30°, over ocean, Global Survey mode (nadir view and retrieved cloud optical depth of less than or equal to 0.01. The TES cloud optical depth retrievals are used only for screening purposes and no effects of clouds on the radiances are included in the forward model. This initial screening results in over 55 000 potential reference spectra spanning the four year period. Presented is a trend analysis of the time series of the residuals (observation minus calculations in the TES 2B1, 1B2, 2A1, and 1A1 bands, with the standard deviation of the residuals being approximately equal to 0.6 K for bands 2B1, 1B2, 2A1, and 0.9 K for band 1A1. The analysis demonstrates that the trend in the residuals is not significantly different from zero over the 4-year period. This is one method used to demonstrate that the relative radiometric calibration is stable over time, which is very important for any longer term analysis of TES retrieved products (L2, particularly well-mixed species such as carbon dioxide and methane.

  20. Development of Ir/Au-TES microcalorimeter

    International Nuclear Information System (INIS)

    Kunieda, Yuichi; Fukuda, Daiji; Ohno, Masashi; Nakazawa, Masaharu; Takahashi, Hiroyuki; Ataka, Manabu; Ohkubo, Masataka; Hirayama, Fuminori

    2004-01-01

    We are developing X-ray microcalorimeters using transition edge sensors (TES) for high resolution x-ray spectroscopy. Microcalorimeters are thermal detectors which measure the energy of an incident x-ray photon using a TES thermometer operated at a sharp transition edge between normal and superconducting states. TES microcalorimeters can achieve faster response than conventional microcalorimeters by keeping the operating point of TES in the transition region through the use of strong negative electrothermal feedback (ETF). We developed a bilayer TES where a normal metal Au was deposited on a superconductor Ir in order to improve the thermal conductivity of the Ir-TES. We investigated resistance-temperature characteristics. As a result, it showed a very sharp transition within 1 mK at the temperature of 110 mK. The energy resolution of 9.4 eV (FWHM) was achieved for a 5899 eV Mn K al line. (author)

  1. Alternative reprocessing schemes evaluation

    International Nuclear Information System (INIS)

    1979-02-01

    This paper reviews the parameters which determine the inaccessibility of the plutonium in reprocessing plants. Among the various parameters, the physical and chemical characteristics of the materials, the various processing schemes and the confinement are considered. The emphasis is placed on that latter parameter, and the advantages of an increased confinement in the socalled PIPEX reprocessing plant type are presented

  2. Nuclear Fuel Reprocessing

    International Nuclear Information System (INIS)

    Simpson, Michael F.; Law, Jack D.

    2010-01-01

    This is a submission for the Encyclopedia of Sustainable Technology on the subject of Reprocessing Spent Nuclear Fuel. Nuclear reprocessing is the chemical treatment of spent fuel involving separation of its various constituents. Principally, it is used to recover useful actinides from the spent fuel. Radioactive waste that cannot be re-used is separated into streams for consolidation into waste forms. The first known application of nuclear reprocessing was within the Manhattan Project to recover material for nuclear weapons. Currently, reprocessing has a peaceful application in the nuclear fuel cycle. A variety of chemical methods have been proposed and demonstrated for reprocessing of nuclear fuel. The two most widely investigated and implemented methods are generally referred to as aqueous reprocessing and pyroprocessing. Each of these technologies is described in detail in Section 3 with numerous references to published articles. Reprocessing of nuclear fuel as part of a fuel cycle can be used both to recover fissionable actinides and to stabilize radioactive fission products into durable waste forms. It can also be used as part of a breeder reactor fuel cycle that could result in a 14-fold or higher increase in energy utilization per unit of natural uranium. Reprocessing can also impact the need for geologic repositories for spent fuel. The volume of waste that needs to be sent to such a repository can be reduced by first subjecting the spent fuel to reprocessing. The extent to which volume reduction can occur is currently under study by the United States Department of Energy via research at various national laboratories and universities. Reprocessing can also separate fissile and non-fissile radioactive elements for transmutation.

  3. TES Level 1 Algorithms: Interferogram Processing, Geolocation, Radiometric, and Spectral Calibration

    Science.gov (United States)

    Worden, Helen; Beer, Reinhard; Bowman, Kevin W.; Fisher, Brendan; Luo, Mingzhao; Rider, David; Sarkissian, Edwin; Tremblay, Denis; Zong, Jia

    2006-01-01

    The Tropospheric Emission Spectrometer (TES) on the Earth Observing System (EOS) Aura satellite measures the infrared radiance emitted by the Earth's surface and atmosphere using Fourier transform spectrometry. The measured interferograms are converted into geolocated, calibrated radiance spectra by the L1 (Level 1) processing, and are the inputs to L2 (Level 2) retrievals of atmospheric parameters, such as vertical profiles of trace gas abundance. We describe the algorithmic components of TES Level 1 processing, giving examples of the intermediate results and diagnostics that are necessary for creating TES L1 products. An assessment of noise-equivalent spectral radiance levels and current systematic errors is provided. As an initial validation of our spectral radiances, TES data are compared to the Atmospheric Infrared Sounder (AIRS) (on EOS Aqua), after accounting for spectral resolution differences by applying the AIRS spectral response function to the TES spectra. For the TES L1 nadir data products currently available, the agreement with AIRS is 1 K or better.

  4. Environmental evaluation of reprocessing

    International Nuclear Information System (INIS)

    1979-01-01

    This paper addresses two specific points. (a) The means by which it is established that reprocessing is carried out within the basic standards for radiological protection set by the ICRP. (b) A summary of the products, wastes and effluents of reprocessing together with the energy and water resources required. It is concluded that reprocessing of spent thermal reactor fuel can be undertaken whilst conforming to the basic standards set by ICRP. For domestic reasons of public acceptability some countries adopt very strict limits. Any attempt at comparisons between limits set by individual countries could lead to misunderstandings if account is not taken of these additional factors which may in turn influence the cost of reprocessing

  5. Wastes from fuel reprocessing

    International Nuclear Information System (INIS)

    Eschrich, H.

    1976-01-01

    Handling, treatment, and interim storage of radioactive waste, problems confronted with during the reprocessing of spent fuel elements from LWR's according to the Purex-type process, are dealt with in detail. (HR/LN) [de

  6. Spent fuel reprocessing options

    International Nuclear Information System (INIS)

    2008-08-01

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

  7. Operating experience in reprocessing

    International Nuclear Information System (INIS)

    Schueller, W.

    1983-01-01

    Since 1953, reprocessing has accumulated 180 years of operating experience in ten plants, six of them with 41 years of operation in reprocessing oxide fuel from light water reactors. After abortive, premature attempts at what is called commercial reprocessing, which had been oriented towards the market value of recoverable uranium and plutonium, non-military reprocessing technologies have proved their technical feasibility, since 1966 on a pilot scale and since 1976 on an industrial scale. Reprocessing experience obtained on uranium metal fuel with low and medium burnups can now certainly be extrapolated to oxide fuel with high burnup and from pilot plants to industrial scale plants using the same technologies. The perspectives of waste management of the nuclear power plants operated in the Federal Republic of Germany should be viewed realistically. The technical problems still to be solved are in a balanced relationship to the benefit arising to the national economy out of nuclear power generation and can be solved in time, provided there are clearcut political boundary conditions. (orig.) [de

  8. Recycling of reprocessed uranium

    International Nuclear Information System (INIS)

    Randl, R.P.

    1987-01-01

    Since nuclear power was first exploited in the Federal Republic of Germany, the philosophy underlying the strategy of the nuclear fuel cycle has been to make optimum use of the resource potential of recovered uranium and plutonium within a closed fuel cycle. Apart from the weighty argument of reprocessing being an important step in the treatment and disposal of radioactive wastes, permitting their optimum ecological conditioning after the reprocessing step and subsequent storage underground, another argument that, no doubt, carried weight was the possibility of reducing the demand of power plants for natural uranium. In recent years, strategies of recycling have emerged for reprocessed uranium. If that energy potential, too, is to be exploited by thermal recycling, it is appropriate to choose a slightly different method of recycling from the one for plutonium. While the first generation of reprocessed uranium fuel recycled in the reactor cuts down natural uranium requirement by some 15%, the recycling of a second generation of reprocessed, once more enriched uranium fuel helps only to save a further three per cent of natural uranium. Uranium of the second generation already carries uranium-232 isotope, causing production disturbances, and uranium-236 isotope, causing disturbances of the neutron balance in the reactor, in such amounts as to make further fabrication of uranium fuel elements inexpedient, even after mixing with natural uranium feed. (orig./UA) [de

  9. Reprocessing in Europe

    Energy Technology Data Exchange (ETDEWEB)

    Rossney, G [United Reprocessors G.m.b.H., Karlsruhe (F.R. Germany)

    1976-04-01

    The status of reprocessing activities within the member organizations of United Reprocessors is reviewed. The U.K. government has approved overseas deals by BNFL which will help to pay for their planned plant of 1000 te U p.a. at Windscale. In Germany KEWA has selected a site at Aschenburg as a fuel cycle centre where they plan to build a utility financed reprocessing plant of 1500 te U p.a. France has formed a new fuel cycle corporation, Cogema, which hopes to participate in the large volume of Japanese business negotiated by BNFL. United Reprocessors have agreed to pool their technology which may be available to organisations wishing to construct reprocessing plants in their own countries.

  10. Economic evaluation of reprocessing

    International Nuclear Information System (INIS)

    This paper, which also appears as an Appendix to the Final Working Group 4 report, considers the economics of the four basic options available in nuclear programmes namely: the once-through cycle; reprocessing with uranium recycle and plutonium storage; reprocessing with both uranium and plutonium recycle; and the fast reactor. These options are represented by four separate areas on a ''phase diagram'' showing the relationship between relative generating costs and uranium ore price. The basic algebra defining each component of electricity cost is given for each option. The diagram can take different forms depending upon the relative magnitudes of the costs of reprocessing and MOX fuel fabrication and whether the once-through fuel cycle is acceptable or not on grounds other than strictly economic, i.e. environmental grounds. The shortcomings of this form of presentation are also identified

  11. Training Exit Survey (TES) Individual Campus

    Data.gov (United States)

    U.S. Department of Health & Human Services — The TES Individual dataset contains information at the individual-level about the persons who attend a GLS funded training event. This dataset includes variables...

  12. Design considerations for TES and QET sensors

    International Nuclear Information System (INIS)

    Cabrera, B.

    2000-01-01

    We summarize some of the effects that must be taken into account in the design of superconducting Transition Edge Sensors (TES) and Quasiparticle-trap-assisted Electrothermal-feedback Transition-edge-sensors (QET). For the TES these include determining time constants, maintaining voltage bias, avoid electrothermal oscillations, critical current limitations, and saturation. For QET phonon sensors, voltage bias was conceived to allow the simultaneous biasing of parallel TESs with different transition temperatures, and preventing normal-superconducting phase separation

  13. Consolidated fuel reprocessing program

    Science.gov (United States)

    1985-04-01

    A survey of electrochemical methods applications in fuel reprocessing was completed. A dummy fuel assembly shroud was cut using the remotely operated laser disassembly equipment. Operations and engineering efforts have continued to correct equipment operating, software, and procedural problems experienced during the previous uranium compaigns. Fuel cycle options were examined for the liquid metal reactor fuel cycle. In high temperature gas cooled reactor spent fuel studies, preconceptual designs were completed for the concrete storage cask and open field drywell storage concept. These and other tasks operating under the consolidated fuel reprocessing program are examined.

  14. Reprocessing the truth

    International Nuclear Information System (INIS)

    Goldsmith, E.; Bunyard, P.; Hildyard, N.

    1978-01-01

    Comments are made on the Report by the Inspector, Mr. Justice Parker, after the public inquiry into the application by British Nuclear Fuels Limited for permission to construct and operate a thermal oxide reprocessing plant at their Windscale works. Particular questions raised include: corrosion or storage of spent fuel, vitrification of radioactive waste; radiation effects, and permissible levels; radioactive emissions, critical groups and critical pathways; risks; reprocessing economics; commitment to the FBR; sociological aspects, including employment, nuclear weapon proliferation and terrorism, and Britain's moral responsibilities. (U.K.)

  15. Seasonal and spatial changes in trace gases over megacities from Aura TES observations: two case studies

    Directory of Open Access Journals (Sweden)

    K. E. Cady-Pereira

    2017-08-01

    Full Text Available The Aura Tropospheric Emission Spectrometer (TES is collecting closely spaced observations over 19 megacities. The objective is to obtain measurements that will lead to better understanding of the processes affecting air quality in and around these cities, and to better estimates of the seasonal and interannual variability. We explore the TES measurements of ozone, ammonia, methanol and formic acid collected around the Mexico City metropolitan area (MCMA and in the vicinity of Lagos (Nigeria. The TES data exhibit seasonal signals that are correlated with Atmospheric Infrared Sounder (AIRS CO and Moderate Resolution Imaging Spectroradiometer (MODIS aerosol optical depth (AOD, with in situ measurements in the MCMA and with Goddard Earth Observing System (GEOS-Chem model output in the Lagos area. TES was able to detect an extreme pollution event in the MCMA on 9 April 2013, which is also evident in the in situ data. TES data also show that biomass burning has a greater impact south of the city than in the caldera where Mexico City is located. TES measured enhanced values of the four species over the Gulf of Guinea south of Lagos. Since it observes many cities from the same platform with the same instrument and applies the same retrieval algorithms, TES data provide a very useful tool for easily comparing air quality measures of two or more cities. We compare the data from the MCMA and Lagos, and show that, while the MCMA has occasional extreme pollution events, Lagos consistently has higher levels of these trace gases.

  16. Processing TES Level-1B Data

    Science.gov (United States)

    DeBaca, Richard C.; Sarkissian, Edwin; Madatyan, Mariyetta; Shepard, Douglas; Gluck, Scott; Apolinski, Mark; McDuffie, James; Tremblay, Dennis

    2006-01-01

    TES L1B Subsystem is a computer program that performs several functions for the Tropospheric Emission Spectrometer (TES). The term "L1B" (an abbreviation of "level 1B"), refers to data, specific to the TES, on radiometric calibrated spectral radiances and their corresponding noise equivalent spectral radiances (NESRs), plus ancillary geolocation, quality, and engineering data. The functions performed by TES L1B Subsystem include shear analysis, monitoring of signal levels, detection of ice build-up, and phase correction and radiometric and spectral calibration of TES target data. Also, the program computes NESRs for target spectra, writes scientific TES level-1B data to hierarchical- data-format (HDF) files for public distribution, computes brightness temperatures, and quantifies interpixel signal variability for the purpose of first-order cloud and heterogeneous land screening by the level-2 software summarized in the immediately following article. This program uses an in-house-developed algorithm, called "NUSRT," to correct instrument line-shape factors.

  17. Technical aspects of fuel reprocessing

    International Nuclear Information System (INIS)

    Groenier, W.S.

    1982-02-01

    The purpose of this paper is to present a brief description of fuel reprocessing and some present developments which show the reliability of nuclear energy as a long-term supply. The following topics are discussed: technical reasons for reprocessing; economic reasons for reprocessing; past experience; justification for advanced reprocessing R and D; technical aspects of current reprocessing development. The present developments are mainly directed at the reprocessing of breeder reactor fuels but there are also many applications to light-water reactor fuel reprocessing. These new developments involve totally remote operation, and maintenance. To demonstrate this advanced reprocessing concept, pilot-scale demonstration facilities are planned with commercial application occurring sometime after the year 2000

  18. Worldwide reprocessing supply and demand

    International Nuclear Information System (INIS)

    Pinto, S.

    1987-01-01

    The aim of this paper is to broadly examine the current situation in the LWR fuel reprocessing services market on a worldwide basis through 2010. The main factors influencing this market (nuclear programs, fuel discharges, reprocessing capacities, buyer philosophies, etc.) are identified in the paper and the most important are highlighted and discussed in more detail. Emphasis has been placed on the situation with respect to reprocessing in those countries having a significant influence on the reprocessing market

  19. Reprocessing: experience and future outlooks

    International Nuclear Information System (INIS)

    Rapin, M.

    1981-01-01

    It is shown that reprocessing is the best way to cope with irradiated fuels since it provides an optimized waste conditioning for long term storage, the possibility to recycle fissile material and the reduction of Pu diversion risk. The reprocessing constraints are discussed from political, technical, safety, public acceptance, and economical points of view. The French reprocessing programme (thermal reactor fuel fast breeder fuels) is presented together with a short review of the reprocessing experience and outlooks out of France [fr

  20. Future trends in reprocessing

    International Nuclear Information System (INIS)

    Rouyer, H.

    1994-01-01

    This paper about future trends in reprocessing essentially reflects French experience and points of view as an example of countries which, like England and Japan, consider that reprocessing is the best solution for the back end of the fuel cycle. In order to know what the future will be, it is necessary to look back at the past and try to find what have been the main reasons for evolution in that period. For reprocessing, it appears that these motivations have been 'safety and economics'. They will remain the motivations for the future. In addition, new motivations for development are starting to appear which are still imprecise but can be expressed as follows: 'which guarantees will public opinion require in order to be convinced that solutions for waste management, proposed by specialists shall ensure that a healthy environment is preserved for the use of future generations'. Consequently the paper examines successively the evolution of reprocessing in the recent past, what the immediate future could be and finally what should be necessary in the long term. (Author)

  1. Irradiated uranium reprocessing

    International Nuclear Information System (INIS)

    Gal, I.

    1961-12-01

    Task concerned with reprocessing of irradiated uranium covered the following activities: implementing the method and constructing the cell for uranium dissolving; implementing the procedure for extraction of uranium, plutonium and fission products from radioactive uranium solutions; studying the possibilities for using inorganic ion exchangers and adsorbers for separation of U, Pu and fission products

  2. Reprocessing of spent plasma

    International Nuclear Information System (INIS)

    Pierini, G.

    1981-01-01

    This invention relates to a process for removing helium and other impurities from a mixture containing deuterium and tritium, a deuterium/tritium mixture when purified in accordance with such a process and, more particularly, to a process for the reprocessing of spent plasma removed from a thermofusion reactor. (U.K.)

  3. Importance of nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Allday, C.

    1977-01-01

    The following topics are discussed: world energy requirements; energy conservation and the economics of recycle environmental considerations and the timescale of reprocessing; and problems associated with reprocessing. The conclusion is reached that reprocessing is essential to the conservation of the world's energy resources and is an environmentally, and probably an economically, more acceptable option to the ''throw away'' alternative

  4. Consolidated fuel reprocessing program

    International Nuclear Information System (INIS)

    Kuban, D.P.; Noakes, M.W.; Bradley, E.C.

    1987-01-01

    The Advanced Servomanipulator (ASM) System consists of three major components: the ASM slave, the dual arm master controller or master, and the control system. The ASM is a remotely maintainable force-reflecting servomanipulator developed at the Oak Ridge National Laboratory (ORNL) as part of the Consolidated Fuel Reprocessing Program of (CFRP). This new manipulator addresses requirements of advanced nuclear fuel reprocessing with emphasis on force reflection, remote maintainability, and reliability. It uses an all-gear force transmission system. The master arms were designed as a kinematic replica of ASM and use cable force transmission. Special digital control algorithms were developed to improve the system performance. The system is presently operational and undergoing evaluation. Preliminary testing has been completed and is reported. The system is now undergoing commercialization by transferring the technology to the private sector

  5. Reprocessing plants safety

    International Nuclear Information System (INIS)

    Davies, A.G.; Leighton, C.; Millington, D.

    1989-01-01

    The reprocessing of irradiated nuclear fuel at British Nuclear Fuels (BNFL) Sellafield site consists of a number of relatively self-contained activities carried out in separate plants across the site. The physical conditions and time scales applied in reprocessing and storage make it relatively benign. The potential for minor releases of radioactivity under fault conditioning is minimised by plant design definition of control procedures, training and supervision. The risks to both the general public and workforce are shown to be low with all the safety criteria being met. Normal operating conditions also have the potential for some occupational radiation exposure and the plant and workers are monitored continuously. Exposure levels have been reduced steadily and will continue to fall with plant improvements. (U.K.)

  6. The international reprocessing situation

    International Nuclear Information System (INIS)

    Sornein, J.

    1976-01-01

    It is investigated what volume and availability of reprocessing capacity is needed for LWR (and AGR) fuel elements for Western Europe, USA, and Japan during the period from 1980 to 1990. Taking into account the technical, financial, and licensing difficulties, an optimistic and pessimistic assessment is made especially for Western Europe, and from the findings conclusions are drawn for spent fuel element storage and nuclear power plant construction. (HR/LN) [de

  7. Reprocessing input data validation

    International Nuclear Information System (INIS)

    Persiani, P.J.; Bucher, R.G.; Pond, R.B.; Cornella, R.J.

    1990-01-01

    The Isotope Correlation Technique (ICT), in conjunction with the gravimetric (Pu/U ratio) method for mass determination, provides an independent verification of the input accountancy at the dissolver or accountancy stage of the reprocessing plant. The Isotope Correlation Technique has been applied to many classes of domestic and international reactor systems (light-water, heavy-water, graphite, and liquid-metal) operating in a variety of modes (power, research, production, and breeder), and for a variety of reprocessing fuel cycle management strategies. Analysis of reprocessing operations data based on isotopic correlations derived for assemblies in a PWR environment and fuel management scheme, yielded differences between the measurement-derived and ICT-derived plutonium mass determinations of (-0.02 ± 0.23)% for the measured U-235 and (+0.50 ± 0.31)% for the measured Pu-239, for a core campaign. The ICT analyses has been implemented for the plutonium isotopics in a depleted uranium assembly in a heavy-water, enriched uranium system and for the uranium isotopes in the fuel assemblies in light-water, highly-enriched systems. 7 refs., 5 figs., 4 tabs

  8. VALIDITAS TES CLOZE, TES-C, DAN PENILAIAN DIRI SEBAGAI ALAT UKUR KEMAMPUAN MEMBACA TEKS BAHASA INGGRIS

    Directory of Open Access Journals (Sweden)

    Suharso Suharso

    2013-09-01

    Full Text Available Penelitian ini bertujuan untuk mengetahui validitas tes cloze (CL dan tes-C (C sebagai alat ukur kemampuan membaca teks bahasa Inggris dengan tes Reading Comprehension (RC dari TOEFL sebagai tolok ukur dan mengetahui validitas penilaian diri (PD dengan mengacu pada ketiga tes tersebut. Populasi penelitian meliputi mahasiswa yang mengambil mata kuliah Reading I, III, dan V pada semester gasal tahun akademik 2006/2007 di Program Studi Pendidikan Bahasa Inggris, Fakultas Bahasa dan Seni, Universitas Negeri Yogyakarta. Sampel penelitian terdiri atas 121 mahasiswa yang dipilih dengan menggunakan teknik sampel acak gugus. Data kemampuan membaca dikumpulkan dengan tes RC, CL dan C. Data PD dikumpulkan dengan tiga kuesioner PD yang menggunakan model Likert. Data penelitian dianalisis dengan menggunakan teknik korelasi Pearson product moment. Hasil analisis data menunjukkan bahwa ada korelasi yang positif antara skor tes RC dan skor tes CL, antara skor tes RC dan tes C, dan antara skor PD dan ketiga skor tes membaca tersebut. Kata kunci:      tes reading comprehension, tes cloze, tes-c, penilaian diri, validitas

  9. Case outsourcing medical device reprocessing.

    Science.gov (United States)

    Haley, Deborah

    2004-04-01

    IN THE INTEREST OF SAVING MONEY, many hospitals are considering extending the life of some single-use medical devices by using medical device reprocessing programs. FACILITIES OFTEN LACK the resources required to meet the US Food and Drug Administration's tough quality assurance standards. BY OUTSOURCING, hospitals can reap the benefits of medical device reprocessing without assuming additional staffing and compliance burdens. OUTSOURCING enables hospitals to implement a medical device reprocessing program quickly, with no capital investment and minimal effort.

  10. MOX fuel reprocessing and recycling

    International Nuclear Information System (INIS)

    Guillet, J.L.

    1990-01-01

    This paper is devoted to the reprocessing of MOX fuel in UP2-800 plant at La Hague, and to the MOX successive reprocessing and recycling. 1. MOX fuel reprocessing. In a first step, the necessary modifications in UP2-800 to reprocess MOX fuel are set out. Early in the UP2-800 project, actions have been taken to reprocess MOX fuel without penalty. They consist in measures regarding: Dissolution; Radiological shieldings; Nuclear instrumentation; Criticality. 2. Mox successive reprocessing and recycling. The plutonium recycling in the LWR is now a reality and, as said before, the MOX fuel reprocessing is possible in UP2-800 plant at La Hague. The following actions in this field consist in verifying the MOX successive reprocessing and recycling possibilities. After irradiation, the fissile plutonium content of irradiated MOX fuel is decreased and, in this case, the re-use of plutonium in the LWR need an important increase of initial Pu enrichment inconsistent with the Safety reactor constraints. Cogema opted for reprocessing irradiated MOX fuel in dilution with the standard UO2 fuel in appropriate proportions (1 MOX for 4 UO2 fuel for instance) in order to save a fissile plutonium content compatible with MOX successive recycling (at least 3 recyclings) in LWR. (author). 2 figs

  11. Economic evaluation of reprocessing

    International Nuclear Information System (INIS)

    1978-11-01

    This discussion paper first identifies the main factors which influence the economic assessment of reprocessing. It proposes the use of a diagram - the so-called ''phase diagram'' - which plots the fast reactor premium against the price of uranium. The diagram delineates areas where the once-through fuel cycle, thermal recycle and fast reactor will be the preferred choice from micro-economic considerations. The paper then goes on to consider the circumstances under which a country may or may not wish to introduce thermal recycle or fast reactors. Finally, a procedure for further discussion on economic considerations with WG4 is proposed

  12. Economic evaluation of reprocessing

    International Nuclear Information System (INIS)

    1979-02-01

    This paper presents a progress report of work undertaken relevant to the economic evaluation of reprocessing. It sets out the assumptions to be made for the preparation of the economic ''phase diagram'' - a plot of fast reactor premium against uranium (U 3 O 8 ) price. The paper discusses the assumptions to be made in respect of present worth methodology, LWR fuel logistics, U 3 O 8 price, enrichment tails, plutonium values, fast reactor premium and proposes a set of reference costs to be used for the preparation of the phase diagram

  13. Advances in reprocessing

    International Nuclear Information System (INIS)

    Giraud, J.P.; Guais, J.C.

    1993-01-01

    In a comprehensive nuclear energy program based on Light Water Reactor, closing the nuclear fuel cycle by reprocessing the spent fuel and recycling the recovered fissile materials is a key activity which is now fully mastered at the industrial level. In France a large, modern commercial reprocessing plant called UP3 is operating at La Hague since 18 months in excellent conditions regarding products quality, plant availability, safety and waste management. At the same time, industrial capacities for plutonium recycling by MOX fuel fabrication are under operation and larger units are in construction in France and in Europe. Our customers, the utilities which are engaged in a complete closed fuel cycle in Japan, in Germany, Switzerland, Belgium, the Netherlands, and in France, are having a comprehensive industrial system available for their spent fuel management. Three main objectives are being met by this system: (1) saving natural resources by recycling energetic material: plutonium and uranium; (2) solving the waste management question by a segregating the waste according to their characteristics for a proper conditioning, in particular with vitrification for HLW; and (3) preparing the future developments of nuclear power generation with advanced reactors, and best Pu use, and keeping open progresses in long lived waste processing and disposal

  14. Japanese national reference reprocessing plant

    International Nuclear Information System (INIS)

    1978-08-01

    This paper gives a general description of the proposed Japanese national reprocessing plant and of the design philosophy. The plant is in most respects similar to the base case reprocessing plant, with an annual throughput of 100-1500 tU. The plant would be co-located with a fuel fabrication facility

  15. Fuel reprocessing/fabrication interface

    International Nuclear Information System (INIS)

    Benistan, G.; Blanchon, T.; Galimberti, M.; Mignot, E.

    1987-01-01

    EDF has conducted a major research, development and experimental programme concerning the recycling of plutonium and reprocessed uranium in pressurized water reactors, in collaboration with its major partners in the nuclear fuel cycle industry. Studies already conducted have demonstrated the technical and economic advantages of this recycling, as also its feasibility with due observance of the safety and reliability criteria constantly applied throughout the industrial development of the nuclear power sector in France. Data feedback from actual experience will make it possible to control the specific technical characteristics of MOX and reprocessed uranium fuels to a higher degree, as also management, viewed from the economic standpoint, of irradiated fuels and materials recovered from reprocessing. The next step will be to examine the reprocessing of MOX for reprocessed uranium fuels, either for secondary recycling in the PWR units, or, looking further ahead, in the fast breeders or later generation PWR units, after a storage period of a few years

  16. Reprocessing of nonoptimally exposed holograms

    International Nuclear Information System (INIS)

    Phipps, G.S.; Robertson, C.E.; Tamashiro, F.M.

    1980-01-01

    Two reprocessing techniques have been investigated that are capable of correcting the effects of nonoptimum optical density of photographic amplitude holograms recorded on Agfa-Gevaert type 10E75 plates. In some cases a reprocessed hologram will exhibit a diffraction efficiency even higher than that obtainable from a hologram exposed and processed to the optimum density. The SNR of the reprocessed holograms is much higher than that of the same holograms belached with cupric bromide. In some cases the SNR approaches the optimum value for a properly exposed amplitude hologram. Subjective image quality and resolution of reprocessed hologram reconstructins appear to be no different than for normal single-development holograms. Repeated reprocessing is feasible and in some cases desirable as a means of increasing diffraction efficiency

  17. Thorex reprocessing characterization

    International Nuclear Information System (INIS)

    1978-11-01

    The purpose of this report is to bring together, in highly condensed form, information which would need to be considered in planning a commercial reprocessing plant for recovering 233 U-Th reactor fuel. This report does not include a discussion of process modifications which would be required for thorium-base fuels that contain plutonium (such as would be required for thorium fuels containing 235 U or 233 U denatured with 238 U). It is the intent of this paper to address only the basic Thorex process for treating 233 U-Th fuels. As will be pointed out, the degree of development of the various proposed operations varies widely, from preliminary laboratory experiments for the dissolution of Zircaloy-clad thoria to engineering scale demonstration of the recovery of moderately irradiated thorium by a solvent extraction process (Thorex)

  18. Aqueous reprocessing - some dreams!

    International Nuclear Information System (INIS)

    Srinivasan, T.G.

    2015-01-01

    India has been pursuing a aqueous reprocessing based closed fuel cycle for both thermal and fast reactor fuels employing the PUREX process. Though the country has more than six decades of experience, the dreams or wish lists such as, a highly efficient process with textbook specifications of 99.9% recovery of U and Pu, a DF of more than 10 7 for both U and Pu from the fission products, operating with name plate capacity with high safety, low waste generation, recovery of useful fission products and minor actinides from high level waste are never ceasing and ever growing. The talk will cover safety precautions and actions to be taken in the steps listed below, to ensure a safe and successful process

  19. Characterization of Ir/Au pixel TES

    International Nuclear Information System (INIS)

    Kunieda, Y.; Takahashi, H.; Zen, N.; Damayanthi, R.M.T.; Mori, F.; Fujita, K.; Nakazawa, M.; Fukuda, D.; Ohkubo, M.

    2006-01-01

    Signal shapes and noise characteristics of an asymmetrical ten-pixel Ir/Au-TES have been studied. The asymmetric design may be effective to realize an imaging spectrometer. Distinct two exponential decays observed for X-ray events are consistent with a two-step R-T curve. A theoretical thermal model for noise in multi-pixel devices reasonably explains the experimental data

  20. Emission Ratios for Ammonia and Formic Acid and Observations of Peroxy Acetyl Nitrate (PAN and Ethylene in Biomass Burning Smoke as Seen by the Tropospheric Emission Spectrometer (TES

    Directory of Open Access Journals (Sweden)

    Vivienne H. Payne

    2011-11-01

    Full Text Available We use the Tropospheric Emission Spectrometer (TES aboard the NASA Aura satellite to determine the concentrations of the trace gases ammonia (NH3 and formic acid (HCOOH within boreal biomass burning plumes, and present the first detection of peroxy acetyl nitrate (PAN and ethylene (C2H4 by TES. We focus on two fresh Canadian plumes observed by TES in the summer of 2008 as part of the Arctic Research of the Composition of the Troposphere from Aircraft and Satellites (ARCTAS-B campaign. We use TES retrievals of NH3 and HCOOH within the smoke plumes to calculate their emission ratios (1.0% ± 0.5% and 0.31% ± 0.21%, respectively relative to CO for these Canadian fires. The TES derived emission ratios for these gases agree well with previous aircraft and satellite estimates, and can complement ground-based studies that have greater surface sensitivity. We find that TES observes PAN mixing ratios of ~2 ppb within these mid-tropospheric boreal biomass burning plumes when the average cloud optical depth is low ( < 0.1 and that TES can detect C2H4 mixing ratios of ~2 ppb in fresh biomass burning smoke plumes.

  1. Experience and prospects in reprocessing

    International Nuclear Information System (INIS)

    Rougeau, J.-P.

    1997-01-01

    Reprocessing nuclear fuels is a long and successful industrial story. For decades, commercial reprocessing plants have been operating in France, the United Kingdom and Japan. The industrial outcome is clear and widely recognized: thousand tons of spent fuels have been reprocessed in these plants. Over the years, these facilities have been adapted to new types of fuel. Thus, the nuclear industry has fully demonstrated its ability to cope with technological change and its capacity to adapt itself to improvements. For decades, technical capability has been stressed and emphasized by nuclear industrial leaders as the most important point. This is no longer the case. Today the industry has to face a new commercial reality and to find the most adaptable answer to the utilities' requirements. This paper presents the current achievements and medium and long-term trends of the nuclear reprocessing activity, the ongoing commercial changes and gives an outlook for future evolutions. International political factors will also be examined. (author)

  2. Present state of reprocessing

    International Nuclear Information System (INIS)

    Huppert, K.L.

    1977-01-01

    The operation of several reprocessing plants - industrial size and pilot plants - has made it possible to build up substantial experience in the processing of irradiated fuels. More than 28,000 tons of fuels from gas-graphite reactors were processed on an industrial basis in Britain and France. For the treatment of both metallic fuels and high burn-up UO 2 -fuels, a solvent extraction process is applied which is based on the Purex process with a TBP kerosene mixture as extractant. A shear-leach technique is used for the break-down of the bundle elements and dissolution of the uranium oxide in nitric acid. Mechanically agitated extractors and pulsed columns have proved to be reliable equipment. The products are uranyl nitrate and plutonium nitrate. Process chemicals are recycled to minimize the volume of radioactive waste and precautions are taken to prevent uncontrolled escape of radioactivity. The technical status will be described as well as experience from pilot operation. (orig.) [de

  3. Base case industrial reprocessing plant

    International Nuclear Information System (INIS)

    1978-11-01

    This paper briefly describes an industrial scale plant for reprocessing thermal oxide fuel. This description was used as a base case by the Group for their later assessments and for comparing actual national plans for reprocessing plants. The plant described uses the Purex process and assumes an annual throughput of 1000 t/U. The maintenance, safety and safeguards philosophy is described. An indication of the construction schedule and capital and operating costs is also given

  4. Reprocessing in breeder fuel cycles

    International Nuclear Information System (INIS)

    Burch, W.D.; Groenier, W.S.

    1982-01-01

    Over the past decade, the United States has developed plans and carried out programs directed toward the demonstration of breeder fuel reprocessing in connection with the first breeder demonstration reactor. A renewed commitment to moving forward with the construction of the Clinch River Breeder Reactor (CRBR) has been made, with startup anticipated near the end of this decade. While plans for the CRBR and its associated fuel cycle are still being firmed up, the basic research and development programs required to carry out the demonstrations have continued. This paper updates the status of the reprocessing plans and programs. Policies call for breeder recycle to begin in the early to mid-1990's. Contents of this paper are: (1) evolving plans for breeder reprocessing (demonstration reprocessing plant, reprocessing head-end colocated at an existing facility); (2) relationship to LWR reprocessing; (3) integrated equipment test (IET) facility and related hardware development activities (mechanical considerations in shearing and dissolving, remote operations and maintenance demonstration phase of IET, integrated process demonstration phase of IET, separate component development activities); and (4) supporting process R and D

  5. Reprocessing of spent nuclear fuel

    International Nuclear Information System (INIS)

    Kidd, S.

    2008-01-01

    The closed fuel cycle is the most sustainable approach for nuclear energy, as it reduces recourse to natural uranium resources and optimises waste management. The advantages and disadvantages of used nuclear fuel reprocessing have been debated since the dawn of the nuclear era. There is a range of issues involved, notably the sound management of wastes, the conservation of resources, economics, hazards of radioactive materials and potential proliferation of nuclear weapons. In recent years, the reprocessing advocates win, demonstrated by the apparent change in position of the USA under the Global Nuclear Energy Partnership (GNEP) program. A great deal of reprocessing has been going on since the fourties, originally for military purposes, to recover plutonium for weapons. So far, some 80000 tonnes of used fuel from commercial power reactors has been reprocessed. The article indicates the reprocessing activities and plants in the United Kigdom, France, India, Russia and USA. The aspect of plutonium that raises the ire of nuclear opponents is its alleged proliferation risk. Opponents of the use of MOX fuels state that such fuels represent a proliferation risk because the plutonium in the fuel is said to be 'weapon-use-able'. The reprocessing of used fuel should not give rise to any particular public concern and offers a number of potential benefits in terms of optimising both the use of natural resources and waste management.

  6. Reprocessing of nuclear fuels

    International Nuclear Information System (INIS)

    Hatfield, G.W.

    1960-11-01

    One of the persistent ideas concerning nuclear power is that the fuel costs are negligible. This, of course, is incorrect and, in fact, one of the major problems in the development of economic nuclear power is to get the cost of the fuel cycles down to an acceptable level. The irradiated fuel removed from the nuclear power reactors must be returned as fresh fuel into the system. Aside from the problems of handling and shipping involved in the reprocessing cycles, the two major steps are the chemical separation and the refabrication. The chemical separation covers the processing of the spent fuel to separate and recover the unburned fuel as well as the new fuel produced in the reactor. This includes the decontamination of these materials from other radioactive fission products formed in the reactor. Refabrication involves the working and sheathing of recycled fuel into the shapes and forms required by reactor design and the economics of the fabrication problem determines to a large extent the quality of the material required from the chemical treatment. At present there appear to be enough separating facilities in the United States and the United Kingdom to handle the recycling of fuel from power reactors for the next few years. However, we understand the costs of recycling fuel in these facilities will be high or low depend ing on whether or not the capital costs of the plant are included in the processing cost. Also, the present plants may not be well adapted to carry out the chemical processing of the very wide variety of power reactor fuel elements which are being considered and will continue to be considered over the years to come. (author)

  7. Indian experience in fuel reprocessing

    International Nuclear Information System (INIS)

    Prasad, A.N.; Kumar, S.V.

    1977-01-01

    Plant scale experience in fuel reprocessing in India was started with the successful design, execution and commissioning of the Trombay plant in 1964 to reprocess aluminium clad metallic uranium fuel from the 40 MWt research reactor. The plant has helped in generating expertise and trained manpower for future reprocessing plants. With the Trombay experience, a larger plant of capacity 100 tonnes U/year to reprocess spent oxide fuels from the Tarapur (BWR) and Rajasthan (PHWR) power reactors has been built at Tarapur which is undergoing precommissioning trial runs. Some of the details of this plant are dealt with in this paper. In view of the highly corrosive chemical attack the equipment and piping are subjected to in a fuel reprocessing plant, some of them require replacement during their service if the plant life has to be extended. This calls for extensive decontamination for bringing the radiation levels low enough to establish direct accesss to such equipment. For making modifications in the plant to extend its life and also to enable expansion of capacity, the Trombay plant has been successfully decontaminated and partially decommissioned. Some aspects of thi decontamination campaign are presented in this paper

  8. Reprocessing of spent nuclear fuel

    International Nuclear Information System (INIS)

    Schmitt, D.

    1985-01-01

    How should the decision in favour of reprocessing and against alternative waste management concepts be judged from an economic standpoint. Reprocessing is not imperative neither for resource-economic reasons nor for nuclear energy strategy reasons. On the contrary, the development of an ultimate storage concept representing a real alternative promising to close, within a short period of time, the nuclear fuel cycle at low cost. At least, this is the result of an extensive economic efficiency study recently submitted by the Energy Economics Institute which investigated all waste management concepts relevant for the Federal Republic of Germany in the long run, i.e. direct ultimate storage of spent fuel elements (''Other waste disposal technologies'' - AE) as well as reprocessing of spent fuel elements where re-usable plutonium and uranium are recovered and radioactive waste goes to ultimate storage (''Integrated disposal'' - IE). Despite such fairly evident results, the government of the Federal Republic of Germany has favoured the construction of a reprocessing plant. From an economic point of view there is no final answer to the question whether or not the argumentation is sufficient to justify the decision to construct a reprocessing plant. This is true for both the question of technical feasibility and issues of overriding significance of a political nature. (orig./HSCH) [de

  9. Radioactive wastes from reprocessing plants

    International Nuclear Information System (INIS)

    Huppert, K.L.

    1977-01-01

    The lecture deals with definition, quantity and type of radioactive waste products occurring in a fuel reprocessing plant. Solid, liquid and gaseous fission and activation products are formed during the dissolution of the fuel and during the extraction process, and they must be separated from the fissionalble uranium and plutonium not spent. The chemical behaviour of these products (Zr, Ru, Np, gaseous substances, radiolysis products), which is sometimes very problematic, necessitates careful process control. However, the lifetime of nuclides is just as important for the conditions of the reprocessing procedure. The types of waste obtained after reprocessing are classified according to their state of aggregation and level of activity and - on the basis of the operational data of a prototype plant - they are quantitatively extrapolated for the operation of a large-scale facility of 1,400 tons of fuel annually. (RB) [de

  10. Fuel reprocessing and waste management

    International Nuclear Information System (INIS)

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

    1989-01-01

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

  11. The recycling of reprocessed uranium

    International Nuclear Information System (INIS)

    Lannegrace, J.-P.

    1991-01-01

    The 1990 update to the Uranium Institute's report ''Uranium Market Issues'', presented to this Symposium last year (1990) stated that the impact of recycled reprocessing products on uranium demand would be limited in the near future to that due to MOX fuel fabrication. The report stated that the recycling of reprocessed uranium was still at an early discussion stage, rather than being a short-term prospect. This paper will set out to challenge this assertion, on the basis both of facts and of economic and environmental incentives. (author)

  12. Determinan Perilaku Tes HIV pada Ibu Hamil

    Directory of Open Access Journals (Sweden)

    Nanik Setiyawati

    2015-04-01

    pengetahuan tentang HIV dan AIDS, persepsi kerentanan diri dan sikap ibu. Ada hubungan antara PITC, ketersediaan sumber informasi tentang HIV dan AIDS dari keluarga dan kader kesehatan dengan perilaku tes HIV pada ibu hamil. PITC merupakan variabel yang paling berpengaruh terhadap perilaku tes HIV pada ibu hamil. Determinant of HIV Testing Behavior among Pregnant Women Human immunodeficiency virus (HIV and Acquired immune deficiency syndrome (AIDS is one of highlighted issues in accomplishing Millenium Development Goals (MDGs target. Pregnant women with HIV will transmit the virus to their babies. HIV testing is such an opening gate of HIV status that is very important to be conducted on pregnant women. This study aimed to determine the determinant of HIV testing behaviour among pregnant women including education level, knowledge level, perception of selfvulnerability to be HIV-infected, attitudes, Provider-Initiated Testing and Counseling (PITC and availability of information (family and health workers. This study was cross sectional using a survey method. This study was conducted in Mantrijeron and Sleman Primary Health Care that had HIV testing facilities and executed prevention of mother to child transmission program. The subjects of this study were pregnant women visiting such primary health care on August up to October 2014, as much as 54 people. Data collecting used questionnaire. Analysed used were univariate, biviariate, and multivariate. The results showed no relation between educational level, knowledge level about HIV and AIDS, perception of self-vulnerability and attitudes of women.There was a relation between PITC, information source availability about HIV and AIDS from the family and health workers with HIV testing behaviour among pregnant women. PITC is the most influencing variable toward HIV testing behaviour among pregnant women.

  13. Development, experience and innovation in reprocessing

    International Nuclear Information System (INIS)

    Delange, M.

    1985-01-01

    The author describes landmarks in the development of the reprocessing industry in France and then presents objectives for the future (extension of reprocessing of fuel from breeder reactors) together with the technological resources deployed to attain them [fr

  14. Outline of human machine interface at Rokkasho reprocessing plant

    International Nuclear Information System (INIS)

    Niioka, T.; Miyazaki, T.; Fujita, D.; Esashika, A.; Yoshida, Y.; Nakamura, W.; Tochigi, T.; Yoshimoto, A.; Yokoi, M.

    2006-01-01

    The Japan Nuclear Fuel Limited (JNFL) has been performing the active tests since the end of March, 2006, for its Rokkasho Reprocessing Plant using the spent fuels retrieved from the Light Water Reactors. At the early stage of the tests relatively low burn-up fuels have been used, and the burn-up will be increased at later stages until the start of commercial operation planned next year. The plant is operated from the main control room in the Control Building, where two types of operator consoles are located for plant monitoring and operation. The Operator Interface Station (OIS) driven by computer systems is chiefly used for instrumentation and control for production activities during normal operation. In addition to this, safety panels composed of hardware circuits are installed for nuclear safety functions such as criticality safety management, explosion protection, and confinement of radioactive materials. This paper outlines the Human Machine Interface features applied to the Rokkasho Reprocessing Plant. (authors)

  15. Nuclear fuel reprocessing is challenged

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    This article is a brief discussion of litigation to determine if the Thermal Oxide Reprocessing Plant (THORP) in the United Kingdom will be allowed to operate. Litigants (including Greenpeace) contend that the government's December approval of discharge permits for the plant was unlawful without a public hearing. A description of the THORP process is also provided in this article

  16. Reprocessing of spent nuclear fuel

    International Nuclear Information System (INIS)

    Gal, I.

    1964-12-01

    This volume contains the following reports: Experimental facility for testing and development of pulsed columns and auxiliary devices; Chemical-technology study of the modified 'Purex' process; Chemical and radiometric control analyses; Chromatographic separation of rare earth elements on paper treated by di-n butylphosphate; Preliminary study of some organic nitrogen extracts significant in fuel reprocessing

  17. Status and prospects for reprocessing

    International Nuclear Information System (INIS)

    Rossney, G.K.

    1977-01-01

    Following the formation of United Reprocessors (U.R.G.) in 1976 by British Nuclear Fuels Limited (B.N.F.L.) in the United Kingdom, the Commissariat a l'Energie Atomique (C.E.A.) in France and K.E.W.A. Kernbrennstoff-Wiederaufarbeitungs-Gesellschaft MBH (K.E.W.A.) in Germany, collaboration is now well established for the marketing of their reprocessing services for irradiated oxide fuel from thermal reactors. In addition collaboration in the continued evolution of the technology has progressed and an extensive research and development programme has been established, the results of which are exchanged between the shareholders. During 1976 the U.K. Government has given approval to B.N.F.L. to sign further contracts with foreign customers, subject to certain conditions. In France, the fuel cycle activities of the C.E.A. have been vested in a new company (Compagnie Generale Des Matieres Nucleaires (C.O.G.E.M.A.)) and their La Hague plant has commenced reprocessing operations on irradiated oxide fuel. In Germany, an agreement has been signed between K.E.W.A. and P.W.K. for the pre-project study for the proposed German plant. Against this background this paper reviews the present status of reprocessing by the shareholders of U.R.G. and the prospects for reprocessing

  18. Demonstration of EnergyNest thermal energy storage (TES) technology

    Science.gov (United States)

    Hoivik, Nils; Greiner, Christopher; Tirado, Eva Bellido; Barragan, Juan; Bergan, Pâl; Skeie, Geir; Blanco, Pablo; Calvet, Nicolas

    2017-06-01

    This paper presents the experimental results from the EnergyNest 2 × 500 kWhth thermal energy storage (TES) pilot system installed at Masdar Institute of Science & Technology Solar Platform. Measured data are shown and compared to simulations using a specially developed computer program to verify the stability and performance of the TES. The TES is based on a solid-state concrete storage medium (HEATCRETE®) with integrated steel tube heat exchangers cast into the concrete. The unique concrete recipe used in the TES has been developed in collaboration with Heidelberg Cement; this material has significantly higher thermal conductivity compared to regular concrete implying very effective heat transfer, at the same time being chemically stable up to 450 °C. The demonstrated and measured performance of the TES matches the predictions based on simulations, and proves the operational feasibility of the EnergyNest concrete-based TES. A further case study is analyzed where a large-scale TES system presented in this article is compared to two-tank indirect molten salt technology.

  19. Fuel reprocessing and environmental problem

    International Nuclear Information System (INIS)

    Ichikawa, Ryushi

    1977-01-01

    The radioactive nuclides which are released from the reprocessing plants of nuclear fuel are 137 Cs, 106 Ru, 95 Zr and 3 H in waste water and 85 Kr in the atmosphere. This release affects the environment for example, the reprocessing plant of the Nuclear Fuel Service Co in the USA releases about 2 x 10 5 Ci/y of 85 Kr, which is evaluated as about 0.025 mr/y as external exposure dose. The radioactivity in milk around this plant was measured as less than 10 pCi/lit of 129sup(I. The radioactive concentration in the sea, especially in fish and shellfish, was measured near the reprocessing plant of Windscale in UK. The radioactive release rate from this plants more than 10)5sup( Ci/y as the total amount of )137sup(Cs, )3sup(H, )106sup(Ru, )95sup(Zr, )95sup(Nb, )90sup(Sr, )144sup(Ce, etc., and the radioactivity in seaweeds near Windscale is about 400 pCi/g as the maximum value, and the mayonnaise which was made of this seaweeds contained about 1 pCi/g of )106sup(Ru, which is estimated as about 7 mr/y for the digestive organ if 100 g is eaten every day. On the other hand, the experimental result is presented for the reprocessing plant of La Hague in France, in which the radioactive release rate from this plant is about 10)4sup( Ci/y, and the radioactivity in sea water and shellfish is about 4 pCi/l of )106sup(Ru and about 400 pCi/kg of )137 Cs, respectively, near this plant. The philosophy of ALAP (as low as practicable) is also applied to reprocessing plants. (Nakai, Y.)

  20. Reprocessing of LEU silicide fuel at Dounreay

    International Nuclear Information System (INIS)

    Cartwright, P.

    1996-01-01

    UKAEA have recently reprocessed two LEU silicide fuel elements in their MTR fuel reprocessing plant at Dounreay. The reprocessing was undertaken to demonstrate UKAEA's commitment to the world-wide research reactor communities future needs. Reprocessing of LEU silicide fuel is seen as a waste treatment process, resulting in the production of a liquid feed suitable for conditioning in a stable form of disposal. The uranium product from the reprocessing can be used as a blending feed with the HEU to produce LEU for use in the MTR cycle. (author)

  1. Reprocessing and waste management in the UK

    International Nuclear Information System (INIS)

    Mogg, C.S.; Howarth, G.G.

    1987-01-01

    The paper concerns the progress in irradiated fuel reprocessing and waste management at the Sellafield site. Magnox fuel reprocessing is reviewed and oxide fuel reprocessing, due to commence in the early 1990s, is compared with existing practices. The article describes how magnox fuel reprocessing will be sustained by recent additions of new plant and shows how waste management downstream of reprocessing will be integrated across the Sellafield site. This article was first presented as a paper at the Waste Management '87 (1-5 March, Tucson, Arizona) conference. (author)

  2. Trends in fuel reprocessing safety research

    International Nuclear Information System (INIS)

    Tsujino, Takeshi

    1981-01-01

    With the operation of a fuel reprocessing plant in the Power Reactor and Nuclear Fuel Development Corporation (PNC) and the plan for a second fuel reprocessing plant, the research on fuel reprocessing safety, along with the reprocessing technology itself, has become increasingly important. As compared with the case of LWR power plants, the safety research in this field still lags behind. In the safety of fuel reprocessing, there are the aspects of keeping radiation exposure as low as possible in both personnel and local people, the high reliability of the plant operation and the securing of public safety in accidents. Safety research is then required to establish the safety standards and to raise the rate of plant operation associated with safety. The following matters are described: basic ideas for the safety design, safety features in fuel reprocessing, safety guideline and standards, and safety research for fuel reprocessing. (J.P.N.)

  3. Training Exit Survey (TES) Individual State and Tribe

    Data.gov (United States)

    U.S. Department of Health & Human Services — The TES Individual dataset contains information at the individual-level about the persons who attend a GLS funded training event. This dataset includes variables...

  4. Management of radioactive solid waste arisings from PFR reprocessing

    International Nuclear Information System (INIS)

    Allardice, R.H.; Hackney, S.; Bailey, G.; Bremner, W.; Lillyman, E.; Pugh, O.; Reekie, J.

    1982-01-01

    A description is given of the solid radioactive waste management facilities for dealing with the arisings from PFR reprocessing at the Dounreay Nuclear Power Development Establishment. Four major categories of solid waste are identified. The 'La Calhene' posting system for the transfer of active wastes which has been installed is discussed. The three new retrievable stores for high α#betta##betta#, high α low #betta##betta# and low α high #betta##betta# are described. The methods of waste categorisation by non-destructive assay techniques are outlined. Finally a review of operating experience with the facilities is presented. (U.K.)

  5. The environmental impact of reprocessing

    International Nuclear Information System (INIS)

    Mummery, P.W.; Howells, H.; Scriven, A.

    1980-01-01

    The subject is discussed under the headings: introduction; basis of hazard assessment (dose limits - ICRP recommendations; biological radiation effects); comparison of standards and practice in the UK and USA in the limitation of exposure of the public as a consequence of discharges of radioactive effluent to the environment; nature of reprocessing operations (Thermal Oxide Fuel Reprocessing Plant (THORP); storage ponds; fuel shearing; leaching; clarification; solvent extraction; finishing); waste management (liquids, solids, gases); waste discharges; environmental impact of normal operations (identification of the critical groups; exposure of critical groups; risks and exposures, occupational and collective); environmental impact of accidents (risk - probability multiplied by consequence of the event; types of accident considered); conclusion. (U.K.)

  6. Waste management in reprocessing plants

    International Nuclear Information System (INIS)

    Mortreuil, M.

    1982-01-01

    This lecture will give a survey of the French policy for the management of wastes in reprocessing plants. In consideration of their radioactivity, they must be immobilized in matrix in such a manner that they are stored under optimal safety conditions. A general review on the nature, nucleide content and quantity of the various wastes arising from thermal nuclear fuel reprocessing is given in the light of the French plants UP1 at Marcoule and UP2 at La Hague. The procedures of treatment of such wastes and their conditioning into inert packages suitable for temporary or terminal storage are presented, especially concerning the continuous vitrification process carried out for fission product solutions. The requirements of each option are discussed and possible alternative solutions are exposed. (orig./RW)

  7. Chemical problems associated with reprocessing

    International Nuclear Information System (INIS)

    Chesne, A.

    1981-09-01

    This paper is an attempt to pinpoint the chemical problems raised by the reprocessing of oxide base fuels. Taking the reprocessing of slightly irradiated metallic fuels as a reference, for which long experience has been gained, a review is made of the various stages of the Purex process, in which the increase in mass and activity of the actinides and fission products engenders constraints related to the recovery of fissile materials, their purification, the release rate and, in general, the operation of the installations. The following subjects are discussed: dissolution from the standpoint of dissolution residues and iodine trapping, extraction cycles with respect to the behavior of ruthenium, neptunium, plutonium, technetium and palladium, the recycling of medium activity wastes

  8. Green light for Japanese reprocessing

    International Nuclear Information System (INIS)

    Patermann, C.

    1981-01-01

    In the last few years, international discussions of peaceful nuclear energy use and non-proliferation have been greatly influenced by the attitude of the US Government. Since the mid-Seventies, in the Carter area, this attitude has changed due to the fear that world-wide use of so-called sensitive technologies, i.e. uranium enrichment, reprocessing, and fast breeder development may increase the hazard of misuse for the production of nuclear weapons. (orig.) [de

  9. Remote handling in reprocessing plants

    International Nuclear Information System (INIS)

    Streiff, G.

    1984-01-01

    Remote control will be the rule for maintenance in hot cells of future spent fuel reprocessing plants because of the radioactivity level. New handling equipments will be developed and intervention principles defined. Existing materials, recommendations for use and new manipulators are found in the PMDS' documentation. It is also a help in the choice and use of intervention means and a guide for the user [fr

  10. Nuclear fuel reprocessing in the UK

    International Nuclear Information System (INIS)

    Allardice, R.; Harris, D.; Mills, A.

    1983-01-01

    Nuclear fuel reprocessing has been carried out on an industrial scale in the United Kingdom since 1952. Two large reprocessing plants have been constructed and operated at Windscale, Cumbria and two smaller specialized plants have been constructed and operated at Dounreay, Northern Scotland. At the present time, the second of the two Windscale plants is operating, and Government permission has been given for a third reprocessing plant to be built on that site. At Dounreay, one of the plants is operating in its original form, whilst the second is now operating in a modified form, reprocessing fuel from the prototype fast reactor. This chapter describes the development of nuclear fuel reprocessing in the UK, commencing with the research carried out in Canada immediately after the Second World War. A general explanation of the techniques of nuclear fuel reprocessing and of the equipment used is given. This is followed by a detailed description of the plants and processes installed and operated in the UK

  11. Commercial Nuclear Reprocessing in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Sherrill, Charles Leland [Brigham Young Univ., Provo, UT (United States); Balatsky, Galya Ivanovna [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-09-09

    The short presentation outline: Reprocessing Overview; Events leading up to Carter’s Policy; Results of the decision; Policy since Nuclear Nonproliferation Act. Conclusions reached: Reprocessing ban has become an easy and visible fix to the public concern about proliferation, but has not completely stopped proliferation; and, Reprocessing needs to become detached from political considerations, so technical research can continue, regardless of the policy decisions we decide to take.

  12. The importance of nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Allday, C.

    1977-01-01

    The subject is discussed under the following main headings: introduction; world energy requirement; energy conservation and the economics of recycle; environmental considerations and the timescale of reprocessing; and problems associated with reprocessing. It is concluded that reprocessing is essential to the conservation of the world's energy resources and is an environmentally and probably an economically more acceptable option to the 'throw away' alternative. The associated problems of proliferation and terrorism, although of the utmost importance, can and will be solved. (U.K.)

  13. Consolidated fuel reprocessing program. Developments for the future in reprocessing

    International Nuclear Information System (INIS)

    Burch, W.D.

    1982-01-01

    The future reprocessing developments focus on three major areas: (1) the retention of gaseous fission products to reduce off-site doses to very low values; (2) the initial steps of breakdown, shearing, and dissolution of breeder fuels; and (3) advanced facility and equipment concepts, which are expected to lead to a reliable, cost-effective, totally remotely operated and maintained plant. Work in the first area - removal of fission gases (the most important of which is 85 Kr) - is largely completed through tracer and bench-scale engineering equipment. Efforts are now mainly devoted to breeder fuels and advanced remote concepts. A facility, the Integrated Equipment Test Facility, which will be used to carry out much of this work, is nearing completion in Oak Ridge. In it a large, simulated, remote reprocessing cell will house a disassembly-shear machine for either breeder or LWR fuels, a rotary continuous dissolver, a solvent extraction cycle utilizing a new generation of centrifugal contactors, and related equipment

  14. Statement on the Consolidated Fuel Reprocessing Program

    International Nuclear Information System (INIS)

    Trauger, D.B.

    1984-01-01

    Oak Ridge National Laboratory has chosen the following objectives for future reprocessing plant design: reduced radiation exposure to workers; minimal environmental impact; improved plant operation and maintenance; improved accountability; no plutonium diversion; and reduced overall capital and operating cost. These objectives lead to a plant with totally remote operation. The Breeder Reactor Engineering Test (BRET) has been designed to perform a key role in demonstrating advanced reprocessing technology. It has been scheduled to be available to reprocess spent fuel from the Fast Flux Test Facility. The principal features of the Consolidated Fuel Reprocessing Program and of the BRET facility are appropriate for all reactor types

  15. Nuclear fuel reprocessing expansion strategies

    International Nuclear Information System (INIS)

    Gallagher, J.M.

    1975-01-01

    A description is given of an effort to apply the techniques of operations research and energy system modeling to the problem of determination of cost-effective strategies for capacity expansion of the domestic nuclear fuel reprocessing industry for the 1975 to 2000 time period. The research also determines cost disadvantages associated with alternative strategies that may be attractive for political, social, or ecological reasons. The sensitivity of results to changes in cost assumptions was investigated at some length. Reactor fuel types covered by the analysis include the Light Water Reactor (LWR), High-Temperature Gas-Cooled Reactor (HTGR), and the Fast Breeder Reactor (FBR)

  16. Waste streams from reprocessing operations

    International Nuclear Information System (INIS)

    Andersson, B.; Ericsson, A.-M.

    1978-03-01

    The three main products from reprocessing operations are uranium, plutonium and vitrified high-level-waste. The purpose of this report is to identify and quantify additional waste streams containing radioactive isotops. Special emphasis is laid on Sr, Cs and the actinides. The main part, more than 99 % of both the fission-products and the transuranic elements are contained in the HLW-stream. Small quantities sometimes contaminate the U- and Pu-streams and the rest is found in the medium-level-waste

  17. Reprocessing and fuel fabrication systems

    International Nuclear Information System (INIS)

    Field, F.R.; Tooper, F.E.

    1978-01-01

    The study of alternative fuel cycles was initiated to identify a fuel cycle with inherent technical resistance to proliferation; however, other key features such as resource use, cost, and development status are major elements in a sound fuel cycle strategy if there is no significant difference in proliferation resistance. Special fuel reprocessing techniques such as coprocessing or spiking provide limited resistance to diversion. The nuclear fuel cycle system that will be most effective may be more dependent on the institutional agreements that can be implemented to supplement the technical controls of fuel cycle materials

  18. Transformative monitoring approaches for reprocessing.

    Energy Technology Data Exchange (ETDEWEB)

    Cipiti, Benjamin B.

    2011-09-01

    The future of reprocessing in the United States is strongly driven by plant economics. With increasing safeguards, security, and safety requirements, future plant monitoring systems must be able to demonstrate more efficient operations while improving the current state of the art. The goal of this work was to design and examine the incorporation of advanced plant monitoring technologies into safeguards systems with attention to the burden on the operator. The technologies examined include micro-fluidic sampling for more rapid analytical measurements and spectroscopy-based techniques for on-line process monitoring. The Separations and Safeguards Performance Model was used to design the layout and test the effect of adding these technologies to reprocessing. The results here show that both technologies fill key gaps in existing materials accountability that provide detection of diversion events that may not be detected in a timely manner in existing plants. The plant architecture and results under diversion scenarios are described. As a tangent to this work, both the AMUSE and SEPHIS solvent extraction codes were examined for integration in the model to improve the reality of diversion scenarios. The AMUSE integration was found to be the most successful and provided useful results. The SEPHIS integration is still a work in progress and may provide an alternative option.

  19. Reprocessing process simulation network; PRONET

    International Nuclear Information System (INIS)

    Mitsui, T.; Takada, H.; Kamishima, N.; Tsukamoto, T.; Harada, N.; Fujita, N.; Gonda, K.

    1991-01-01

    The effectiveness of simulation technology and its wide application to nuclear fuel reprocessing plants has been recognized recently. The principal aim of applying simulation is to predict the process behavior accurately based on the quantitative relations among substances in physical and chemical phenomena. Mitsubishi Heavy Industries Ltd. has engaged positively in the development and the application study of this technology. All the software products of its recent activities were summarized in the integrated form named 'PRONET'. The PRONET is classified into two independent software groups from the viewpoint of computer system. One is off-line Process Simulation Group, and the other is Dynamic Real-time Simulator Group. The former is called 'PRONET System', and the latter is called 'PRONET Simulator'. These have several subsystems with the prefix 'MR' meaning Mitsubishi Reprocessing Plant. Each MR subsystem is explained in this report. The technical background, the objective of the PRONET, the system and the function of the PRONET, and the future application to an on-line real-time simulator and the development of MR EXPERT are described. (K.I.)

  20. Tritium control in reprocessing plants

    International Nuclear Information System (INIS)

    Goumondy, J.P.; Miquel, P.

    1977-01-01

    There is a danger that the T which is formed in water reactors will prove detrimental to the environment over the next few years, and studies have been undertaken to develop techniques to contain and process it where possible. In order to retain T, which is present largely in the fuel and on the possible to adapt for use in the conventional design of reprocessing plant. In this process T is maintained in the form of an aqueous solution in the high-active area of the plant. Control is achieved by restricting as far as possible the ingress of non-tritiated water into this area, and by setting up a tritiated water barrier at the first U and Pu extraction stage, stripping the tritium-containing solvent at that point with ordinary water. In this way the T can be extracted in a small volume of water with a view to intermediate storage, disposal at sea additional processing to remove the T from the water. Experiments carried out so far have demonstrated the effectiveness of the T barrier and have shown what equipment would be required for the application of the process in new reprocessing plants. (orig.) [de

  1. Transport and reprocessing of irradiated nuclear fuel

    International Nuclear Information System (INIS)

    Lenail, B.

    1981-01-01

    This contribution deals with transport and packaging of oxide fuel from and to the Cogema reprocessing plant at La Hague (France). After a general discussion of nuclear fuel and the fuel cycle, the main aspects of transport and reprocessing of oxide fuel are analysed. (Auth.)

  2. THORP and the economics of reprocessing

    International Nuclear Information System (INIS)

    Berkhout, F.; Walker, W.

    1990-11-01

    This Report compares the costs of reprocessing spent fuels at the new THORP reprocessing plant at Sellafield with the alternative of storing them prior to final disposal. It finds that even when the cost of constructing THORP is treated as a sunk cost, reprocessing has no decisive economic advantage over spent fuel storage. Electric utilities in Western Europe and Japan have already largely paid for the construction of the new British and French reprocessing plants. Today, their economic judgements therefore depend on the future costs of operating and eventually decommissioning the plants, and of dealing with the resulting wastes and separated products. The costs attached to reprocessing have risen mainly due to the higher estimated costs of waste management and decommissioning, and to the costs of coping with unwanted plutonium. Most of these costs are passed directly on to utilities and thus electricity consumers under the terms of cost-plus contracts. Using cost estimates favourable to the reprocessing option, the total future undiscounted liabilities arising from the first ten years of THORP reprocessing come to Pound 2.4-3.7 billion at today's prices. This compares with the more predictable although still burdensome fuel storage, conditioning and disposal costs of Pound 3.0-3.8 billion. If disposal is not anticipated, the economic advantage shifts decisively in favour of spent fuel storage: Pound 0.9-1.3 billion against Pound 1.4-2.4 billion for reprocessing. (author)

  3. Reprocessing of nuclear fuels - status report

    International Nuclear Information System (INIS)

    Schueller, W.

    1976-01-01

    The paper gives a survey on reprocessing plants at present under construction, in operation, and planned, as well as on the most important process steps such as receipt, storage, conversion, the extraction process, purification of the end products, gaseous waste treatment and waste treatment, and repair and maintenance of reprocessing plants. An outline on operational experience with WAK follows. (HR/LN) [de

  4. New rules set for uranium reprocessing

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    The Australian Government policy regarding the reprocessing of Australian uranium overseas is outlined. Buyer nations will be required to sign an agreement that the uranium will be reprocessed only for energy uses and that approved waste management standards will be met

  5. Fast reactor fuel reprocessing. An Indian perspective

    International Nuclear Information System (INIS)

    Natarajan, R.; Raj, Baldev

    2005-01-01

    The Department of Atomic Energy (DAE) envisioned the introduction of Plutonium fuelled fast reactors as the intermediate stage, between Pressurized Heavy Water Reactors and Thorium-Uranium-233 based reactors for the Indian Nuclear Power Programme. This necessitated the closing of the fast reactor fuel cycle with Plutonium rich fuel. Aiming to develop a Fast Reactor Fuel Reprocessing (FRFR) technology with low out of pile inventory, the DAE, with over four decades of operating experience in Thermal Reactor Fuel Reprocessing (TRFR), had set up at the India Gandhi Center for Atomic Research (IGCAR), Kalpakkam, R and D facilities for fast reactor fuel reprocessing. After two decades of R and D in all the facets, a Pilot Plant for demonstrating FRFR had been set up for reprocessing the FBTR (Fast Breeder Test Reactor) spent mixed carbide fuel. Recently in this plant, mixed carbide fuel with 100 GWd/t burnup fuel with short cooling period had been successfully reprocessed for the first time in the world. All the challenging problems encountered had been successfully overcome. This experience helped in fine tuning the designs of various equipments and processes for the future plants which are under construction and design, namely, the DFRP (Demonstration Fast reactor fuel Reprocessing Plant) and the FRP (Fast reactor fuel Reprocessing Plant). In this paper, a comprehensive review of the experiences in reprocessing the fast reactor fuel of different burnup is presented. Also a brief account of the various developmental activities and strategies for the DFRP and FRP are given. (author)

  6. Management of radioactive waste from reprocessing plants

    International Nuclear Information System (INIS)

    Kanwar Raj

    2010-01-01

    Reprocessing and recycling of both fissile and fertile components back into appropriate reactor systems is an integral part of three stage nuclear energy programme of India. Different steps involved in processing of spent nuclear fuel (SNF) are decladding, dissolution and recovery of fissile and fertile materials. Reprocessing of SNF is a complex process involving handling of large quantity of radioactive materials and processing chemicals. There are three reprocessing plants in operation in the country at Trombay, Tarapur and Kalpakkam. Out of these plants, Trombay reprocessing plant is engaged in reprocessing of SNF from research reactors and other two plants are processing of SNF from PHWRs. A facility is being built for reprocessing of thorium based spent fuel at BARC, Trombay based on the experience of pilot plant scale. Like other industrial activities of nuclear fuel cycle, fuel reprocessing facilities too generate various types of radioactive waste streams. These are generated in all the three physical forms namely solid, liquid and gas. These waste streams are primarily categorized on the basis of concentration of radionuclides, their half lives and toxicity. Management of these wastes aims at (a) recovery and recycle of useful materials, (b) concentration and confinement of radioactivity in inert and stable matrices, (c) minimization of final waste volume for disposal, (d) decontamination of effluents following ALARA principle and (e) minimization of radioactive discharge to the environment. The present paper outlines the salient features of management of different types of radioactive waste generated in reprocessing plants handling SNF from research reactors and PHWR

  7. Pengembangan The Two-Tier Diagnostic Tes pada Bidang Biologi secara Terkomputersisasi

    Directory of Open Access Journals (Sweden)

    Suwarto Suwarto

    2013-01-01

    Full Text Available Abstrak Penelitian bertujuan mengembangkan tes diagnostik dua tingkat (the two-tier diagnostic test pada bidang biologi dan mengembangkan program komputer untuk mendiagnosis kesulitan belajar siswa. Tes disusun melalui tiga fase, yaitu (1 defining the content boundaries; (2 identifying students’ misconceptions; dan (3 developing instrument. Pengembangan program komputer terkait dengan soal, siswa, tabel kerja, SQL (Structured Query Language, ketuntasan, dan grade. Tes diagnostik yang dikembangkan ada 3, yaitu tes A, tes B, dan tes C. Responden untuk tes A dan tes B ada 130 siswa dan untuk tes C ada 128 siswa. Analisis statistik dilakukan dengan program iteman versi 3,00. Program komputer yang dikembangkan diujicobakan di SMAN 1 Tawangsari dan SMA Veteran 1 Sukoharjo. Hasil penelitian adalah Tes A terdiri atas 73 butir, dengan rentang kesulitan butir 0,031-0,962, rentang daya beda butir 0,013-1,000 dan reliabilitas 0,871; Tes B terdiri atas 39 butir, dengan rentang kesulitan butir 0,038-0,762, rentang daya beda butir 0,009-0,918 dan reliabilitas 0,768; dan Tes C terdiri atas 79 butir, dengan rentang kesulitan butir 0,102-0,938, daya beda butir 0,029-1,000 dan reliabilitas 0,894. Program komputer untuk mendiagnosis kesulitan belajar telah berfungsi dengan baik. Kata kunci: tes terkomputerisasi

  8. Simulation of Transient Response of Ir-TES for Position-Sensitive TES with Waveform Domain Multiplexing

    Science.gov (United States)

    Minamikawa, Y.; Sato, H.; Mori, F.; Damayanthi, R. M. T.; Takahashi, H.; Ohno, M.

    2008-04-01

    We are developing a new x-ray microcalorimeter based on a superconducting transition edge sensor (TES) as an imaging sensor. Our measurement shows unique waveforms which we consider as an expression of thermal nonuniformity of TES films. This arises from the different thermal responses, so that response signal shapes would vary according to the position of the incident x-ray. This position dependency deteriorate the measured energy resolution, but with appropriate waveform analysis, this would be useful for imaging device. For more inspection, we have developed a simulation code which enables a dynamic simulation to obtain a transient response of the TES by finite differential method. Temperature and electric current distributions are calculated. As a result, we successfully obtained waveform signals. The calculated signal waveforms have similar characteristics to the measured signals. This simulation visualized the transition state of the device and will help to design better detector.

  9. Present status of foreign reprocessing technology

    International Nuclear Information System (INIS)

    Otagaki, Takao; Ishikawa, Yasusi; Mori, Jyunichi

    2000-03-01

    In considering extensively and evaluating advanced nuclear fuel recycle technologies then selecting credible one among those technology options and establishing practicable plan of future fast reactor fuel recycle technology, it is important to investigate foreign reprocessing information extensively and minutely as much as possible then to know trends of reprocessing technology development in the world and present technology level of each country. This report is intending to present information of the status and the technology of operating, constructing and closed foreign reprocessing facilities in the world, including, mixed oxide (MOX) fuel reprocessing technology. The conceptual study of 'Foreign Reprocessing Technology Database' was also performed in order to add or revise the information easily. The eight countries, France, The U.K., Russia, The U.S., Germany, Belgium, India and China, were studied regarding outline of the facilities, operation status, future plan, technical information of process flow sheet, primary components, maintenance system etc, construction and operating costs, accidents or troubles, decommissioning status. (author)

  10. Reprocessing of MTR fuel at Dounreay

    International Nuclear Information System (INIS)

    Hough, N.

    1997-01-01

    UKAEA at Dounreay has been reprocessing MTR fuel for over 30 years. During that time considerable experience has been gained in the reprocessing of traditional HEU alloy fuel and more recently with dispersed fuel. Latterly a reprocessing route for silicide fuel has been demonstrated. Reprocessing of the fuel results in a recycled uranium product of either high or low enrichment and a liquid waste stream which is suitable for conditioning in a stable form for disposal. A plant to provide this conditioning, the Dounreay Cementation Plant is currently undergoing active commissioning. This paper details the plant at Dounreay involved in the reprocessing of MTR fuel and the treatment and conditioning of the liquid stream. (author)

  11. Electrochemical reprocessing of nuclear fuels

    International Nuclear Information System (INIS)

    Brambilla, G.; Sartorelli, A.

    1980-01-01

    A method is described for the reprocessing of irradiated nuclear fuel which is particularly suitable for use with fuel from fast reactors and has the advantage of being a dry process in which there is no danger of radiation damage to a solvent medium as in a wet process. It comprises the steps of dissolving the fuel in a salt melt under such conditions that uranium and plutonium therein are converted to sulphate form. The plutonium sulphate may then be thermally decomposed to PuO 2 and removed. The salt melt is then subjected to electrolysis conditions to achieve cathodic deposition of UO 2 (and possibly PuO 2 ). The salt melt can then be recycled or conditioned for final disposal. (author)

  12. Ecological problems of fuel reprocessing

    International Nuclear Information System (INIS)

    Huebschmann, W.G.

    1981-01-01

    The problem of the effects of a reprocessing plant to its environment lies in the amount of the handled radioactivity and its longerity. According to the toxicity of the nuclides extensive measures for retainings and filtering are necessary, in order to keep the resulting radiation load in the surrounding within justified limits. The experiences with the WAK prove, that they managed to reduce that radiation load to values that are negligible compared with the natural one. The expected adaptation of the radiation protection legislation to the latest recommendations of the ICRP will in addition help to do more realistic estimations as to the radiotoxicity of certain nuclides (Kr-85, J-129), which means at lower levels than up to now. (orig./HP) [de

  13. Lojalitātes programmas mazumtirdzniecībā.

    OpenAIRE

    Magone, Laura

    2014-01-01

    Bakalaura darba mērķis ir izpētīt klientu lojalitātes būtību un veidošanos, izmantojot mārketinga literatūrā piedāvātās koncepcijas, izpētīt mazumtirdzniecību lojalitātes programmas, salīdzināt uzņēmumu Prisma, Rimi un Maxima lojalitātes programmas un izstrādāt priekšlikumus kā uzlabot to darbību. Bakalaura darbs sastāv no trijām daļām. Pirmajā nodaļā ir raksturota un analizēta lojalitāte mārketinga teorijā. Otrajā nodaļā ir analizētas lojalitātes programmas kā mārketinga instruments. Tre...

  14. Frequency-domain multiplexing of TES microcalorimeter array with CABBAGE

    International Nuclear Information System (INIS)

    Iyomoto, N.; Ichitsubo, T.; Mitsuda, K.; Yamasaki, N.Y.; Fujimoto, R.; Oshima, T.; Futamoto, K.; Takei, Y.; Fujimori, T.; Yoshida, K.; Ishisaki, Y.; Morita, U.; Koga, T.; Shinozaki, K.; Sato, K.; Takai, N.; Ohashi, T.; Miyazaki, T.; Nakayama, S.; Tanaka, K.; Morooka, T.; Chinone, K.

    2004-01-01

    Properties of Transition-Edge Sensor (TES) microcalorimeters operated with AC bias are studied utilizing the calorimeter Wheatstone bridge circuit called Calorimeter Bridge Biased by an AC Generator (CABBAGE). The CABBAGE eliminates the AC carrier significantly, thus enables us to study the AC responses of the TES with high sensitivity. We tested two kinds of TES devices operating at 110 and 440 mK, respectively. With the 110 mK device biased with 25 kHz, an energy resolution of 28 eV is obtained for Mn Kα line. On the other hand, we multiplexed the signals from two 440 mK device biased with 50 and 20 kHz, respectively, and obtained 167 and 271 eV energy resolutions. Even at the balance point of the bridge, AC signal did not disappear and odd-order harmonics were observed. They are considered to arise from the current dependence of the TES resistance, which is characterized by β≡d log R/d log I. Numerical solution for the CABBAGE response can reproduce the experimental results well if β=0.24±0.02. Since the harmonics may cause severe problem in the SQUID operation even after attenuated by a band-pass filter, especially at high bias frequency operation such as several hundred kHz, it is important to make β small

  15. Gloves Reprocessing: Does It Really Save Money?

    Science.gov (United States)

    Arora, Pankaj; Kumari, Santosh; Sodhi, Jitender; Talati, Shweta; Gupta, Anil Kumar

    2015-12-01

    Gloves are reprocessed and reused in health-care facilities in resource-limited settings to reduce the cost of availability of gloves. The study was done with the aim to compute the cost of reprocessing of gloves so that an economically rationale decision can be taken. A retrospective record-based cross-sectional study was undertaken in a central sterile supply department where different steps during reprocessing of gloves were identified and the cost involved in reprocessing per pair of gloves was calculated. The cost of material and manpower was calculated to arrive at the cost of reprocessing per pair of gloves. The cost of a reprocessed pair of surgical gloves was calculated to be Indian Rupee (INR) 14.33 which was greater than the cost of a new pair of disposable surgical gloves (INR 9.90) as the cost of sterilization of one pair of gloves itself came out to  be INR 10.97. The current study showed that the purchase of sterile disposable single-use gloves is cheaper than the process of recycling. Reprocessing of gloves is not economical on tangible terms even in resource-limited settings, and from the perspective of better infection control as well as health-care worker safety, it further justifies the use of disposable gloves.

  16. Reprocessing of spent fuel and public acceptance

    International Nuclear Information System (INIS)

    Imai, Ryukichi

    1977-01-01

    The public acceptance has to be considered regarding whole atomic power rather than the reprocessing of nuclear fuel separately, and the problems concerned are as follows; the release of radioactive materials in the normal and abnormal operations of reprocessing plants, the disposal of wastes with high level radioactivity, the transportation of high level radioactive material, the relation to the economic activity near nuclear plants, the environmental effect of 85 Kr. and 3 H, etc., and the physical protection for reprocessing facility itself, the special handling of the materials of very high radioactivity level such as fission products and plutonium, the radiation exposure of operators, and the demonstration of reprocessing techniques of commercial base, etc., as a part of the nuclear fuel cycle, and the relation between atomic power and other technologies in energy supply, the evalution of atomic power as the symbol of huge scale science, and the energy problem within the confrontation of economic development and the preservation of environment and resources regarding whole nuclear energy. The situations of fuel reprocessing in USA, UK, France, Germany and Japan are explained from the viewpoint of the history. The general background for the needs of nuclear energy in Japan, the image of nuclear energy and fuel reprocessing entertained by the general public, and the special feature of reprocessing techniques are described. (Nakai, Y.)

  17. Fast breeder reactor fuel reprocessing in France

    International Nuclear Information System (INIS)

    Bourgeois, M.; Le Bouhellec, J.; Eymery, R.; Viala, M.

    1984-08-01

    Simultaneous with the effort on fast breeder reactors launched several years ago in France, equivalent investigations have been conducted on the fuel cycle, and in particular on reprocessing, which is an indispensable operation for this reactor. The Rapsodie experimental reactor was associated with the La Hague reprocessing plant AT1 (1 kg/day), which has reprocessed about one ton of fuel. The fuel from the Phenix demonstration reactor is reprocessed partly at the La Hague UP2 plant and partly at the Marcoule pilot facility, undergoing transformation to reprocess all the fuel (TOR project, 5 t/y). The fuel from the Creys Malville prototype power plant will be reprocessed in a specific plant, which is in the design stage. The preliminary project, named MAR 600 (50 t/y), will mobilize a growing share of the CEA's R and D resources, as the engineering needs of the UP3 ''light water'' plant begins to decline. Nearly 20 tonnes of heavy metals irradiated in fast breeder reactors have been processed in France, 17 of which came from Phenix. The plutonium recovered during this reprocessing allowed the power plant cycle to be closed. This power plant now contains approximately 140 fuel asemblies made up with recycled plutonium, that is, more than 75% of the fuel assemblies in the Phenix core

  18. Remote maintenance in nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Herndon, J.N.

    1985-01-01

    Remote maintenance techniques applied in large-scale nuclear fuel reprocessing plants are reviewed with particular attention to the three major maintenance philosophy groupings: contact, remote crane canyon, and remote/contact. Examples are given, and the relative success of each type is discussed. Probable future directions for large-scale reprocessing plant maintenance are described along with advanced manipulation systems for application in the plants. The remote maintenance development program within the Consolidated Fuel Reprocessing Program at the Oak Ridge National Laboratory is also described. 19 refs., 19 figs

  19. Corrosion control in nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Steele, D.F.

    1986-01-01

    This article looks in detail at tribology-related hazards of corrosion in irradiated fuel reprocessing plants and tries to identify and minimize problems which could contribute to disaster. First, the corrosion process is explained. Then the corrosion aspects at each of four stages in reprocessing are examined, with particular reference to oxide fuel reprocessing. The four stages are fuel receipt and storage, fuel breakdown and dissolution, solvent extraction and product concentration and waste management. Results from laboratory and plant corrosion trails are used at the plant design stage to prevent corrosion problems arising. Operational procedures which minimize corrosion if it cannot be prevented at the design stage, are used. (UK)

  20. Discharges from a fast reactor reprocessing plant

    International Nuclear Information System (INIS)

    Barnes, D.S.

    1987-01-01

    The purpose of this paper is to assess the environmental impact of the calculated routine discharges from a fast reactor fuel reprocessing plant. These assessments have been carried out during the early stages of an evolving in-depth study which culminated in the design for a European demonstration reprocessing plant (EDRP). This plant would be capable of reprocessing irradiated fuel from a series of European fast reactors. Cost-benefit analysis has then been used to assess whether further reductions in the currently predicted routine discharges would be economically justified

  1. Profiles of CH4, HDO, H2O, and N2O with improved lower tropospheric vertical resolution from Aura TES radiances

    Directory of Open Access Journals (Sweden)

    D. Noone

    2012-02-01

    Full Text Available Thermal infrared (IR radiances measured near 8 microns contain information about the vertical distribution of water vapor (H2O, the water isotopologue HDO, and methane (CH4, key gases in the water and carbon cycles. Previous versions (Version 4 or less of the TES profile retrieval algorithm used a "spectral-window" approach to minimize uncertainty from interfering species at the expense of reduced vertical resolution and sensitivity. In this manuscript we document changes to the vertical resolution and uncertainties of the TES version 5 retrieval algorithm. In this version (Version 5, joint estimates of H2O, HDO, CH4 and nitrous oxide (N2O are made using radiances from almost the entire spectral region between 1100 cm−1 and 1330 cm−1. The TES retrieval constraints are also modified in order to better use this information. The new H2O estimates show improved vertical resolution in the lower troposphere and boundary layer, while the new HDO/H2O estimates can now profile the HDO/H2O ratio between 925 hPa and 450 hPa in the tropics and during summertime at high latitudes. The new retrievals are now sensitive to methane in the free troposphere between 800 and 150 mb with peak sensitivity near 500 hPa; whereas in previous versions the sensitivity peaked at 200 hPa. However, the upper troposphere methane concentrations are biased high relative to the lower troposphere by approximately 4% on average. This bias is likely related to temperature, calibration, and/or methane spectroscopy errors. This bias can be mitigated by normalizing the CH4 estimate by the ratio of the N2O estimate relative to the N2O prior, under the assumption that the same systematic error affects both the N2O and CH4 estimates. We demonstrate that applying this ratio theoretically reduces the CH4 estimate for non-retrieved parameters that jointly affect both the N2O and CH4 estimates. The relative upper troposphere to lower troposphere bias is approximately 2.8% after this bias

  2. Bilateral Alternating Auditory Stimulations Facilitate Fear Extinction and Retrieval

    OpenAIRE

    Boukezzi, Sarah; Silva, Catarina; Nazarian, Bruno; Rousseau, Pierre-François; Guedj, Eric; Valenzuela-Moguillansky, Camila; Khalfa, Stéphanie

    2017-01-01

    Disruption of fear conditioning, its extinction and its retrieval are at the core of posttraumatic stress disorder (PTSD). Such deficits, especially fear extinction delay, disappear after alternating bilateral stimulations (BLS) during eye movement desensitization and reprocessing (EMDR) therapy. An animal model of fear recovery, based on auditory cued fear conditioning and extinction learning, recently showed that BLS facilitate fear extinction and fear extinction retrieval. Our goal was to ...

  3. Reprocessing of spent nuclear fuels in OECD countries

    International Nuclear Information System (INIS)

    1977-01-01

    This report deals with the adequacy of projected reprocessing capacity, the short-term measures proposed in view of the lack of sufficient reprocessing capacity, the longer term measures proposed in view of the lack of sufficient reprocessing capacity, the alternatives to reprocessing and the cooperative arrangements

  4. Refurbishment of the BNFL Magnox reprocessing plant

    International Nuclear Information System (INIS)

    Carr, V.M.; Edgar, R.

    1998-01-01

    The Magnox Reprocessing Plant was commissioned in 1964. Since then it has reprocessed more than 35,000 t of irradiated uranium metal fuel. The plant is subject to routine shutdowns to allow maintenance and project work to be undertaken. During the 1997 shutdown the opportunity was taken to replace several life limiting parts of the plant to ensure Magnox reprocessing capability well beyond the year 2010. This shutdown was the largest and most complex undertaken by Magnox Reprocessing, with a total committed value of 130 million UK pounds, 17.5 million UK pounds committed in the shutdown itself and the balance on installation, design and procurement preparing for the shutdown. The work was completed within safety targets, to programme and within budget. The lessons learned and experience gained have been fed into the methodologies and procedures for planning future project and shutdown work within BNFL. This report is part of the output from this process of continually improving performance. (author)

  5. Conditions for Australian consent to reprocessing

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    This article contains the text of the statement by the Australian Minister for Foreign Affairs to the House of Representatives, Noember 1980, on conditions for Australian consent to the reprocessing of nuclear material of Australian origin

  6. Storage and Reprocessing of Spent Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Karpius, Peter Joseph [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-02-02

    Addressing the problem of waste, especially high-level waste (HLW), is a requirement of the nuclear fuel cycle that cannot be ignored. We explore the two options employed currently, long-term storage and reprocessing.

  7. Reprocessing considerations for a developing country

    International Nuclear Information System (INIS)

    This paper describes some of the alternatives for dealing with spent fuel that face a developing country. It then discusses the considerations that affect decisions on the size and siting of reprocessing plants, and shows how small plants may be suitable in countries without the means to transport spent fuel easily. The paper also outlines the reasons for reprocessing in India, and describes the development of India's reprocessing capability. It shows how the economic conditions in India, such as low skilled labour costs, make reprocessing plants of 100 to 200 tonnes U/yr capacity economic, and includes a table giving technical data on a 100 t U/yr national plant for inclusion in the reference cases used by INFCE Working Group 4

  8. Spent fuel management: reprocessing or storage

    International Nuclear Information System (INIS)

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

    1986-01-01

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

  9. Spent fuel management: reprocessing or storage

    International Nuclear Information System (INIS)

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

    1986-01-01

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

  10. PENGEMBANGAN TES BERPIKIR KRITIS DENGAN PENDEKATAN ITEM RESPONSE THEORY

    Directory of Open Access Journals (Sweden)

    Fajrianthi Fajrianthi

    2016-06-01

    Full Text Available Penelitian ini bertujuan untuk menghasilkan sebuah alat ukur (tes berpikir kritis yang valid dan reliabel untuk digunakan, baik dalam lingkup pendidikan maupun kerja di Indonesia. Tahapan penelitian dilakukan berdasarkan tahap pengembangan tes menurut Hambleton dan Jones (1993. Kisi-kisi dan pembuatan butir didasarkan pada konsep dalam tes Watson-Glaser Critical Thinking Appraisal (WGCTA. Pada WGCTA, berpikir kritis terdiri dari lima dimensi yaitu Inference, Recognition Assumption, Deduction, Interpretation dan Evaluation of arguments. Uji coba tes dilakukan pada 1.453 peserta tes seleksi karyawan di Surabaya, Gresik, Tuban, Bojonegoro, Rembang. Data dikotomi dianalisis dengan menggunakan model IRT dengan dua parameter yaitu daya beda dan tingkat kesulitan butir. Analisis dilakukan dengan menggunakan program statistik Mplus versi 6.11 Sebelum melakukan analisis dengan IRT, dilakukan pengujian asumsi yaitu uji unidimensionalitas, independensi lokal dan Item Characteristic Curve (ICC. Hasil analisis terhadap 68 butir menghasilkan 15 butir dengan daya beda yang cukup baik dan tingkat kesulitan butir yang berkisar antara –4 sampai dengan 2.448. Sedikitnya jumlah butir yang berkualitas baik disebabkan oleh kelemahan dalam menentukan subject matter experts di bidang berpikir kritis dan pemilihan metode skoring. Kata kunci: Pengembangan tes, berpikir kritis, item response theory   DEVELOPING CRITICAL THINKING TEST UTILISING ITEM RESPONSE THEORY Abstract The present study was aimed to develop a valid and reliable instrument in assesing critical thinking which can be implemented both in educational and work settings in Indonesia. Following the Hambleton and Jones’s (1993 procedures on test development, the study developed the instrument by employing the concept of critical thinking from Watson-Glaser Critical Thinking Appraisal (WGCTA. The study included five dimensions of critical thinking as adopted from the WGCTA: Inference, Recognition

  11. Process control of an HTGR fuel reprocessing cold pilot plant

    International Nuclear Information System (INIS)

    Rode, J.S.

    1976-10-01

    Development of engineering-scale systems for a large-scale HTGR fuel reprocessing demonstration facility is currently underway in a cold pilot plant. These systems include two fluidized-bed burners, which remove the graphite (carbon) matrix from the crushed HTGR fuel by high temperature (900 0 C) oxidation. The burners are controlled by a digital process controller with an all analog input/output interface which has been in use since March, 1976. The advantages of such a control system to a pilot plant operation can be summarized as follows: (1) Control loop functions and configurations can be changed easily; (2) control constants, alarm limits, output limits, and scaling constants can be changed easily; (3) calculation of data and/or interface with a computerized information retrieval system during operation are available; (4) diagnosis of process control problems is facilitated; and (5) control panel/room space is saved

  12. Fast reactor fuel reprocessing in the UK

    International Nuclear Information System (INIS)

    Allardice, R.H.; Williams, J.; Buck, C.

    1977-01-01

    Enriched uranium metal fuel irradiated in the Dounreay Fast Reactor has been reprocessed and refabricated in plants specifically designed for the purpose in the U.K. since 1961. Efficient and reliable fuel recycle is essential to the development of a plutonium based fast reactor system and the importance of establishing at an early stage fast reactor fuel reprocessing has been reinforced by current world difficulties in reprocessing high burn-up thermal reactor oxide fuel. In consequence, the U.K. has decided to reprocess irradiated fuel from the 250 MW(E) Prototype Fast Reactor as an integral part of the fast reactor development programme. Flowsheet and equipment development work for the small scale fully active demonstration plant have been carried out over the past 5 years and the plant will be commissioned and ready for active operation during 1977. In parallel, a comprehensive waste management system has been developed and installed. Based on this development work and the information which will arise from active operation of the plant a parallel development programme has been initiated to provide the basis for the design of a large scale fast reactor fuel reprocessing plant to come into operation in the late 1980s to support the projected U.K. fast reactor installation programme. The paper identifies the important differences between fast reactor and thermal reactor fuel reprocessing technologies and describes some of the development work carried out in these areas for the small scale P.F.R. fuel reprocessing operation. In addition, the development programme in aid of the design of a larger scale fast reactor fuel reprocessing plant is outlined and the current design philosophy is discussed

  13. Reprocessing of ''fast'' fuel in France

    International Nuclear Information System (INIS)

    Sauteron, J.; Bourgeois, M.; Le Bouhellec, J.; Miquel, P.

    1976-05-01

    The results of laboratory studies as well as pilot testing (AT-I La Hague, Marcoule, Fontenay-aux-Roses) in reprocessing of fast breeder reactor fuels are described. The paper covers all steps: head end, aqueous and fluoride volatility processes, and waste treatment. In conclusion, it is demonstrated why it is still too early to define a strategy of industrial reprocessing for this reactor type

  14. Simulation of nuclear fuel reprocessing for safeguards

    International Nuclear Information System (INIS)

    Canty, M.J.; Dayem, H.A.; Kern, E.A.; Spannagel, G.

    1983-11-01

    For safeguarding the chemical process area of future reprocessing plants the near-real-time material accountancy (NRTMA) method might be applied. Experimental data are not yet available for testing the capability of the NRTMA method but can be simulated using a digital computer. This report describes the mathematical modeling of the Pu-bearing components of reprocessing plants and presents first results obtained by simulation models. (orig.) [de

  15. Nuclear fuel reprocessing in the UK

    International Nuclear Information System (INIS)

    Allardice, R.H.; Harris, D.W.; Mills, A.

    1983-01-01

    Nuclear fuel reprocessing has been carried out on an industrial scale in the United Kingdom since 1952. Two large reprocessing plants have been constructed and operated at Windscale, Cumbria and two smaller specialized plants have been constructed and operated at Dounreay, Northern Scotland. At the present time, the second of the two Windscale plants is operating, and Government permission has been given for a third reprocessing plant to be built on that site. At Dounreay, one of the plants is operating in its original form, whilst the second is now operating in a modified form, reprocessing fuel from the prototype fast reactor. This chapter describes the development of nuclear fuel reprocessing in the UK, commencing with the research carried out in Canada immediately after the Second World War. A general explanation of the techniques of nuclear fuel reprocessing and of the equipment used is given. This is followed by a detailed description of the plants and processes installed and operated in the UK. (author)

  16. Cross-validation of IASI/MetOp derived tropospheric δD with TES and ground-based FTIR observations

    Science.gov (United States)

    Lacour, J.-L.; Clarisse, L.; Worden, J.; Schneider, M.; Barthlott, S.; Hase, F.; Risi, C.; Clerbaux, C.; Hurtmans, D.; Coheur, P.-F.

    2015-03-01

    The Infrared Atmospheric Sounding Interferometer (IASI) flying onboard MetOpA and MetOpB is able to capture fine isotopic variations of the HDO to H2O ratio (δD) in the troposphere. Such observations at the high spatio-temporal resolution of the sounder are of great interest to improve our understanding of the mechanisms controlling humidity in the troposphere. In this study we aim to empirically assess the validity of our error estimation previously evaluated theoretically. To achieve this, we compare IASI δD retrieved profiles with other available profiles of δD, from the TES infrared sounder onboard AURA and from three ground-based FTIR stations produced within the MUSICA project: the NDACC (Network for the Detection of Atmospheric Composition Change) sites Kiruna and Izaña, and the TCCON site Karlsruhe, which in addition to near-infrared TCCON spectra also records mid-infrared spectra. We describe the achievable level of agreement between the different retrievals and show that these theoretical errors are in good agreement with empirical differences. The comparisons are made at different locations from tropical to Arctic latitudes, above sea and above land. Generally IASI and TES are similarly sensitive to δD in the free troposphere which allows one to compare their measurements directly. At tropical latitudes where IASI's sensitivity is lower than that of TES, we show that the agreement improves when taking into account the sensitivity of IASI in the TES retrieval. For the comparison IASI-FTIR only direct comparisons are performed because the sensitivity profiles of the two observing systems do not allow to take into account their differences of sensitivity. We identify a quasi negligible bias in the free troposphere (-3‰) between IASI retrieved δD with the TES, which are bias corrected, but important with the ground-based FTIR reaching -47‰. We also suggest that model-satellite observation comparisons could be optimized with IASI thanks to its high

  17. Computational Analysis on Performance of Thermal Energy Storage (TES) Diffuser

    Science.gov (United States)

    Adib, M. A. H. M.; Adnan, F.; Ismail, A. R.; Kardigama, K.; Salaam, H. A.; Ahmad, Z.; Johari, N. H.; Anuar, Z.; Azmi, N. S. N.

    2012-09-01

    Application of thermal energy storage (TES) system reduces cost and energy consumption. The performance of the overall operation is affected by diffuser design. In this study, computational analysis is used to determine the thermocline thickness. Three dimensional simulations with different tank height-to-diameter ratio (HD), diffuser opening and the effect of difference number of diffuser holes are investigated. Medium HD tanks simulations with double ring octagonal diffuser show good thermocline behavior and clear distinction between warm and cold water. The result show, the best performance of thermocline thickness during 50% time charging occur in medium tank with height-to-diameter ratio of 4.0 and double ring octagonal diffuser with 48 holes (9mm opening ~ 60%) acceptable compared to diffuser with 6mm ~ 40% and 12mm ~ 80% opening. The conclusion is computational analysis method are very useful in the study on performance of thermal energy storage (TES).

  18. Computational Analysis on Performance of Thermal Energy Storage (TES) Diffuser

    International Nuclear Information System (INIS)

    Adib, M A H M; Ismail, A R; Kardigama, K; Salaam, H A; Ahmad, Z; Johari, N H; Anuar, Z; Azmi, N S N; Adnan, F

    2012-01-01

    Application of thermal energy storage (TES) system reduces cost and energy consumption. The performance of the overall operation is affected by diffuser design. In this study, computational analysis is used to determine the thermocline thickness. Three dimensional simulations with different tank height-to-diameter ratio (HD), diffuser opening and the effect of difference number of diffuser holes are investigated. Medium HD tanks simulations with double ring octagonal diffuser show good thermocline behavior and clear distinction between warm and cold water. The result show, the best performance of thermocline thickness during 50% time charging occur in medium tank with height-to-diameter ratio of 4.0 and double ring octagonal diffuser with 48 holes (9mm opening ∼ 60%) acceptable compared to diffuser with 6mm ∼ 40% and 12mm ∼ 80% opening. The conclusion is computational analysis method are very useful in the study on performance of thermal energy storage (TES).

  19. Komparasi Metode Penyetaraan Tes Menurut teori Respons Butir

    Directory of Open Access Journals (Sweden)

    Erna Miyatun

    2004-01-01

    Full Text Available Penelitian ini bertujuan menemukan metode penyetaraan tes dengan teori respons butir yang paling akurat. Sebelum dilakukan pengujian keakuratan metode penyetaraan tes, terlebih dahulu dilakukan: 1 Pemeriksaan setara atau tidaknya perangkat tes, 2 Penemuan persamaan konversi antarpaket soal yang tidak setara dan 3 Estimasi parameter butir. Penentuan metode penyetaraan tes yang akurat didasarkan pada besarnya kesalahan standar penyetaraan (SEE; yang paling akurat adalah metode penyetaraan tes yang mempunyai SEE paling kecil. Dalam penelitian ini, terdapat dua macam objek penelitian yaitu paket soal dan jawaban peserta EBTANAS. Soal EBTANAS terdiri dari 3 paket soal utama, 1 paket soal susulan, dan 1 paket soal cadangan. Peserta EBTANAS SLTP di Jawa Tengah Tahun Ajaran 1998/1999 terdiri dari 370.187 siswa. Teknik Purposive Sampling digunakan untuk menentukan sampel paket soal, yaitu ketiga paket soal utama terpilih sebagai sampel penelitian. Teknik Cluster Stratified Systematic Random Sampling digunakan untuk menentukan sampel jawaban peserta EBTANAS. Jawaban peserta sebanyak 8.251, terpilih sebagai sampel penelitian. Paket soal EBTANAS SLTP bidang studi Matematika dan data jawaban peserta tes, diperoleh melalui pengambilan data dokumentasi. Keparalelan tes diuji dengan analisis varians, uji Scheffe, dan uji Levene. Penyetaraan tes dilakukan dengan metode: Rerata dan Sigma, Rerata dan Sigma Tegar, dan Kurva Karakteristik. Estimasi parameter butir dilakukan dengan analisis program Bilog. Hasil analisis menunjukkan, pasangan paket soal utama-1 dan 2 serta pasangan paket soal utama-1 dan 3 tidak paralel, sehingga diperlukan proses penyetaraan. Pasangan paket soal utama-2 dan paket soal utama-3 bersifat paralel. Oleh karena itu tidak diperlukan proses penyetaraan. Penyetaraan paket soal utama-1 ke paket soal utama-2, dengan metode Rerata dan Sigma didapatkan persamaan konversi X2 - 1,19495 X] + 0,25766; dengan metode Rerata dan Sigma Tegar, X2 = 0

  20. PENILAIAN PEMAHAMAN REPRESENTASI GRAFIK MATERI OPTIKA GEOMETRI MENGGUNAKAN TES DIAGNOSTIK

    Directory of Open Access Journals (Sweden)

    Wawan Bunawan

    2015-06-01

    Full Text Available Abstrak: Tujuan penelitian adalah mengembangkan dan menerapkan tes diagnostik pilihan ganda tiga tingkat untuk mengukur pemahaman representasi grafik mahasiswa terkait esensi inkuiri sains dan materi optika geometri. Penelitian menggunakan metode campuran melibatkan 83 mahasiswa calon guru fisika di satu LPTK Sumatera Utara. Instrumen tes diagnostik terlebih dahulu didesain kemudian disempurnakan selama proses, direvisi, dan digunakan untuk mendeteksi dan menilai pemahaman representasi grafik mahasiswa calon guru fisika. Instrumen tes telah dikembangkan untuk dapat mendiagnosis dan memperbaiki kesalahan-kesalahan yang dilakukan calon guru fisika terkait dengan keterampilan mengonstruk grafik, menemukan kesulitan-kesulitan dalam membaca dan menginterpretasi grafik. Analisis data dilakukan secara kualitatif dan kuantitatif. Hasil studi menunjukkan pembacaan grafik dan keterampilan menginterpretasi grafik calon guru fisika masih belum memadai dan juga kemahiran dalam menganalisis grafik bergantung pada jenis grafik dan level atau tipe pertanyaan yang dikembangkan. Kata Kunci: representasi grafik, optik geometri, diagnostik tes ASSESSING OF UNDERSTANDING GRAPHICAL REPRESENTATION CONTENT GEOMETRICAL OPTIC USING DIAGNOSTIC TEST Abstract: The purpose of this study is to develop and apply three tier multiple choice diagnostic test to measure student’s understanding of graphical representation about essential features of inquiry and content geometrical optic. The study was conducted using mixed methods and carried out with 83 prephysics teachers at a University of Teachers Education in North Sumatera. The diagnostic instrument was designed and then progressively refined, revised, and implemented to detect and assess student’s understanding of graphical representation. Test instrument was developed to diagnose and correct the mistakes made by pre-service physics teachers about construction graphic skills, difficulties in the reading and interpretation

  1. Antenna-coupled TES bolometers for the SPIDER experiment

    Energy Technology Data Exchange (ETDEWEB)

    Kuo, C.L. [Jet Propulsion Laboratory, 4800 Oak Grove Drive, Pasadena, CA 91109 (United States)]|[California Institute of Technology, 1200 E California Boulevard, Pasadena, CA 91125 (United States)]. E-mail: clkuo@astro.caltech.edu; Ade, P. [University of Wales, Cardiff, 5 The Parade, Cardiff, CF24 3YB, Wales (United Kingdom); Bock, J.J. [Jet Propulsion Laboratory, 4800 Oak Grove Drive, Pasadena, CA 91109 (United States)]|[California Institute of Technology, 1200 E California Boulevard, Pasadena, CA 91125 (United States); Day, P. [Jet Propulsion Laboratory, 4800 Oak Grove Drive, Pasadena, CA 91109 (United States)]|[California Institute of Technology, 1200 E California Boulevard, Pasadena, CA 91125 (United States); Goldin, A.; Golwala, S.; Hristov, V.; Jones, W.C.; Lange, A.E.; Rossinot, P.; Vayonakis, A.; Wang, G. [California Institute of Technology, 1200 E California Boulevard, Pasadena, CA 91125 (United States); Halpern, M. [University of British Columbia, 2329 West Mall, Vancouver, BC, V6T 1Z4 (Canada); Hilton, G.; Irwin, K. [National Institute of Standards and Technology, 325 Broadway, Boulder, CO (United States); Holmes, W.; Kenyon, M.; LeDuc, H.G. [Jet Propulsion Laboratory, 4800 Oak Grove Drive, Pasadena, CA 91109 (United States); MacTavish, C. [University of Toronto, 60 St. George Street, Toronto, ON, M5S 1A7 (Canada); Montroy, T.; Ruhl, J. [Case Western Reserve University, 10900 Euclid Avenue, Cleveland, OH 44106 (United States); Netterfield, C.B. [University of Toronto, 60 St. George Street, Toronto, ON, M5S 1A7 (Canada); Yun, M. [Jet Propulsion Laboratory, 4800 Oak Grove Drive, Pasadena, CA 91109 (United States)]|[University of Pittsburgh, 348 Benedum Engineering Hall, Pittsburgh, PA 15261 (United States); Zmuidzinas, J. [Jet Propulsion Laboratory, 4800 Oak Grove Drive, Pasadena, CA 91109 (United States)]|[California Institute of Technology, 1200 E California Boulevard, Pasadena, CA 91125 (United States)

    2006-04-15

    SPIDER is a proposed balloon-borne experiment designed to search for the imprints of gravity waves on the polarization of the cosmic microwave background radiation. The required wide frequency coverage, large number of sensitive detectors, and the stringent power constraints on a balloon are made possible by antenna-coupled TES bolometers. Several prototype devices have been fabricated and optically characterized. Their spectral and angular responses agree well with the theoretical expectations.

  2. Parametric Characterization of TES Detectors Under DC Bias

    Science.gov (United States)

    Chiao, Meng P.; Smith, Stephen James; Kilbourne, Caroline A.; Adams, Joseph S.; Bandler, Simon R.; Betancourt-Martinez, Gabriele L.; Chervenak, James A.; Datesman, Aaron M.; Eckart, Megan E.; Ewin, Audrey J.; hide

    2016-01-01

    The X-ray integrated field unit (X-IFU) in European Space Agency's (ESA's) Athena mission will be the first high-resolution X-ray spectrometer in space using a large-format transition-edge sensor microcalorimeter array. Motivated by optimization of detector performance for X-IFU, we have conducted an extensive campaign of parametric characterization on transition-edge sensor (TES) detectors with nominal geometries and physical properties in order to establish sensitivity trends relative to magnetic field, dc bias on detectors, operating temperature, and to improve our understanding of detector behavior relative to its fundamental properties such as thermal conductivity, heat capacity, and transition temperature. These results were used for validation of a simple linear detector model in which a small perturbation can be introduced to one or multiple parameters to estimate the error budget for X-IFU. We will show here results of our parametric characterization of TES detectors and briefly discuss the comparison with the TES model.

  3. Power Reactor Fuel Reprocessing Plant-2, Tarapur: a benchmark in Indian PHWR spent fuel reprocessing

    International Nuclear Information System (INIS)

    Pradhan, Sanjay; Dubey, K.; Qureshi, F.T.; Lokeswar, S.P.

    2017-01-01

    Power Reactor Fuel Reprocessing Plant-2 (PREFRE-2) is latest operating spent nuclear fuel reprocessing plant in India. This plant has improved design based on latest technology and feedback provided by the earlier plants. The design of PREFRE-2 plant is in five cycles of solvent extraction using TBP as extractant. The plant is commissioned in year 2011 after regulatory clearances

  4. Nuclear fuel reprocessing and high level waste disposal: informational hearings. Volume V. Reprocessing. Part 2

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-03-08

    Testimony was presented by a four member panel on the commercial future of reprocessing. Testimony was given on the status of nuclear fuel reprocessing in the United States. The supplemental testimony and materials submitted for the record are included in this report. (LK)

  5. Safeguarding a future industrial reprocessing plant

    International Nuclear Information System (INIS)

    1978-11-01

    This paper is submitted to Working Group 5, Sub-Group B for information. It is being submitted to Working Group 4 for discussion at their meeting in January 1979 and shows that by a combination of accountancy, surveillance and containment a reliable safeguards system can be designed for the reprocessing of fuels of the BWR and PWR type. Its arguments can, in general terms, be applied to plants for reprocessing LMFBR fuels, with due allowance for future advances which should improve our overall knowledge of the reliability of safeguards systems. In the reprocessing of fast reactor (LMFBR) fuels, as compared with LWR fuels, the main differences are the higher plutonium concentration and lower heavy metal throughput in the early stages of the reprocessing operations. At later stages in the process (after plutonium/uranium separation) the plants could be similar and have similar safeguarding problems. Plants for reprocessing LMFBR on a commercial scale will not be in operation for a number of years. In these plants greater attention may have to be paid to safeguards at the early stages, especially to waste/raffinate streams, than in the PWR/BWR reprocessing plant. The actual balance between containment, surveillance and accountancy adopted will depend on the status of the technology of safeguards and reprocessing. It can be anticipated that improvements to measurement systems will be made which may allow greater reliance on actual measurement. Treatment and recycle of solid wastes will advance and could therefore lead to improvements in accountancy in, for example, the ''head-end''

  6. Analysis of the impact of retrievable spent fuel storage

    International Nuclear Information System (INIS)

    Merrill, E.T.; White, M.K.; Fleischman, R.M.

    1978-03-01

    The impact of retrievably storing spent fuel is measurable in terms of the contribution the stored spent fuel makes to implementing the fuel management option selected. For the case of a decision to recycle LWR fuel in LWRs, a useful indicator of impact is the ratio of energy production with varying degrees of spent fuel retrievability to that achievable with total spent fuel retrievability. For a decision made in the year 2000, this ratio varies from 0.81 (10 yr storage in reactor basins) to 0.97 (retrievable storage for 25 years after fuel discharge). An earlier decision to recycle in LWRs results in both of these ratios being nearer to 1.0. If a decision is reached to implement a breeder reactor economy, the chosen comparison is the installed breeder capacity achievable with varying degrees of spent fuel retrievability. If a decision to build breeder reactors is reached in the year 2000, the maximum possible installed breeder capacity in 2040 varies from 490 GWe (10 yr storage in reactor basins) to 660 GWe (all fuel retrievably stored). If all fuel is retrievably stored 25 years, 635 GWe of breeder capacity is achievable by 2040. For an earlier decision date, such as 1985, the maximum possible installed breeder capacity in 2040 ranges from 740 GWe (no retrievable storage) to 800 GWe (all fuel retrievably stored). As long as a decision to reprocess is reached before 2000, most of the potential benefit of retrievable storage may be realized by implementing retrievable storage after such a decision is made. Neither providing retrievable spent fuel storage prior to a decision to reprocess, nor designing such storage for more than 25 years of retrievability appear to offer significant incremental benefit

  7. Impact of nonlinearity on changing the a priori of trace gas profile estimates from the Tropospheric Emission Spectrometer (TES

    Directory of Open Access Journals (Sweden)

    S. S. Kulawik

    2008-06-01

    Full Text Available Non-linear maximum a posteriori (MAP estimates of atmospheric profiles from the Tropospheric Emission Spectrometer (TES contains a priori information that may vary geographically, which is a confounding factor in the analysis and physical interpretation of an ensemble of profiles. One mitigation strategy is to transform profile estimates to a common prior using a linear operation thereby facilitating the interpretation of profile variability. However, this operation is dependent on the assumption of not worse than moderate non-linearity near the solution of the non-linear estimate. The robustness of this assumption is tested by comparing atmospheric retrievals from the Tropospheric Emission Spectrometer processed with a uniform prior with those processed with a variable prior and converted to a uniform prior following the non-linear retrieval. Linearly converting the prior following a non-linear retrieval is shown to have a minor effect on the results as compared to a non-linear retrieval using a uniform prior when compared to the expected total error, with less than 10% of the change in the prior ending up as unbiased fluctuations in the profile estimate results.

  8. Existing reflection seismic data re-processing

    International Nuclear Information System (INIS)

    Higashinaka, Motonori; Sano, Yukiko; Kozawa, Takeshi

    2005-08-01

    This document is to report the results of existing seismic data re-processing around Horonobe town, Hokkaido, Japan, which is a part of the Horonobe Underground Research Project. The main purpose of this re-processing is to recognize the subsurface structure of Omagari Fault and fold system around Omagari Fault. The seismic lines for re-processing are TYHR-A3 line and SHRB-2 line, which JAPEX surveyed in 1975. Applying weathering static correction using refraction analysis and noise suppression procedure, we have much enhanced seismic profile. Following information was obtained from seismic re-processing results. TYHR-A3 line: There are strong reflections, dipping to the west. These reflections are corresponding western limb of anticline to the west side of Omagari Fault. SHRB-2 line: There are strong reflections, dipping to the west, at CDP 60-140, while there are reflections, dipping to the east, to the east side of CDP 140. These reflections correspond to the western limb and the eastern limb of the anticline, which is parallel to Omagari FAULT. This seismic re-processing provides some useful information to know the geological structure around Omagari Fault. (author)

  9. Problems of nuclear fuel reprocessing in Japan

    International Nuclear Information System (INIS)

    Tanaka, Naojiro

    1974-01-01

    The reprocessing capacity of the plant No. 1 of Power Reactor and Nuclear Fuel Development Corporation, which is scheduled to start operation in fiscal year 1975, will be insufficient after fiscal year 1978 for the estimated demand for reprocessing based on Japanese nuclear energy development program. Taking into consideration the results examined by JAIF's study team to Europe and the U.S., it is necessary that Japan builds 2nd reprocessing plant. But there will be a gap from 1978 to 1984 during which Japan must rely on overseas reprocessing services. The establishment of a reprocessing system is a task of national scale, and there are many problems to be solved before it can be done. These include the problems of site and environment, the problem of treatment and disposal of radioactive wastes, the raising of huge required funds and so on. Therefore, even if a private enterprise is allowed to undertake the task, it will be impossible to achieve the aim without the cooperation and assistance of the government. (Wakatsuki, Y.)

  10. Occupational dose at Rokkasho reprocessing plant (RRP)

    International Nuclear Information System (INIS)

    Takashima, F.; Taguchi, R.; Kano, M.; Moriyama, T.; Ogaki, K.; Noda, K.

    2008-01-01

    In Japan, Rokkasho Reprocessing Plant (RRP) is going to start the operation in service as the first large-scale commercial reprocessing plant of spent fuels that has annual reprocessing quantity of 800tU pr in maximum. The occupational external exposure is controlled for the purpose of keeping dose as low as reasonably achievable, and it is monitored by the personal dosimeter. On the other hand, the occupational internal exposure is controlled for the purpose of preventing, and it is monitored by the periodical evaluation of internal dose from the radioactive concentration in air of workplace. The individual doses of radiation workers are less than the dose limits in the statute and our lower management values enough. Dose data will be stored continuously and the rational management method will be examined. (author)

  11. EURATOM safeguards. Safeguards verifications in reprocessing plants

    International Nuclear Information System (INIS)

    Heppleston, M.

    1999-01-01

    This paper provides a brief historical view of the legal basis for EURATOM. The specific application of safeguards to large scale reprocessing plants, from the theoretical model to the practical application of inspection is considered. The challenge to adequately safeguard major commercial reprocessing facilities has led to many novel approaches being developed. These lessons will also benefit other safeguard projects as a result. Good cooperation between the operator and regulator is essential for the satisfactory installation of adequate safeguard controls. The use of modern data processing technology combined with other diverse monitoring techniques has shown that a major industrial scale reprocessing plant can be controlled under international safeguards to provide a high level of assurance [ru

  12. Review of thorium fuel reprocessing experience

    International Nuclear Information System (INIS)

    Brooksbank, R.E.; McDuffee, W.T.; Rainey, R.H.

    1978-01-01

    The review reveals that experience in the reprocessing of irradiated thorium materials is limited. Plants that have processed thorium-based fuels were not optimized for the operations. Previous demonstrations of several viable flowsheets provide a sound technological base for the development of optimum reprocessing methods and facilities. In addition to the resource benefit by using thorium, recent nonproliferation thrusts have rejuvenated an interest in thorium reprocessing. Extensive radiation is generated as the result of 232 U-contamination produced in the 233 U, resulting in the remote operation and fabrication operations and increased fuel cycle costs. Development of the denatured thorium flowsheet, which is currently of interest because of nonproliferation concerns, represents a difficult technological challenge

  13. Technical study report on reprocessing system

    International Nuclear Information System (INIS)

    Tanaka, Hiroshi; Kasai, Yoshimitsu; Kawamura, Fumio

    2000-07-01

    The feasibility studies on commercialized fast breeder reactor (FBR) recycle system, in which reactor system and recycle technologies are related on consideration, are performed considering the attainable perspectives for the followings: ensuring safety, economic competitiveness to future LWRs, efficient utilization of resources, reduction of environmental burden, and enhancement of nuclear non-proliferation. In the studies of Reprocessing system of FBR, evaluation was made for the non-aqueous reprocessing of pyrochemical and fluoride volatility process and also for the aqueous reprocessing with a view to streamlining. As a result, it was estimated that each system has prospects of coming into practical use in terms of technique. In the economical efficiency assessment, it was estimated to have economic competitiveness to future LWRs. And the technical research items of each system are picked out. Hereafter, more detail design study will be performed for each system. (author)

  14. Inventory estimation for nuclear fuel reprocessing systems

    International Nuclear Information System (INIS)

    Beyerlein, A.L.; Geldard, J.F.

    1987-01-01

    The accuracy of nuclear material accounting methods for nuclear fuel reprocessing facilities is limited by nuclear material inventory variations in the solvent extraction contactors, which affect the separation and purification of uranium and plutonium. Since in-line methods for measuring contactor inventory are not available, simple inventory estimation models are being developed for mixer-settler contactors operating at steady state with a view toward improving the accuracy of nuclear material accounting methods for reprocessing facilities. The authors investigated the following items: (1) improvements in the utility of the inventory estimation models, (2) extension of improvements to inventory estimation for transient nonsteady-state conditions during, for example, process upset or throughput variations, and (3) development of simple inventory estimation models for reprocessing systems using pulsed columns

  15. Italian experience with pilot reprocessing plants

    International Nuclear Information System (INIS)

    Cao, S.; Dworschak, H.; Rolandi, G.; Simonetta, R.

    1977-01-01

    Problems and difficulties recently experienced in the reprocessing technology of high burnup power reactor fuel elements have shown the importance of pilot plant experiments to optimize the separation processes and to test advanced equipment on a representative scale. The CNEN Eurex plant, in Saluggia (Vercelli), with a 50 kg/d thruput, in operation since '71, has completed several reprocessing campaigns on MTR type fuel elements. Two different chemical flowsheets based respectively on TBP and tertiary amines were thoroughly tested and compared: a concise comparative evaluation of the results obtained with the two schemes is given. Extensive modifications have then been introduced (namely a new headend cell equipped with a shear) to make the plant suitable to reprocess power reactor fuels. The experimental program of the plant includes a joint CNEN-AECL reprocessing experiment on CANDU (Pickering) type fuel elements to demonstrate a two cycle, amine based recovery of the plutonium. Later, a stock of high burnup fuel elements from the PWR Trino power station will be reprocessed to recover Pu and U with a Purex type flowsheet. ITREC, the second CNEN experimental reprocessing plant located at Trisaia Nuclear Center (Matera), started active operation two years ago. In the first campaign Th-U mixed oxide fuel elements irradiated in the Elk River reactor were processed. Results of this experiment are reported. ITREC special design features confer a high degree of versability to the plant allowing for substantial equipment modification under remote control conditions. For this reason the plant will be principally devoted in the near future to advanced equipment testing. Along this line high speed centrifugal contactor of a new type developed in Poland will be tested in the plant in the frame of a joint experiment between CNEN and the Polish AEC. Later on the plant program will include experimental campaign on fast reactor fuels; a detailed study on this program is in

  16. Economic evaluation of reprocessing - Indicative Canadian position

    International Nuclear Information System (INIS)

    1979-05-01

    This paper, which also appears as an Appendix to the final Working Group 4 report, forms part of the overall economic evaluation of reprocessing. The indicative national position and illustrative ''phase diagram'' for Canada is presented. Three fuel cycles are considered. (1) CANDU operating on the natural uranium, once-through fuel cycle. (2) CANDU operating with low enrichment (1.2%) once-through fuel cycle. (3) CANDU operating with recycle of plutonium and depleted uranium which has been extracted from spent CANDU natural uranium fuel. The diagrams show that reprocessing and recycle of fuel can be used to reduce further the sensitivity of CANDU fuelling costs to increasing uranium ore price

  17. TIGA Tide Gauge Data Reprocessing at GFZ

    Science.gov (United States)

    Deng, Zhiguo; Schöne, Tilo; Gendt, Gerd

    2014-05-01

    To analyse the tide gauge measurements for the purpose of global long-term sea level change research a well-defined absolute reference frame is required by oceanographic community. To create such frame the data from a global GNSS network located at or near tide gauges are processed. For analyzing the GNSS data on a preferably continuous basis the International GNSS Service (IGS) Tide Gauge Benchmark Monitoring Working Group (TIGA-WG) is responsible. As one of the TIGA Analysis Centers the German Research Centre for Geosciences (GFZ) is contributing to the IGS TIGA Reprocessing Campaign. The solutions of the TIGA Reprocessing Campaign will also contribute to 2nd IGS Data Reprocessing Campaign with GFZ IGS reprocessing solution. After the first IGS reprocessing finished in 2010 some improvements were implemented into the latest GFZ software version EPOS.P8: reference frame IGb08 based on ITRF2008, antenna calibration igs08.atx, geopotential model (EGM2008), higher-order ionospheric effects, new a priori meteorological model (GPT2), VMF mapping function, and other minor improvements. GPS data of the globally distributed tracking network of 794 stations for the time span from 1994 until end of 2012 are used for the TIGA reprocessing. To handle such large network a new processing strategy is developed and described in detail. In the TIGA reprocessing the GPS@TIGA data are processed in precise point positioning (PPP) mode to clean data using the IGS reprocessing orbit and clock products. To validate the quality of the PPP coordinate results the rates of 80 GPS@TIGA station vertical movement are estimated from the PPP results using Maximum Likelihood Estimation (MLE) method. The rates are compared with the solution of University of LaRochelle Consortium (ULR) (named ULR5). 56 of the 80 stations have a difference of the vertical velocities below 1 mm/yr. The error bars of PPP rates are significant larger than those of ULR5, which indicates large time correlated noise in

  18. Light water reactor fuel reprocessing and recycling

    International Nuclear Information System (INIS)

    1977-07-01

    This document was originally intended to provide the basis for an environmental impact statement to assist ERDA in making decisions with respect to possible LWR fuel reprocessing and recycling programs. Since the Administration has recently made a decision to indefinitely defer reprocessing, this environmental impact statement is no longer needed. Nevertheless, this document is issued as a report to assist the public in its consideration of nuclear power issues. The statement compares the various alternatives for the LWR fuel cycle. Costs and environmental effects are compared. Safeguards for plutonium from sabotage and theft are analyzed

  19. Radiation risk assessment of reprocessed uranium

    International Nuclear Information System (INIS)

    Cardenas, Hugo R.; Perez, Aldo E.; Luna, Manuel F.; Becerra, Fabian A.

    1999-01-01

    Reprocessed uranium contains 232 U, which is not found in nature, as well as 234 U which is present in higher proportion than in natural uranium. Both isotopes modify the radiological properties of the material. The paper evaluates the increase of the internal and external radiation risk on the base of experimental data and theoretical calculations. It also suggests measures to be taken in the production of fuel elements with slightly enriched uranium.The radiation risk of reprocessed uranium is directly proportional to the content of 232 U and 234 U as well as to the aging time of the material

  20. Contamination of incinerator at Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Takahashi, Mutsuo

    1994-01-01

    Originally, at Tokai Reprocessing Plant an incinerator was provided in the auxiliary active facility(waste treatment building). This incinerator had treated low level solid wastes generated every facilities in the Tokai Reprocessing Plant since 1974 and stopped the operation in March 1992 because of degeneration. The radioactivity inventory and distribution was evaluated to break up incinerator, auxiliary apparatuses(bag filter, air scrubbing tower, etc.), connecting pipes and off-gas ducts. This report deals with the results of contamination survey of incinerator and auxiliary apparatuses. (author)

  1. Nondestructive assay measurements applied to reprocessing plants

    International Nuclear Information System (INIS)

    Ruhter, Wayne D.; Lee, R. Stephen; Ottmar, Herbert; Guardini, Sergio

    1999-01-01

    Nondestructive assay for reprocessing plants relies on passive gamma-ray spectrometry for plutonium isotopic and plutonium mass values of medium-to-low-density samples and holdup deposits; on active x-ray fluorescence and densitometry techniques for uranium and plutonium concentrations in solutions; on calorimetry for plutonium mass in product; and passive neutron techniques for plutonium mass in spent fuel, product, and waste. This paper will describe the radiation-based nondestructive assay techniques used to perform materials accounting measurements. The paper will also discuss nondestructive assay measurements used in inspections of reprocessing plants [ru

  2. PYRO, a system for modeling fuel reprocessing

    International Nuclear Information System (INIS)

    Ackerman, J.P.

    1989-01-01

    Compact, on-site fuel reprocessing and waste management for the Integral Fast Reactor are based on the pyrochemical reprocessing of metal fuel. In that process, uranium and plutonium in spent fuel are separated from fission products in an electrorefiner using liquid cadmium and molten salt solvents. Quantitative estimates of the distribution of the chemical elements among the metal and salt phases are essential for development of both individual pyrochemical process steps and the complete process. This paper describes the PYRO system of programs used to generate reliable mass flows and compositions

  3. Criticality safety evaluation in Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Shirai, Nobutoshi; Nakajima, Masayoshi; Takaya, Akikazu; Ohnuma, Hideyuki; Shirouzu, Hidetomo; Hayashi, Shinichiro; Yoshikawa, Koji; Suto, Toshiyuki

    2000-04-01

    Criticality limits for equipments in Tokai Reprocessing Plant which handle fissile material solution and are under shape and dimension control were reevaluated based on the guideline No.10 'Criticality safety of single unit' in the regulatory guide for reprocessing plant safety. This report presents criticality safety evaluation of each equipment as single unit. Criticality safety of multiple units in a cell or a room was also evaluated. The evaluated equipments were ones in dissolution, separation, purification, denitration, Pu product storage, and Pu conversion processes. As a result, it was reconfirmed that the equipments were safe enough from a view point of criticality safety of single unit and multiple units. (author)

  4. Industrial experience of irradiated nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Delange, M.

    1981-01-01

    At the moment and during the next following years, France and La Hague plant particularly, own the greatest amount of industrial experience in the field of reprocessing, since this experience is referred to three types of reactors, either broadly spread all through the world (GCR and LWR) or ready to be greatly developed in the next future (FBR). Then, the description of processes and technologies used now in France, and the examination of the results obtained, on the production or on the security points of view, are a good approach of the actual industrial experience in the field of spent fuel reprocessing. (author)

  5. Working conditions in nuclear reprocessing plants

    International Nuclear Information System (INIS)

    1986-12-01

    In the context of the project, the working conditions of workers in reprocessing plants and associated plant of the fuel circuit were thoroughly examined. The project design and course of the project are a good example of a precautionary technical assessment necessary for social policy reasons, which is in the public interest and is required by the Trade Unions. By working conditions, one means the whole set of scientific/technical, medical, legal, economic and political conditions for the permanent employment of workers in reprocessing plants including the associated parts of the fuel circuit. (orig./HP) [de

  6. Comparative Results of AIRS/AMSU and CrIS/ATMS Retrievals Using a Scientifically Equivalent Retrieval Algorithm

    Science.gov (United States)

    Susskind, Joel; Kouvaris, Louis; Iredell, Lena

    2016-01-01

    The AIRS Science Team Version-6 retrieval algorithm is currently producing high quality level-3 Climate Data Records (CDRs) from AIRS/AMSU which are critical for understanding climate processes. The AIRS Science Team is finalizing an improved Version-7 retrieval algorithm to reprocess all old and future AIRS data. AIRS CDRs should eventually cover the period September 2002 through at least 2020. CrIS/ATMS is the only scheduled follow on to AIRS/AMSU. The objective of this research is to prepare for generation of long term CrIS/ATMS CDRs using a retrieval algorithm that is scientifically equivalent to AIRS/AMSU Version-7.

  7. Comparative Results of AIRS AMSU and CrIS/ATMS Retrievals Using a Scientifically Equivalent Retrieval Algorithm

    Science.gov (United States)

    Susskind, Joel; Kouvaris, Louis; Iredell, Lena

    2016-01-01

    The AIRS Science Team Version 6 retrieval algorithm is currently producing high quality level-3 Climate Data Records (CDRs) from AIRSAMSU which are critical for understanding climate processes. The AIRS Science Team is finalizing an improved Version-7 retrieval algorithm to reprocess all old and future AIRS data. AIRS CDRs should eventually cover the period September 2002 through at least 2020. CrISATMS is the only scheduled follow on to AIRSAMSU. The objective of this research is to prepare for generation of a long term CrISATMS level-3 data using a finalized retrieval algorithm that is scientifically equivalent to AIRSAMSU Version-7.

  8. Power Reactor Fuel Reprocessing Plant-1: a stepping stone in Indian PHWR spent fuel reprocessing

    International Nuclear Information System (INIS)

    Pradhan, Sanjay; Dubey, K.; Qureshi, F.T.; Lokeswar, S.P.

    2017-01-01

    India has low reserves of uranium and high reserves of thorium. In order to optimize resource utilization India has adopted a closed fuel cycle to ensure long-term energy security. The optimum resource utilization is feasible only by adopting reprocessing, conditioning and recycle options. It is very much imperative to view spent fuel as a vital resource material and not a waste to be disposed off. Thus, spent nuclear fuel reprocessing forms an integral part of the Indian Nuclear Energy Programme. Aqueous reprocessing based on PUREX technology is in use for more than 50 years and has reached a matured status

  9. Foreign Body Retrieval

    Medline Plus

    Full Text Available ... Physician Resources Professions Site Index A-Z Foreign Body Retrieval Foreign body retrieval is the removal of ... foreign body detection and removal? What is Foreign Body Retrieval? Foreign body retrieval involves the removal of ...

  10. DELFIC-TES, Gamma Doses from Nuclear Explosion Radioactive Clouds

    International Nuclear Information System (INIS)

    1991-01-01

    1 - Description of program or function: DELFIC-TES computes the transit gamma exposure from the airborne cloud resulting from a nuclear burst for fixed targets located on or above the earth's surface. 2 - Method of solution - The system is based on a method of producing 'snapshots' of the moving cloud of airborne particles during the transport process of DELFIC. Each particle in each snapshot is then assigned an activity and these data are used to calculate transit exposure by employing an energy-dependent buildup factor technique

  11. Perbandingan Keefektifan Bentuk Tes Uraian dan Teslet dengan Penerapan Graded Response Model (GRM

    Directory of Open Access Journals (Sweden)

    Purwo susongko

    2013-01-01

    Full Text Available Abstrak Penelitian ini bertujuan untuk menemukan: (1 perbandingan nilai fungsi informasi item pada bentuk tes uraian dan testlet secara empirik dan simulasi, (2 pengaruh banyaknya item dan ukuran sampel terhadap perbandingan nilai fungsi informasi item pada bentuk tes uraian dan testlet secara simulasi, dan (3 keakuratan pemodelan GRM pada bentuk uraian dan testlet. Data empirik diambil dari respons siswa terhadap tes bentuk uraian dan bentuk testlet dari 772 siswa SMA kelas XI yang tersebar di lima SMA di Kabupaten Tegal. Bentuk tes uraian dan testlet bersama-sama diberikan pada siswa pada akhir semester I dan di awal semester II dengan waktu tenggang minimal 1 bulan. Data pada penelitian simulasi dibangkitkan dari parameter item hasil estimasi pada penelitian empirik dengan program WinGen 2. Hasil penelitian menunjukkan bahwa: (1 secara empirik dan simulasi, tes yang disajikan dalam bentuk uraian cenderung memiliki nilai fungsi informasi item yang lebih tinggi dibanding dengan tes yang disajikan dalam bentuk testlet, (2 secara simulasi, ada pengaruh banyaknya item dan ukuran sampel terhadap perbandingan nilai fungsi informasi item pada bentuk tes uraian dan bentuk testlet, dan (3 pemodelan GRM pada bentuk tes uraian dan testlet paling akurat pada kondisi banyaknya item 20 dan ukuran sampel 2000. Kata kunci: keefektifan, bentuk tes, graded response model

  12. Image retrieval

    DEFF Research Database (Denmark)

    Ørnager, Susanne

    1997-01-01

    The paper touches upon indexing and retrieval for effective searches of digitized images. Different conceptions of what subject indexing means are described as a basis for defining an operational subject indexing strategy for images. The methodology is based on the art historian Erwin Panofsky......), special knowledge about image codes, and special knowledge about history of ideas. The semiologist Roland Barthes has established a semiology for pictorial expressions based on advertising photos. Barthes uses the concepts denotation/connotation where denotations can be explained as the sober expression...

  13. Summary of nuclear fuel reprocessing activities around the world

    International Nuclear Information System (INIS)

    Mellinger, P.J.; Harmon, K.M.; Lakey, L.T.

    1984-11-01

    This review of international practices for nuclear fuel reprocessing was prepared to provide a nontechnical summary of the current status of nuclear fuel reprocessing activities around the world. The sources of information are widely varied

  14. Overview of technologies to reprocess ion-exchange resins

    International Nuclear Information System (INIS)

    Gavrish, V.M.; Chernikova, N.P.; Ivanets, V.G.

    2010-01-01

    The article deals with overview of technologies for reprocessing of ion-exchange resins and determining the most optimal solutions for Ukraine. The technologies for cementations, thermal reprocessing, bituminization and deep decontamination are considered.

  15. Reprocessing of nuclear fuels: economical, ecological and technical aspects

    International Nuclear Information System (INIS)

    Kueffer, K.

    1994-01-01

    The report deals with the questions on reprocessing and final storage of spent fuel elements from the point of view of the Swiss. The contractual obligations were discussed, of the present situation of reprocessing and their assessment. 1 fig

  16. TES/Aura L2 Summary Profiles V005

    Data.gov (United States)

    National Aeronautics and Space Administration — Atmospheric vertical profile estimates, along with retrieved surface temperature, cloud effective optical depth, column estimates, quality flags, and a priori...

  17. TES/Aura L2 Summary Profiles V003

    Data.gov (United States)

    National Aeronautics and Space Administration — Atmospheric vertical profile estimates, along with retrieved surface temperature, cloud effective optical depth, column estimates, quality flags, and a priori...

  18. International cooperation in the field of reprocessing

    International Nuclear Information System (INIS)

    Busekist, O. von

    1983-01-01

    Following a definition of the concept of international cooperation, this paper discusses existing and possible legal and institutional arrangements in the reprocessing field, with particular reference to the legal framework set up for the European Company for the Chemical Processing of Irradiated Fuels (Eurochemic). (NEA) [fr

  19. Plutonium, proliferation, and the price of reprocessing

    International Nuclear Information System (INIS)

    Gilinsky, V.

    1978-01-01

    France and Britain disagree with the US on whether deferring fuel reprocessing that provides plutonium for export can help contain proliferation. The US has veto power over reprocessing of US-supplied fuels for non-EURATOM countries, but exceptions will be made for movement within the EURATOM community. Political issues will be influenced by the magnitude of the financial investments, however, and commercial considerations have until recently dominated and complicated international safeguards. The author notes that US policy was reversed by the gradual acknowledgment that the same international inspection of plutonium stockpiles would not work as it had for low-enriched fuel and that economic interests must have a lower priority to avoiding proliferation. He cites the combination of sudden policy shifts, failure to prove that present reactors are best, and long-term distrust of US economic motives as failing to persuade either the French or British, who feel the best safeguard is provided by their high-security reprocessing facilities. Still to be resolved are the conditions under which plutonium must be returned to its owners, a problem that must determine safe international transport and storage and international management. Technical fixes, such as the CIVEX process, cannot contribute to the solution for several decades, while reprocessing is no longer considered a first step in waste disposal and would be more expensive and complicated than present waste disposal procedures. The author concedes merit in President Carter's requirement of separating ''the legitimate and necessary use of uranium'' and nuclear fuels that are also explosives

  20. Simulation of solvent extraction in reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Kumar, Shekhar; Koganti, S B [Reprocessing Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)

    1994-06-01

    A SIMulation Program for Solvent EXtraction (SIMPSEX) has been developed for simulation of PUREX process used in nuclear fuel reprocessing. This computer program is written in double precision structured FORTRAN77 and at present it is used in DOS environment on a PC386. There is a plan to port it to ND supermini computers in future. (author). 5 refs., 3 figs.

  1. Economic evaluation of reprocessing - Indicative Belgian position

    International Nuclear Information System (INIS)

    1979-05-01

    This paper, which also appears as an Appendix to the final Working Group 4 report, forms part of the overall economic evaluation of reprocessing. The indicative national position and illustrative ''phase diagram'' for Belgium is presented. Other factors which influence the Belgian viewpoint and which are not included on the phase diagram are given

  2. Irradiated uranium reprocessing; Prerada ozracenog urana

    Energy Technology Data Exchange (ETDEWEB)

    Gal, I [Institute of Nuclear Sciences Boris Kidric, Laboratorijaza visoku aktivnost, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Task concerned with reprocessing of irradiated uranium covered the following activities: implementing the method and constructing the cell for uranium dissolving; implementing the procedure for extraction of uranium, plutonium and fission products from radioactive uranium solutions; studying the possibilities for using inorganic ion exchangers and adsorbers for separation of U, Pu and fission products.

  3. reprocesser gennem struktureret refleksion

    DEFF Research Database (Denmark)

    Engell, Christian; Hansen, Torben

    2009-01-01

    Udgangspunktet for "Læreprocesser Gennem strukturerede refleksion" er spørgsmålet om, hvordan strukturering af refleksion kan bidrage til at sikre (det nærmeste umulige) at eleverne lærer, det tilsigtede i (boldspil-)undervisningen. Forfatterne Christian Engell og Torben Hansen viser, hvordan beg...

  4. Fuel reprocessing: Citizens' questions and experts' answers

    International Nuclear Information System (INIS)

    1982-10-01

    In connection with the intention of DWK to erect a fuel reprocessing plant in the Oberpfalz, citizens have asked a great number of questions which are of interest to the general public. They have been collected, grouped into subject categories and answered by experts. (orig./HSCH) [de

  5. Optimizing near real time accountability for reprocessing

    International Nuclear Information System (INIS)

    Cipiti, Benjamin B.

    2010-01-01

    Near Real Time Accountability (NRTA) of actinides at high precision in reprocessing plants has been a long sought-after goal in the safeguards community. Achieving this goal is hampered by the difficulty of making precision measurements in the reprocessing environment, equipment cost, and impact to plant operations. Thus the design of future reprocessing plants requires an optimization of different approaches. The Separations and Safeguards Performance Model, developed at Sandia National Laboratories, was used to evaluate a number of NRTA strategies in a UREX+ reprocessing plant. Strategies examined include the incorporation of additional actinide measurements of internal plant vessels, more use of process monitoring data, and the option of periodic draining of inventory to key tanks. Preliminary results show that the addition of measurement technologies can increase the overall measurement uncertainty due to additional error propagation, so care must be taken when designing an advanced system. Initial results also show that relying on a combination of different NRTA techniques will likely be the best option. The model provides a platform for integrating all the data. The modeling results for the different NRTA options under various material loss conditions will be presented.

  6. Radioactive Semivolatiles in Nuclear Fuel Reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Jubin, R. T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Strachan, D. M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ilas, G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Spencer, B. B. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Soelberg, N. R. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-09-01

    In nuclear fuel reprocessing, various radioactive elements enter the gas phase from the unit operations found in the reprocessing facility. In previous reports, the pathways and required removal were discussed for four radionuclides known to be volatile, 14C, 3H, 129I, and 85Kr. Other, less volatile isotopes can also report to the off-gas streams in a reprocessing facility. These were reported to be isotopes of Cs, Cd, Ru, Sb, Tc, and Te. In this report, an effort is made to determine which, if any, of 24 semivolatile radionuclides could be released from a reprocessing plant and, if so, what would be the likely quantities released. As part of this study of semivolatile elements, the amount of each generated during fission is included as part of the assessment for the need to control their emission. Also included in this study is the assessment of the cooling time (time out of reactor) before the fuel is processed. This aspect is important for the short-lived isotopes shown in the list, especially for cooling times approaching 10 y. The approach taken in this study was to determine if semivolatile radionuclides need to be included in a list of gas-phase radionuclides that might need to be removed to meet Environmental Protection Agency (EPA) and Nuclear Regulatory Commission (NRC) regulations. A list of possible elements was developed through a literature search and through knowledge and literature on the chemical processes in typical aqueous processing of nuclear fuels. A long list of possible radionuclides present in irradiated fuel was generated and then trimmed by considering isotope half-life and calculating the dose from each to a maximum exposed individual with the US EPA airborne radiological dispersion and risk assessment code CAP88 (Rosnick 1992) to yield a short list of elements that actually need to be considered for control because they require high decontamination factors to meet a reasonable fraction of the regulated release. Each of these elements is

  7. EOS Data Products Latency and Reprocessing Evaluation

    Science.gov (United States)

    Ramapriyan, H. K.; Wanchoo, L.

    2012-12-01

    NASA's Earth Observing System (EOS) Data and Information System (EOSDIS) program has been processing, archiving, and distributing EOS data since the launch of Terra platform in 1999. The EOSDIS Distributed Active Archive Centers (DAACs) and Science-Investigator-led Processing Systems (SIPSs) are generating over 5000 unique products with a daily average volume of 1.7 Petabytes. Initially EOSDIS had requirements to make process data products within 24 hours of receiving all inputs needed for generating them. Thus, generally, the latency would be slightly over 24 and 48 hours after satellite data acquisition, respectively, for Level 1 and Level 2 products. Due to budgetary constraints these requirements were relaxed, with the requirement being to avoid a growing backlog of unprocessed data. However, the data providers have been generating these products in as timely a manner as possible. The reduction in costs of computing hardware has helped considerably. It is of interest to analyze the actual latencies achieved over the past several years in processing and inserting the data products into the EOSDIS archives for the users to support various scientific studies such as land processes, oceanography, hydrology, atmospheric science, cryospheric science, etc. The instrument science teams have continuously evaluated the data products since the launches of EOS satellites and improved the science algorithms to provide high quality products. Data providers have periodically reprocessed the previously acquired data with these improved algorithms. The reprocessing campaigns run for an extended time period in parallel with forward processing, since all data starting from the beginning of the mission need to be reprocessed. Each reprocessing activity involves more data than the previous reprocessing. The historical record of the reprocessing times would be of interest to future missions, especially those involving large volumes of data and/or computational loads due to

  8. Future of the reprocessing business at the RT-1 plant

    International Nuclear Information System (INIS)

    Bukharin, O.

    1995-01-01

    Economic viability of reprocessing operations at the RT-1 plant is provided by the contracts with nuclear utilities from Finland and Hungary. Finland will stop sending fuel to Mayak for reprocessing after 1996. Hungary will be capable to resolve the problem of spent fuel domestically some time in the future. This increases vulnerability of the reprocessing business at Mayak to future political uncertainties. (author)

  9. The 4th technological meeting of Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Ohnishi, Tohru; Maki, Akira; Shibata, Satomi; Yatogi, Hideo; Nyui, Daisuke; Hashimoto, Takakazu; Fukuda, Kazuhito; Ohzeki, Tatsuya

    2001-11-01

    ''The 4th technological meeting of Tokai Reprocessing Plant (TRP)'' was held in JNFL Rokkasho site on October 11 th , 2001. The report contains the proceedings, transparencies and questionnaires of the meeting. This time, we reported about ''Maintenance and repair results of Tokai Reprocessing Plant'' based on technology and knowledge accumulated in Tokai Reprocessing Plant. (author)

  10. Spent fuel reprocessing system availability definition by process simulation

    International Nuclear Information System (INIS)

    Holder, N.; Haldy, B.B.; Jonzen, M.

    1978-05-01

    To examine nuclear fuel reprocessing plant operating parameters such as maintainability, reliability, availability, equipment redundancy, and surge storage requirements and their effect on plant throughput, a computer simulation model of integrated HTGR fuel reprocessing plant operations is being developed at General Atomic Company (GA). The simulation methodology and the status of the computer programming completed on reprocessing head end systems is reported

  11. Direction of reprocessing technology development based on 30 years operation of Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Nomura, S; Tanaka, T.; Ohshima, H.

    2006-01-01

    Full text: Full text: Recent global interest focuses the possibility of recycling of spent fuel with advanced fast reactor fuel cycle system. Goal of closed fuel cycle is to achieve the maximum use of uranium resources and minimum disposal of waste by multi recycle of TRU as a competitive nuclear energy system. The future reprocessing and fuel fabrication system should be synchronized completely with the advanced reactor system and waste treatment and disposal back-end system to complete closed fuel cycle. To realize such system, current reprocessing system should be changed to handle Pu-U-Minor Actinide with more reductions in the cost and less waste volume, as well as an inherent proliferation resistance. For the successful industrialization of advanced reprocessing technology, it is necessary to combine three key elements of R and D efforts, engineering base demonstration and experiences of plant operation. Tokai Reprocessing Facilities licensed a maximum capacity of 0.7tHM/day began a hot operation in 1977 and reprocessed l,100tHM U02 spent fuel and 20tHM ATR-MOX with a continuous technological improvements under IAEA full scope safeguards. With 30 years experience, candidate of key technologies proposed for realizing the next advanced reprocessing are as follows: 1) Simplified co-extraction process of Pu-Np-U by using multistage centrifugal extractors in stead of pulsed columns; 2) Corrosion free components in acid condition by using corrosion resistant refractory alloys and ceramics; 3) Co-conversion technology to MA containing MOX powder by micro-wave heating method for a short process for MA containing MOX pellets fabrication; 4) Advanced verification of high level radioactive liquid waste combining separation technology of TRU and LLFP elements; 5) Advanced chemical analysis and monitoring system for TRU elements in a plant. These advanced reprocessing technologies will be applied mainly to reprocess the LWR spent fuel accumulated past and future

  12. Tropospheric methanol observations from space: retrieval evaluation and constraints on the seasonality of biogenic emissions

    Directory of Open Access Journals (Sweden)

    K. C. Wells

    2012-07-01

    Full Text Available Methanol retrievals from nadir-viewing space-based sensors offer powerful new information for quantifying methanol emissions on a global scale. Here we apply an ensemble of aircraft observations over North America to evaluate new methanol measurements from the Tropospheric Emission Spectrometer (TES on the Aura satellite, and combine the TES data with observations from the Infrared Atmospheric Sounding Interferometer (IASI on the MetOp-A satellite to investigate the seasonality of methanol emissions from northern midlatitude ecosystems. Using the GEOS-Chem chemical transport model as an intercomparison platform, we find that the TES retrieval performs well when the degrees of freedom for signal (DOFS are above 0.5, in which case the model:TES regressions are generally consistent with the model:aircraft comparisons. Including retrievals with DOFS below 0.5 degrades the comparisons, as these are excessively influenced by the a priori. The comparisons suggest DOFS >0.5 as a minimum threshold for interpreting retrievals of trace gases with a weak tropospheric signal. We analyze one full year of satellite observations and find that GEOS-Chem, driven with MEGANv2.1 biogenic emissions, underestimates observed methanol concentrations throughout the midlatitudes in springtime, with the timing of the seasonal peak in model emissions 1–2 months too late. We attribute this discrepancy to an underestimate of emissions from new leaves in MEGAN, and apply the satellite data to better quantify the seasonal change in methanol emissions for midlatitude ecosystems. The derived parameters (relative emission factors of 11.0, 0.26, 0.12 and 3.0 for new, growing, mature, and old leaves, respectively, plus a leaf area index activity factor of 0.5 for expanding canopies with leaf area index <1.2 provide a more realistic simulation of seasonal methanol concentrations in midlatitudes on the basis of both the IASI and TES measurements.

  13. Contribution à la connaissance des micromycètes du Maroc. Cas ...

    African Journals Online (AJOL)

    Contribution à la connaissance des micromycètes du Maroc. Cas des ... et qualitative des micromycètes d'origine terrestre de la région de Rabat (Maroc). ... elles ont été entraînées dans le milieu aquatique par différents moyens de transport.

  14. History and current status of nuclear fuel reprocessing technology

    International Nuclear Information System (INIS)

    Funasaka, Hideyuki; Nagai, Toshihisa; Washiya, Tadahiro

    2008-01-01

    History and present state of fast breeder reactor was reviewed in series. As a history and current status of nuclear fuel reprocessing technology, this ninth lecture presented the progress of the FBR fuel reprocessing technology and advanced reprocessing processes. FBR fuel reprocessing technology had been developed to construct the reprocessing equipment test facilities (RETF) based on PUREX process technologies. With economics, reduction of environmental burdens and proliferation resistance taken into consideration, advanced aqueous method for nuclear fuel cycle activities has been promoted as the government's basic policy. Innovative technologies on mechanical disassembly, continuous rotary dissolver, crystallizer, solvent extraction and actinides recovery have been mainly studied. (T. Tanaka)

  15. Safety guide data on radiation shielding in a reprocessing facility

    International Nuclear Information System (INIS)

    Sekiguchi, Noboru; Naito, Yoshitaka

    1986-04-01

    In a reprocessing facility, various radiation sources are handled and have many geometrical conditions. To aim drawing up a safety guidebook on radiation shielding in order to evaluate shielding safety in a reprocessing facility with high reliability and reasonableness, JAERI trusted investigation on safety evaluation techniques of radiation shielding in a reprocessing facility to Nuclear Safety Research Association. This report is the collection of investigation results, and describes concept of shielding safety design principle, radiation sources in reprocessing facility and estimation of its strength, techniques of shielding calculations, and definite examples of shielding calculation in reprocessing facility. (author)

  16. Status and trends in spent fuel reprocessing

    International Nuclear Information System (INIS)

    2005-09-01

    The management of spent fuel arising from nuclear power production is a crucial issue for the sustainable development of nuclear energy. The IAEA has issued several publications in the past that provide technical information on the global status and trends in spent fuel reprocessing and associated topics, and one reason for this present publication is to provide an update of this information which has mostly focused on the conventional technology applied in the industry. However, the scope of this publication has been significantly expanded in an attempt to make it more comprehensive and by including a section on emerging technologies applicable to future innovative nuclear systems, as are being addressed in such international initiatives as INPRO, Gen IV and MICANET. In an effort to be informative, this publication attempts to provide a state-of-the-art review of these technologies, and to identify major issues associated with reprocessing as an option for spent fuel management. It does not, however, provide any detailed information on some of the related issues such as safety or safeguards, which are addressed in other relevant publications. This report provides an overview of the status of reprocessing technology and its future prospects in terms of various criteria in Section 2. Section 3 provides a review of emerging technologies which have been attracting the interest of Member States, especially in the international initiatives for future development of innovative nuclear systems. A historical review of IAEA activities associated with spent fuel reprocessing, traceable back to the mid-1970s, is provided in Section 4, and conclusions in Section 5. A list of references is provided at the end the main text for readers interested in further information on the related topics. Annex I summarizes the current status of reprocessing facilities around the world, including the civil operational statistics of Purex-based plants, progress with decommissioning and

  17. Bismuth X-ray absorber studies for TES microcalorimeters

    International Nuclear Information System (INIS)

    Sadleir, J.E.; Bandler, S.R.; Brekosky, R.P.; Chervenak, J.; Figueroa-Feliciano, E.; Finkbeiner, F.; Iyomoto, N.; Kelley, R.L.; Kilbourne, C.A.; King, J.M.; Porter, F.S.; Robinson, I.K.; Saab, T.; Talley, D.J.

    2006-01-01

    Bismuth's large atomic number and low carrier density makes it an attractive X-ray absorber material for microcalorimeters. Bismuth's long Fermi wavelength and long mean free paths have motivated much interest in the fabrication of high quality bismuth films to study quantum size effects. Despite such incentives, fabrication of high quality bismuth films has proven difficult, and measured properties of such films are highly variable in the literature. Implementing a bismuth deposition process for TES (superconducting Transition Edge Sensor) device fabrication presents additional challenges particularly at interfaces due to the inherent granularity and surface roughness of its films, its low melting point, and its tendency to diffuse and form undesired intermetallic phases. We report observations of Bi-Cu and Bi-Au diffusion in our devices correlating with large shifts in T c (superconducting transition temperature). Using SEM and in situ R vs T annealing experiments we have been able to study these diffusion processes and identify their activation temperatures

  18. Veikala lojalitātes programmas iOS lietotne

    OpenAIRE

    Freibergs, Kristaps

    2013-01-01

    Pasaulē izmantoto tehnoloģiju klāstam augot, ir pieaudzis arī mobilo ierīču piedāvājums un to iespējas. Salīdzinoši lielu daļu tirgus ir iekarojusi Apple Inc. ar savu produkciju, tai skaitā iPhone viedtālruņiem. Šajā kvalifikācijas darbā tiek aprakstīta un izstrādāta iPhone ierīces lietotne veikala lojalitātes programmas realizācijai. Lietotnes mērķis ir popularizēt konkrēto veikalu, piedāvājot dažādas lietotājam saistošas funkcijas, tai skaitā, apskatīt tuvākos veikalus, izveidot iepirkumu g...

  19. International safeguards for reprocessing plants. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Kratzer, M.; Scheinman, L.; Sievering, N.; Wonder, E.; Lipman, D.; Immerman, W.; Elliott, J.M.; Crane, F.

    1981-04-01

    Proliferation risks inherent in reprocessing show the need to employ technically effective safeguards which can detect, with a high degree of assurance and on a timely basis, the diversion of significant quantities of fissionable material. A balance must be struck between what is technically feasible and effective and what is institutionally acceptable. Purpose of this report is to examine the several technical approaches to safeguards in light of their prospective acceptability. This study defines the economic, political and institutional nature of the safeguards problem; surveys generically alternative technical approaches to international safeguards including their effectiveness and relative development; characterizes the institutional implications and uncertainties associated with the acceptance and implementation of each technical alternative; and integrates these assessments into a set of overall judgments on feasible directions for reprocessing plant safeguards systems.

  20. UP3 plant first reprocessing campaigns

    International Nuclear Information System (INIS)

    Leudet, A.; Hugelmann, D.; Fournier, W.; Dalverny, G.

    1991-01-01

    The UP3 plant start up has been achieved in two successive steps. The first one, from November 89 to April 90, involved all the facilities but T1, the head-end facility. During that period, shearing, dissolution and the first cycle extraction operations were performed in UP2 plant. 100 tons of fuel have been reprocessed that way. The second step began in August 1990, with the T1 facility start-up and the reprocessing of the resulting active solutions in the rest of the plant. This second phase involving the entire UP3 plant continued until the end of January 1991. At that time, 160 tons of fuel have been completely treated in UP3 plant

  1. Management of spent solvents of reprocessing origin

    International Nuclear Information System (INIS)

    Manohar, S.; Srinivas, C.; Vincent, T.; Wattal, P.K.

    2001-01-01

    Spent solvents of reprocessing origin constitute a major portion of radioactive liquid organic wastes arising from nuclear activity. An in-depth study of this waste stream has led to the evolution of a complete management option, which addresses not only the concern of radioactivity but also its organic nature. This is based on alkaline hydrolysis of Tri-n-butyl phosphate (TBP), which converts it into aqueous soluble products, viz. sodium salt of dibutyl phosphoric acid and butanol. During the process of alkaline hydrolysis almost all the activity associated with the waste gets transferred into the aqueous phase. The recovered diluent virtually free of activity and TBP can be recycled, and in case of it not meeting reprocessing standards, can be incinerated. The process generated aqueous waste is found compatible with cement and can be immobilized in cement matrix. (author)

  2. Power Reactor Thoria Reprocessing Facility (PRTRF), Trombay

    International Nuclear Information System (INIS)

    Dhami, P.S; Yadav, J.S; Agarwal, K.

    2017-01-01

    Exploitation of the abundant thorium resources to meet sustained energy demand forms the basis of the Indian nuclear energy programme. To gain reprocessing experience in thorium fuel cycle, thoria was irradiated in research reactor CIRUS in early sixties. Later in eighties, thoria bundles were used for initial flux flattening in some of the pressurized heavy water reactors (PHWRs). The research reactor irradiated thoria contained small content (∼ 2-3ppm) of "2"3"2U in "2"3"3U product, which did not pose any significant radiological problems during processing in Uranium Thorium Separation Facility (UTSF), Trombay. Thoria irradiated in PHWRs on discharge contained (∼ 0.5-1.5% "2"3"3U with significant "2"3"2U content (100-500 ppm) requiring special radiological attention. Based on the experience from UTSF, a new facility viz. Power Reactor Thoria Reprocessing Facility (PRTRF), Trombay was built which was hot commissioned in the year 2015

  3. Reprocessing in Sweden: History and perspective

    International Nuclear Information System (INIS)

    Hultgren, Aa.; Oesterlund, C.G.

    1990-10-01

    Against the background of nuclear power development and installation in Sweden an overview is presented of the parallel domestic development of the reprocessing of spent nuclear fuel. The original selection of the natural uranium - heavy water reactor in the 1950s included spent fuel reprocessing and recycle, and process and plant studies were performed to that end. The switch to light water reactors in the 1960s did not change the planning to recycle; however, the participation in the Eurochemic undertaking, and the delay in the nuclear programme stopped further domestic development work. A number of governmental committee investigations in the 1970s on the radioactive waste issue and, above all, the decision to phase out nuclear power by 2010, after a referendum following the TMI-accident, finally resulted in a decision to plan only for direct disposal of spent nuclear fuel. This policy still prevails. (42 refs.)

  4. Reprocessing technology for present water reactor fuels

    International Nuclear Information System (INIS)

    McMurray, P.R.

    1977-01-01

    The basic Purex solvent extraction technology developed and applied in the U.S. in the 1950's provides a well-demonstrated and efficient process for recovering uranium and plutonium for fuel recycle and separating the wastes for further treatment and packaging. The technologies for confinement of radioactive effluents have been developed but have had limited utilization in the processing of commercial light water reactor fuels. Technologies for solidification and packaging of radioactive wastes have not yet been demonstrated but significant experience has been gained in laboratory and engineering scale experiments with simulated commercial reprocessing wastes and intermediate level wastes. Commercial scale experience with combined operations of all the required processes and equipment are needed to demonstrate reliable reprocessing centers

  5. An improved sampling system installed for reprocessing

    International Nuclear Information System (INIS)

    Finsterwalder, L.; Zeh, H.

    1979-03-01

    Sampling devices are needed for taking representative samples from individual process containers during the reprocessing of irradiated fuel. The aqueous process stream in a reprocessing plant frequently contains, in addition to the dissolved radioactive materials, more or less small quantities of solid matter fraction of fuel material still remaining undissolved, insoluble fission-, corrosion-, or degradation products as well, in exceptional cases, ion exchange resin or silica gel. The solid matter is deposited partly on the upper surfaces of the sampling system and the radiation due to this makes maintenance and repair of the sampler more difficult. The purpose of the development work was to reduce the chance of accident and the maintenance costs and to lower the radiation exposure of the personnel. A new sampling system was developed and is described. (author)

  6. International safeguards for reprocessing plants. Final report

    International Nuclear Information System (INIS)

    Kratzer, M.; Scheinman, L.; Sievering, N.; Wonder, E.; Lipman, D.; Immerman, W.; Elliott, J.M.; Crane, F.

    1981-04-01

    Proliferation risks inherent in reprocessing show the need to employ technically effective safeguards which can detect, with a high degree of assurance and on a timely basis, the diversion of significant quantities of fissionable material. A balance must be struck between what is technically feasible and effective and what is institutionally acceptable. Purpose of this report is to examine the several technical approaches to safeguards in light of their prospective acceptability. This study defines the economic, political and institutional nature of the safeguards problem; surveys generically alternative technical approaches to international safeguards including their effectiveness and relative development; characterizes the institutional implications and uncertainties associated with the acceptance and implementation of each technical alternative; and integrates these assessments into a set of overall judgments on feasible directions for reprocessing plant safeguards systems

  7. Reprocessing: A reasonable way of waste disposal

    International Nuclear Information System (INIS)

    Merz, E.

    1986-01-01

    Reprocessing is the only way to recover the valuable substances contained in the burnt fuel elements and to make them utilizable for energy generation again. It is easier to adapt a national solution to the special domestic needs than a waste management plant which is operated on an international basis and is therefore simpler to be implemented. It guarantees independence, stands for the meeting of requirements resulting from the Non-Proliferation Treaty and creates safe jobs. Furthermore, it offers more liberty in applying optimized recycling strategies. A national reprocessing industry leads to an improved competitive position in the nuclear business, due to technological development and demonstration. A country like the Federal Republic of Germany, which depends on exports, does need top-level technologies. (HSCH) [de

  8. Integrated international safeguards concepts for fuel reprocessing

    International Nuclear Information System (INIS)

    Hakkila, E.A.; Gutmacher, R.G.; Markin, J.T.; Shipley, J.P.; Whitty, W.J.; Camp, A.L.; Cameron, C.P.; Bleck, M.E.; Ellwein, L.B.

    1981-12-01

    This report is the fourth in a series of efforts by the Los Alamos National Laboratory and Sandia National Laboratories, Albuquerque, to identify problems and propose solutions for international safeguarding of light-water reactor spent-fuel reprocessing plants. Problem areas for international safeguards were identified in a previous Problem Statement (LA-7551-MS/SAND79-0108). Accounting concepts that could be verified internationally were presented in a subsequent study (LA-8042). Concepts for containment/surveillance were presented, conceptual designs were developed, and the effectiveness of these designs was evaluated in a companion study (SAND80-0160). The report discusses the coordination of nuclear materials accounting and containment/surveillance concepts in an effort to define an effective integrated safeguards system. The Allied-General Nuclear Services fuels reprocessing plant at Barnwell, South Carolina, was used as the reference facility

  9. Optimization of X-ray Absorbers for TES Microcalorimeters

    Science.gov (United States)

    Iyomoto, Naoko; Sadleir, John E.; Figueroa-Feliciano, Enectali; Saab, Tarek; Bandler, Simon; Kilbourne, Caroline; Chervenak, James; Talley, Dorothy; Finkbeiner, Fred; Brekosky, Regis

    2004-01-01

    We have investigated the thermal, electrical, and structural properties of Bi and BiCu films that are being developed as X-ray absorbers for transition-edge sensor (TES) microcalorimeter arrays for imaging X-ray spectroscopy. Bi could be an ideal material for an X-ray absorber due to its high X-ray stopping power and low heat capacity, but it has a low thermal conductivity, which can result in position dependence of the pulses in the absorber. In order to improve the thermal conductivity, we added Cu layers in between the Bi layers. We measured electrical and thermal conductivities of the films around 0.1 K(sub 1) the operating temperature of the TES calorimeter, to examine the films and to determine the optimal thickness of the Cu layer. From the electrical conductivity measurements, we found that the Cu is more resistive on the Bi than on a Si substrate. Together with an SEM picture of the Bi surface, we concluded that the rough surface of the Bi film makes the Cu layer resistive when the Cu layer is not thick enough t o fill in the roughness. From the thermal conductivity measurements, we determined the thermal diffusion constant to be 2 x l0(exp 3) micrometers squared per microsecond in a film that consists of 2.25 micrometers of Bi and 0.1 micrometers of Cu. We measured the position dependence in the film and found that its thermal diffusion constant is too low to get good energy resolution, because of the resistive Cu layer and/or possibly a very high heat capacity of our Bi films. We show plans to improve the thermal diffusion constant in our BiCu absorbers.

  10. Selected studies in HTGR reprocessing development

    International Nuclear Information System (INIS)

    Notz, K.J.

    1976-03-01

    Recent work at ORNL on hot cell studies, off-gas cleanup, and waste handling is reviewed. The work includes small-scale burning tests with irradiated fuels to study fission product release, development of the KALC process for the removal of 85 Kr from a CO 2 stream, preliminary work on a nonfluidized bed burner, solvent extraction studies including computer modeling, characterization of reprocessing wastes, and initiation of a development program for the fixation of 14 C as CaCO 3

  11. Solvent management in a reprocessing plant

    International Nuclear Information System (INIS)

    Guillaume, B.; Germain, M.; Puyou, M.; Rouyer, H.

    1987-01-01

    Solvent management in large capacity reprocessing plant is studied to limit production of organic wastes. Chemical processing increases life time of solvent. Low pressure distillation allows the recycling of TBP and diluent at a low activity level. Besides heavy degradation products are eliminated. For the safety the flash point of distillated diluent increases slightly. Tests on an industrial scale started in 1985 and since more than 500 cubic meters were treated [fr

  12. Economic evaluation of reprocessing. Indicative Netherlands position

    International Nuclear Information System (INIS)

    1979-05-01

    The paper, which also appears as an Appendix to the final Working Group 4 report, forms part of the overall economic evaluation of reprocessing. The indicative national position and illustrative ''phase diagram'' for the Netherlands is presented. Two alternative scenarios have been assumed for the variation of uranium price in the future; a 2% per annum price rise and a 5% per annum price rise

  13. Fuel fabrication and reprocessing at UKAEA Dounreay

    International Nuclear Information System (INIS)

    Anderson, B.

    1994-01-01

    The Dounreay fuel plants, which are the most flexible anywhere in the world, will continue to carry out work for foreign commercial customers. A number of German companies are important customers of UKAEA and examples of the wide variety of the work currently being carried out for them in the Dounreay plants is given (reprocessing and fabrication of fuel elements from and for research reactors). (orig./HP) [de

  14. Reprocessing on the whole fuel cycle operations

    International Nuclear Information System (INIS)

    Megy, J.

    1983-11-01

    Spent fuel reprocessing, in France, is become an industrial reality which takes an importance place in several fields: place surely essential in the fuel cycle from the energetic material economy and waste management point of view; place priority in the CEA (Commissariat a l'Energie Atomique) research and development programs; place in the industry where it is an important activity sector with the realizations in progress [fr

  15. Nuclear safety in fuel-reprocessing plants

    International Nuclear Information System (INIS)

    Hennies, H.H.; Koerting, K.

    1976-01-01

    The danger potential of nuclear power and fuel reprocessing plants in normal operation is compared. It becomes obvious that there are no basic differences. The analysis of possible accidents - blow-up of an evaporator for highly active wastes, zircaloy burning, cooling failure in self-heating process solutions, burning of a charged solvent, criticality accidents - shows that they are kept under control by the plant layout. (HP) [de

  16. Noble gas atmospheric monitoring at reprocessing facilities

    International Nuclear Information System (INIS)

    Nakhleh, C.W.; Perry, R.T. Jr.; Poths, J.; Stanbro, W.D.; Wilson, W.B.; Fearey, B.L.

    1997-01-01

    The discovery in Iraq after the Gulf War of the existence of a large clandestine nuclear-weapon program has led to an across-the-board international effort, dubbed Programme 93+2, to improve the effectiveness and efficiency of International Atomic Energy Agency (IAEA) safeguards. One particularly significant potential change is the introduction of environmental monitoring (EM) techniques as an adjunct to traditional safeguards methods. Monitoring of stable noble gas (Kr, Xe) isotopic abundances at reprocessing plant stacks appears to be able to yield information on the burnup and type of the fuel being processed. To estimate the size of these signals, model calculations of the production of stable Kr, Xe nuclides in reactor fuel and the subsequent dilution of these nuclides in the plant stack are carried out for two case studies: reprocessing of PWR fuel with a burnup of 35 GWd/tU, and reprocessing of CAND fuel with a burnup of 1 GWd/tU. For each case, a maximum-likelihood analysis is used to determine the fuel burnup and type from the isotopic data

  17. Multipurpose simulator ''MR TRIOS'' for reprocessing plant

    International Nuclear Information System (INIS)

    Mitsui, Takeshi; Uehara, Shigeru; Takata, Hideo; Kamishima, Naoyuki

    1993-01-01

    MHI (Mitsubishi Heavy Industries) has developed MR TRIOS (Mitsubishi Reprocessing plant TRansient simulation code for Integrated process for Operation Support), the realtime dynamic simulator, for multipurpose use to support the Reprocessing Plant operation in various aspects. MR TRIOS integrates the Simulation Models of the unit process in a Reprocessing Plant, including Shearing, Dissolution, NOx absorption, Accountability and Adjustment and Co-decontamination process, where each Simulation Model has two kinds of models: Process and Control System. MR TRIOS can simulate the process behavior of the unit process in an integrated manner as well as independently. It is supported by MR CONTROL, the simulator control program developed by MHI. From MR TRIOS one can obtain real-time process values, such as temperature, pressure, density, flow rate, and concentration of nuclides, enabling the evaluation of the process dynamic characteristics under various operating conditions. MR TRIOS has proved to be an effective tool for the comprehensive study of the process and system dynamics, for operation technique improvements and for training

  18. Material control for a reprocessing plant

    International Nuclear Information System (INIS)

    Rundquist, D.; Bray, G.; Donelson, S.; Glancy, J.; Gozani, T.; Harris, L.; McNamera, R.; Pence, D.; Ringham, M.

    1976-01-01

    Adequate control of special nuclear material (SNM) implies a basic knowledge of the quantities of SNM processed through or contained within a fuels processing facility with sufficient accuracy that diversion of the SNM for deleterious purposes can be detected in a timely manner. This report to the Lawrence Livermore Laboratory (LLL) describes the primary process streams containing plutonium that are handled routinely within a spent fuel reprocessing plant and conversion facility. As an aid in implementing the objectives of the accountability system in a realistic situation, the Allied General Nuclear Services (AGNS) reprocessing plant now under construction near Barnwell, South Carolina, was chosen as the study model. The AGNS plant processes are discussed in detail emphasizing those portions of the process that contain significant quantities of plutonium. The unit processes within the separations plant, nitrate storage, plutonium product facility and the analytical laboratory are described with regard to the SNM control system currently planned for use in the facilities. A general discussion of laboratory techniques, nondestructive assay and process instrumentation for plutonium process and product material from a reprocessing plant is included. A comprehensive discussion is given of holdup measurements in plutonium recycle facilities. A brief preliminary overview is presented of alternative processing strategies for LWR fuel. An extensive review and summary of modeling efforts for liquid-liquid extraction cycles is included. A comprehensive bibliography of previous modeling efforts is covered

  19. Legal problems of nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Rossnagel, A.

    1987-01-01

    The contributions in this book are intended to exemplify the legal situation in connection with the reprocessing of spent nuclear fuel from the point of view of constitutional law, administrative law, and international law. Outline solutions are presented with regard to ensuring health, personal freedom, democratic rights and other rights, and are discussed. The author Rossnagel investigates whether the principle of essential matter can guarantee a parliamentary prerogative concerning this field of large-scale technology. The author Schmidt shows that there is no legal obligation of commitment to a reprocessing technology that would exclude research for or application of a less hazardous technology. The contribution by Baumann explains the problems presented by a technology not yet developed to maturity with regard to the outline approval of the technological concept, which is a prerequisite of any partial licence to be issued. The final contribution by Guendling investigates the duties under international law, as for instance transfrontier information, consultation, and legal protection, and how these duties can be better put into practice in order to comply the seriousness of the hazards involved in nuclear fuel reprocessing. (orig./HP) [de

  20. Aerosols released in accidents in reprocessing plants

    International Nuclear Information System (INIS)

    Ballinger, M.Y.; Owczarski, P.C.; Hashimoto, K.; Nishio, G.; Jordan, S.; Lindner, W.

    1987-01-01

    For analyzing the thermodynamic and radiological consequences of solvent fire accidents in reprocessing plants, intensive investigations on burning contaminated condensible liquids were performed at Kernforschungszentrum Karlsruhe (KfK), Pacific Northwest Laboratory (PNL), and Japan Atomic Energy Research Institute (JAERI). In small- and large-scale tests, KfK studied the behavior of kerosene, tributyl phosphate, HNO 3 mixture fires in open air and closed containments. The particle release from uranium-contaminated pool fires was investigated. Different filter devices were tested. For analyzing fires, PNL has developed the FIRIN computer code and has generated small-scale fire data in support of that code. The results of the experiments in which contaminated combustible liquids were burned demonstrate the use of the FIRIN code in simulating a solvent fire in a nuclear reprocessing plant. To demonstrate the safety evaluation of a postulated solvent fire in an extraction process of a reprocessing pant, JAERI conducted large-scale fire tests. Behavior of solvent fires in a cell and the integrity of high-efficiency particulate air (HEPA) filters due to smoke plugging were investigated. To evaluate confinement of radioactive materials released from the solvent fire, the ventilation systems with HEPA filters were tested under postulated fire conditions

  1. The regulations concerning the reprocessing business of spent fuels

    International Nuclear Information System (INIS)

    1981-01-01

    This rule is stipulated under the provisions of reprocessing business in the law concerning regulation of nuclear raw materials, nuclear fuel materials and nuclear reactors and to execute them. Basic terms are defined, such as exposure radiation dose, cumulative dose, control area, security area, surrounding monitoring area, worker, radioactive waste and facility for discharging into the sea. The application for the designation for reprocessing business under the law shall include the maximum reprocessing capacities per day and per year of each kind of spent fuel, to be reprocessed and the location, structure and equipment of reprocessing facilities as specified in the regulation. Records shall be made in each works or enterprise on the inspection, operation and maintenance of reprocessing facilities, radiation control, accidents and weather, and kept for particular periods respectively. Reprocessing enterprisers shall set up control area, security area and surrounding monitoring area to restrict entrance, etc. Specified measures shall be taken by these enterprisers concerning the exposure radiation doses of workers. Reprocessing facilities shall be inspected and examined more than once a day. The regular self-inspection and operation of reprocessing facilities, the transport and storage of nuclear fuel materials, the disposal of radioactive wastes in works or enterprises where reprocessing facilities are located, and security rules are defined in detail, respectively. (Okada, K.)

  2. The case for reprocessing: the operational experience of a modern reprocessing industry

    International Nuclear Information System (INIS)

    Giraud, J.P.; Kelly, W.

    1993-01-01

    Reprocessing is a high-tech industry that works. An impressive effort of R and D, industrial deployment and operational experience has been accumulated by COGEMA and BNFL, leading these companies to offer a commercial service which is the only proper management of spent fuel and waste that is both technically demonstrated and qualified by the safety authorities of European and overseas countries. Reprocessing, as every technology-based industry will continue to progress in the future. Recycling the fissile materials reclaimed from spent fuel: uranium and plutonium, is the complementary and indispensable last link to effectively close the fuel cycle and control in particular the production of plutonium and other long-lived actinides. This paper will describe the state of development attained in France and Great Britain and will underline the main advantages of the reprocessing/recycling strategy

  3. A work procedure of utilising PCMs as thermal storage systems based on air-TES systems

    International Nuclear Information System (INIS)

    Iten, M.; Liu, S.

    2014-01-01

    Highlights: • A procedure to design effective thermal energy storage (TES) system. • A guidance for the selection of the working material (PCM) and the heat exchanger development. • Suggestions for heat transfer enhancement techniques for the air-TES system. • Mathematical, computational and experimental methods optimising the air-TES system. - Abstract: The paper seeks to offer a procedure to design an effective short term thermal energy storage (TES) system using phase change materials. The methodology focus on two main aspects: the selection of the working material and the heat exchanger development. The selection of the appropriate PCMs is one of the main keys for any TES therefore their classifications, properties, advantages and disadvantages need to be investigated. Due to the intensive researches using this kind of materials in the recent years, there are a range of commercial PCMs available and supplied by different companies. However, all types of PCM present their specific problems and therefore requirements are defined in order to select the most suitable PCMs. The other main key when designing TES is related to the heat exchanger formed by the PCM and the cold/hot heat sources. For this step, the choice of the appropriate container to encapsulate the PCM and the heat transfer enhancement techniques are analysed. Distinct methodologies such as experimental and numerical study methods and modelling software tools are presented to analyse the thermal energy performance of the system and achieve the optimal design of the TES system

  4. Development of Tokai reprocessing plant maintenance support system (TORMASS) in the Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Shimizu, Kazuyuki; Tomita, Tsuneo; Sakai, Katsumi

    2008-01-01

    The maintenance work of many equipments such as mechanical, electrical and instrumentations installed in Tokai reprocessing plant has been performed more then 10,000 times per year and about 90% of maintenances were preventive work. For the maintenance management, optimization of maintenance information is required. Therefore, Tokai Reprocessing Plant Maintenance Support System (TORMASS) was developed from 1985 to 1992 as the aim of construction for suitable maintenance management system. About 24,000 equipments of specifications and about 261,000 maintenance detail were registered in this system. TORMASS has been used for the repair, inspection and replacement of equipment since 1992. (author)

  5. Development of X-ray microcalorimeter using Ir/Au-TES

    International Nuclear Information System (INIS)

    Kunieda, Yuichi; Ohno, Masashi; Nakazawa, Masaharu; Takahashi, Hiroyuki; Fukuda, Daiji; Ohkubo, Masataka; Hirayama, Huminori; Ataka, Manabu

    2004-01-01

    We are developing x-ray mirocalorimeters using transition edge sensors of iridium/gold (Ir/Au-TES) for high resolution x-ray spectroscopy. TES microcalorimeters can achieve faster response than conventional microcalorimeters by keeping the operating point of TES in the transition region through the use of strong negative electrothermal feedback (ETF). At present, the energy resolution of 9.4 eV (FWHM) was achieved for a 5899 eV Mn K al line. At a synchrotron X-ray radiation facility, we demonstrated microscopic signal response profile of the device and high-resolution X-ray fluorescence spectroscopy using a small amount of sample. (author)

  6. Handbook on process and chemistry on nuclear fuel reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Atsuyuki [Tokyo Univ., Tokyo (Japan); Asakura, Toshihide; Adachi, Takeo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; and others

    2001-12-01

    'Wet-type' nuclear fuel reprocessing technology, based on PUREX technology, has wide applicability as the principal reprocessing technology of the first generation, and relating technologies, waste management for example, are highly developed, too. It is quite important to establish a database summarizing fundamental information about the process and the chemistry of 'wet-type' reprocessing, because it contributes to establish and develop fuel reprocessing process and nuclear fuel cycle treating high burn-up UO{sub 2} fuel and spent MOX fuel, and to utilize 'wet-type' reprocessing technology much widely. This handbook summarizes the fundamental data on process and chemistry, which was collected and examined by 'Editing Committee of Handbook on Process and Chemistry of Nuclear Fuel Reprocessing', from FY 1993 until FY 2000. (author)

  7. Handbook on process and chemistry on nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Suzuki, Atsuyuki; Asakura, Toshihide; Adachi, Takeo

    2001-12-01

    'Wet-type' nuclear fuel reprocessing technology, based on PUREX technology, has wide applicability as the principal reprocessing technology of the first generation, and relating technologies, waste management for example, are highly developed, too. It is quite important to establish a database summarizing fundamental information about the process and the chemistry of 'wet-type' reprocessing, because it contributes to establish and develop fuel reprocessing process and nuclear fuel cycle treating high burn-up UO 2 fuel and spent MOX fuel, and to utilize 'wet-type' reprocessing technology much widely. This handbook summarizes the fundamental data on process and chemistry, which was collected and examined by 'Editing Committee of Handbook on Process and Chemistry of Nuclear Fuel Reprocessing', from FY 1993 until FY 2000. (author)

  8. Handbook on process and chemistry on nuclear fuel reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Atsuyuki (ed.) [Tokyo Univ., Tokyo (Japan); Asakura, Toshihide; Adachi, Takeo (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

    2001-12-01

    'Wet-type' nuclear fuel reprocessing technology, based on PUREX technology, has wide applicability as the principal reprocessing technology of the first generation, and relating technologies, waste management for example, are highly developed, too. It is quite important to establish a database summarizing fundamental information about the process and the chemistry of 'wet-type' reprocessing, because it contributes to establish and develop fuel reprocessing process and nuclear fuel cycle treating high burn-up UO{sub 2} fuel and spent MOX fuel, and to utilize 'wet-type' reprocessing technology much widely. This handbook summarizes the fundamental data on process and chemistry, which was collected and examined by 'Editing Committee of Handbook on Process and Chemistry of Nuclear Fuel Reprocessing', from FY 1993 until FY 2000. (author)

  9. Sulfates on Mars: TES Observations and Thermal Inertia Data

    Science.gov (United States)

    Cooper, C. D.; Mustard, J. F.

    2001-05-01

    The high resolution thermal emission spectra returned by the TES spectrometer on the MGS spacecraft have allowed the mapping of a variety of minerals and rock types by different sets of researchers. Recently, we have used a linear deconvolution approach to compare sulfate-palagonite soil mixtures created in the laboratory with Martian surface spectra. This approach showed that a number of areas on Mars have spectral properties that match those of sulfate-cemented soils (but neither loose powder mixtures of sulfates and soils nor sand-sized grains of disaggregated crusted soils). These features do not appear to be caused by atmospheric or instrumental effects and are thus believed to be related to surface composition and texture. The distribution and physical state of sulfate are important pieces of information for interpreting surface processes on Mars. A number of different mechanisms could have deposited sulfate in surface layers. Some of these include evaporation of standing bodies of water, aerosol deposition of volcanic gases, hydrothermal alteration from groundwater, and in situ interaction between the atmosphere and soil. The areas on Mars with cemented sulfate signatures are spread across a wide range of elevations and are generally large in spatial scale. Some of the areas are associated with volcanic regions, but many are in dark red plains that have previously been interpreted as duricrust deposits. Our current work compares the distribution of sulfate-cemented soils as mapped by the spectral deconvolution approach with thermal inertia maps produced from both Viking and MGS-TES. Duricrust regions, interpreted from intermediate thermal inertia values, are large regions thought to be sulfate-cemented soils similar to coherent, sulfate-rich materials seen at the Viking lander sites. Our observations of apparent regions of cemented sulfate are also large in spatial extent. This scale information is important for evaluating formation mechanisms for the

  10. Are BiTEs the "missing link" in cancer therapy?

    Science.gov (United States)

    Suryadevara, Carter M; Gedeon, Patrick C; Sanchez-Perez, Luis; Verla, Terence; Alvarez-Breckenridge, Christopher; Choi, Bryan D; Fecci, Peter E; Sampson, John H

    2015-06-01

    Conventional treatment for cancer routinely includes surgical resection and some combination of chemotherapy and radiation. These approaches are frequently accompanied by unintended and highly toxic collateral damage to healthy tissues, which are offset by only marginal prognostic improvements in patients with advanced cancers. This unfortunate balance has driven the development of novel therapies that aim to target tumors both safely and efficiently. Over the past decade, mounting evidence has supported the therapeutic utility of T-cell-centered cancer immunotherapy, which, in its various iterations, has been shown capable of eliciting highly precise and robust antitumor responses both in animal models and human trials. The identification of tumor-specific targets has further fueled a growing interest in T-cell therapies given their potential to circumvent the non-specific nature of traditional treatments. Of the several strategies geared toward achieving T-cell recognition of tumor, bispecific antibodies (bsAbs) represent a novel class of biologics that have garnered enthusiasm in recent years due to their versatility, specificity, safety, cost, and ease of production. Bispecific T-cell Engagers (BiTEs) are a subclass of bsAbs that are specific for CD3 on one arm and a tumor antigen on the second. As such, BiTEs function by recruiting and activating polyclonal populations of T-cells at tumor sites, and do so without the need for co-stimulation or conventional MHC recognition. Blinatumomab, a well-characterized BiTE, has emerged as a promising recombinant bscCD19×CD3 construct that has demonstrated remarkable antitumor activity in patients with B-cell malignancies. This clinical success has resulted in the rapid extension of BiTE technology against a greater repertoire of tumor antigens and the recent US Food and Drug Administration's (FDA) accelerated approval of blinatumomab for the treatment of a rare form of acute lymphoblastic leukemia (ALL). In this review

  11. Characteristics of radioactive waste streams generated in HTGR fuel reprocessing

    International Nuclear Information System (INIS)

    Lin, K.H.

    1976-01-01

    Results are presented of a study concerned with identification and characterization of radioactive waste streams from an HTGR fuel reprocessing plant. Approximate quantities of individual waste streams as well as pertinent characteristics of selected streams have been estimated. Most of the waste streams are unique to HTGR fuel reprocessing. However, waste streams from the solvent extraction system and from the plant facilities do not differ greatly from the corresponding LWR fuel reprocessing wastes

  12. Structural damage and chemical contaminants on reprocessed arthroscopic shaver blades.

    Science.gov (United States)

    Kobayashi, Masahiko; Nakagawa, Yasuaki; Okamoto, Yukihiro; Nakamura, Shinichiro; Nakamura, Takashi

    2009-02-01

    In response to socioeconomic pressure to cut budgets in medicine, single-use surgical instruments are often reprocessed despite potential biological hazard. To evaluate the quality and contaminants of reprocessed shaver blades. Reprocessed shaver blades have mechanical damage and chemical contamination. Controlled laboratory study. Seven blades and 3 abraders were reprocessed 1 time or 3 times and then were assessed. In the first part of the study, structural damage on the blades after 3 reprocessings was compared to that after 1 reprocessing using optical microscopy. In the second part, surface damage was observed using optical microscopy and scanning electron microscopy; elemental and chemical analyses of contaminants found by the microscopy were performed using scanning electron microscopy/energy dispersive x-ray spectroscopy, scanning Auger microscopy, and Fourier transform infrared spectroscopy. Optical microscopic examination revealed abrasion on the surface of the inner blade and cracks on the inner tube after 1 reprocessing. These changes were more evident after 3 reprocessings. Scanning electron microscopy/energy dispersive x-ray spectroscopy of the inner cutter of the blade reprocessed once showed contaminants containing calcium, carbon, oxygen, and silicon, and Fourier transform infrared spectroscopy demonstrated biological protein consisting mainly of collagen, some type of salts, and polycarbonate used in plastic molding. Scanning electron microscopy/energy dispersive x-ray spectroscopy of the inner cutter of the reprocessed abrader revealed contaminants containing carbon, calcium, phosphorous, and oxygen, and Fourier transform infrared spectroscopy showed H2O, hydroxyapatite, and hydroxyl proteins. Scanning Auger microscopy showed that the tin-nickel plating on the moving blade and abrader was missing in some locations. This is the first study to evaluate both mechanical damage and chemical contaminants containing collagen, hydroxyapatite, and salts

  13. Evaluation on maintenance technology developed in Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Yamamura, Osamu

    2008-01-01

    Tokai reprocessing plant (TRP) has been processing 1,140 tons of spent fuels, including 29tons of Fugen MOX fuels, since the beginning of its active operation in Sept.1977. For 30 years operation of TRP, many technological problems have been overcome to obtain the stable and reliable operation. This knowledge of maintenance technology could contribute to the safety and stable operation of Rokkasho reprocessing plant (RRP), as well as to the design and construction of the next reprocessing plant. (author)

  14. Safeguards for reprocessing and enrichment plants

    International Nuclear Information System (INIS)

    1977-01-01

    Agency safeguards are entering a new phase with the coming under active safeguards for the first time of reprocessing plants in several regions of the world. This is taking place at a time when not only the safeguards aspect itself is coming under international scrutiny, but also at a time when the necessity of reprocessing plants is being called into question. Attracting less attention at the moment, but potentially of equal significance, are the enrichment plants that soon will be coming under Agency safeguards. It is not unreasonable in view of the present controversies to ask what is the significance of these reprocessing and enrichment plants, what are the problems concerning safeguards that appear to have given rise to the controversies, and how these problems are to be solved. The question of significance is an easy one to answer. The output of these plants is material which some people consider can be used directly for military purposes, whereas the output from other plants, for instance, reactors, would require long and extensive processing before it could be used for military purposes. Like most short answers, this one is an over-simplification which requires some elaboration to make it strictly accurate. For example, the material output of a power reactor is in the form of irradiate assemblies containing plutonium which is potentially of military use if the irradiation had been within a certain range. However, to utilize this plutonium under clandestine conditions, the highly radioactive material would have to be secretly transported to a reprocessing plant and there would have to be simultaneous falsification of the reactor material accounts and the plant records. Such falsification would be difficult to conceal. The total time required to obtain usable plutonium would be many months. Diversion of material from a uranium fabrication plant making fuel for power reactors would be easier physically but strategically it would be of little value. The

  15. The regulations concerning the reprocessing business of spent fuels

    International Nuclear Information System (INIS)

    1980-01-01

    The office ordinance is established under the provisions related to reprocessing businesses of the law concerning regulation of nuclear raw materials, nuclear fuel materials and reactors, to enforce the provisions. The basic terms are defined, such as exposure radiation dose; accumulated dose; controlled area; maintenance area; surrounding watch area; employee; radioactive waste; the facilities for discharge to sea. An application for the designation of reprocessing businesses shall be filed, listing the following matters: the maximum daily and yearly reprocessing capacities for each kind of spent fuel; the location and general structure of reprocessing facilities; the structures of buildings; the structure and equipments of main reprocessing facilities, the storage facilities for products and the disposal facilities for radioactive wastes; the equipments of measuring and control system facilities and radiation control facilities, etc. Records shall be made on the inspection of reprocessing facilities, radiation control, operation, maintenance, the accidents of reprocessing facilities and weather, and kept for the period from one to ten years, respectively. Any person engaging in reprocessing businesses shall set up control, maintenance and surrounding watch areas, and take specified measures to restrict the entrance of persons. The measures to be taken against exposure radiation dose, the inspection, regular independent examination and operation of reprocessing facilities and other related matters are stipulated in detail. (Okada, K.)

  16. Predicting the behaviour or neptunium during nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Drake, V.A.

    1988-01-01

    Behaviour of Np and its distribution over reprocessing flowsheet is studied due to the necessity of improvement of reprocessing methods of wastes formed during purex-process. Valency states of Np in solutions of reprocessing cycles, Np distribution in organic and acid phases, Np(5) oxidation by nitric acid at the stage of extraction, effect of U and Pu presence on Np behaviour, are considered. Calculation and experimental data are compared; the possibility of Np behaviour forecasting in the process of nuclear fuel reprocessing, provided initial data vay, is shown. 7 refs.; 4 figs.; 1 tab

  17. Fuel reprocessing at a loss to prove its justification

    International Nuclear Information System (INIS)

    Traube, K.

    1986-01-01

    Commercial utilization of nuclear energy is possible with or without fuel reprocessing of spent fuel elements. Demands on terminal storage are about equal in both cases. There is no reason - excluding the military one - to decide in favour of fuel reprocessing instead of direct terminal storage, for neither does fuel reprocessing offer advantages in regard of the safety of nuclear waste disposal, nor is it necessary to produce plutonium for the breeder reactor. Fuel reprocessing is analyzed considering those changed aspects with a view to scarcer uranium resources, juridical motives, and what is termed the development deficit. (DG) [de

  18. The regulations concerning the reprocessing business of spent fuels

    International Nuclear Information System (INIS)

    1987-01-01

    Regulations specified here cover application for such matters as designation of reprocessing undertaking, permission of construction of reprocessing facilities, permission and approval of alteration (of plan for reprocessing facilities), etc. The regulations also cover application for prior inspection, execution of prior inspection, technical standards concerning performance of reprocessing facilities, certificate of prior inspection, reprocessing facilities subject to welding inspection, application for welding inspection, execution of welding inspection, facilities not subject to welding inspection, approval of welding method, welding inspection for imported equipment, certificate of welding inspection, reprocessing facilities subject to regular inspection, application for regular inspection, technical standards for regular inspection, operation plan, application for approval of joint management, record keeping, restriction on access to areas under management, measures concerning exposure to radioactive rays, patrol and checking in reprocessing facilities, operation of reprocessing facilities, self-imposed regular inspection of reprocessing facilities, transportation within plant or operation premises, storage, waste disposal within plant or operation premises, safety rules, notice of disassembly, measures for emergency, notice of abolition of business, notice of disorganization, measures concerning cancellation of designation, submission of report, etc. (Nogami, K.)

  19. Legal questions concerning the termination of spent fuel element reprocessing

    International Nuclear Information System (INIS)

    John, Michele

    2005-01-01

    The thesis on legal aspects of the terminated spent fuel reprocessing in Germany is based on the legislation, jurisdiction and literature until January 2004. The five chapters cover the following topics: description of the problem; reprocessing of spent fuel elements in foreign countries - practical and legal aspects; operators' responsibilities according to the atomic law with respect to the reprocessing of Geman spent fuel elements in foreign countries; compatibility of the prohibition of Geman spent fuel element reprocessing in foreign countries with international law, European law and German constitutional law; results of the evaluation

  20. Economic evaluation of reprocessing - Indicative German position

    International Nuclear Information System (INIS)

    1979-05-01

    This paper, which also appears as an Appendix to the final Working Group 4 report, forms part of the overall economic assessment of reprocessing. The indicative national position and illustrative ''phase diagram'' for the Federal Republic of Germany is presented. Advantages to be gained from the recycling of plutonium in thermal reactors are identified and it is concluded that many of these are not explicitly taken into account in the ''phase diagram''. Under the conditions pertaining in the Federal Republic of Germany thermal recycle will be economic under present day uranium prices. On the other hand the fast breeder reactor might become commercially economic around the year 2000

  1. Reprocessing in the thorium fuel cycle

    International Nuclear Information System (INIS)

    Merz, E.

    1984-01-01

    An overview of the authors personal view is presented on open questions in regard to still required research and development work for the thorium fuel cycle before its application in a technical-industrial scale may be tackled. For a better understanding, all stations of the back-end of the thorium fuel cycle are briefly illustrated and their special features discussed. They include storage and transportation measures, all steps of reprocessing, as well as the entire radioactive waste treatment. Knowledge gaps are, as far as they are obvious, identified and proposals put forward for additional worthwile investigations. (orig.) [de

  2. Radiological prevention in a reprocessing plant

    International Nuclear Information System (INIS)

    Trenta, G.

    1983-01-01

    Prevention has received a peculiar conceptual formulation in working activities with radiation risk. In order to point out the operative aspects of this formulation the authors relates here the considerations, the criteria an the precautionary measures which have guided the choice or that have been actuated to reduce the risk for the workers of the EUREX reprocessing plant. The general aspect of this formulationa has a philosophical and doctrinarian course, peculiar in the probabilistic safety approach and in radioprotection methodology. The authors quotes here some concepts and some specific application of both but he shows above all the medical aspects of the radioprotection

  3. Economic evaluation of reprocessing. Indicative UK position

    International Nuclear Information System (INIS)

    1979-05-01

    This paper, which also appears as an Appendix to the final Working Group 4 report, forms part of the overall economic assessment of reprocessing. The indicative national position and illustrative ''phase diagram'' for the United Kingdom is presented. Under conditions pertaining in the United Kingdom the diagram suggests that: if uranium prices rise rapidly the fast reactor would become economic in the decade 1990-2000, if uranium prices rise more slowly, the fast reactor would become economic in the decade 2000-2010

  4. Application of probabilistic risk assessment to reprocessing

    International Nuclear Information System (INIS)

    Perkins, W.C.

    1984-01-01

    The Savannah River Laboratory uses probabilistic methods of risk assessment in safety analyses of reprocessing facilities at the Savannah River Plant. This method uses both the probability of an accident and its consequence to calculate the risks from radiological, chemical, and industrial hazards. The three principal steps in such an assesment are identification of accidents, calculation of frequencies, and consequence quantification. The tools used at SRL include several databanks, logic tree methods, and computer-assisted methods for calculating both frequencies and consequences. 5 figures

  5. Process information systems in nuclear reprocessing

    International Nuclear Information System (INIS)

    Jaeschke, A.; Keller, H.; Orth, H.

    1987-01-01

    On a production management level, a process information system in a nuclear reprocessing plant (NRP) has to fulfill conventional operating functions and functions for nuclear material surveillance (safeguards). Based on today's state of the art of on-line process control technology, the progress in hardware and software technology allows to introduce more process-specific intelligence into process information systems. Exemplified by an expert-system-aided laboratory management system as component of a NRP process information system, the paper demonstrates that these technologies can be applied already. (DG) [de

  6. Nuclear fuel cycle: reprocessing. A bibliography

    International Nuclear Information System (INIS)

    Smith, L.B.

    1982-12-01

    This bibliography contains information on the reprocessing portion of the nuclear fuel cycle included in the Department of Energy's Energy Data Base from January 1981 through November 1982. The abstracts are grouped by subject category. Entries in the subject index also facilitate access by subject. Within each category the arrangement is by report number for reports, followed by nonreports in reverse chronological order. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes, each preceded by a brief description, are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number

  7. The fuel reprocessing plant at Wackersdorf

    International Nuclear Information System (INIS)

    Held, M.

    1986-01-01

    For a more systematic discussion about the fuel reprocessing plant at Wackersdorf, the colloquium tried to cover the most important questions put forward in the controversies: economic efficiency and energy-political needs; safety and ecological repercussions; inner safety and consequences for basic rights and the regional economic structure; majority decisions and participation of the population of the region. Elements of evaluation are the conservation of resources, health, economic efficiency, and citizens' rights of liberty. The related basic ethical questions are considered. The 18 contributions are individually recorded in the data base. (DG) [de

  8. Reprocessing of irradiated fuel: pros and cons

    International Nuclear Information System (INIS)

    Lebedev, O.G.; Novikov, V.M.

    1991-01-01

    The acceptable-safety nuclear reactors (APWR, LMFBR, MSBR, MSCR) can be provided by the enrichment industry and by plutonium reserves. But steady accumulation of spent fuel will inevitably make to return to the problems of fuel recycle. PUREX-processing increases a danger of radionuclides spreading due to the presence of large buffer tanks. Using of compact fluoride - volatility process will sharply reduce a nuclide leakage likewise permit to reprocess a fuel with a burnup as high as possible. Success of a powerful robots development give an opportunity to design a fluoride-volatility plant twice cheaper than PUREX. (author)

  9. Nuclear fuel reprocessing: A time for decision

    International Nuclear Information System (INIS)

    O'Donnell, A.J.; Sandbery, R.O.

    1983-01-01

    Availability of adequate supplies of energy at an affordable cost is essential to continued growth of the world's economics. The tie between economic growth and electricity usage is particularly strong and the pervasive wordwide trend toward increasing electrification shows no signs of abating. Very few viable alternatives are available for supplying the projected increase in baseload electric generating capacity in the next several decades, and most industrialized nations have chosen nuclear power to play a major role. Sustained growth of nuclear power can only be achieved, however, by reprocessing spent fuel to recover and utilize the residual uranium and plutonium energy values

  10. Study of assessing aqueous reprocessing process for the pipeless reprocessing plant

    International Nuclear Information System (INIS)

    Hanzawa, Masatoshi; Morioka, Nobuo; Fumoto, Hiromichi; Nishimura, Kenji; Chikazawa, Takahiro

    2000-02-01

    The purpose of this study is to investigate the possibility of new reprocessing process for the purpose of introducing pipeless plant concept, where aqueous separation methods other than solvent extraction method are adopted in order to develop more economical FBR fuel (MOX fuel) reprocessing process. At it's first stage, literature survey on precipitation method, crystallization method and ion-exchange method was performed. Based on the results, following processes were candidated for pipeless reprocessing plant. (1) The process adopting crystallization method and peroxide precipitation method (2) The process adopting oxalate precipitation method (3) The process under mild aqueous conditions (crystallization method and precipitation method) (4) The process adopting crystallization method and ion-exchange method (5) The process adopting crystallization method and solvent extraction method. The processes (1)-(5) were compared with each others in terms of competitiveness to the conventional reference process, and merits and demerits were evaluated from the viewpoint of applicability to pipeless reprocessing plant, safety, economy, Efficiencies in consumption of Resources, non-proliferation, and, Operation and Maintenance. As a result, (1) The process adopting crystallization method and peroxide precipitation method was selected as the most reasonable process to pipeless plant. Preliminary criticality safety analyses, main process chemical flowsheet, main equipment list and layout of mobile vessels and stations were reported for the (1) process. (author)

  11. TES/Aura L3 H2O Monthly Gridded V004

    Data.gov (United States)

    National Aeronautics and Space Administration — The TES Aura L3 H2O data consist of daily atmospheric temperature and VMR for the atmospheric species. Data are provided at 2 degree latitude X 4 degree longitude...

  12. The 160 TES bolometer read-out using FDM for SAFARI

    Science.gov (United States)

    Hijmering, R. A.; den Hartog, R. H.; van der Linden, A. J.; Ridder, M.; Bruijn, M. P.; van der Kuur, J.; van Leeuwen, B. J.; van Winden, P.; Jackson, B.

    2014-07-01

    For the read out of the Transition Edge Sensors (TES) bolometer arrays of the SAFARI instrument on the Japanese background-limited far-IR SPICA mission SRON is developing a Frequency Domain Multiplexing (FDM) read-out system. The next step after the successful demonstration of the read out of 38 TES bolometers using FDM was to demonstrate the FDM readout of the required 160 TES bolometers. Of the 160 LC filter and TES bolometer chains 151 have been connected and after cooldown 148 of the resonances could be identified. Although initial operation and locking of the pixels went smoothly the experiment revealed several complications. In this paper we describe the 160 pixel FDM set-up, show the results and discuss the issues faced during operation of the 160 pixel FDM experiment.

  13. User's Manual for the Biodiversity and Threatened and Endangered Species Experts (BioTES) Tool

    National Research Council Canada - National Science Library

    Sebesta, Georgia

    1996-01-01

    The Biodiversity and Threatened and Endangered Species Experts (BioTES), version 1.0 helps installation and government personnel locate points of contact for experts in the areas of biodiversity and threatened and endangered species...

  14. TES/Aura L2 Instantaneous Radiative Kernel Nadir V007

    Data.gov (United States)

    National Aeronautics and Space Administration — Using TES radiances, Jacobians and ozone profiles with hemispherical integration, it is possible to compute the TOA (top-of-atmosphere) flux from the infrared ozone...

  15. TES/Aura L2 Instantaneous Radiative Kernel Nadir Special Observation V007

    Data.gov (United States)

    National Aeronautics and Space Administration — Using TES radiances, Jacobians and ozone profiles with hemispherical integration, it is possible to compute the TOA (top-of-atmosphere) flux from the infrared ozone...

  16. An Optimisation Study on Integrating and Incentivising Thermal Energy Storage (TES in a Dwelling Energy System

    Directory of Open Access Journals (Sweden)

    Gbemi Oluleye

    2018-04-01

    Full Text Available In spite of the benefits from thermal energy storage (TES integration in dwellings, the penetration rate in Europe is 5%. Effective fiscal policies are necessary to accelerate deployment. However, there is currently no direct support for TES in buildings compared to support for electricity storage. This could be due to lack of evidence to support incentivisation. In this study, a novel systematic framework is developed to provide a case in support of TES incentivisation. The model determines the costs, CO2 emissions, dispatch strategy and sizes of technologies, and TES for a domestic user under policy neutral and policy intensive scenarios. The model is applied to different building types in the UK. The model is applied to a case study for a detached dwelling in the UK (floor area of 122 m2, where heat demand is satisfied by a boiler and electricity imported from the grid. Results show that under a policy neutral scenario, integrating a micro-Combined Heat and Power (CHP reduces the primary energy demand by 11%, CO2 emissions by 21%, but with a 16 year payback. Additional benefits from TES integration can pay for the investment within the first 9 years, reducing to 3.5–6 years when the CO2 levy is accounted for. Under a policy intensive scenario (for example considering the Feed in Tariff (FIT, primary energy demand and CO2 emissions reduce by 17 and 33% respectively with a 5 year payback. In this case, the additional benefits for TES integration can pay for the investment in TES within the first 2 years. The framework developed is a useful tool is determining the role TES in decarbonising domestic energy systems.

  17. Collection and dissemination of TES system information for the paper and pulp industry

    Science.gov (United States)

    Dietrich, M. W.; Edde, H.

    1980-01-01

    A survey of U.S. and international paper and pulp mills using thermal energy storage (TES) systems as a part of their production processes was conducted to obtain sufficient operating data to conduct a benefits analysis encompassing: (1) an energy conservation assessment, (2) an economic benefits analysis, and (3) an environmental impact assessment. An information dissemination plan was then proposed to effectively present the benefits of TES to the U.S. paper and pulp industry.

  18. Safety problems in fuel reprocessing plants

    International Nuclear Information System (INIS)

    Amaury, P.; Jouannaud, C.; Niezborala, F.

    1979-01-01

    The document first situates the reprocessing in the fuel cycle as a whole. It shows that a large reprocessing plant serves a significant number of reactors (50 for a plant of 1500 tonnes per annum). It then assesses the potential risks with respect to the environment as well as with respect to the operating personnel. The amounts of radioactive matter handled are very significant and their easily dispersible physical form represents very important risks. But the low potential energy likely to bring about this dispersion and the very severe and plentiful confinement arrangements are such that the radioactive risks are very small, both with respect to the environment and the operating personnel. The problems of the interventions for maintenance or repairs are mentioned. The intervention techniques in a radioactive environment are perfected, but they represent the main causes of operating personnel irradiation. The design principle applied in the new plants take this fact into account, involving a very significant effort to improve the reliability of the equipment and ensuring the provision of devices enabling the failing components to be replaced without causing irradiation of the personnel [fr

  19. Simplified probabilistic risk assessment in fuel reprocessing

    International Nuclear Information System (INIS)

    Solbrig, C.W.

    1993-01-01

    An evaluation was made to determine if a backup mass tracking computer would significantly reduce the probability of criticality in the fuel reprocessing of the Integral Fast Reactor. Often tradeoff studies, such as this, must be made that would greatly benefit from a Probably Risk Assessment (PRA). The major benefits of a complete PRA can often be accrued with a Simplified Probabilistic Risk Assessment (SPRA). An SPRA was performed by selecting a representative fuel reprocessing operation (moving a piece of fuel) for analysis. It showed that the benefit of adding parallel computers was small compared to the benefit which could be obtained by adding parallelism to two computer input steps and two of the weighing operations. The probability of an incorrect material moves with the basic process is estimated to be 4 out of 100 moves. The actual values of the probability numbers are considered accurate to within an order of magnitude. The most useful result of developing the fault trees accrue from the ability to determine where significant improvements in the process can be made. By including the above mentioned parallelism, the error move rate can be reduced to 1 out of 1000

  20. Deactivating a major nuclear fuels reprocessing facility

    International Nuclear Information System (INIS)

    LeBaron, G.J.

    1997-01-01

    This paper describes three key processes used in deactivating the Plutonium Uranium Extraction (PUREX) Facility, a large, complex nuclear reprocessing facility, 15 months ahead of schedule and $77 million under budget. The organization was reengineered to refine its business processes and more effectively organize around the deactivation work scope. Multi-disciplined work teams were formed to be self-sufficient and empowered to make decisions and perform work. A number of benefits were realized by reengineering. A comprehensive process to develop end points which clearly identified specific results and the post-project facility configuration was developed so all areas of a facility were addressed. Clear and specific end points allowed teams to focus on completing deactivation activities and helped ensure there were no unfulfilled end-of-project expectations. The RCRA regulations require closure of permitted facilities within 180 days after cessation of operations which may essentially necessitate decommissioning. A more cost effective approach was adopted which significantly reduced risk to human health and the environment by taking the facility to a passive, safe, inexpensive-to-maintain surveillance and maintenance condition (deactivation) prior to disposition. PUREX thus became the first large reprocessing facility with active TSD [treatment, storage, and disposal] units to be deactivated under the RCRA regulations

  1. Nuclear fuel re-processing plant

    International Nuclear Information System (INIS)

    Sasaki, Yuko; Honda, Takashi; Shoji, Saburo; Kobayashi, Shiro; Furuya, Yasumasa

    1989-01-01

    In a nuclear fuel re-processing plant, high Si series stainless steels not always have sufficient corrosion resistance in a solution containing only nitric acid at medium or high concentration. Further, a method of blowing NOx gases may possibly promote the corrosion of equipment constituent materials remarkably. In view of the above, the corrosion promoting effect of nuclear fission products is suppressed without depositing corrosive metal ions as metals in the nitric acid solution. That is, a reducing atmosphere is formed by generating NOx by electrolytic reduction thereby preventing increase in the surface potential of stainless steels. Further, an anode is disposed in the nitric acid solution containing oxidative metal ions to establish an electrical conduction and separate them by way of partition membranes and a constant potential or constant current is applied while maintaining an ionic state so as not to deposit metals. Thus, equipments of re-processing facility can be protected from corrosion with no particular treatment for wastes as radioactive materials. (K.M.)

  2. To reprocess to recycle. The nuclear safety

    International Nuclear Information System (INIS)

    1999-01-01

    After a summary of fundamental notions of radioactivity and nuclear safety, the first part of this work is devoted to the organisation in France to provide the nuclear facilities safety. The second part related to the fuel cycle describes the big steps of this cycle and particularly the stakes and objectives of the reprocessing -recycling as well as the valorization of reusable matters such plutonium and uranium. The risks identification, means to control them, in conception, realisation and operation are described in the third, fourth and fifth parts. In this last part the managements of accidental situations is treated. The sixth and last part is devoted to the environment protection, treats the control of waste release of reprocessing -recycling facilities, of these waste management that is to say every disposition made by Cogema to limit the impact of its installations on environment. In this last part are also described the safety of nuclear and radioactive matters transport, and the definitive breakdown of installations. (N.C.)

  3. APLIKASI TES KEPRIBADIAN UNTUK PENEMPATAN KARYAWAN MENGGUNAKAN METODE MBTI (MYERS-BRIGGS TYPEINDICATORBERBASISWEB (STUDI KASUS: PT. WINATA PUTRA MANDIRI

    Directory of Open Access Journals (Sweden)

    Fiftin Noviyanto

    2012-04-01

    Full Text Available Penempatan karyawan merupakan salah satu fungsi terpenting dalam Manajemen Sumber Daya Manusia. Penempatan karyawan yang tepat sesuai dengan harapan, bakat dan kepribadian karyawan, akan mampu meningkatkan motivasi, produltifitas dan kepuasan kerja. Salah satu tes penunjang penempatan karyawan adalah tes kepribadian. Tes kepribadian yang dilakukan menggunakan metode Myers-Briggs Type Indicator (MBTI. Pelaksanaan tes yang dilakukan manual dan terpisah antara kantor pusat dan kantor cabang membuat PT. Winata Putra Mandiri memerlukan waktu yang lama untuk melihat keseluruhan hasil tes seluruh karyawan. Tujuan penelitian ini membuat aplikasi tes kepribadian yang dapat diakses melalui internet adalah agar karyawan dapat melihat hasil tes kepribadian secara langsung dan cepat serta dapat mengintegrasikan hasil tes dari kantor pusat dan kantor cabang. Pengumpulan data dilakukan dengan berbagai metode antara lain : Studi kepustakaan, metode interview dan browsing. Model proses yang digunakan adalah waterfall yang terdiri dari analisa kebutuhan sistem, perancangan, implementasi dan pengujian. Pada perancangan sistem dimulai dari perancangan proses, perancangan tabel, perancangan menu dan perancangan interface. Pada tahap implementasi menggunakan PHPMyAdmin untuk membangun basisdata dan PHP untuk teknologi Serverside. Tahap terakhir adalah pengujian sistem yang dilakukan dengan Black Box Test dan Alpha Test. Hasil penelitian ini berupa aplikasi tes kepribadian menggunakan metode Myers- Briggs Type Indicator (MBTI berbasis web yang dapat membantu PT. Winata Putra Mandiri dalam mengintegrasikan hasil tes seluruh karyawan baik dari kantor pusat maupun kantor cabang

  4. Status of ANSI standards on decommissioning of nuclear reprocessing facilities

    International Nuclear Information System (INIS)

    Graham, H.B.

    1975-01-01

    A definition of decommissioning is given, and the preparation of ANSI Standard, ''General Design Criteria for Nuclear Reprocessing Facilities'' (N101.3) is discussed. A Eurochemic report, entitled ''The Shutdown of Reprocessing Facilities--Results of Preliminary Studies on the Installations Belonging to Eurochemic,'' was used in the preparation of this standard. (U.S.)

  5. Feasibility study for adapting ITREC plant to reprocessing LMFBR fuels

    International Nuclear Information System (INIS)

    Moccia, A.; Rolandi, G.

    1976-05-01

    The report evaluates the feasibility of adapting ITREC plant to the reprocessing LMFBR fuels, with the double purpose of: 1) recovering valuable Pu contained in these fuels and recycling it to the fabrication plant; 2) trying, on a pilot scale, the chemical process technology to be applied in a future industrial plant for reprocessing the fuel elements discharged from fast breeder power reactors

  6. Effectiveness of reprocessing for flexible bronchoscopes and endobronchial ultrasound bronchoscopes.

    Science.gov (United States)

    Ofstead, Cori L; Quick, Mariah R; Wetzler, Harry P; Eiland, John E; Heymann, Otis L; Sonetti, David A; Ferguson, J Scott

    2018-05-30

    Infections have been linked to inadequately-reprocessed flexible bronchoscopes, and recent investigations determined that pathogen transmission occurred even when bronchoscope cleaning and disinfection practices aligned with current guidelines. This multisite, prospective study evaluated the effectiveness of real-world bronchoscope reprocessing methods using a systematic approach. This study involved direct observation of reprocessing methods for flexible bronchoscopes, multifaceted evaluations performed after manual cleaning and after high-level disinfection, and assessments of storage conditions. Visual inspections of ports and channels were performed using lighted magnification and borescopes. Contamination was detected using microbial cultures and tests for protein, hemoglobin, and adenosine triphosphate. Researchers assessed reprocessing practices, and storage cabinet cleanliness was evaluated by visual inspection and adenosine triphosphate tests. Researchers examined 24 clinically used bronchoscopes. After manual cleaning, 100% of bronchoscopes had residual contamination. Microbial growth was found in 14 (58%) fully-reprocessed bronchoscopes, including mold, Stenotrophomonas maltophilia, and Escherichia coli/Shigella spp. Visible irregularities were observed in 100% of bronchoscopes, including retained fluid; brown, red, or oily residue; scratches; damaged insertion tubes and distal ends; and filamentous debris in channels. Reprocessing practices were substandard at two of three sites. Damaged and contaminated bronchoscopes were in use at all sites. Inadequate reprocessing practices may have contributed to bioburden found on bronchoscopes. However, even when guidelines were followed, high-level disinfection was not effective. A shift toward the use of sterilized bronchoscopes is recommended. In the meantime, quality management programs and updated reprocessing guidelines are needed. Copyright © 2018. Published by Elsevier Inc.

  7. Management of reprocessed uranium. Current status and future prospects

    International Nuclear Information System (INIS)

    2007-02-01

    There is worldwide interest in developing advanced and innovative technologies for nuclear fuel cycles, minimizing waste and environmental impacts. As of the beginning of 2003, about 171000 tonnes heavy metal spent nuclear fuel is in storage, while smaller amounts have been reprocessed. In several countries, including France, India, Japan and the Russian Federation, spent fuel has been viewed as a national energy resource. Some countries hold reprocessed uranium as the result of their commercial reprocessing service contracts for reprocessing the spent fuel of others. Reprocessed uranium has a potential value for recycling either directly or after appropriate treatment. This report analyses the existing options, approaches and developments in the management of reprocessed uranium. It includes the technical issues involved in managing reprocessed uranium which are RepU arisings, storage, chemical conversion, re-enrichment, fuel fabrication, transport, reactor irradiation, subsequent reprocessing and disposal options, as well as assessment of holistic environmental impacts. The objective of this document is to overview the information on the current status and future trends in the management of RepU and to identify major issues to be considered for future projects

  8. Sterilization and reprocessing of materials and medical devices--reusability.

    Science.gov (United States)

    Jayabalan, M

    1995-07-01

    Problems associated with reprocessing of disposable medical devices such as hemodialysers with resterilization for reuse and changes in material properties with resterilization of polymeric (PVC, polypropylene, polyester, polycarbonate) materials intended for development of disposable devices are reviewed. Reprocessing of hospital supplies, polystyrene microtiter plate and angiographic catheter for reuse is also discussed.

  9. Reliability engineering analysis of ATLAS data reprocessing campaigns

    International Nuclear Information System (INIS)

    Vaniachine, A; Golubkov, D; Karpenko, D

    2014-01-01

    During three years of LHC data taking, the ATLAS collaboration completed three petascale data reprocessing campaigns on the Grid, with up to 2 PB of data being reprocessed every year. In reprocessing on the Grid, failures can occur for a variety of reasons, while Grid heterogeneity makes failures hard to diagnose and repair quickly. As a result, Big Data processing on the Grid must tolerate a continuous stream of failures, errors and faults. While ATLAS fault-tolerance mechanisms improve the reliability of Big Data processing in the Grid, their benefits come at costs and result in delays making the performance prediction difficult. Reliability Engineering provides a framework for fundamental understanding of the Big Data processing on the Grid, which is not a desirable enhancement but a necessary requirement. In ATLAS, cost monitoring and performance prediction became critical for the success of the reprocessing campaigns conducted in preparation for the major physics conferences. In addition, our Reliability Engineering approach supported continuous improvements in data reprocessing throughput during LHC data taking. The throughput doubled in 2011 vs. 2010 reprocessing, then quadrupled in 2012 vs. 2011 reprocessing. We present the Reliability Engineering analysis of ATLAS data reprocessing campaigns providing the foundation needed to scale up the Big Data processing technologies beyond the petascale.

  10. Low Thermal Conductance Transition Edge Sensor (TES) for SPICA

    International Nuclear Information System (INIS)

    Khosropanah, P.; Dirks, B.; Kuur, J. van der; Ridder, M.; Bruijn, M.; Popescu, M.; Hoevers, H.; Gao, J. R.; Morozov, D.; Mauskopf, P.

    2009-01-01

    We fabricated and characterized low thermal conductance transition edge sensors (TES) for SAFARI instrument on SPICA. The device is based on a superconducting Ti/Au bilayer deposited on suspended SiN membrane. The critical temperature of the device is 113 mK. The low thermal conductance is realized by using long and narrow SiN supporting legs. All measurements were performed having the device in a light-tight box, which to a great extent eliminates the loading of the background radiation. We measured the current-voltage (IV) characteristics of the device in different bath temperatures and determine the thermal conductance (G) to be equal to 320 fW/K. This value corresponds to a noise equivalent power (NEP) of 3x10 -19 W/√(Hz). The current noise and complex impedance is also measured at different bias points at 55 mK bath temperature. The measured electrical (dark) NEP is 1x10 -18 W/√(Hz), which is about a factor of 3 higher than what we expect from the thermal conductance that comes out of the IV curves. Despite using a light-tight box, the photon noise might still be the source of this excess noise. We also measured the complex impedance of the same device at several bias points. Fitting a simple first order thermal-electrical model to the measured data, we find an effective time constant of about 2.7 ms and a thermal capacity of 13 fJ/K in the middle of the transition.

  11. MODEL TES FISIK PENCARIAN BAKAT OLAHRAGA BULUTANGKIS USIA DI BAWAH 11 TAHUN DI DIY

    Directory of Open Access Journals (Sweden)

    Utvi Hinda Zhannisa

    2015-04-01

    Full Text Available Penelitian ini bertujuan untuk mengembangkan model tes fisik pencarian bakat cabang olahraga bulutangkis usia di bawah 11 tahun. Jenis penelitian ini adalah penelitian R and D (Research and Development. Dalam penelitian pengembangan ini, langkah-langkah yang harus ditempuh meliputi: (1 studi pendahuluan (studi pustaka dan studi lapangan, (2 perencanaan (melakukan analisis, (3 desain draft awal, (4 validasi draft (5 ujcoba produk kelompok kecil dan revisi, (6 uji coba kelompok besar dan revisi, (7 hasil akhir. Validitas menggunakan validitas isi, reliabilitas menggunakan test retest Conbrach’s Alpha dan Z skor untuk menyamakan satuan. Uji reliabilitas diperoleh hasil (a tes kelentukan (sit and reach 0,743; (b tes kecepatan (lari 30 m 0,844; (c tes power otot tungkai (vertical jump 0,663; (d tes kelincahan (lari 4 sudut 0,848; (e tes power otot lengan (lempar bola 0,943; (f tes reaksi (step test 0,987; (g tes daya tahan (lari 600 m 0,861. Produk yang dihasilkan berupa sebuah model tes dan norma tes untuk pencarian bakat.   A MODEL OF PHYSICAL TEST FOR TALENT SCOUTING IN BADMINTON SKILL UNDER 11 YEARS OLD IN DIY   Abstract The purpose of the research it to develop a model of physical test in looking for a sport talent in badminton skill under 11 years old. The type of this research is R and D (Research and Development in this development research, the steps are (1 introduction study (bibiliography study, and field study, (2 planning (doing analysis, (3introduction draft design, (4 validation draft, (5 trying out product in small group and revision, (6 trying out product in big group and revision, (7 final result. Validation used content validation, reliability used test retest and Z score to the same the unit.  The model of the test that has been arranged is suitable to be to look for talent in badminton skill. Reability test shows that: (a sit and reach 0.743; (b sprint 30 m 0.844; (c vertical jump 0.663; (d run 4 corner 0.848; (e throw ball

  12. Fuel salt reprocessing influence on the MSFR behavior and on its associated reprocessing unit

    International Nuclear Information System (INIS)

    Doligez, X.

    2010-10-01

    In order to face with the growing of the energy demand, the nuclear industry has to reach the fourth generation technology. Among those concept, molten salt reactor, and especially the fast neutron spectrum configuration, seems very promising: indeed breeding is achievable while the feedback coefficient are still negative. However, the reprocessing salt scheme is not totally set down yet. A lot of uncertainties remain on chemical properties of the salt. Thanks to numerical simulation we studied the behavior of the molten Salt Fast Reactor coupled to a nominal reprocessing unit. We are now able to determine heat transfer and radiation in each elementary step of the unit and, by this way determine those that need special study for radioprotection. We also studied which elements are fundamental to extract for the reactor operation. Finally, we present a sensibility analysis of the chemical uncertainties to few relevant properties of the reactor behavior. (author)

  13. Enhancement of safety for reprocessing facilities

    International Nuclear Information System (INIS)

    2012-06-01

    The adequacy of the safety measures for utility loss accidents in nuclear fuel reprocessing facilities which have been formulated by the nuclear enterprises is investigated in JNES which organizes an advanced committee to specifically study this problem. The results are reviewed in the present report including the case of such severe accidents as in Fukushima Daiichi Nuclear Power Plant. The report also represents a tentative proposal for examination standards of such unimaginable severe accidents as 'station blackout,' urgent safety measures necessary for reoperation of nuclear power plants and requested by nuclear and industrial safety agency, and pointing out and clarification of the potential weakness from the safety point of view, and collective and composite evaluation of safety of the relevant facilities. Furthermore, the definition of accident management is given as of controlled condition and the authorized way of thinking for the cases of plural events happening at the same time and the cases when risks exist radioactivity emits with explosion. (S. Ohno)

  14. Solvent distillations studies for a reprocessing plant

    International Nuclear Information System (INIS)

    Ginisty, C.; Guillaume, B.

    1989-01-01

    The substantial amounts of solvent used in large reprocessing plants are such that considerable care must be paid to solvent management to limit the production of organic wastes. The installation of intensive treatment by chemical regeneration serves to increase the service life of the solvent. General solvent management, combined with a distillation unit under reduced pressure also helps to recycle the two components of the solvent at a low activity level. Distillation also serves to remove the heavy degradation products that are generally responsible for poor hydraulic behavior and for the holdup of radioactive products such as plutonium, zirconium and ruthenium. From the safety standpoint, the flashpoint of the distilled diluent tends to rise. It can therefore be recycled without risk

  15. Method of reprocessing radioactive asphalt solidification products

    International Nuclear Information System (INIS)

    Nakaya, Iwao; Murakami, Tadashi; Miyake, Takafumi; Inagaki, Yuzo.

    1986-01-01

    Purpose: To obtain heat-stable solidification products and decrease the total volume thereof by modifying the solidified form by the reprocessing of existent radioactive asphalt solidification products. Method: Radioactive asphalt solidification products are heated into a fluidized state. Then, incombustible solvents such as perchloroethylene or trichloroethylene are added to a dissolving tank to gradually dissolve the radioactive asphalt solidification products. Thus, organic materials such as asphalts are transferred into the solvent layer, while inorganic materials containing radioactive materials remain as they are in the separation tank. Then, the inorganic materials containing the radioactive materials are taken out and then solidified, for example, by converting them into a rock or glass form. (Kawakami, Y.)

  16. Flowsheet development for HTGR fuel reprocessing

    International Nuclear Information System (INIS)

    Baxter, B.; Benedict, G.E.; Zimmerman, R.D.

    1976-01-01

    Development studies to date indicate that the HTGR fuel blocks can be effectively crushed with two stages of eccentric jaw crushing, followed by a double-roll crusher, a screener and an eccentrically mounted single-roll crusher for oversize particles. Burner development results indicate successful long-term operation of both the primary and secondary fluidized-bed combustion systems can be performed with the equipment developed in this program. Aqueous separation development activities have centered on adapting known Acid-Thorex processing technology to the HTGR reprocessing task. Significant progress has been made on dissolution of burner ash, solvent extraction feed preparation, slurry transfer, solids drying and solvent extraction equipment and flowsheet requirements

  17. Natural uranium utilization without enrichment and reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Sekimoto, H.; Toshinsky, V.; Ryu, K. [Tokyo Inst. of Tech. (Japan). Research Lab. for Nuclear Reactors

    2001-07-01

    Two types of fast reactor are investigated to utilize the natural uranium without enrichment and reprocessing in an equilibrium state. The first trial is SFPR. Its fuel-shuffling pattern is optimized. An obtained result gives its peak fuel burnup of 22,5%, power peaking factor of 1.5 and peak excess reactivity of 2,15%. The second trial is CANDLE burnup scheme, where distribution shapes of neutron flux and nuclide densities are constant but move in axial direction with a constant velocity. A feasible solution gives the speed of burning region of 4,1 cm/year, k{sub eff} of 1,02 and average spent fuel burnup of 41%. (author)

  18. Criticality management of Tokai reprocessing facility

    Energy Technology Data Exchange (ETDEWEB)

    Nojiri, Ichiro [Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)

    2001-01-01

    In fuel cycle centers a number of equipment and vessels of various types and of complex design are used in several processes, i.e. dissolution of spent fuels, separation and storage of uranium and plutonium from fission products and transuranium elements. For each processes, Monte Carlo codes are frequently applied to manage the fuel criticality. Safety design depends largely on specific features of each facilities. The present report describes status of criticality management for main processes in Tokai Reprocessing Facility, JNC, and the criticality conditions specifically existing there. The guiding principle throughout consists of mass control, volume control, design (form) control, concentration control, and control due to employment of neutron poisons. (S. Ohno)

  19. Operations monitoring concept. Consolidated Fuel Reprocessing Program

    International Nuclear Information System (INIS)

    Kerr, H.T.

    1985-01-01

    Operations monitoring is a safeguards concept which could be applied in future fuel cycle facilities to significantly enhance the effectiveness of an integrated safeguards system. In general, a variety of operations monitoring techniques could be developed for both international and domestic safeguards application. The goal of this presentation is to describe specific examples of operations monitoring techniques as may be applied in a fuel reprocessing facility. The operations monitoring concept involves monitoring certain in-plant equipment, personnel, and materials to detect conditions indicative of the diversion of nuclear material. An operations monitoring subsystem should be designed to monitor operations only to the extent necessary to achieve specified safeguards objectives; there is no intent to monitor all operations in the facility. The objectives of the operations monitoring subsystem include: verification of reported data; detection of undeclared uses of equipment; and alerting the inspector to potential diversion activities. 1 fig

  20. Pyroelectrochemical process for reprocessing irradiated nuclear fuels

    International Nuclear Information System (INIS)

    Brambilla, G.; Sartorelli, A.

    1982-01-01

    A pyroelectrochemical process for reprocessing irradiated fast reactor mixed oxide or carbide fuels is described. The fuel is dissolved in a bath of molten alkali metal sulfates. The Pu(SO 4 ) 2 formed in the bath is thermally decomposed, leaving crystalline PuO 2 on the bottom of the reaction vessel. Electrodes are then introduced into the bath, and UO 2 is deposited on the cathode. Alternatively, both UO 2 and PuO 2 may be electrodeposited. The molten salts, after decontamination by precipitating the fission products dissolved in the bath by introducing basic agents such as oxides, carbonates, or hydroxides, may be recycled. Since it is not possible to remove cesium from the molten salt bath, periodic disposal and partial renewal with fresh salts is necessary. The melted salts that contain the fission products are conditioned for disposal by embedding them in a metallic matrix

  1. Steel construction in the nuclear reprocessing industry

    International Nuclear Information System (INIS)

    Jordan, G.W.

    1990-01-01

    Over the past decade British Nuclear Fuels plc (BNFL) has pursued a large capital expenditure programme at Sellafield in Cumbria. This has used large quantities of structural steelwork. For example, Thorp plant for reprocessing spend AGR and LWR fuels, due for completion in 1992, has 20,000 tonnes. The design of these plants has been entrusted to BNFL Engineering based at Risley near Warrington, England. These safety-related structures are designed, as required by the Nuclear Installations Inspectorate, to withstand the effects of environmental hazards such as extremes of earthquake, wind, temperature, ice, snow, flooding, and lightning strikes. In some cases they may be subjected to impact loading from possible mishandling of lifted loads such as fuel transportation flasks. Design criteria for these structures have been developed by BNFL Engineering. Some examples are mentioned. (author)

  2. Enhancements in the thorp reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Wakem, M.J.; Brownridge, M. [Thorp Technical Dept. and Research and Technology, BNFL plc, Sellafield, seascale, Cumbria, CA (United Kingdom)

    2000-07-01

    A number of successful enhancements have been made to the process at the Thorp reprocessing plant at Sellafield. After a long and detailed Research and Development programme followed by an intensive design/construction project, Thorp was inactively commissioned with first active shear in March 1994. The plant has now reached a mature stage in its development, following successful active commissioning demonstrating flowsheet or better performance in the solvent extraction cycles. Enhancements are now sought to achieve a range of objectives. Against a background of ever tighter regulatory control both in terms of safety and environmental discharge, BNFL are continuing to invest in further improvements with short, medium and longer term objectives to improve plant throughput; expand the range of feed fuels; reduce environmental discharges and reduce running costs. This paper describes a few of these enhancements. (authors)

  3. Enhancements in the thorp reprocessing plant

    International Nuclear Information System (INIS)

    Wakem, M.J.; Brownridge, M.

    2000-01-01

    A number of successful enhancements have been made to the process at the Thorp reprocessing plant at Sellafield. After a long and detailed Research and Development programme followed by an intensive design/construction project, Thorp was inactively commissioned with first active shear in March 1994. The plant has now reached a mature stage in its development, following successful active commissioning demonstrating flowsheet or better performance in the solvent extraction cycles. Enhancements are now sought to achieve a range of objectives. Against a background of ever tighter regulatory control both in terms of safety and environmental discharge, BNFL are continuing to invest in further improvements with short, medium and longer term objectives to improve plant throughput; expand the range of feed fuels; reduce environmental discharges and reduce running costs. This paper describes a few of these enhancements. (authors)

  4. Method of reprocessing spent nuclear fuels

    International Nuclear Information System (INIS)

    Kamiyama, Hiroaki; Inoue, Tadashi; Miyashiro, Hajime.

    1987-01-01

    Purpose: To facilitate the storage management for the wastes resulting from reprocessing by chemically separating transuranium elements such as actionoid elements together with uranium and plutonium. Method: Spent fuels from a nuclear reactor are separated into two groups, that is, a mixture of uranium, plutonium and transuranium elements and cesium, strontium and other nuclear fission products. Virgin uranium is mixed to adjust the mixture of uranium, plutonium and transuranium elements in the first group, which is used as the fuels for the nuclear reactor. After separating to recover useful metals such as cesium and strontium are separated from short half-decay nuclear fission products of the second group, other nuclear fission products are stored and managed. This enables to shorten the storage period and safety storage and management for the wastes. (Takahashi, M.)

  5. Safeguards implementation in UP3 reprocessing plant

    International Nuclear Information System (INIS)

    Laurent, J.P.; Regnier, J.; Talbourdet, Y.; De Jong, P.

    1991-01-01

    The implementation of safeguards in a large size reprocessing plant is a challenge, considering the high throughput of nuclear material and the sophisticated automation of such facilities. In the case of UP3, a pragmatic and realistic approach has been devised and is applied through an efficient cooperation between the safeguards organizations, the french national authorities and the operator. In essence, they consist in verification of every significant inputs and outputs, in timely analysis by NDA (e.g. solutions of dissolution through an on site k-edge equipment), in monitoring selected parts of the inprocess inventory and in specific containment/surveillance systems for the spent fuel storage ponds and the PuO2 storage. (author)

  6. Economic evaluation of reprocessing. Indicative US position

    International Nuclear Information System (INIS)

    1979-05-01

    This paper, which also appears as an Appendix to the final Working Group 4 report, forms part of the overall economic assessment of reprocessing. The indicative national position and illustrative ''phase diagram'' for the United States is presented. The prospective costs of nuclear power are given for four equilibrium modes of LWR operation: once-through, 15% and 25% improved once-through and thermal recycle. For a particular representative choice of fuel cycle parameters the economic cross over at which thermal recycle becomes economic relative to a 15% improved once-through cycle is above 100/lb U 3 O 8 . Thus the US believes that for the next several decades there is no economic incentive for thermal recycle. As a planning guide the US considers that the fast reactor will not become commercialised in the US before the year 2020

  7. Analytical developments in reprocessing at the CEA

    International Nuclear Information System (INIS)

    Buffereau, M.

    1989-01-01

    Analytical developments in reprocessing, which are based on extensive basic research, are aimed at fulfilling current requirements of R and D laboratories, pilot plants and industrial plants. They are also intended to propose and provide new opportunities. On-line measurements are a long term goal. One must be confident of their outcome. New equipment and procedures must be tested and their specifications determined, first at the laboratory level, and then in a pilot plant. In this respect we are considering equipment which will be in operation in the ATALANTE laboratories. And APM is also both a necessary and useful resource. However, many measurements must still be done and will continue to have to be done in analytical laboratories. Along with the improvement of accuracy the main developments aim at reducing manpower requirements and effluents and waste releases

  8. Brief description of the Wackersdorf Reprocessing Facility

    International Nuclear Information System (INIS)

    1986-01-01

    The DWK is now planning the construction and operation of a facility for the reprocessing of spent fuel elements and the fabrication of mixed-oxide fuel elements which will initially have an average daily throughput of 2 tons (t) of nuclear fuel. The application required by the Atomic Law was submitted to the Bavarian State Ministry for State Development and Environmental Matters on October 28, 1982. According to Par. 3, Section 1, No. 1 of the Atomic Law Procedural Ordinance such an application for permission in accordance with par. 7 AtL must explicitly be accompanied by a safety report which shall make it possible for third parties to make a judgment whether the impacts associated with the facility and its operation could damage their rights. The safety report is intended to present and explain the concept of the facility, the safety-technological design bases, and the operation of the plant, including its operation and safety systems and the impacts and proposed preventive measures. In addition to the detailed presentations in the safety report, Par. 3 of the Atomic Law Procedural Ordinance also requires a brief description of the plant designed for general public understanding, suitable for the design, which will also explain the expected impacts on the general environment and the surrounding area. Hence the brief description presents and explains the following matters: the site; the technology and state of the art for reprocessing of spent nuclear fuel; the structure and function of the proposed facility; safety provisions of the proposed facility and the management of perturbations in operation; the impacts of the facility and its operation on the environment; measures to be taken for dealing with the radioactive wastes; and provisions for ultimate shut-down of the facility

  9. Separation of tritium from reprocessing effluents

    International Nuclear Information System (INIS)

    Bruggeman, A.; Doyen, W.; Harnie, R.; Leysen, R.; Meynendonckx, L.; Monsecour, M.; Goossens, W.R.A.; Baetsle, L.H.

    1980-01-01

    For several years tritium retention has been studied at the Belgian Nuclear Research Centre, SCK/CEN; initially attention was focused on the removal of tritium from gaseous reprocessing effluents. If tritium can be released from the spent fuel into the gaseous phase before any aqueous operation, adsorption on molecular sieves after some isotopic dilution with hydrogen and after complete conversion to (tritiated) water is the most practical collection method. A once-through 15 m 3 .h -1 oxidation-adsorption unit with a closed regeneration system and with a decontamination factor of 1000 at total (tritiated) hydrogen and water inlet concentrations down to 1000 vpm (parts per million by volume) has been constructed and tested at SCK/CEN and it is described in the text. If no special head-end treatment is used an appropriate liquid management inside the reprocessing plant restricts the volume of tritiated aqueous effluents to about 3 m 3 per tonne of LWR fuel processed. However, for further reduction an isotope separation process becomes necessary. SCK/CEN is developing the ELEX process, which is a combination of water ELectrolysis and tritium EXchange between hydrogen and water, the exchange being promoted by a hydrophobic catalyst. For electrolysis under normal conditions an elementary tritium separation factor of 11.6 with a standard deviation of 6% was obtained. As concerns the exchange step a hydrophobic catalyst has been developed which yields for the flow rates used at atmospheric pressure and at 20 0 C an overall exchange rate constant of 9 mol.s -1 .m -3 in a countercurrent trickle-bed reactor. At present an integrated bench scale de-tritiation unit is being built for further tests and for a dynamic demonstration of the ELEX process

  10. Karakteristik Pengembangan Tes Keterampilan Berpiki Kritis Bumi dan Antariksa Untuk Calon Guru

    Directory of Open Access Journals (Sweden)

    Taufik Ramlan Ramalis

    2015-12-01

    Full Text Available Abstract The purpose of this study was to analyze the characteristics of the f critical thinking skills test and measurement errors according to classical test theory and item response theory. The test is based on the basic concepts and essential principles of the Earth Space, with reference to the core critical thinking skills. The research method used a mixed methods design with embedded experimental models. The analysis in this study is based on 41 responses of students teacher prospective who have taken IPBA courses at the Physics education department of FPMIPA UPI. Based on classical test theory indicates that of 18 test items were analyzed 15 items were good quality, reliability index of 0.89. From information function and standard error measurement of item response theory, the overall conclusion of this evaluation is that the model 2PL is better to use when evaluating the test. Keywords: critical thinking skills, earth and space, classical test theory, item response theory Abstrak Tujuan penelitian ini untuk menganalisis karakteristik tes keterampilan berpikir kritis serta kesalahan pengukuran menurut teori tes klasik dan teori respons item. Tes disusun berdasarkan konsep dasar dan prinsip esensial sains Bumi dan Antariksa, dengan mengacu pada inti keterampilan berpikir kritis. Metode penelitiannya menggunakan mixed methods dengan desain embedded experimental model. Analisis dalam penelitian ini didasarkan pada respons 41 mahasiswa calon guru yang telah mengambil matakuliah IPBA di departemen pendidikan Fisika FPMIPA UPI. Berdasarkan teori tes klasik menunjukkan bahwa dari 18 item tes yang dianalisis 15 item yang berkualitas baik, indeks reliabilitas 0,89. Dari fungsi informasi dan pengukuran kesalahan baku pada teori respons item, kesimpulan keseluruhan dari evaluasi ini adalah bahwa model 2PL adalah lebih baik untuk digunakan ketika mengevaluasi tes. Kata-kata kunci: keterampilan berpikir kritis, bumi dan antariksa, teori tes klasik

  11. Connectionist Interaction Information Retrieval.

    Science.gov (United States)

    Dominich, Sandor

    2003-01-01

    Discussion of connectionist views for adaptive clustering in information retrieval focuses on a connectionist clustering technique and activation spreading-based information retrieval model using the interaction information retrieval method. Presents theoretical as well as simulation results as regards computational complexity and includes…

  12. Simatik : Aplikasi Simulasi Bank Soal Tes Potensi Akademik (TPA Berbasis Multi Platform

    Directory of Open Access Journals (Sweden)

    Made Hendra Yudha Saputra

    2017-01-01

    Full Text Available Abstrak---Penelitian ini bertujuan untuk : (1 menghasilkan rancang bangun dan implementasi Simatik : Aplikasi Simulasi Bank Soal Tes Potensi Akademik (TPA Berbasis Multi Platform, (2 Mengetahui respon dari Pengguna terhadap Simatik : Aplikasi Simulasi Bank Soal Tes Potensi Akademik (TPA Berbasis Multi Platform. Dalam perancangannya, aplikasi ini akan menggunakan arsitektur client-server untuk melakukan proses pertukaran data. Perancangan dilakukan dengan menggunakan model fungsional berupa UML. Model fungsional berupa UML tersebut diimplementasikan dalam sebuah framework yaitu Phonegap dengan bahasa pemrograman HTML5. Untuk mengetahui respon terhadap Simatik : Aplikasi Simulasi Bank Soal Tes Potensi Akademik (TPA Berbasis Multi Platform ini diperoleh dengan menggunakan metode angket. Hasil akhirnya yaitu berupa Aplikasi Simatik berbasis Multi Platform yang dapat diinstall pada perangkat mobile untuk digunakan dalam latihan soal-soal yang terkait dengan Tes Potensi Akademik (TPA. Berdasarkan hasil uji usability, aplikasi Simatik berbasis Multi Platform ini mendapatkan persentase hasil sebesar 95,6 % dengan kategori sangat baik yang berarti dalam pengoperasiannya aplikasi ini mudah untuk digunakan dan dapat berfungsi sesuai dengan fungsi seharusnya. Kata Kunci : Phonegap, Multi Platform, Client Server, Mobile, Tes Potensi Akademik (TPA, Simatik   Abstract--- This research is purpose to : (1 produce generate design and implementation Simatik : Aplikasi Simulasi Bank Soal Tes Potensi Akademik (TPA Berbasis Multi Platform (2 To knowing the response of users to Simatik : Aplikasi Simulasi Bank Soal Tes Potensi Akademik (TPA Berbasis Multi Platform. In its design, this application will use the client-server architecture to make the exchange process of data. The design were done by using a functional model UML form. The functional model UML form is implemented within a framework that is phonegap with HTML 5 programming languages. To determine the

  13. The regulations concerning the reprocessing business of spent fuels

    International Nuclear Information System (INIS)

    1979-01-01

    The regulations are defined under provisions concerning the reprocessing business in the law for the regulations of nuclear source materials, nuclear fuel materials and reactors. The basic concepts and terms are explained, such as: exposure dose; accumulative dose; controlled area; safeguarded area; inspected surrounding area; employee; radioactive waste and marine discharging facilities. Any person who gets permission for design of reprocessing facilities and method of the construction shall file an application, listing name and address of the person and the works or the place of enterprise where reprocessing facilities are to be set up, design of such facilities and method of the construction, in and out-put chart of nuclear fuel materials in reprocessing course, etc. Records shall be made and kept for particularly periods in each works or enterprise on inspection of reprocessing facilities, control of dose, operation, maintenance, accident of reprocessing facilities and weather. Detailed prescriptions are settled on entrance limitation to controlled area, exposure dose, inspection and check, regular independent examination and operation of reprocessing facilities, transportation in the works or the enterprise, storage, disposal, safeguard and measures in dangerous situations, etc. Reports shall be filed on exposure dose of employees and other specified matters in the forms attached and in the case otherwise defined. (Okada, K.)

  14. Used mixed oxide fuel reprocessing at RT-1 plant

    Energy Technology Data Exchange (ETDEWEB)

    Kolupaev, D.; Logunov, M.; Mashkin, A.; Bugrov, K.; Korchenkin, K. [FSUE PA ' Mayak' , 30, Lenins str, Ozersk, 460065 (Russian Federation); Shadrin, A.; Dvoeglazov, K. [ITCP ' PRORYV' , 2/8 Malaya Krasmoselskay str, Moscow, 107140 (Russian Federation)

    2016-07-01

    Reprocessing of the mixed uranium-plutonium spent nuclear fuel of the BN-600 reactor was performed at the RT-1 plant twice, in 2012 and 2014. In total, 8 fuel assemblies with a burn-up from 73 to 89 GW day/t and the cooling time from 17 to 21 years were reprocessed. The reprocessing included the stages of dissolution, clarification, extraction separation of U and Pu with purification from the fission products, refining of uranium and plutonium at the relevant refining cycles. Dissolution of the fuel composition of MOX used nuclear fuel (UNF) in nitric acid solutions in the presence of fluoride ion has occurred with the full transfer of actinides into solution. Due to the high content of Pu extraction separation of U and Pu was carried out on a nuclear-safe equipment designed for the reprocessing of highly enriched U spent nuclear fuel and Pu refining. Technological processes of extraction, separation and refining of actinides proceeded without deviations from the normal mode. The output flow of the extraction outlets in their compositions corresponded to the regulatory norms and remained at the level of the compositions of the streams resulting from the reprocessing of fuel types typical for the RT-1 plant. No increased losses of Pu into waste have been registered during the reprocessing of BN-600 MOX UNF an compare with VVER-440 uranium UNF reprocessing. (authors)

  15. International and institutional aspects of reprocessing and plutonium management

    International Nuclear Information System (INIS)

    1978-09-01

    Various institutional alternatives applicable to reprocessing, plutonium management and recycle are considered, not as a definitive analysis but rather as a basis for identifying the institutional approaches and measures which the Working Group might wish to examine more thoroughly. Seven alternatives arrangements for reprocessing are presented. These range from suspending the operation of existing reprocessing plants through placing national facilities under safeguards to limiting reprocessing to a few large facilities subject to plutonium management, multinational or international control. Finally, the comprehensive alternative of an International Nuclear Fuel Authority with worldwide responsibility for reprocessing and plutonium management is considered. Plutonium management alternatives to complement the reprocessing options, are then outlined. These include national discretion on the separation and disposition of plutonium under safeguards, an agreed Code of Practice for plutonium management at national facilities and the international storage of plutonium. The advantages and disadvantages of the alternative are discussed tentatively. It is recognised that the alternatives are presented in a simplified form and that their elements can be combined or separated in many ways. Although strengthening the institutions relating to the peaceful uses of nuclear energy is imperative and can contribute to non-proliferation, such arrangements might open other proliferation risks through the spread of sensitive materials, facilities and technology. While there are risks with any fuel cycle, where plutonium in quantity is separated these risks are of a high order. Although these can be mitigated, they will have to be set against the energy and economic case for reprocessing and alternatives other than plutonium considered

  16. Flory-Stockmayer analysis on reprocessable polymer networks

    Science.gov (United States)

    Li, Lingqiao; Chen, Xi; Jin, Kailong; Torkelson, John

    Reprocessable polymer networks can undergo structure rearrangement through dynamic chemistries under proper conditions, making them a promising candidate for recyclable crosslinked materials, e.g. tires. This research field has been focusing on various chemistries. However, there has been lacking of an essential physical theory explaining the relationship between abundancy of dynamic linkages and reprocessability. Based on the classical Flory-Stockmayer analysis on network gelation, we developed a similar analysis on reprocessable polymer networks to quantitatively predict the critical condition for reprocessability. Our theory indicates that it is unnecessary for all bonds to be dynamic to make the resulting network reprocessable. As long as there is no percolated permanent network in the system, the material can fully rearrange. To experimentally validate our theory, we used a thiol-epoxy network model system with various dynamic linkage compositions. The stress relaxation behavior of resulting materials supports our theoretical prediction: only 50 % of linkages between crosslinks need to be dynamic for a tri-arm network to be reprocessable. Therefore, this analysis provides the first fundamental theoretical platform for designing and evaluating reprocessable polymer networks. We thank McCormick Research Catalyst Award Fund and ISEN cluster fellowship (L. L.) for funding support.

  17. Reprocessing of research reactor fuel the Dounreay option

    Energy Technology Data Exchange (ETDEWEB)

    Cartwright, P.

    1997-08-01

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

  18. Fuel reprocessing experience in India: Technological and economic considerations

    International Nuclear Information System (INIS)

    Prasad, A.N.; Kumar, S.V.

    1983-01-01

    The approach to the reprocessing of irradiated fuel from power reactors in India is conditioned by the non-availability of highly enriched uranium with the consequent need for plutonium for the fast-reactor programme. With this in view, the fuel reprocessing programme in India is developing in stages matching the nuclear power programme. The first plant was set up in Trombay to reprocess the metallic uranium fuel from the research reactor CIRUS. The experience gained in the construction and operation of this plant, and in its subsequent decommissioning and reconstruction, has not only provided the know-how for the design of subsequent plants but has indicated the fruitful areas of research and development for efficient utilization of limited resources. The Trombay plant also handled successfully, on a pilot scale, the reprocessing of irradiated thorium fuel to separate uranium-233. The second plant at Tarapur has been built for reprocessing spent fuels from the power reactors at Tarapur (BWR) and Rajasthan (PHWR). The third plant, at present under design, will reprocess the spent fuels from the power reactors (PHWR) and the Fast Breeder Test Reactor (FBTR) located at Kalpakkam. Through the above approach experience has been acquired which will be useful in the design and construction of even larger plants which will become necessary in the future as the nuclear power programme grows. The strategies considered for the sizing and siting of reprocessing plants extend from the idea of small plants, located at nuclear power station sites, to a large-size central plant, located at an independent site, serving many stations. The paper discusses briefly the experience in reprocessing uranium and thorium fuels and also in decommissioning. An attempt is made to outline the technological and economic aspects which are relevant under different circumstances and which influence the size and siting of the fuel reprocessing plants and the expected lead times for construction

  19. Use of risk information to safety regulation. Reprocessing facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    A procedure of probabilistic risk assessment (PRA) for a reprocessing facility has been under the development aiming to utilize risk information for safety regulations in this project. Activities in the fiscal year 2012 are summarized in the paper. A major activity is a fundamental study on a concept of serious accidents, requirements of serious accident management, and a policy of utilizing risk information for fabrication and reprocessing facilities. Other than the activity a study on release and transport of aerial radioactive materials at a serious accident in a reprocessing facility has been conducted. The outline and results are provided in the chapter 1 and 2 respectively. (author)

  20. Reprocessing flowsheet and material balance for MEU spent fuel

    International Nuclear Information System (INIS)

    Abraham, L.

    1978-10-01

    In response to nonproliferation concerns, the high-temperature gas-cooled reactor (HTGR) Fuel Recycle Development Program is investigating the processing requirements for a denatured medium-enriched uranium--thorium (MEU/Th) fuel cycle. Prior work emphasized the processing requirements for a high-enriched uranium--thorium (HEU/Th) fuel cycle. This report presents reprocessing flowsheets for an HTGR/MEU fuel recycle base case. Material balance data have been calculated for reprocessing of spent MEU and recycle fuels in the HTGR Recycle Reference Facility (HRRF). Flowsheet and mass flow effects in MEU-cycle reprocessing are discussed in comparison with prior HEU-cycle flowsheets

  1. The influence of size of plant upon reprocessing costs

    International Nuclear Information System (INIS)

    1978-10-01

    This paper reviews recent published estimates for capital and operating costs of reprocessing plants in an attempt to establish a relative variation of unit reprocessing costs with plant design capacity and load factor. It is concluded that capital costs follow the well established ''rule of thumb'' for chemical plants in being proportional to (design capacity)sup(2/3). Operating costs vary significantly with variation in labour costs. Unit reprocessing costs are presented as a function of plant design capacity, load factor and method of financing

  2. Nuclear fuel cycle: (5) reprocessing of irradiated fuel

    Energy Technology Data Exchange (ETDEWEB)

    Williams, J.A.

    1977-09-01

    The evolution of the reprocessing of irradiated fuel and the recovery of plutonium from it is traced out, starting by following the Manhatten project up to the present time. A brief description of the plant and processes used for reprocessing is given, while the Purex process, which is used in all plants today, is given special attention. Some of the important safety problems of reprocessing plants are considered, together with the solutions which have been adopted. Some examples of the more important safety aspects are the control of activity, criticality control, and the environmental impact. The related topic of irradiated fuel transport is briefly discussed.

  3. Economic assessment factors relating to spent nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    This paper is in two parts. Part I discusses the factors to be applied in an economic assessment of reprocessing. It sets forth three basic cost components, namely capital costs, operating costs and the cost of capital utilization. It lists the various components of each cost area. Part II proposes a relationship between these respective cost areas, tabulates a range of costs and then develops unit costs for reprocessing operations. Finally, an addendum to the paper gives a more detailed breakdown of the capital costs of a reprocessing plant

  4. Gas chromatographic analysis of extractive solvent in reprocessing plants

    International Nuclear Information System (INIS)

    Marlet, B.

    1984-01-01

    Operation of a reprocessing plant using the Purex process is recalled and analytical controls for optimum performance are specified. The aim of this thesis is the development of analytical methods using gas chromatography required to follow the evolution of the extraction solvent during spent fuel reprocessing. The solvent at different concentrations, is analysed along the reprocessing lines in organic or aqueous phases. Solvent degradation interferes with extraction and decomposition products are analysed. The solvent becomes less and less efficient, also it is distilled and quality is checked. Traces of solvent should also be checked in waste water. Analysis are made as simple as possible to facilitate handling of radioactive samples [fr

  5. On-Line Monitoring for Control and Safeguarding of Radiochemical Streams at Spent Fuel Reprocessing Plant

    International Nuclear Information System (INIS)

    Bryan, Samuel A.; Levitskaia, Tatiana G.; Billing, Justin M.; Casella, Amanda J.; Johnsen, Amanda M.; Peterson, James M.

    2009-01-01

    Advanced techniques enabling enhanced safeguarding of the spent fuel reprocessing plants are urgently needed. Our approach is based on prerequisite that real time monitoring of the solvent extraction flowsheets provides unique capability to quickly detect unwanted manipulations with fissile isotopes present in the radiochemical streams during reprocessing activities. The methods used to monitor these processes must be robust and must be able to withstand harsh radiation and chemical environments. A new on-line monitoring system satisfying these requirements and featuring Raman spectroscopy combined with a Coriolis and conductivity probes, has been recently developed by our research team. It provides immediate chemical data and flow parameters of high-level radioactive waste streams with high brine content generated during retrieval activities from Hanford nuclear waste storage tanks. The nature of the radiochemical streams at the spent fuel reprocessing plant calls for additional spectroscopic information, which can be gained by the utilization of UV-vis-NIR capabilities. Raman and UV-vis-NIR spectroscopies are analytical techniques that have extensively been extensively applied for measuring the various organic and inorganic compounds including actinides. The corresponding spectrometers used under the laboratory conditions are easily convertible to the process-friendly configurations allowing remote measurements under the flow conditions. A fiber optic Raman probe allows monitoring of the high concentration species encountered in both aqueous and organic phases within the UREX suite of flowsheets, including metal oxide ions, such as uranyl, components of the organic solvent, inorganic oxo-anions, and water. The actinides and lanthanides are monitored remotely by UV-vis-NIR spectroscopy in aqueous and organic phases. In this report, we will present our recent results on spectroscopic measurements of simulant flowsheet solutions and commercial fuels available at

  6. Safety aspects of a fuel reprocessing plant

    International Nuclear Information System (INIS)

    Donoghue, J.K.; Charlesworth, F.R.; Fairbairn, A.

    1977-01-01

    decommissioning and demolition procedures must be anticipated and suitable provision made. Application of these principles is illustrated by experience gained in the surveillance of reprocessing plants. United Kingdom regulatory procedures for the licensing and inspection of reprocessing plant, and statutory requirements influencing safety in design, construction and operation are reviewed. Recent developments in safety legislation including the Health and Safety at Work Act, 1974, are discussed

  7. Digital Signal Processing Based on a Clustering Algorithm for Ir/Au TES Microcalorimeter

    Science.gov (United States)

    Zen, N.; Kunieda, Y.; Takahashi, H.; Hiramoto, K.; Nakazawa, M.; Fukuda, D.; Ukibe, M.; Ohkubo, M.

    2006-02-01

    In recent years, cryogenic microcalorimeters using their superconducting transition edge have been under development for possible application to the research for astronomical X-ray observations. To improve the energy resolution of superconducting transition edge sensors (TES), several correction methods have been developed. Among them, a clustering method based on digital signal processing has recently been proposed. In this paper, we applied the clustering method to Ir/Au bilayer TES. This method resulted in almost a 10% improvement in the energy resolution. Conversely, from the point of view of imaging X-ray spectroscopy, we applied the clustering method to pixellated Ir/Au-TES devices. We will thus show how a clustering method which sorts signals by their shapes is also useful for position identification

  8. Fabrication of Low-Noise TES Arrays for the SAFARI Instrument on SPICA

    Science.gov (United States)

    Ridder, M. L.; Khosropanah, P.; Hijmering, R. A.; Suzuki, T.; Bruijn, M. P.; Hoevers, H. F. C.; Gao, J. R.; Zuiddam, M. R.

    2016-07-01

    Ultra-low-noise transition edge sensors (TES) with noise equivalent power lower than 2 × 10^{-19} W/Hz^{1/2 } have been fabricated by SRON, which meet the sensitivity requirements for the far-infrared SAFARI instrument on space infrared telescope for cosmology and astrophysics. Our TES detector is based on a titanium/gold (Ti/Au) thermistor on a silicon nitride (SiN) island. The island is thermally linked with SiN legs to a silicon support structure at the bath temperature. The SiN legs are very thin (250 nm), narrow (500 nm), and long (above 300 {\\upmu } m); these dimensions are needed in leg-isolated bolometers to achieve the required level of sensitivity. In this paper, we describe the latest fabrication process for our TES bolometers with improved sensitivity.

  9. Recent Patents on Nano-Enhanced Materials for Use in Thermal Energy Storage (TES).

    Science.gov (United States)

    Ferrer, Gerard; Barreneche, Camila; Solé, Aran; Juliá, José Enrique; Cabeza, Luisa F

    2017-07-10

    Thermal energy storage (TES) systems using phase change materials (PCM) have been lately studied and are presented as one of the key solutions for the implementation of renewable energies. These systems take advantage of the latent heat of phase change of PCM during their melting/ solidification processes to store or release heat depending on the needs and availability. Low thermal conductivity and latent heat are the main disadvantages of organic PCM, while corrosion, subcooling and thermal stability are the prime problems that inorganic PCM present. Nanotechnology can be used to overcome these drawbacks. Nano-enhanced PCM are obtained by the dispersion of nanoparticles in the base material and thermal properties such as thermal conductivity, viscosity and specific heat capacity, within others, can be enhanced. This paper presents a review of the patents regarding the obtaining of nano-enhanced materials for thermal energy storage (TES) in order to realize the development nanotechnologies have gained in the TES field. Patents regarding the synthesis methods to obtain nano-enhanced phase materials (NEPCM) and TES systems using NEPCM have been found and are presented in the paper. The few existing number of patents found is a clear indicator of the recent and thus low development nanotechnology has in the TES field so far. Nevertheless, the results obtained with the reviewed inventions already show the big potential that nanotechnology has in TES and denote a more than probable expansion of its use in the next years. Copyright© Bentham Science Publishers; For any queries, please email at epub@benthamscience.org.

  10. French experience and prospects in the reprocessing of fast breeder reactor fuels

    International Nuclear Information System (INIS)

    Megy, J.

    1983-06-01

    Experience acquired in France in the field of reprocessing spent fuels from fast breeder reactors is recalled. Emphasis is put on characteristics and quantities of spent fuels reprocessed in La Hague and Marcoule facilities. Then reprocessing developments with the realisation of the new pilot plant TOR at Marcoule, new equipments and study of industrial reprocessing units are reviewed [fr

  11. Coastal Bend Texas Benthic Habitat Mapping Reprocessed DOQQ Aerial Imagery

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — In 2006 and 2007 the NOAA Office for Coastal Management purchased services to reprocess existing digital multi-spectral imagery (ADS-40) and create digital benthic...

  12. Research and development of FBR fuel reprocessing in PNC

    International Nuclear Information System (INIS)

    Hoshino, T.

    1976-05-01

    The research program of the PNC for FBR fuel reprocessing in Japan is discussed. The general characteristics of FBR fuel reprocessing are pointed out and a comparison with LWR fuel is made. The R and D program is based on reprocessing using the aqueous Purex process. So far, some preliminary steps of the research program have been carried out, these include solvent extraction test, off-gas treatment test, voloxidation process study, solidification test of high-level liquid waste, and study of the dissolution behaviour of irradiated mixed oxide fuel. By the end of the 1980s, a pilot plant for FBR fuel reprocessing will be completed. For the design of the pilot plant, further research will be carried out in the following fields: head-end techniques; voloxidation process; dissolution and extraction techniques; waste treatment techniques. A time schedule for the different steps of the program is included

  13. Reprocessing yields and material throughput: HTGR recycle demonstration facility

    International Nuclear Information System (INIS)

    Holder, N.; Abraham, L.

    1977-08-01

    Recovery and reuse of residual U-235 and bred U-233 from the HTGR thorium-uranium fuel cycle will contribute significantly to HTGR fuel cycle economics and to uranium resource conservation. The Thorium Utilization National Program Plan for HTGR Fuel Recycle Development includes the demonstration, on a production scale, of reprocessing and refabrication processes in an HTGR Recycle Demonstration Facility (HRDF). This report addresses process yields and material throughput that may be typically expected in the reprocessing of highly enriched uranium fuels in the HRDF. Material flows will serve as guidance in conceptual design of the reprocessing portion of the HRDF. In addition, uranium loss projections, particle breakage limits, and decontamination factor requirements are identified to serve as guidance to the HTGR fuel reprocessing development program

  14. Open problems in reprocessing of a molten salt reactor fuel

    International Nuclear Information System (INIS)

    Lelek, Vladimir; Vocka, Radim

    2000-01-01

    The study of fuel cycle in a molten salt reactor (MSR) needs deeper understanding of chemical methods used for reprocessing of spent nuclear fuel and preparation of MSR fuel, as well as of the methods employed for reprocessing of MSR fuel itself. Assuming that all the reprocessing is done on the basis of electrorefining, we formulate some open questions that should be answered before a flow sheet diagram of the reactor is designed. Most of the questions concern phenomena taking place in the vicinity of an electrode, which influence the efficiency of the reprocessing and sensibility of element separation. Answer to these questions would be an important step forward in reactor set out. (Authors)

  15. Safety aspects of solvent nitration in HTGR fuel reprocessing

    International Nuclear Information System (INIS)

    Wilbourn, R.G.

    1977-06-01

    Reprocessing of HTGR fuels requires evaporative concentration of uranium and thorium nitrate solutions. The results of a bench-scale test program conducted to assess the safety aspects of planned concentrator operations are reported

  16. Effect of Reprocessing and Excipient Characteristics on Ibuprofen ...

    African Journals Online (AJOL)

    Methods: The effect of excipient type, technology and reprocessing on flow, compressibility and compactibility was ... granulation technology is used, the ... powders improve particle size distribution, .... 8.04 (Stat-Easy Inc., Minneapolis, USA).

  17. Application of electrochemical techniques in fuel reprocessing- an overview

    Energy Technology Data Exchange (ETDEWEB)

    Rao, M K; Bajpai, D D; Singh, R K [Power Reactor Fuel Reprocessing Plant, Tarapur (India)

    1994-06-01

    The operating experience and development work over the past several years have considerably improved the wet chemical fuel reprocessing PUREX process and have brought the reprocessing to a stage where it is ready to adopt the introduction of electrochemical technology. Electrochemical processes offer advantages like simplification of reprocessing operation, improved performance of the plant and reduction in waste volume. At Power Reactor Fuel Reprocessing plant, Tarapur, work on development and application of electrochemical processes has been carried out in stages. To achieve plant scale application of these developments, a new electrochemical cycle is being added to PUREX process at PREFRE. This paper describes the electrochemical and membrane cell development activities carried out at PREFRE and their current status. (author). 5 refs., 4 tabs.

  18. Capability of minor nuclide confinement in fuel reprocessing

    International Nuclear Information System (INIS)

    Fujine, Sachio; Uchiyama, Gunzo; Mineo, Hideaki; Kihara, Takehiro; Asakura, Toshihide

    1999-01-01

    Experiment with spent fuels has started with the small scale reprocessing facility in NUCEF-BECKY αγ cell. Primary purpose of the experiment is to study the capability of long-lived nuclide confinement both in the PUREX flow sheet applied to the large scale reprocessing plant and also in the PARC (Partitioning Conundrum key process) flow sheet which is our proposal as a simplified reprocessing of one cycle extraction system. Our interests in the experiment are the behaviors of minor long-lived nuclides and the behaviors of the heterogeneous substances, such as sedimentation in the dissolver, organic cruds in the extraction banks. The significance of those behaviors will be assessed from the standpoint of the process safety of reprocessing for high burn-up fuels and MOX fuels. (author)

  19. Reliability Engineering Analysis of ATLAS Data Reprocessing Campaigns

    CERN Document Server

    Vaniachine, A; The ATLAS collaboration; Karpenko, D

    2013-01-01

    During three years of LHC data taking, the ATLAS collaboration completed three petascale data reprocessing campaigns on the Grid, with up to 2 PB of data being reprocessed every year. In reprocessing on the Grid, failures can occur for a variety of reasons, while Grid heterogeneity makes failures hard to diagnose and repair quickly. As a result, Big Data processing on the Grid must tolerate a continuous stream of failures, errors and faults. While ATLAS fault-tolerance mechanisms improve the reliability of Big Data processing in the Grid, their benefits come at costs and result in delays making the performance prediction difficult. Reliability Engineering provides a framework for fundamental understanding of the Big Data processing on the Grid, which is not a desirable enhancement but a necessary requirement. In ATLAS, cost monitoring and performance prediction became critical for the success of the reprocessing campaigns conducted in preparation for the major physics conferences. In addition, our Reliability...

  20. Reliability Engineering Analysis of ATLAS Data Reprocessing Campaigns

    CERN Document Server

    Vaniachine, A; The ATLAS collaboration; Karpenko, D

    2014-01-01

    During three years of LHC data taking, the ATLAS collaboration completed three petascale data reprocessing campaigns on the Grid, with up to 2 PB of data being reprocessed every year. In reprocessing on the Grid, failures can occur for a variety of reasons, while Grid heterogeneity makes failures hard to diagnose and repair quickly. As a result, Big Data processing on the Grid must tolerate a continuous stream of failures, errors and faults. While ATLAS fault-tolerance mechanisms improve the reliability of Big Data processing in the Grid, their benefits come at costs and result in delays making the performance prediction difficult. Reliability Engineering provides a framework for fundamental understanding of the Big Data processing on the Grid, which is not a desirable enhancement but a necessary requirement. In ATLAS, cost monitoring and performance prediction became critical for the success of the reprocessing campaigns conducted in preparation for the major physics conferences. In addition, our Reliability...

  1. Evironmental assessment factors relating to reprocessing of spent nuclear fuel

    International Nuclear Information System (INIS)

    1978-05-01

    This document is in two parts. Part I presents the criteria and evaluation factors, based primarily on US experience, which may be used to carry out an environmental assessment of spent fuel reprocessing. The concept of As Low as is Reasonably Achievable (ALARA) is introduced in limiting radiation exposure. The factors influencing both occupational and general public radiation exposure are reviewed. Part II provides information on occupational and general public radiation exposure in relation to reprocessing taken from various sources including UNSCEAR and GESMO. Some information is provided in relation to potential accidents at reprocessing or MOX fuel refabrication plants. The magnitude of the services, energy, land use and non-radiological effluents for the reference design of reprocessing plant are also presented

  2. Simulation of spent fuel reprocessing processes: Realizations and prospects

    International Nuclear Information System (INIS)

    Boullis, B.

    1986-12-01

    The separation of uranium and plutonium in the Purex process is very complex and for the extension of reprocessing plants optimization of the process requires mathematical modelling. The development of this model is reviewed [fr

  3. Enhancement of safety for reprocessing facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-08-15

    After the accident in Fukushima Daiichi Nuclear Power Station, eight emergency projects taking into account the accident were newly launched in JNES. This project for a reprocessing facility was one of them. Major items conducted in the project were as follows. (1) Researches, studies and evaluations etc. on various events under a total AC (alternating current) power loss condition Under this condition following subjects of the events were performed. a) An equipment with a removing function of decay heat and a time to reach a certain critical condition, e.g. a solution boiling, b) An equipment with a preventing function of accumulation of hydrogen gas and a time to reach a concentration of hydrogen gas to that of the lowest limit of combustion, c) Specifications of an alternative electric source and how to supply power. (2) Researches, studies and evaluations etc. on beyond design basis events. Following subjects on these events were performed. a) An event progression scenario, a consequence, a time period between an initiating event and a resultant accident or a certain critical condition, and draft inspection criteria, b) Draft inspection criteria for a stress test. (author)

  4. Release of gaseous tritium during reprocessing

    International Nuclear Information System (INIS)

    Bruecher, H.; Hartmann, K.

    1983-01-01

    About 50% of the tritium put through an LWR reprocessing plant is obtained as tritium-bearing water, HTO. Gaseous tritium, HT has a radiotoxicity which is by 4 orders of magnitude lower than that of HTO. A possibility for the removal of HTO could therefore be its conversion into the gas phase with subsequent emission of the HT into the atmosphere. However, model computations which are, in part, supported by experimental data reveal that the radiation exposure caused by HT release is only by about one order of magnitude below that caused by HTO. This is being attributed to the relatively quick reoxidation of HT by soil bacteria. Two alternatives for producing HT from HTO (electrolysis; voloxidation with subsequent electrolysis) are presented and compared with the reference process of deep-well injection of HTO. The authors come to the conclusion that tritium removal by HT release into the atmosphere cannot be recommended at present under either radiological or economic aspects. (orig.) [de

  5. PSA application on the Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Ishida, Michihiko; Nakano, Takafumi; Morimoto, Kazuyuki; Nojiri, Ichiro

    2003-01-01

    The Periodic Safety Review (PSR) of the Tokai Reprocessing Plant (TRP) has been carrying out to obtain an overall view of actual plant safety. As a part of the PSR, Probabilistic Safety Assessment (PSA) methodology has been applied to evaluate the relative importance of safety functions that prevent the progress of events causing to postulated accidents. Based on the results of the safety reassessments of the TRP that was carried out in 1999, event trees were developed to model sequences of postulated accidents. Event trees were quantified by using the results of fault tree analysis and human reliability analysis. In the quantification, the reliability data generally used in PSA of nuclear power plants were mainly used. Operating experiences of the TRP were also utilized to evaluated both component/system reliability and human reliability. The relative importance of safety functions was evaluated by using two major importance measures, Fussell-Vesely and Risk Achievement Worth both generally used in PSA of nuclear power plants. Through these evaluations, some useful insights into the safety of the TRP have been obtained. The results of the relative importance measures would be utilized to qualify TRP component/equipment important to the safety. (author)

  6. Fast-reactor fuel reprocessing in the United Kingdom

    International Nuclear Information System (INIS)

    Allardice, R.H.; Buck, C.; Williams, J.

    1977-01-01

    Enriched uranium metal fuel irradiated in the Dounreay Fast Reactor has been reprocessed and refabricated in plants specifically designed for the purpose in the United Kingdom since 1961. Efficient and reliable fuel recycle is essential to the development of a plutonium-based fast-reactor system, and the importance of establishing at an early stage fast-reactor fuel reprocessing has been reinforced by current world difficulties in reprocessing high-burnup thermal-reactor oxide fuel. The United Kingdom therefore decided to reprocess irradiated fuel from the 250MW(e) Prototype Fast Reactor (PFR) as an integral part of the fast reactor development programme. Flowsheet and equipment development work for the small-scale fully active demonstration plant has been carried out since 1972, and the plant will be commissioned and ready for active operation during 1977. In parallel, a comprehensive waste-management system has been developed and installed. Based on this development work and the information which will arise from active operation of the plant, a parallel development programme has been initiated to provide the basis for the design of a large-scale fast-reactor fuel-reprocessing plant to come into operation in the late 1980s to support the projected UK fast-reactor installation programme. The paper identifies the important differences between fast-reactor and thermal-reactor fuel-reprocessing technologies and describes some of the development work carried out in these areas for the small-scale PFR fuel-reprocessing operation. In addition, the development programme in aid of the design of a larger scale fast-reactor fuel-reprocessing plant is outlined and the current design philosophy discussed. (author)

  7. Study on remain actinides recovery in pyro reprocessing

    International Nuclear Information System (INIS)

    Suharto, Bambang

    1996-01-01

    The spent fuel reprocessing by dry process called pyro reprocessing have been studied. Most of U, Pu and MA (minor actinides) from the spent fuel will be recovered and be fed back to the reactor as new fuel. Accumulation of remain actinides will be separated by extraction process with liquid cadmium solvent. The research was conducted by computer simulation to calculate the stage number required. The calculation's results showed on the 20 stages extractor more than 99% actinides can be separated. (author)

  8. Benefit analysis of reprocessing and recycling light water reactor fuel

    International Nuclear Information System (INIS)

    1976-12-01

    The macro-economic impact of reprocessing and recycling fuel for nuclear power reactors is examined, and the impact of reprocessing on the conservation of natural uranium resources is assessed. The LWR fuel recycle is compared with a throwaway cycle, and it is concluded that fuel recycle is favorable on the basis of economics, as well as being highly desirable from the standpoint of utilization of uranium resources

  9. Cost and availability of gadolinium for nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    Klepper, O.H.

    1985-06-01

    Gadolinium is currently planned for use as a soluble neutron poison in nuclear fuel reprocessing plants to prevent criticality of solutions of spent fuel. Gadolinium is relatively rare and expensive. The present study was undertaken therefore to estimate whether this material is likely to be available in quantities sufficient for fuel reprocessing and at reasonable prices. It was found that gadolinium, one of 16 rare earth elements, appears in the marketplace as a by-product and that its present supply is a function of the production rate of other more prevalent rare earths. The potential demand for gadolinium in a fuel reprocessing facility serving a future fast reactor industry amounts to only a small fraction of the supply. At the present rate of consumption, domestic supplies of rare earths containing gadolinium are adequate to meet national needs (including fuel reprocessing) for over 100 years. With access to foreign sources, US demands can be met well beyond the 21st century. It is concluded therefore that the supply of gadolinium will quite likely be more than adequate for reprocessing spent fuel for the early generation of fast reactors. The current price of 99.99% pure gadolinium oxide lies in the range $50/lb to $65/lb (1984 dollars). By the year 2020, in time for reprocessing spent fuel from an early generation of large fast reactors, the corresponding values are expected to lie in the $60/lb to $75/lb (1984 dollars) price range. This increase is modest and its economic impact on nuclear fuel reprocessing would be minor. The economic potential for recovering gadolinium from the wastes of nuclear fuel reprocessing plants (which use gadolinium neutron poison) was also investigated. The cost of recycled gadolinium was estimated at over twelve times the cost of fresh gadolinium, and thus recycle using current recovery technology is not economical. 15 refs., 4 figs., 11 tabs

  10. Example of material accounting and verification of reprocessing input

    International Nuclear Information System (INIS)

    Koch, L.; Schoof, S.

    1981-01-01

    An example is described in this paper of material accounting at the reprocessing input point. Knowledge of the fuel history and chemical analyses of the spent fuel permitted concepts to be tested which have been developed for the determination of the input by the operator and for its verification by nuclear material safeguards with the intention of detecting a protracted as well as an abrupt diversion. Accuracies obtained for a material balance of a PWR fuel reprocessing campaign are given. 6 refs

  11. Management and disposal of used nuclear fuel and reprocessing wastes

    International Nuclear Information System (INIS)

    1983-01-01

    The subject is dealt with in chapters, entitled: introduction (general statement of problem); policy framework (criteria for waste management policy); waste management and disposal, as practised and planned (general; initial storage; reprocessing and conditioning of reprocessing wastes; intermediate storage; transportation; packaging; disposal); international co-operation. Details of the situation in each country concerned (Australia, Belgium, Canada, France, Federal Republic of Germany, Spain, Sweden, Switzerland and United Kingdom) are included as annexes. (U.K.)

  12. Containment/surveillance concepts for international safeguards in reprocessing plants

    International Nuclear Information System (INIS)

    Bleck, M.E.; Cameron, C.P.; Camp, A.L.

    1980-01-01

    This paper examines the potential role of advanced containment/surveillance instrumentation systems for international safeguards in reprocessing plants. Several conceptual systems for the surveillance of containment boundary penetrations in a reference reprocessing plant are described and evaluated. The results of the evaluation aid in understanding the potential capabilities and limitations of containment/surveillance as an international safeguards concept in this type of facility

  13. Reprocessing and reuse of urological armamentarium: How correct are we!

    Directory of Open Access Journals (Sweden)

    Krutik Vipulbhai Raval

    2017-01-01

    Full Text Available Healthcare is expensive for a large proportion of the population in spite of high per capita income and good health insurance penetration. In an effort to reduce cost of the procedure, reprocessing of devices was started in the late 1970s. Reprocessing practice includes various measures such as proper cleaning, disinfection, and sterilization procedures. As reprocessing is aimed at reducing cost, there is a potential risk of compromising patient safety due to cross contamination after inadequate sterilization. There is also risk of performance alteration of urological reprocessed devices during sterilization/disinfection processing. Therefore, there is a need for formulating proper guidelines to decide methods of reprocessing for various urological equipment. There is also need to discuss the problematic areas that urologists face and to find their solutions. A PubMed search was made in September 2016, using key words “reprocessing of medical devices,” “Single Use Devices,” “methods of reprocessing of devices in clinical practice,” “use of formalin chamber,” “urological disposable sterilization,” etc., After excluding duplicates, all English articles were reviewed by title and abstract. Full texts of selected articles were obtained, and these articles were cross-referenced to find any other related articles. All the articles were reviewed. A product can be reused if it can be economically reprocessed with validated protocols with preservation of its function. There is no reason to discard it after one use. This practice is useful for controlling economics of a urological case and to reduce the financial burden. Current Food and Drug Administration guidelines are stringent. The contamination described to test the sterilization process in the suggested guidelines actually does never exist in clinical practice. Therefore, new guidelines considering the clinical practice scenario are desirable.

  14. The search for advanced remote technology in fast reactor reprocessing

    International Nuclear Information System (INIS)

    Burch, W.D.; Herndon, J.N.; Stradley, J.G.

    1990-01-01

    Research and development in fast reactor reprocessing has been under way about 20 years in several countries throughout the world. During the past decade in France and the United Kingdom, active development programs have been carried out in breeder reprocessing. Actual fuels from their demonstration reactors have been reprocessed in small-scale facilities. Early US work in breeder reprocessing was carried out at the EBR-II facilities with the early metal fuels, and interest has renewed recently in metal fuels. A major, comprehensive program, focused on oxide fuels, has been carried out in the Consolidated Fuel Reprocessing Program (CFRP) at the Oak Ridge National Laboratory (ORNL) since 1974. Germany and Japan have also carried out development programs in breeder reprocessing, and Japan appears committed to major demonstration of breeder reactors and their fuel cycles. While much of the effort in all of these programs addressed process chemistry and process hardware, a significant element of many of these programs, particularly the CFRP, has been on advancements in facility concepts and remote maintenance features. This paper will focus principally on the search for improved facility concepts and better maintenance systems in the CFRP and, in turn, on how developments at ORNL have influenced the technology elsewhere

  15. Effect of repeated tracheostomy tube reprocessing on biofilm formation.

    Science.gov (United States)

    Rodney, Jennifer; Ojano-Dirain, Carolyn P; Antonelli, Patrick J; Silva, Rodrigo C

    2016-04-01

    To determine the effect of repeated reprocessing of pediatric tracheostomy tubes (TTs) on biofilm formation. In vitro microbiological study. Pediatric, uncuffed, polyvinyl chloride (PVC) TTs from two different manufacturers (Tracoe Mini and Shiley) were reprocessed mechanically with household detergent and soaked in sodium hypochlorite (bleach). Two TTs of each brand were reprocessed 0 (control), 10, or 20 times. Twenty 2-mm coupons were then obtained from each TT, immersed in human mucus, and cultured with either Staphylococcus aureus or Pseudomonas aeruginosa. Biofilm formation was evaluated with bacterial counts. Bacterial counts of S. aureus for both brands were significantly higher on the TTs that were reprocessed 20 times compared to those that were not reprocessed (Tracoe: P = .040, Shiley: P  attachment. Further investigation is needed to determine the optimal technique and limits of reprocessing TTs in clinical practice. NA. Laryngoscope published by Wiley on behalf of the American Laryngological, Rhinological and Otological Society, Inc, “The Triological Society” and American Laryngological Association (the “Owner”).

  16. Processes for the control of 14CO2 during reprocessing

    International Nuclear Information System (INIS)

    Notz, K.J.; Holladay, D.W.; Forsberg, C.W.; Haag, G.L.

    1980-01-01

    The fixation of 14 CO 2 may be required at some future time because of the significant fractional contribution of 14 C, via the ingestion pathway, to the total population dose from the nuclear fuel cycle, even though the actual quantity of this dose is very small when compared to natural background. The work described here was done in support of fuel reprocessing development, of both graphite fuel (HTGRs) and metal-clad fuel (LWRs and LMFBRs), and was directed to the control of 14 CO 2 released during reprocessing operations. However, portions of this work are also applicable to the control of 14 CO 2 released during reactor operation. The work described falls in three major areas: (1) The application of liquid-slurry fixation with Ca(OH) 2 , which converts the CO 2 to CaCO 3 , carried out after treatment of the CO 2 -containing stream to remove other gaseous radioactive components, mainly 85 Kr. This approach is primarily for application to HTGR fuel reprocessing. (2) The above process for CO 2 fixation, but used ahead of Kr removal, and followed by a molecular sieve process to take out the 85 Kr. This approach was developed for use with HTGR reprocessing, but certain aspects also have application to metal-clad fuel reprocessing and to reactor operation. (3) The use of solid Ba(OH) 2 hydrate reacting directly with the gaseous phase. This process is generally applicable to both reprocessing and to reactor operation

  17. SeTES, a Self-Teaching Expert System for the analysis, design and prediction of gas production from shales and a prototype for a new generation of Expert Systems in the Earth Sciences

    Science.gov (United States)

    Kuzma, H. A.; Boyle, K.; Pullman, S.; Reagan, M. T.; Moridis, G. J.; Blasingame, T. A.; Rector, J. W.; Nikolaou, M.

    2010-12-01

    A Self Teaching Expert System (SeTES) is being developed for the analysis, design and prediction of gas production from shales. An Expert System is a computer program designed to answer questions or clarify uncertainties that its designers did not necessarily envision which would otherwise have to be addressed by consultation with one or more human experts. Modern developments in computer learning, data mining, database management, web integration and cheap computing power are bringing the promise of expert systems to fruition. SeTES is a partial successor to Prospector, a system to aid in the identification and evaluation of mineral deposits developed by Stanford University and the USGS in the late 1970s, and one of the most famous early expert systems. Instead of the text dialogue used in early systems, the web user interface of SeTES helps a non-expert user to articulate, clarify and reason about a problem by navigating through a series of interactive wizards. The wizards identify potential solutions to queries by retrieving and combining together relevant records from a database. Inferences, decisions and predictions are made from incomplete and noisy inputs using a series of probabilistic models (Bayesian Networks) which incorporate records from the database, physical laws and empirical knowledge in the form of prior probability distributions. The database is mainly populated with empirical measurements, however an automatic algorithm supplements sparse data with synthetic data obtained through physical modeling. This constitutes the mechanism for how SeTES self-teaches. SeTES’ predictive power is expected to grow as users contribute more data into the system. Samples are appropriately weighted to favor high quality empirical data over low quality or synthetic data. Finally, a set of data visualization tools digests the output measurements into graphical outputs.

  18. The economic influence of reprocessing strategy in the early stages of a commercial breeder programme

    International Nuclear Information System (INIS)

    Pounder, F.

    1982-01-01

    The effect on reprocessing cost of constructing fast reactors in nuclear parks is examined and compared with carrying out reprocessing for a range of installation programmes of fast reactor in central reprocessing facilities. Consideration is also given to the economics of storing irradiated fuel to improve the load factor of reprocessing plants and to reprocessing both thermal reactor and fast reactor fuel in a common plant. (author)

  19. Laparoscopic specimen retrieval bags.

    Science.gov (United States)

    Smorgick, Noam

    2014-10-01

    Specimen retrieval bags have long been used in laparoscopic gynecologic surgery for contained removal of adnexal cysts and masses. More recently, the concerns regarding spread of malignant cells during mechanical morcellation of myoma have led to an additional use of specimen retrieval bags for contained "in-bag" morcellation. This review will discuss the indications for use retrieval bags in gynecologic endoscopy, and describe the different specimen bags available to date.

  20. Private information retrieval

    CERN Document Server

    Yi, Xun; Bertino, Elisa

    2013-01-01

    This book deals with Private Information Retrieval (PIR), a technique allowing a user to retrieve an element from a server in possession of a database without revealing to the server which element is retrieved. PIR has been widely applied to protect the privacy of the user in querying a service provider on the Internet. For example, by PIR, one can query a location-based service provider about the nearest car park without revealing his location to the server.The first PIR approach was introduced by Chor, Goldreich, Kushilevitz and Sudan in 1995 in a multi-server setting, where the user retriev

  1. Risk assessment approach for Rokkasho reprocessing plant

    International Nuclear Information System (INIS)

    Ootou, Y.; Tamauchi, Y.; Hayashi, Y.; Takebe, K.; Miyata, T.

    2006-01-01

    Full text: It is desirable that the operation and maintenance of Rokkasho Reprocessing Plant (RRP) be established and conducted with maximum effectiveness and efficiency, making the best use of risk information to help the plant achieve further enhanced safety. Risk assessment is applied for RRP, and upgraded risk information is established. In the basic design phase, the potential incidents and accidents that might occur in the plant were identified systematically and exhaustively adopting the HAZOP method. After screening the potential for occurrence, the design basis accidents (DBAs) were identified and it was confirmed that the plant would not put the general public at risk of significant radiation exposure in the case of such accidents, even when assuming the single failure of dynamic apparatus in the prevention and mitigation systems. To support the deterministic safety assessment mentioned above, the risk assessment was conducted during the basic design phase. Of the DBAs and out-of-design basis accidents excluded from DBAs because of extremely rare occurrence possibilities, the risk assessment was conducted for such accidents which might cause relatively high consequence for the general public. The risk assessment was conducted using the PSA method generally used for nuclear power plants. After that, a review of the occurrence frequency assessment for some of the accidents was made, taking into account information relating to detailed design and operation procedures. Typical examples are a loss of the hydrogen scavenging function in the plutonium solution tank and a loss of cooling capability in the high-active liquid waste storage tank. The occurrence frequency for a loss of the hydrogen scavenging function was less than 10 -5 /year. The occurrence frequency for a loss of cooling capability was less than 10 -7 /year. In addition, an importance assessment (FV index, Risk Achievement Worth) was conducted, such as a contribution to the occurrence frequency

  2. Institutional arrangements for a multinational reprocessing plant

    International Nuclear Information System (INIS)

    Smith, C.B.; Chayes, A.

    1977-01-01

    The paper lists some of the major issues that would have to be faced in negotiating the institutional structure of a multinational nuclear-fuel center. None of the organization problems is inherently insoluble. Difficulties are exacerbated by the large number of questions, their interrelations, and the complexity of the assumed structure. However, the assumptions posed the most difficult case. A reduction in membership and in the ambitious scope of the enterprise, at least at the outset, would greatly reduce the complexity of the organizational structure and the difficulty of negotiations. The analysis suggests that multinational fuel-cycle activities should start out more modestly, perhaps only with joint appraisal by a relatively few countries with existing geographic or economic connections. If operations are contemplated it would seem that the first step should be joint arrangements for spent-fuel storage, with the decision to go forward to more elaborate activities deferred. This approach would not only be simpler and permit the parties to gain experience working together, but it would have the virtue of delaying reprocessing until it was clear that there was a real need for it. Even on this reduced basis, the negotiating task would not be easy. The key, of course, to overcoming difficult technical problems of institutional structure is politial will--the genuine commitment of the participants to the aims and values of the enterprise. This suggests that any effort to cajole--not to say coerce--participation in a multinational fuel-cycle enterprise would be wholly misplaced. A reluctant partner would have available an infinitude of points and issues to create plausible, irritating, and ultimately defeating delay and complication in the negotiating process. Only assent freely given in the perception that the enterprise really serves the interest of the countries involved will be able to surmount the many institutional problems that will inevitably arise

  3. Fuel reprocessing: safety analysis of extraction cycles

    International Nuclear Information System (INIS)

    Dinh, B.; Mauborgne, B.; Baron, P.; Mercier, J.P.

    1991-01-01

    An essential part of the safety analysis related to the extraction cycles of reprocessing plants, is the analysis of their behaviour during steady-state and transient operations, by means of simulation codes. These codes are based on the chemical properties of the main species involved (distribution coefficient and kinetics) and the hydrodynamics inside the contactors (mixer-settlers and pulsed columns). These codes have been consolidated by comparison of calculations with experimental results. The safety analysis is essentially performed in two steps. The first step is a parametric sensitivity analysis of the chemical flowsheet operated: the effect of a misadjustment (flowrate of feed, solvent, etc) is evaluated by successive steady-state calculations. These calculations help the identification of the sensitive parameters for the risk of plutonium accumulation, while indicating the permissible level of misadjustment. These calculations also serve to identify the parameters which should be measured during plant operation. The second step is the study of transient regimes, for the most sensitive parameters related to plutonium accumulation risk. The aim is to confirm the conclusions of the first step and to check that the characteristic process parameters chosen effectively allow, the early and reliable detection of any drift towards a plutonium accumulating regime. The procedures to drive the process backwards to a specified convenient steady-state regime from a drifting-state are also verified. The identification of the sensitive parameters, the process status parameters and the process transient analysis, allow a good control of process operation. This procedure, applied to the first purification cycle of COGEMA's UP3-A La Hague plant has demonstrated the total safety of facility operations

  4. Optimal installation program for reprocessing plants

    International Nuclear Information System (INIS)

    Kubokawa, Toshihiko; Kiyose, Ryohei

    1976-01-01

    Optimization of the program of installation of reprocessing plants is mathematically formulated as problem of mixed integer programming, which is numerically solved by the branch-and-bound method. A new concept of quasi-penalty is used to obviate the difficulties associated with dual degeneracy. The finiteness of the useful life of the plant is also taken into consideration. It is shown that an analogous formulation is possible for the cases in which the demand forecasts and expected plant lives cannot be predicted with certainty. The scale of the problem is found to have kN binary variables, (k+2)N continuous variables, and (k+3)N constraint conditions, where k is the number of intervals used in the piece-wise linear approximation of a nonlinear objective function, and N the overall duration of the period covered by the installation program. Calculations are made for N=24 yr and k=3, with the assumption that the plant life is 15 yr, the plant scale factor 0.5, and the maximum plant capacity 900 (t/yr). The results are calculated and discussed for four different demand forecasts. The difference of net profit between optimal and non-optimal installation programs is found to be in the range of 50 -- 100 M$. The pay-off matrix is calculated, and the optimal choice of action when the demand cannot be forecast with certainty is determined by applying Bayes' theory. The optimal installation program under such conditions of uncertainty is obtained also with a stochastic mixed integer programming model. (auth.)

  5. Crystallization of the acyl-CoA thioesterase TesB from Yersinia pestis

    International Nuclear Information System (INIS)

    Swarbrick, Crystall M. D.; Patterson, Edward I.; Forwood, Jade K.

    2013-01-01

    The expression, purification, crystallization and diffraction of the acyl-CoA thioesterase TesB from Y. pestis are reported. X-ray crystallographic diffraction data to 2.0 Å resolution were collected at the Australian Synchrotron. Yersinia pestis is a highly virulent human pathogen and is the causative agent of bubonic plague. Spread through the bite of infected fleas, plague epidemics have marked important events in history, including the Justinian plague (6th century), the Black Death (14th century) which decimated nearly one quarter of the European population, and more recently the Orientalis plague (1894). To date, deaths are still being reported and, without treatment, the disease kills most people within 4 days. One of the thioesterases from Y. pestis, TesB, is a broad-range acyl-CoA thioesterase and is highly conserved within prokaryotes and throughout evolution, sharing sequence similarity with the HIV Nef binding protein ACOT8. Here the expression, purification, crystallization and diffraction of TesB are reported. TesB has been recombinantly expressed and crystallized using the vapour-diffusion hanging-drop technique at pH 7.0 and 290 K. After optimization, crystals diffracted to 2.0 Å resolution at the Australian Synchrotron and belong to the space group P12 1 1 (a = 73.55, b = 170.82, c = 101.98 Å), with eight molecules likely to be present in the asymmetric unit

  6. Pengembangan Sistem E-Learning yang Adaptif untuk Pelatihan dan Tes TOEFL

    Directory of Open Access Journals (Sweden)

    Sofian Arifianto

    2012-09-01

    Full Text Available TOEFL (Test of English as a Foreign Language memiliki 3 bagian jenis soal, Listening Comprehension, Structure & Write Expression dan Reading Comprehension. Untuk saat ini, kebanyakan TOEFL dilakukan dengan manual, yaitu dengan pengerjaan dengan kertas dan membutuhkan waktu beberapa hari agar bisa mengetahui hasil tes tersebut. Dalam artikel ini, LMS Dokeos dikembangkan dengan beberapa perubahan, sehingga didapatkan suatu sistem yang adaptif yang mampu menganalisis kelemahan user dan memberikan soal yang menjadi kelemahan. Dokeos sendiri dibangun dengan bahasa pemrograman PHP&MySQL. Pada sistem ini ada 2 macam tes, Pretest dan posttest. Pretest merupakan suatu latihan TOEFL. Sedangkan Posttest merupakan TOEFL yang sesungguhnya. Posttest bisa dilakukan setelah user lulus dari pretest. Nilai untuk kelulusan dalam  pretest dan posttest ini adalah 477. Pada pretest, sistem bisa menganalisis kelemahan seorang user berdasarkan nilai tes yang telah didapat dari tiap section. Pengguna juga bisa memonitor nilai yang didapatkan pada saat pretest. Sedangkan pada posttest, terdapat pin yang digunakan sebagai hak akses untuk melakukan tes. Dengan begitu, diharapkan aplikasi ini bisa lebih aman dan efisien dalam menghemat waktu dan biaya

  7. High-temperature thermocline TES combining sensible and latent heat - CFD modeling and experimental validation

    Science.gov (United States)

    Zavattoni, Simone A.; Geissbühler, Lukas; Barbato, Maurizio C.; Zanganeh, Giw; Haselbacher, Andreas; Steinfeld, Aldo

    2017-06-01

    The concept of combined sensible/latent heat thermal energy storage (TES) has been exploited to mitigate an intrinsic thermocline TES systems drawback of heat transfer fluid outflow temperature reduction during discharging. In this study, the combined sensible/latent TES prototype under investigation is constituted by a packed bed of rocks and a small amount of encapsulated phase change material (AlSi12) as sensible heat and latent heat sections respectively. The thermo-fluid dynamics behavior of the combined TES prototype was analyzed by means of a computational fluid dynamics approach. Due to the small value of the characteristic vessel-to-particles diameter ratio, the effect of radial void-fraction variation, also known as channeling, was accounted for. Both the sensible and the latent heat sections of the storage were modeled as porous media under the assumption of local thermal non-equilibrium (LTNE). The commercial code ANSYS Fluent 15.0 was used to solve the model's constitutive conservation and transport equations obtaining a fairly good agreement with reference experimental measurements.

  8. Common Bias Readout for TES Array on Scanning Transmission Electron Microscope

    Science.gov (United States)

    Yamamoto, R.; Sakai, K.; Maehisa, K.; Nagayoshi, K.; Hayashi, T.; Muramatsu, H.; Nakashima, Y.; Mitsuda, K.; Yamasaki, N. Y.; Takei, Y.; Hidaka, M.; Nagasawa, S.; Maehata, K.; Hara, T.

    2016-07-01

    A transition edge sensor (TES) microcalorimeter array as an X-ray sensor for a scanning transmission electron microscope system is being developed. The technical challenge of this system is a high count rate of ˜ 5000 counts/second/array. We adopted a 64 pixel array with a parallel readout. Common SQUID bias, and common TES bias are planned to reduce the number of wires and the resources of a room temperature circuit. The reduction rate of wires is 44 % when a 64 pixel array is read out by a common bias of 8 channels. The possible degradation of the energy resolution has been investigated by simulations and experiments. The bias fluctuation effects of a series connection are less than those of a parallel connection. Simple calculations expect that the fluctuations of the common SQUID bias and common TES bias in a series connection are 10^{-7} and 10^{-3}, respectively. We constructed 8 SQUIDs which are connected to 8 TES outputs and a room temperature circuit for common bias readout and evaluated experimentally. Our simulation of crosstalk indicates that at an X-ray event rate of 500 cps/pixel, crosstalk will broaden a monochromatic line by about 0.01 %, or about 1.5 eV at 15 keV. Thus, our design goal of 10 eV energy resolution across the 0.5-15 keV band should be achievable.

  9. A joint data record of tropospheric ozone from Aura-TES and MetOp-IASI

    Directory of Open Access Journals (Sweden)

    H. Oetjen

    2016-08-01

    Full Text Available The Tropospheric Emission Spectrometer (TES on Aura and Infrared Atmospheric Sounding Interferometer (IASI on MetOp-A together provide a time series of 10 years of free-tropospheric ozone with an overlap of 3 years. We characterise the differences between TES and IASI ozone measurements and find that IASI's coarser vertical sensitivity leads to a small (< 5 ppb low bias relative to TES for the free troposphere. The TES-IASI differences are not dependent on season or any other factor and hence the measurements from the two instruments can be merged, after correcting for the offset, in order to study decadal-scale changes in tropospheric ozone. We calculate time series of regional monthly mean ozone in the free troposphere over eastern Asia, the western United States (US, and Europe, carefully accounting for differences in spatial sampling between the instruments. We show that free-tropospheric ozone over Europe and the western US has remained relatively constant over the past decade but that, contrary to expectations, ozone over Asia in recent years does not continue the rapid rate of increase observed from 2004 to 2010.

  10. Pengembangan Instrumen Tes Keterampilan Pemecahan Masalah pada Materi Getaran, Gelombang, dan Bunyi

    Directory of Open Access Journals (Sweden)

    Syarif Rokhmat Hidayat

    2017-12-01

    Full Text Available Abstract Problem-solving is one of the fundamental skills in the 21st century. Students’ problem-solving skill is defined as students’ abilities to use their knowledge to solve the daily life problems. This study main goal is to develop a test instrument of junior high school students’ problem-solving skills on oscillation, wave, and sound concepts. The test items are arranged based on problem-solving skills indicator that proposed by Doctor and Heler (2009, there are problems visualization/description, physics approach, mathematic procedure, and logically conclusion. This study used 4D (define, design, develop, and disseminate model of research and development method. Fifteen test sets are designed based on five problem-solving skill indicators that grouped to each oscillation, wave, and sound sub concept. The result of instrument development shows all test items are valid through Pearson moment correlation coefficient test. Alpha Cronbach test the instrument shows the instrument reliability is 0.88 with the criteria of reliability is high. Based on expert judgment and data collections, the test instruments were well developed and could be used to measure students’ problem-solving skills on oscillation, wave, and sound wave concepts. Keywords: problem solving skills; problem solving skills instrument; oscillation, wave, and sound concept. Abstrak Pemecahan masalah adalah salah satu keterampilan yang penting di abad ke-21. Keterampilan pemecahan masalah siswa adalah kemampuan siswa menggunakan pengetahuan-pengetahuan yang dimilikinya untuk memecahkan masalah dalam kehidupan sehari-hari. Penelitian ini bertujuan mengembangkan instrumen tes untuk mengukur keterampilan pemecahan masalah pada siswa SMP terkait materi getaran, gelombang, dan bunyi. Instrumen tes disusun berdasarkan indikator keterampilan pemecahan masalah yang dikembangkan oleh Doctor dan Heler (2009 yaitu visualisasi/deskripsi masalah, pendekatan fisika, prosedur matematika

  11. RETRIEVAL EVENTS EVALUATION

    International Nuclear Information System (INIS)

    Wilson, T.

    1999-01-01

    The purpose of this analysis is to evaluate impacts to the retrieval concept presented in the Design Analysis ''Retrieval Equipment and Strategy'' (Reference 6), from abnormal events based on Design Basis Events (DBE) and Beyond Design Basis Events (BDBE) as defined in two recent analyses: (1) DBE/Scenario Analysis for Preclosure Repository Subsurface Facilities (Reference 4); and (2) Preliminary Preclosure Design Basis Event Calculations for the Monitored Geologic Repository (Reference 5) The objective of this task is to determine what impacts the DBEs and BDBEs have on the equipment developed for retrieval. The analysis lists potential impacts and recommends changes to be analyzed in subsequent design analyses for developed equipment, or recommend where additional equipment may be needed, to allow retrieval to be performed in all DBE or BDBE situations. This analysis supports License Application design and therefore complies with the requirements of Systems Description Document input criteria comparison as presented in Section 7, Conclusions. In addition, the analysis discusses the impacts associated with not using concrete inverts in the emplacement drifts. The ''Retrieval Equipment and Strategy'' analysis was based on a concrete invert configuration in the emplacement drift. The scope of the analysis, as presented in ''Development Plan for Retrieval Events Evaluation'' (Reference 3) includes evaluation and criteria of the following: Impacts to retrieval from the emplacement drift based on DBE/BDBEs, and changes to the invert configuration for the preclosure period. Impacts to retrieval from the main drifts based on DBE/BDBEs for the preclosure period

  12. Retrieval from semantic memory.

    NARCIS (Netherlands)

    Noordman-Vonk, Wietske

    1977-01-01

    The present study has been concerned with the retrieval of semantic information. Retrieving semantic information is a fundamental process in almost any kind of cognitive behavior. The introduction presented the main experimental paradigms and results found in the literature on semantic memory as

  13. STUDI SIMULASI MENGGUNAKAN FUZZY C-MEANS DALAM MENGKLASIFIKASI KONSTRUK TES

    Directory of Open Access Journals (Sweden)

    Rukli Rukli

    2013-01-01

    Full Text Available Tulisan ini memperkenalkan metode fuzzy c-means dalam mengklasifikasi konstruk tes. Untuk memverifikasi sifat unidimensional suatu tes biasanya menggunakan analisis faktor sebagai bagian dari statistik parametrik dengan beberapa persyaratan yang ketat sedangkan metode fuzzy c-means termasuk metode heuristik yang tidak memerlukan persyaratan yang ketat. Studi simulasi penelitian ini menggunakan dua metode yakni analisis faktor menggunakan program SPSS dan fuzzy c-means menggunakan program Matlab. Data simulasi menggunakan tipe data dikotomi dan politomi yang dibangkitkan lewat prog-ram Microsoft Office Excel dengan desain 2 kategori, yakni: tiga butir soal dengan banyak peserta tes 10, dan 30 butir soal dengan banyak peserta tes 100. Hasil simulasi menunjukkan bahwa metode fuzzy c-means lebih memberikan gambaran pengelompokan secara deskriptif dan dinamis pada semua desain yang telah dibuat dalam memverifikasi unidimensional pada suatu tes. Kata kunci: fuzzy c-means, analisis faktor, unidimensional _____________________________________________________________ SIMULATION STUDY USING FUZZY C-MEANS FOR CLASIFYING TEST CONSTRUCTION Abstract This paper introduces the fuzzy c-means method for classifying the test constructs. To verify the unidimensional a test typically uses factor analysis as part of parametric statistics with some strict requirements, while fuzzy c-means methods including method heuristic that do not require strict require-ments. Simulation comparison between the method of factor analysis using SPSS program and fuzzy c-means methods using Matlab. Simulation data using data type dichotomy and politomus generated through Microsoft Office Excel programs each with a number of 3 items using the number of participants 10 tests, while the number of 30 test items using the number as many as 100 participants. The simulation results show that the fuzzy c-means method provides a more descriptive and dyna-mic grouping of all the designs that

  14. The Trypanosoma cruzi satellite DNA OligoC-TesT and Trypanosoma cruzi kinetoplast DNA OligoC-TesT for diagnosis of Chagas disease: a multi-cohort comparative evaluation study.

    Directory of Open Access Journals (Sweden)

    Koen De Winne

    Full Text Available BACKGROUND: The Trypanosoma cruzi satellite DNA (satDNA OligoC-TesT is a standardised PCR format for diagnosis of Chagas disease. The sensitivity of the test is lower for discrete typing unit (DTU TcI than for TcII-VI and the test has not been evaluated in chronic Chagas disease patients. METHODOLOGY/PRINCIPAL FINDINGS: We developed a new prototype of the OligoC-TesT based on kinetoplast DNA (kDNA detection. We evaluated the satDNA and kDNA OligoC-TesTs in a multi-cohort study with 187 chronic Chagas patients and 88 healthy endemic controls recruited in Argentina, Chile and Spain and 26 diseased non-endemic controls from D.R. Congo and Sudan. All specimens were tested in duplicate. The overall specificity in the controls was 99.1% (95% CI 95.2%-99.8% for the satDNA OligoC-TesT and 97.4% (95% CI 92.6%-99.1% for the kDNA OligoC-TesT. The overall sensitivity in the patients was 67.9% (95% CI 60.9%-74.2% for the satDNA OligoC-TesT and 79.1% (95% CI 72.8%-84.4% for the kDNA OligoC-Test. CONCLUSIONS/SIGNIFICANCE: Specificities of the two T. cruzi OligoC-TesT prototypes are high on non-endemic and endemic controls. Sensitivities are moderate but significantly (p = 0.0004 higher for the kDNA OligoC-TesT compared to the satDNA OligoC-TesT.

  15. The Trypanosoma cruzi Satellite DNA OligoC-TesT and Trypanosoma cruzi Kinetoplast DNA OligoC-TesT for Diagnosis of Chagas Disease: A Multi-cohort Comparative Evaluation Study

    Science.gov (United States)

    De Winne, Koen; Büscher, Philippe; Luquetti, Alejandro O.; Tavares, Suelene B. N.; Oliveira, Rodrigo A.; Solari, Aldo; Zulantay, Ines; Apt, Werner; Diosque, Patricio; Monje Rumi, Mercedes; Gironès, Nuria; Fresno, Manuel; Lopez-Velez, Rogelio; Perez-Molina, José A.; Monge-Maillo, Begoña; Garcia, Lineth; Deborggraeve, Stijn

    2014-01-01

    Background The Trypanosoma cruzi satellite DNA (satDNA) OligoC-TesT is a standardised PCR format for diagnosis of Chagas disease. The sensitivity of the test is lower for discrete typing unit (DTU) TcI than for TcII-VI and the test has not been evaluated in chronic Chagas disease patients. Methodology/Principal Findings We developed a new prototype of the OligoC-TesT based on kinetoplast DNA (kDNA) detection. We evaluated the satDNA and kDNA OligoC-TesTs in a multi-cohort study with 187 chronic Chagas patients and 88 healthy endemic controls recruited in Argentina, Chile and Spain and 26 diseased non-endemic controls from D.R. Congo and Sudan. All specimens were tested in duplicate. The overall specificity in the controls was 99.1% (95% CI 95.2%–99.8%) for the satDNA OligoC-TesT and 97.4% (95% CI 92.6%–99.1%) for the kDNA OligoC-TesT. The overall sensitivity in the patients was 67.9% (95% CI 60.9%–74.2%) for the satDNA OligoC-TesT and 79.1% (95% CI 72.8%–84.4%) for the kDNA OligoC-Test. Conclusions/Significance Specificities of the two T. cruzi OligoC-TesT prototypes are high on non-endemic and endemic controls. Sensitivities are moderate but significantly (p = 0.0004) higher for the kDNA OligoC-TesT compared to the satDNA OligoC-TesT. PMID:24392177

  16. Waste Minimization Study on Pyrochemical Reprocessing Processes

    International Nuclear Information System (INIS)

    Boussier, H.; Conocar, O.; Lacquement, J.

    2006-01-01

    Ideally a new pyro-process should not generate more waste, and should be at least as safe and cost effective as the hydrometallurgical processes currently implemented at industrial scale. This paper describes the thought process, the methodology and some results obtained by process integration studies to devise potential pyro-processes and to assess their capability of achieving this challenging objective. As example the assessment of a process based on salt/metal reductive extraction, designed for the reprocessing of Generation IV carbide spent fuels, is developed. Salt/metal reductive extraction uses the capability of some metals, aluminum in this case, to selectively reduce actinide fluorides previously dissolved in a fluoride salt bath. The reduced actinides enter the metal phase from which they are subsequently recovered; the fission products remain in the salt phase. In fact, the process is not so simple, as it requires upstream and downstream subsidiary steps. All these process steps generate secondary waste flows representing sources of actinide leakage and/or FP discharge. In aqueous processes the main solvent (nitric acid solution) has a low boiling point and evaporate easily or can be removed by distillation, thereby leaving limited flow containing the dissolved substance behind to be incorporated in a confinement matrix. From the point of view of waste generation, one main handicap of molten salt processes, is that the saline phase (fluoride in our case) used as solvent is of same nature than the solutes (radionuclides fluorides) and has a quite high boiling point. So it is not so easy, than it is with aqueous solutions, to separate solvent and solutes in order to confine only radioactive material and limit the final waste flows. Starting from the initial block diagram devised two years ago, the paper shows how process integration studies were able to propose process fittings which lead to a reduction of the waste variety and flows leading at an 'ideal

  17. Assessment of Mars Atmospheric Temperature Retrievals from the Thermal Emission Spectrometer Radiances

    Science.gov (United States)

    Hoffman, Matthew J.; Eluszkiewicz, Janusz; Weisenstein, Deborah; Uymin, Gennady; Moncet, Jean-Luc

    2012-01-01

    Motivated by the needs of Mars data assimilation. particularly quantification of measurement errors and generation of averaging kernels. we have evaluated atmospheric temperature retrievals from Mars Global Surveyor (MGS) Thermal Emission Spectrometer (TES) radiances. Multiple sets of retrievals have been considered in this study; (1) retrievals available from the Planetary Data System (PDS), (2) retrievals based on variants of the retrieval algorithm used to generate the PDS retrievals, and (3) retrievals produced using the Mars 1-Dimensional Retrieval (M1R) algorithm based on the Optimal Spectral Sampling (OSS ) forward model. The retrieved temperature profiles are compared to the MGS Radio Science (RS) temperature profiles. For the samples tested, the M1R temperature profiles can be made to agree within 2 K with the RS temperature profiles, but only after tuning the prior and error statistics. Use of a global prior that does not take into account the seasonal dependence leads errors of up 6 K. In polar samples. errors relative to the RS temperature profiles are even larger. In these samples, the PDS temperature profiles also exhibit a poor fit with RS temperatures. This fit is worse than reported in previous studies, indicating that the lack of fit is due to a bias correction to TES radiances implemented after 2004. To explain the differences between the PDS and Ml R temperatures, the algorithms are compared directly, with the OSS forward model inserted into the PDS algorithm. Factors such as the filtering parameter, the use of linear versus nonlinear constrained inversion, and the choice of the forward model, are found to contribute heavily to the differences in the temperature profiles retrieved in the polar regions, resulting in uncertainties of up to 6 K. Even outside the poles, changes in the a priori statistics result in different profile shapes which all fit the radiances within the specified error. The importance of the a priori statistics prevents

  18. Interim guidance for the safe transport of reprocessed uranium

    International Nuclear Information System (INIS)

    1994-06-01

    Increasingly reprocessed uranium is being used for the fabrication of nuclear fuel elements. Different intermediate reprocessing steps are carried out at different locations. Therefore, transportation of uranium material is necessary. Due to the difference in isotope composition of reprocessed uranium then unirradiated uranium a doubt is casted on the presumption that packages used for the transport of unirradiated uranium are automatically suitable for reprocessed uranium compounds. The Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM) recommended that the issue be reviewed by consultants and that a document be developed that would give guidance to users of the Regulations. This TECDOC is the result of the endeavors of the experts convened at two Consultants Services meetings. It contains guidance on the provisions in the current Regulations as well as proposals for changes to the new Revised Edition whose publication is planned for 1996. This document demonstrates that under the present Transport Regulations it is possible in most cases to ship reprocessed uranium compounds in the same packages as unirradiated uranium compounds. In few cases a more stringent package type is required. 8 refs, 22 figs, 19 tabs

  19. Reprocessing RTR fuel in the La Hague plants

    International Nuclear Information System (INIS)

    Thomasson, J.; Drain, F.; David, A.

    2001-01-01

    Starting in 2006, research reactors operators will be fully responsible for the back-end management of their spent fuel. It appears that the only solution for this management is treatment-conditioning, which could be done at the La Hague reprocessing complex in France. The fissile material can be separated in the reprocessing plants and the final waste can be encapsulated in a matrix adapted to its potential hazards. RTR reprocessing at La Hague would require some modifications, since the plant had been primarily designed to reprocess fuel from light water reactors. Many provisions have been taken at the plant design stage, however, and the modifications would be feasible even during active operations, as was done from 1993 to 1995 when a new liquid waste management was implemented, and when one of the two vitrification facilities was improved. To achieve RTR back-end management, COGEMA and its partners are also conducting R and D to define a new generation of LEU fuel with performance characteristics approximating those of HEU fuel. This new-generation fuel would be easier to reprocess. (author)

  20. Technology development of fast reactor fuel reprocessing technology in India

    International Nuclear Information System (INIS)

    Natarajan, R.; Raj, Baldev

    2009-01-01

    India is committed to the large scale induction of fast breeder reactors beginning with the construction of 500 MWe Prototype Fast Breeder Reactor, PFBR. Closed fuel cycle is a prerequisite for the success of the fast reactors to reduce the external dependence of the fuel. In the Indian context, spent fuel reprocessing, with as low as possible out of pile fissile inventory, is another important requirement for increasing the share in power generation through nuclear route as early as possible. The development of this complex technology is being carried out in four phases, the first phase being the developmental phase, in which major R and D issues are addressed, while the second phase is the design, construction and operation of a pilot plant, called CORAL (COmpact Reprocessing facility for Advanced fuels in Lead shielded cell. The third phase is the construction and operation of Demonstration of Fast Reactor Fuel Reprocessing Plant (DFRP) which will provide experience in fast reactor fuel reprocessing with high availability factors and plant throughput. The design, construction and operation of the commercial plant (FRP) for reprocessing of PFBR fuel is the fourth phase, which will provide the requisite confidence for the large scale induction of fast reactors

  1. Radiological impact of emissions from reprocessing plants during normal operation

    International Nuclear Information System (INIS)

    Bonka, H.; Gruendler, D.; Hesel, D.; Muenster, M.; Schmidtlein, P.; Suender, B.

    1977-01-01

    When comparing the expected radiation exposure due to emissions from reprocessing plants with those from nuclear power plants it can be seen that the emissions from reprocessing plants contribute much more to the radiation exposure of the population than those from nuclear power plants. In the vicinity of reprocessing plants the highest contributions to the radiation exposure of the population are delivered by the following radionuclides: T, C 14 , Kr 85 , Sr 90 , Ru 106 , I 129 , Cs 134 , Cs 137 and Ce 144 as will as the Pu- and Cm-isotopes. Among these nuclides T, C 14 , Kr 85 und I 129 are globally distributed. While for T the contribution to the collective dose due to globally distributed T is small in comparison with the first pass exposure, the global contribution predominates for C 14 and Kr 85 . If an integration time of less than 10 5 years is considered, the contribution due to first pass exposure predominates for I 129 . When taking the radiation protection of the population into consideration, it seems sensible to retain 10% of T, 80 to 90% of C 14 , 90% of Kr 85 and 99,5% of I 129 in reprocessing plants and dispose of this material in a controlled manner. The fraction of the aerosols released should be about 10 -9 . Considering the global effects and the increasing number of nuclear power plants and reprocessing plants, an international agreement should be reached on these matters. (orig.) [de

  2. Cost analysis of the US spent nuclear fuel reprocessing facility

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, E.A.; Deinert, M.R. [Department of Mechanical Engineering, University of Texas, Austin TX (United States); Cady, K.B. [Department of Theoretical and Applied Mechanics, Cornell University, Ithaca NY (United States)

    2009-09-15

    The US Department of Energy is actively seeking ways in which to delay or obviate the need for additional nuclear waste repositories beyond Yucca Mountain. All of the realistic approaches require the reprocessing of spent nuclear fuel. However, the US currently lacks the infrastructure to do this and the costs of building and operating the required facilities are poorly established. Recent studies have also suggested that there is a financial advantage to delaying the deployment of such facilities. We consider a system of government owned reprocessing plants, each with a 40 year service life, that would reprocess spent nuclear fuel generated between 2010 and 2100. Using published data for the component costs, and a social discount rate appropriate for intergenerational analyses, we establish the unit cost for reprocessing and show that it increases slightly if deployment of infrastructure is delayed by a decade. The analysis indicates that achieving higher spent fuel discharge burnup is the most important pathway to reducing the overall cost of reprocessing. The analysis also suggests that a nuclear power production fee would be a way for the US government to recover the costs in a manner that is relatively insensitive to discount and nuclear power growth rates. (author)

  3. Reprocessing RTR fuel in the La Hague plants

    Energy Technology Data Exchange (ETDEWEB)

    Thomasson, J. [Cogema, F-78140 Velizy (France); Drain, F.; David, A. [SGN, F-78182 Saint Quentin en Yvelines (France)

    2001-07-01

    Starting in 2006, research reactors operators will be fully responsible for the back-end management of their spent fuel. It appears that the only solution for this management is treatment-conditioning, which could be done at the La Hague reprocessing complex in France. The fissile material can be separated in the reprocessing plants and the final waste can be encapsulated in a matrix adapted to its potential hazards. RTR reprocessing at La Hague would require some modifications, since the plant had been primarily designed to reprocess fuel from light water reactors. Many provisions have been taken at the plant design stage, however, and the modifications would be feasible even during active operations, as was done from 1993 to 1995 when a new liquid waste management was implemented, and when one of the two vitrification facilities was improved. To achieve RTR back-end management, COGEMA and its partners are also conducting R and D to define a new generation of LEU fuel with performance characteristics approximating those of HEU fuel. This new-generation fuel would be easier to reprocess. (author)

  4. Reprocessing RTR fuel in the La Hague plants

    Energy Technology Data Exchange (ETDEWEB)

    Thomasson, J. [Cogema, 78 - Velizy Villacoublay (France); Drain, F.; David, A. [SGN, 78 - Saint Quentin en Yveline (France)

    2001-07-01

    Starting in 2006, research reactors operators will be fully responsible for their research and testing reactors spent fuel back-end management. It appears that the only solution for this management is treatment-conditioning, which could be done at the La Hague reprocessing complex in France. The fissile material can be separated in the reprocessing plants and the final waste can be encapsulated in a matrix adapted to its potential hazards. RTR reprocessing at La Hague would require some modifications, since the plant had been primarily designed to reprocess fuel from light water reactors. Many provisions have been taken at the plant design stage, however, and the modifications would be feasible even during active operations, as was done from 1993 to 1995 when a new liquid waste management was implemented, and when one of the two vitrification facilities was improved. To achieve RTR back-end management, COGEMA and its partners are also conducting R and D to define a new generation of LEU fuel with performance characteristics approximating those of HEU fuel. This new-generation fuel would be easier to reprocess. (author)

  5. Spent fuel reprocessing past experience and future prospects

    International Nuclear Information System (INIS)

    Megy, J.

    1983-09-01

    A large experience has been gathered from the early fifties till now in the field of spent fuel reprocessing. As the main efforts in the world have been made for developping the reactors and the fuel fabrication industry to feed them, the spent fuel reprocessing activities came later and have not yet reached the industrial maturity existing to day for plants such as PWRs. But in the principal nuclear countries spent fuel reprocessing is to day considered as a necessity with two simultaneous targets: 1. Recovering the valuable materials, uranium and plutonium. 2. Conditionning the radioactive wastes to ensure safe definitive storage. The paper reviews the main steps: 1. Reprocessing for thermal reactor fuels: large plants are already operating or in construction, but in parallel a large effort of R and D is still under way for improvements. 2. The development of fast breeder plants implies associated fuel reprocessing facilities: pilot plants have demonstrated the closing of the cycle. The main difficulties encountered will be examined and particularly the importance of taking into account the problems of effluents processing and wastes storage [fr

  6. Fabrication of close-packed TES microcalorimeter arrays using superconducting molybdenum/gold transition-edge sensors

    Science.gov (United States)

    Finkbeiner, F. M.; Brekosky, R. P.; Chervenak, J. A.; Figueroa-Feliciano, E.; Li, M. J.; Lindeman, M. A.; Stahle, C. K.; Stahle, C. M.; Tralshawala, N.

    2002-02-01

    We present an overview of our efforts in fabricating Transition-Edge Sensor (TES) microcalorimeter arrays for use in astronomical x-ray spectroscopy. Two distinct types of array schemes are currently pursued: 5×5 single pixel TES array where each pixel is a TES microcalorimeter, and Position-Sensing TES (PoST) array. In the latter, a row of 7 or 15 thermally-linked absorber pixels is read out by two TES at its ends. Both schemes employ superconducting Mo/Au bilayers as the TES. The TES are placed on silicon nitride membranes for thermal isolation from the structural frame. The silicon nitride membranes are prepared by a Deep Reactive Ion Etch (DRIE) process into a silicon wafer. In order to achieve the concept of closely packed arrays without decreasing its structural and functional integrity, we have already developed the technology to fabricate arrays of cantilevered pixel-sized absorbers and slit membranes in silicon nitride films. Furthermore, we have started to investigate ultra-low resistance through-wafer micro-vias to bring the electrical contact out to the back of a wafer. .

  7. Retrieval options study

    Energy Technology Data Exchange (ETDEWEB)

    1980-03-01

    This Retrieval Options Study is part of the systems analysis activities of the Office of Nuclear Waste Isolation to develop the scientific and technological bases for radioactive waste repositories in various geologic media. The study considers two waste forms, high level waste and spent fuel, and defines various classes of waste retrieval and recovery. A methodology and data base are developed which allow the relative evaluation of retrieval and recovery costs and the following technical criteria: safety; technical feasibility; ease of retrieval; probable intact retrieval time; safeguards; monitoring; criticality; and licensability. A total of 505 repository options are defined and the cost and technical criteria evaluated utilizing a combination of facts and engineering judgments. The repositories evaluated are selected combinations of the following parameters: Geologic Media (salt, granite, basalt, shale); Retrieval Time after Emplacement (5 and 25 years); Emplacement Design (nominal hole, large hole, carbon steel canister, corrosion resistant canister, backfill in hole, nominal sleeves, thick wall sleeves); Emplacement Configuration (single vertical, multiple vertical, single horizontal, multiple horizontal, vaults; Thermal Considerations; (normal design, reduced density, once-through ventilation, recirculated ventilation); Room Backfill; (none, run-of-mine, early, 5 year delay, 25 year delay, decommissioned); and Rate of Retrieval; (same as emplacement, variably slower depending on repository/canister condition).

  8. Retrieval options study

    International Nuclear Information System (INIS)

    1980-03-01

    This Retrieval Options Study is part of the systems analysis activities of the Office of Nuclear Waste Isolation to develop the scientific and technological bases for radioactive waste repositories in various geologic media. The study considers two waste forms, high level waste and spent fuel, and defines various classes of waste retrieval and recovery. A methodology and data base are developed which allow the relative evaluation of retrieval and recovery costs and the following technical criteria: safety; technical feasibility; ease of retrieval; probable intact retrieval time; safeguards; monitoring; criticality; and licensability. A total of 505 repository options are defined and the cost and technical criteria evaluated utilizing a combination of facts and engineering judgments. The repositories evaluated are selected combinations of the following parameters: Geologic Media (salt, granite, basalt, shale); Retrieval Time after Emplacement (5 and 25 years); Emplacement Design (nominal hole, large hole, carbon steel canister, corrosion resistant canister, backfill in hole, nominal sleeves, thick wall sleeves); Emplacement Configuration (single vertical, multiple vertical, single horizontal, multiple horizontal, vaults; Thermal Considerations; (normal design, reduced density, once-through ventilation, recirculated ventilation); Room Backfill; (none, run-of-mine, early, 5 year delay, 25 year delay, decommissioned); and Rate of Retrieval;

  9. Storage fee analysis for a retrievable surface storage facility

    International Nuclear Information System (INIS)

    Field, B.B.; Rosnick, C.K.

    1973-12-01

    Conceptual design studies are in progress for a Water Basin Concept (WBC) and an alternative Sealed Storage Cask Concept (SSCC) of a Retrievable Surface Storage Facility (RSSF) intended as a Federal government facility for storing high-level radioactive wastes until a permanent disposal method is established. The RSSF will be a man-made facility with a design life of at least 100 y, and will have capacity to store all of the high-level waste from the reprocessing of nuclear power plant spent fuels generated by the industry through the year 2000. This report is a basic version of ARH-2746, ''Retrievable Surface Storage Facility, Water Basin Concept, User Charge Analysis.'' It is concerned with the issue of establishing a fee to cover the cost of storing nuclear wastes both in the RSSF and at the subsequent disposal facility. (U.S.)

  10. Topological Aspects of Information Retrieval.

    Science.gov (United States)

    Egghe, Leo; Rousseau, Ronald

    1998-01-01

    Discusses topological aspects of theoretical information retrieval, including retrieval topology; similarity topology; pseudo-metric topology; document spaces as topological spaces; Boolean information retrieval as a subsystem of any topological system; and proofs of theorems. (LRW)

  11. Fast reactor system factors affecting reprocessing plant design

    International Nuclear Information System (INIS)

    Allardice, R.H.; Pugh, O.

    1982-01-01

    The introduction of a commercial fast reactor electricity generating system is very dependent on the availability of an efficient nuclear fuel cycle. Selection of fuel element constructional materials, the fuel element design approach and the reactor operation have a significant influence on the technical feasibility and efficiency of the reprocessing and waste management plants. Therefore the fast reactor processing plant requires liaison between many design teams -reactor, fuel design, reprocessing and waste management -often with different disciplines and conflicting objectives if taken in isolation and an optimised approach to determining several key parameters. A number of these parameters are identified and the design approach discussed in the context of the reprocessing plant. Radiological safety and its impact on design is also briefly discussed. (author)

  12. Status of the decommissioning program of the Eurochemic reprocessing plant

    International Nuclear Information System (INIS)

    Detilleux, E.J.

    1976-01-01

    Reprocessing operations at the Eurochemic demonstration plant stopped in December 1974, after 8 years of operation. Immediately thereafter, cleaning and decontamination were begun as the first phase of the decommissioning program. The facility and reprocessing program are described to indicate the magnitude of the problem, and the requirements of the local authorities are reviewed. The technical decommissioning program consists of several phases: (1) plant cleaning and rinsing, (2) establishment of the final fissile-material balance, (3) plant decontamination for access to process equipment, (4) equipment dismantling, and (5) conditioning and storage of newly generated wastes. The two first phases have been completed, and the third one is nearing completion. Some dismantling has been performed, including the plutonium dioxide production unit. Waste-conditioning and surface-storage facilities have been built to meet the dismantling requirements. Since reprocessing may be resumed in the future, decontamination has been performed with ''smooth'' reagents to limit corrosion and dismantling has been limited to subfacilities

  13. Environmental assessment for Breeder Reprocessing Engineering Test (BRET): Revision 1

    International Nuclear Information System (INIS)

    Lerch, R.E.

    1989-03-01

    This Environmental Assessment (EA) is for the proposed installation and operation of an integrated breeder fuel reprocessing test system in the shielded cells of the Fuels and Materials Examination Facility (FMEF) at Hanford and the associated modifications to the FMEF to accommodate BRET. These modifications would begin in FY-1986 subject to Congressional authorization. Hot operations would be scheduled to start in the early 1990's. The system, called the Breeder Reprocessing Engineering Test (BRET), is being designed to provide a test capability for developing the demonstrating fuel reprocessing, remote maintenance, and safeguards technologies for breeder reactor fuels. This EA describes (1) the action being proposed, (2) the existing environment which would be affected, (3) the potential environmental impacts from normal operations and severe accidents from the proposed action, (4) potential conflicts with federal, state, regional, and/or local plans for the area, and (5) environmental implications of alternatives considered to the proposed action. 41 refs., 10 figs., 31 tabs

  14. Consolidated Reprocessing Progam. Quarterly progress report ending February 28, 1979

    International Nuclear Information System (INIS)

    1979-03-01

    This publication continues the quarterly series presenting results of work performed under the Consolidated Reprocessing Program at General Atomic Company. Results of work on this program prior to June 1974 were included in a quarterly series on the HTGR Base Program. The work reported includes the development of unit processes and equipment for reprocessing of High-Temperature Gas-Cooled Reactor (HTGR) fuel, the design and development of an integrated pilot line to demonstrate the head end of HTGR reprocessing using unirradiated fuel materials, and design work in support of Hot Engineering Tests (HET). Work is also described on trade-off studies concerning the required design of facilities and equipment for the large-scale recycle of HTGR fuels in order to guide the development activities for HTGR fuel recycle

  15. Analytical chemistry needs for nuclear safeguards in nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Hakkila, E.A.

    1977-01-01

    A fuel reprocessing plant designed to process 1500 tons of light water reactor fuel per year will recover 15 tons of Pu during that time, or approximately 40 to 50 kg of Pu per day. Conventional nuclear safeguards accountability has relied on batch accounting at the head and tail ends of the reprocessing plant with semi-annual plant cleanout to determine in-process holdup. An alternative proposed safeguards system relies on dynamic material accounting whereby in-line NDA and conventional analytical techniques provide indications on a daily basis of SNM transfers into the system and information of Pu holdup within the system. Some of the analytical requirements and problems for dynamic materials accounting in a nuclear fuel reprocessing plant are described. Some suggestions for further development will be proposed

  16. Development of exhaust air filters for reprocessing plants

    International Nuclear Information System (INIS)

    Furrer, J.; Kaempffer, R.; Jannakos, K.; Apenberg, W.

    1975-01-01

    Investigations of the iodine loading capacity of highly impregnated iodine sorption material (AC 6,120/H 1 ) for the GWA-filters (GWA: reprocessing plant for 1,500 metric tons per year of uranium) have been continued for low NO 2 -contents of the simulated dissolver offgas from GWA. When fully loading AC 6,120/H 1 , a conversion to silver iodides of Ag + of the impregnation of about 80% was reached in experiments with 1% NO 2 in the carrier gas. Despite the consumption of a substantial portion of the impregnation removal efficiencies > 99.99% were measured for a bed depth corresponding to a GWA filter stage. The test facility allowing to examine the behavior and the capacity of the AC 6,120/H 1 iodine sorption material under actual conditions at SAP Marcoule (reprocessing plant) has been completed except for installation in the reprocessing plant. (orig.) [de

  17. Reprocessing decision: a study in policymaking under uncertainty

    International Nuclear Information System (INIS)

    Heising, C.D.

    1978-01-01

    The U.S. reprocessing decision is examined in this thesis. Decision analysis is applied to develop a rational framework for the assessment of policy alternatives. Benefits and costs for each alternative are evaluated and compared in dollar terms to determine the optimal decision. A fuel cycle simulation model is constructed to assess the economic value of reprocessing light water reactor (LWR) spent fuel and recycling plutonium. In addition, a dynamic fuel substitution model is used to estimate the economic effects of the reprocessing decision's influence on the introduction date of the liquid metal fast breeder reactor (LMFBR). Risks estimated in dollar terms for comparison with the economic values include those related to health, the environment and safety, nuclear theft and sabotage, and nuclear proliferation

  18. Equipment specifications for an electrochemical fuel reprocessing plant

    International Nuclear Information System (INIS)

    Hemphill, Kevin P.

    2010-01-01

    Electrochemical reprocessing is a technique used to chemically separate and dissolve the components of spent nuclear fuel, in order to produce new metal fuel. There are several different variations to electrochemical reprocessing. These variations are accounted for by both the production of different types of spent nuclear fuel, as well as different states and organizations doing research in the field. For this electrochemical reprocessing plant, the spent fuel will be in the metallurgical form, a product of fast breeder reactors, which are used in many nuclear power plants. The equipment line for this process is divided into two main categories, the fuel refining equipment and the fuel fabrication equipment. The fuel refining equipment is responsible for separating out the plutonium and uranium together, while getting rid of the minor transuranic elements and fission products. The fuel fabrication equipment will then convert this plutonium and uranium mixture into readily usable metal fuel.

  19. Fuel reprocessing at THORP: profitability and public liabilities

    International Nuclear Information System (INIS)

    Berkhout, F.

    1992-01-01

    Since the economics of British Nuclear Fuels Limited's (BNFL) Thermal Oxide Reprocessing Plant (THORP) were analysed in an earlier report, a number of domestic and international developments have affected the prospects for THORP. The present report outlines these changes, and analyses their implications for the profits and public liabilities associated with the project. Timing is of some significance because once THORP becomes radioactive (planned to occur in March 1993) the bill for decommissioning the plant will rise from a trivial sum to a very large one - Pound 900 million (1992 prices) in BNFL's own estimates. The report begins with a brief outline of reprocessing and the THORP project. It then examines the market prospects for reprocessing beyond THORP's first ten years and revises BNFL's own projections. It then considers the potential profitability of THORP in relation to various possible cost increases and finally outlines the possible implications of different THORP scenarios for the public purse. (author)

  20. Remote maintenance ''lessons learned'' on prototypical reprocessing equipment

    International Nuclear Information System (INIS)

    Kring, C.T.; Schrock, S.L.

    1990-01-01

    Hardware representative of essentially every major equipment item necessary for reprocessing breeder reactor nuclear fuel has been installed and tested for remote maintainability. This testing took place in a cold mock-up of a remotely maintained hot cell operated by the Consolidated Fuel Reprocessing Program (CFRP) within the Fuel Recycle Division at Oak Ridge National Laboratory (ORNL). The reprocessing equipment tested included a Disassembly System, a Shear System, a Dissolver System, an Automated Sampler System, removable Equipment Racks on which various chemical process equipment items were mounted, and an advanced servomanipulator (ASM). These equipment items were disassembled and reassembled remotely by using the remote handling systems that are available within the cold mock-up area. This paper summarizes the ''lessons learned'' as a result of the numerous maintenance activities associated with each of these equipment items. 4 refs., 3 figs., 1 tab

  1. ERDA activities related to reprocessing and plutonium recycle

    International Nuclear Information System (INIS)

    Spurgeon, D.R.

    1977-01-01

    ERDA has redirected its program in support of the LWR fuel cycle from one emphasizing the commercialization of existing fuel cycle technology to a broader based assessment of alternative fuel cycle concepts with the emphasis on safeguardability and avoidance of proliferation risks. As part of this program, ERDA will evaluate a number of possible technical and institutional options to reduce proliferation risks. ERDA will continue its current program of LWR fuel reprocessing R and D with added emphasis on improved safeguards capability as well as the applicability of conventional reprocessing technology to large multinational plants. These activities and supporting design studies will provide the basis for a decision regarding the design of an optimized system for the management of spent LWR fuel. Such a system would provide a model for the development of future domestic and foreign facilities and programs. A recently completed ERDA study of the benefits of LWR reprocessing and recycle would also be expected to be factored into such a decision. The study concluded that based on currently available data, recycle of uranium and plutonium in LWR's is attractive from the standpoint of economics and resource utilization relative to the discarding of spent fuel. The LWR reprocessing/recycle picture today is clouded by several unresolved policy issues. These include the need for adequate spent fuel storage capacity for both domestic and foreign reactors; the possibility of foreign reprocessing of U.S. produced fuel; the possibility of the disposal of foreign fuel in the U.S.; the possible need to dispose of wastes generated by multinational reprocessing plants; and finally, determination of the optimum balance between recycling recovered plutonium and saving it for the breeder

  2. Optimizing Endoscope Reprocessing Resources Via Process Flow Queuing Analysis.

    Science.gov (United States)

    Seelen, Mark T; Friend, Tynan H; Levine, Wilton C

    2018-05-04

    The Massachusetts General Hospital (MGH) is merging its older endoscope processing facilities into a single new facility that will enable high-level disinfection of endoscopes for both the ORs and Endoscopy Suite, leveraging economies of scale for improved patient care and optimal use of resources. Finalized resource planning was necessary for the merging of facilities to optimize staffing and make final equipment selections to support the nearly 33,000 annual endoscopy cases. To accomplish this, we employed operations management methodologies, analyzing the physical process flow of scopes throughout the existing Endoscopy Suite and ORs and mapping the future state capacity of the new reprocessing facility. Further, our analysis required the incorporation of historical case and reprocessing volumes in a multi-server queuing model to identify any potential wait times as a result of the new reprocessing cycle. We also performed sensitivity analysis to understand the impact of future case volume growth. We found that our future-state reprocessing facility, given planned capital expenditures for automated endoscope reprocessors (AERs) and pre-processing sinks, could easily accommodate current scope volume well within the necessary pre-cleaning-to-sink reprocessing time limit recommended by manufacturers. Further, in its current planned state, our model suggested that the future endoscope reprocessing suite at MGH could support an increase in volume of at least 90% over the next several years. Our work suggests that with simple mathematical analysis of historic case data, significant changes to a complex perioperative environment can be made with ease while keeping patient safety as the top priority.

  3. Fuel reprocessing and waste management in the UK

    International Nuclear Information System (INIS)

    Heafield, W.; Griffin, N.L.

    1994-01-01

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

  4. Combined orbits and clocks from IGS second reprocessing

    Science.gov (United States)

    Griffiths, Jake

    2018-05-01

    The Analysis Centers (ACs) of the International GNSS Service (IGS) have reprocessed a large global network of GPS tracking data from 1994.0 until 2014.0 or later. Each AC product time series was extended uniformly till early 2015 using their weekly operational IGS contributions so that the complete combined product set covers GPS weeks 730 through 1831. Three ACs also included GLONASS data from as early as 2002 but that was insufficient to permit combined GLONASS products. The reprocessed terrestrial frame combination procedures and results have been reported already, and those were incorporated into the ITRF2014 multi-technique global frame released in 2016. This paper describes the orbit and clock submissions and their multi-AC combinations and assessments. These were released to users in early 2017 in time for the adoption of IGS14 for generating the operational IGS products. While the reprocessing goal was to enable homogeneous modeling, consistent with the current operational procedures, to be applied retrospectively to the full history of observation data in order to achieve a more suitable reference for geophysical studies, that objective has only been partially achieved. Ongoing AC analysis changes and a lack of full participation limit the consistency and precision of the finished IG2 products. Quantitative internal measures indicate that the reprocessed orbits are somewhat less precise than current operational orbits or even the later orbits from the first IGS reprocessing campaign. That is even more apparent for the clocks where a lack of robust AC participation means that it was only possible to form combined 5-min clocks but not the 30-s satellite clocks published operationally. Therefore, retrospective precise point positioning solutions by users are not recommended using the orbits and clocks. Nevertheless, the orbits do support long-term stable user solutions when used with network processing with either double differencing or explicit clock

  5. Report of the LASCAR forum: Large scale reprocessing plant safeguards

    International Nuclear Information System (INIS)

    1992-01-01

    This report has been prepared to provide information on the studies which were carried out from 1988 to 1992 under the auspices of the multinational forum known as Large Scale Reprocessing Plant Safeguards (LASCAR) on safeguards for four large scale reprocessing plants operated or planned to be operated in the 1990s. The report summarizes all of the essential results of these studies. The participants in LASCAR were from France, Germany, Japan, the United Kingdom, the United States of America, the Commission of the European Communities - Euratom, and the International Atomic Energy Agency

  6. Gaseous isotope correlation technique for safeguards at reprocessing facilities

    International Nuclear Information System (INIS)

    Ohkubo, Michiaki.

    1988-03-01

    The isotope correlation technique based on gaseous stable fission products can be used as a means of verifying the input measurement to fuel reprocessing plants. This paper reviews the theoretical background of the gaseous fission product isotope correlation technique. The correlations considered are those between burnup and various isotopic ratios of Kr and Xe nuclides. The feasibility of gaseous ICT application to Pu input accountancy of reprocessing facilities is also discussed. The technique offers the possibility of in situ measurement verification by the inspector. (author). 16 refs, 7 figs

  7. Head-end reprocessing equipment remote maintenance demonstration

    International Nuclear Information System (INIS)

    Evans, J.H.; Metz, C.F. III.

    1989-01-01

    Prototype equipment for reprocessing breeder reactor nuclear fuel was installed in the Remote Operation and Maintenance Demonstration (ROMD) area of the Consolidated Fuel Reprocessing Program (CFRP) facility at the Oak Ridge National Laboratory (ORNL) in order to evaluate the design of this equipment in a cold mock-up of a remotely maintained hot cell. This equipment included the Remote Disassembly System (RDS) and the Remote Shear System (RSS). These systems were disassembled and reassembled remotely by using the extensive remote handling systems that are installed in this simulated hot-cell environment. 5 refs., 5 figs

  8. Survey of economics of spent nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Valvoda, Z.

    1976-01-01

    Literature data are surveyed on the economic problems of reprocessing spent fuel from light-water reactors in the period 1970 to 1975 and on the capacity of some reprocessing plants, such as NFS, Windscale, Marcoule, etc. The sharp increase in capital and production costs is analyzed and the future trend is estimated. The question is discussed of the use of plutonium and the cost thereof. The economic advantageousness previously considered to be the primary factor is no longer decisive due to new circumstances. The main objective today is to safeguard uninterrupted operation of nuclear power plants and the separation of radioactive wastes from the fuel cycle and the safe disposal thereof. (Oy)

  9. Nuclear material inventory estimation in a nuclear fuel reprocessing facility

    International Nuclear Information System (INIS)

    Bennett, J.E.; Beyerlein, A.L.

    1981-01-01

    A new approach in the application of modern system identification and estimation techniques is proposed to help nuclear reprocessing facilities meet the nuclear accountability requirement proposed by the International Atomic Energy Agency. The proposed identification and estimation method considers the material inventory in a portion of the chemical separations area of a reprocessing facility. The method addresses the nonlinear aspects of the problem, the time delay through the separation facility, and the lack of measurement access. The method utilizes only input-output measured data and knowledge of the uncertainties associated with the process and measured data. 14 refs

  10. Information retrieval system

    Science.gov (United States)

    Berg, R. F.; Holcomb, J. E.; Kelroy, E. A.; Levine, D. A.; Mee, C., III

    1970-01-01

    Generalized information storage and retrieval system capable of generating and maintaining a file, gathering statistics, sorting output, and generating final reports for output is reviewed. File generation and file maintenance programs written for the system are general purpose routines.

  11. RETRIEVAL EQUIPMENT DESCRIPTIONS

    International Nuclear Information System (INIS)

    J. Steinhoff

    1997-01-01

    The objective and the scope of this document are to list and briefly describe the major mobile equipment necessary for waste package (WP) retrieval from the proposed subsurface nuclear waste repository at Yucca Mountain. Primary performance characteristics and some specialized design features of the equipment are explained and summarized in the individual subsections of this document. There are no quality assurance requirements or QA controls in this document. Retrieval under normal conditions is accomplished with the same fleet of equipment as is used for emplacement. Descriptions of equipment used for retrieval under normal conditions is found in Emplacement Equipment Descriptions, DI: BCAF00000-01717-5705-00002 (a document in progress). Equipment used for retrieval under abnormal conditions is addressed in this document and consists of the following: (1) Inclined Plane Hauler; (2) Bottom Lift Transporter; (3) Load Haul Dump (LHD) Loader; (4) Heavy Duty Forklift for Emplacement Drifts; (5) Covered Shuttle Car; (6) Multipurpose Vehicle; and (7) Scaler

  12. Foreign Body Retrieval

    Medline Plus

    Full Text Available ... object is solid or filled with fluid). In medicine, ultrasound is used to detect changes in appearance, ... Anesthesia Safety X-ray, Interventional Radiology and Nuclear Medicine Radiation Safety Videos related to Foreign Body Retrieval ...

  13. Foreign Body Retrieval

    Medline Plus

    Full Text Available ... tissues. top of page What are some common uses of the procedure? Foreign body retrieval is used ... bones also may be difficult to visualize. Additional evaluation is required when the suspected foreign body is ...

  14. Changing Information Retrieval Behaviours

    DEFF Research Database (Denmark)

    Constantiou, Ioanna D.; Lehrer, Christiane; Hess, Thomas

    2014-01-01

    on the continuance of LBS use and indicate changes in individuals' information retrieval behaviours in everyday life. In particular, the distinct value dimension of LBS in specific contexts of use changes individuals' behaviours towards accessing location-related information....

  15. Retrieve An Image

    Indian Academy of Sciences (India)

    First page Back Continue Last page Overview Graphics. Retrieve An Image. “A building”. “Box-shaped”. “Brown Color”. “Foreshortened view”. OR. Why not specify a similar looking picture? -- Main Motivation!

  16. Foreign Body Retrieval

    Medline Plus

    Full Text Available ... related to Foreign Body Retrieval Sponsored by Please note RadiologyInfo.org is not a medical facility. Please ... is further reviewed by committees from the American College of Radiology (ACR) and the Radiological Society of ...

  17. Foreign Body Retrieval

    Medline Plus

    Full Text Available ... tissues. top of page What are some common uses of the procedure? Foreign body retrieval is used ... community, you can search the ACR-accredited facilities database . This website does not provide cost information. The ...

  18. tes depresijas simptomu un dusmu saistība ar mātes audzināšanas stiliem un bērna uzvedību

    OpenAIRE

    Krūmiņa, Evija

    2015-01-01

    Šī bakalaura darba mērķis bija noskaidrot saistības starp mātes depresijas simptomu un dusmu rādītājiem ar mātes audzināšanas stiliem un bērna uzvedības izpausmēm respondentu grupā, kuru bērni ir vecumā no 4-6 gadiem. Pētījuma izlasi veidoja 63 mātes vecumā no 21 līdz 42 gadiem (vidējais vecums bija 29 gadi). Pētījumā mātes dusmu un depresijas rādītāju noteikšanai tika izmantota Traumu simptomu aptauja (Trauma Symptom Inventory, Briere, 1995), Vecāku audzināšanas stila aptauja (Parental Autho...

  19. Rotation Invariant Color Retrieval

    OpenAIRE

    Swapna Borde; Udhav Bhosle

    2013-01-01

    The new technique for image retrieval using the color features extracted from images based on LogHistogram is proposed. The proposed technique is compared with Global color histogram and histogram ofcorners .It has been observed that number of histogram bins used for retrieval comparison of proposedtechnique (Log Histogram)is less as compared to Global Color Histogram and Histogram of corners. Theexperimental results on a database of 792 images with 11 classes indicate that proposed method (L...

  20. Retrievability of high level waste and spent nuclear fuel. Proceedings of an international seminar

    International Nuclear Information System (INIS)

    2000-12-01

    The possibility of retrieving spent nuclear fuel or reprocessing high-level radioactive wastes placed in geological repositories is an issue that has attracted increased attention during the past few years, not only among technical experts but also among politicians at different levels, environmental organisations and other interested representatives of the public. This publication contains the presented invited papers, an edited record of the discussions and some concluding remarks. The seminar addressed a wide range of aspects of retrievability including technical options; public acceptance; ethical aspects; long term monitoring and cost considerations; safety and regulatory aspects. Each of the presented papers was indexed separately

  1. Retrievability of high level waste and spent nuclear fuel. Proceedings of an international seminar

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-12-01

    The possibility of retrieving spent nuclear fuel or reprocessing high-level radioactive wastes placed in geological repositories is an issue that has attracted increased attention during the past few years, not only among technical experts but also among politicians at different levels, environmental organisations and other interested representatives of the public. This publication contains the presented invited papers, an edited record of the discussions and some concluding remarks. The seminar addressed a wide range of aspects of retrievability including technical options; public acceptance; ethical aspects; long term monitoring and cost considerations; safety and regulatory aspects. Each of the presented papers was indexed separately.

  2. Development of TES microcalorimeters with Sn absorber for hard x-ray detection

    International Nuclear Information System (INIS)

    Hatakeyama, Shuichi; Ohno, Masashi; Damayanthi, R.M. Thushara; Takahashi, Hiroyuki

    2013-01-01

    Superconducting transition edge sensors (TES) are used for high-resolution X-ray spectroscopy. In this study, we have designed a new TES detector using a superconducting tin (Sn) absorber to detect high energy photons over 100 keV. The Sn absorber is coupled to an Ir/Au super-conducting film which is deposited on an ultra-thin SiN membrane (500 nm thick) with a small amount of epoxy post (Stycast 2850FT) by handling with a flip-chip bonding machine. The 241 Am photoelectron peak, the Sn K α and K β X-ray escape peaks are clearly observed. The measured energy resolution is 320 eV FWHM at 59.5 keV and is better than that of HPGe detector. (author)

  3. Gestion des côtes marocaines : renforcement des capacités d ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Les répercussions de la hausse du niveau de la mer, de l'inondation des côtes et des ondes de tempête constituent un enjeu de plus en plus important en matière de politiques pour les planificateurs, les autorités locales et les intervenants de secteurs comme la côte nord-est du Maroc. Ce projet financera le renforcement ...

  4. Mini-TES Observations of the Gusev and Meridiani Landing Sites

    Science.gov (United States)

    Christensen, Philip; Arvidson, Raymond; Bandfield, Joshua L.; Blaney, Diana; Budney, Charles; Calvin, Wendy; Ciccolella, Sandra; Fallacro, Alicia; Fergason, Robin; Glotch, Timothy

    2004-01-01

    The Miniature Thermal Emission Spectrometer (Mini-TES) has provided remote measurements of the mineralogy and thermophysical properties of the scene surrounding the Mars Exploration Rovers. The specific scientific objectives of this investigation are to: (1) determine the mineralogy of rocks and soils; (2) determine the thermophysical properties of surface materials; and (3) determine the temperature profile, dust and water-ice opacity, and water vapor abundance in the lower atmospheric boundary layer.

  5. Reflectance and Thermal Infrared Spectroscopy of Mars: Relationship Between ISM and TES for Compositional Determinations

    Science.gov (United States)

    Boyce, Joseph (Technical Monitor); Mustard, John

    2004-01-01

    Reflectance spectroscopy has demonstrated that high albedo surfaces on Mars contain heavily altered materials with some component of hematite, poorly crystalline ferric oxides, and an undefined silicate matrix. The spectral properties of many low albedo regions indicate crystalline basalts containing both low and high calcium pyroxene, a mineralogy consistent with the basaltic SNC meteorites. The Thermal Emission Spectrometer (TES) experiment on the Mars Geochemical Surveyor has acquired critical new data relevant to surface composition and mineralogy, but in a wavelength region that is complementary to reflectance spectroscopy. The essence of the completed research was to analyze TES data in the context of reflectance data obtained by the French ISM imaging spectrometer experiment in 1989. This approach increased our understanding of the complementary nature of these wavelength regions for mineralogic determinations using actual observations of the martian surface. The research effort focused on three regions of scientific importance: Syrtis Major-Isidis Basin, Oxia Palus-Arabia, and Valles Marineris. In each region distinct spatial variations related to reflectance, and in derived mineralogic information and interpreted compositional units were analyzed. In addition, specific science questions related to the composition of volcanics and crustal evolution, soil compositions and pedogenic processes, and the relationship between pristine lithologies and weathering provided an overall science-driven framework for the work. The detailed work plan involved colocation of TES and ISM data, extraction of reflectance and emissivity spectra from areas of known reflectance variability, and quantitative analysis using factor analysis and statistical techniques to determine the degree of correspondence between these different wavelength regions. Identified coherent variations in TES spectroscopy were assessed against known atmospheric effects to validate that the variations

  6. Domestic demand-side management (DSM): Role of heat pumps and thermal energy storage (TES) systems

    International Nuclear Information System (INIS)

    Arteconi, A.; Hewitt, N.J.; Polonara, F.

    2013-01-01

    Heat pumps are seen as a promising technology for load management in the built environment, in combination with the smart grid concept. They can be coupled with thermal energy storage (TES) systems to shift electrical loads from high-peak to off-peak hours, thus serving as a powerful tool in demand-side management (DSM). This paper analyzes heat pumps with radiators or underfloor heating distribution systems coupled with TES with a view to showing how a heat pump system behaves and how it influences the building occupants' thermal comfort under a DSM strategy designed to flatten the shape of the electricity load curve by switching off the heat pump during peak hours (16:00–19:00). The reference scenario for the analysis was Northern Ireland (UK). The results showed that the heat pump is a good tool for the purposes of DSM, also thanks to the use of TES systems, in particular with heating distribution systems that have a low thermal inertia, e.g. radiators. It proved possible to achieve a good control of the indoor temperature, even if the heat pump was turned off for 3 h, and to reduce the electricity bill if a “time of use” tariff structure was adopted. -- Highlights: ► Heat pump heating systems with thermal energy storage are considered. ► System behavior is investigated during a DSM strategy for reducing peak energy demand. ► Heat pump heating systems demonstrate to be able to have an active role in DSM programs. ► A TES system must be coupled with the heat pump in presence of low thermal inertia heating distribution systems. ► Central role played by incentives schemes to promote this technology

  7. Assembly, characterization, and operation of large-scale TES detector arrays for ACTPol

    Science.gov (United States)

    Pappas, Christine Goodwin

    2016-01-01

    The Polarization-sensitive Receiver for the Atacama Cosmology Telescope (ACTPol) is designed to measure the Cosmic Microwave Background (CMB) temperature and polarization anisotropies on small angular scales. Measurements of the CMB temperature and polarization anisotropies have produced arguably the most important cosmological data to date, establishing the LambdaCDM model and providing the best constraints on most of its parameters. To detect the very small fluctuations in the CMB signal across the sky, ACTPol uses feedhorn-coupled Transition-Edge Sensor (TES) detectors. A TES is a superconducting thin film operated in the transition region between the superconducting and normal states, where it functions as a highly sensitive resistive thermometer. In this thesis, aspects of the assembly, characterization, and in-field operation of the ACTPol TES detector arrays are discussed. First, a novel microfabrication process for producing high-density superconducting aluminum/polyimide flexible circuitry (flex) designed to connect large-scale detector arrays to the first stage of readout is presented. The flex is used in parts of the third ACTPol array and is currently being produced for use in the AdvACT detector arrays, which will begin to replace the ACTPol arrays in 2016. Next, we describe methods and results for the in-lab and on-telescope characterization of the detectors in the third ACTPol array. Finally, we describe the ACTPol TES R(T,I) transition shapes and how they affect the detector calibration and operation. Methods for measuring the exact detector calibration and re-biasing functions, taking into account the R(T,I) transition shape, are presented.

  8. UJI VALIDASI TES FROSTIG UNTUK MENGUKUR KEMAMPUAN PERSEPSI VISUAL ANAK PRASEKOLAH DI YOGYAKARTA

    Directory of Open Access Journals (Sweden)

    Rahma Widyana

    2016-08-01

    Full Text Available Penelitian ini bertujuan untuk mengetahui validitas dan reliabilitas Marianne Frostig Developmental Test of Visual Perception (Tes Frostig untuk mengukur kemampuan persepsi visual anak-anak prasekolah. Subjek penelitian 102 anak-anak prasekolah yang mengikuti pendidikan Taman Kanak-Kanak di TKIT Salman Al Farisi 2 Sleman Yogyakarta, TKIT Insan Utama, Bantul, TKIT Ibnu Abbas 3 Minggir Sleman, TKIT Insan Mulia Sentolo Kulon Progo, TK ABA Margakaton 3 Seyegan Sleman Yogyakarta, dengan rentang usia antara 4 tahun 1 bulan sampai 6 tahun 3 bulan. Hasil penelitian menunjukkan bahwa sebagian besar aitem Tes Persepsi Visual yang disusun oleh Frostig, berkolaborasi dengan Lefever dan Whittlesey pada tahun 1963 masih teruji validitas dan reliabilitasnya hingga saat ini. Meskipun demikian, penggunaannya perlu dikuatkan dengan tes lainnya mengingat koefisien reliabilitas khususnya subtes 3 dan 5 yang relatif rendah. Untuk subtes pertama (eye motor coordination yang terdiri dari 16 butir ditemukan 11 aitem valid dengan angka korelasi antara 0,213 sampai dengan 0,564. Untuk subtes kedua figure ground terdiri dari 8 aitem, semua aitem valid dengan angka korelasi 0,330 sampai dengan 0,673. Subtes ketiga (constancy of shape bagian pertama dan kedua, terdiri dari 32 aitem, terdapat 18 aitem valid dengan angka korelasi antara 0,223 sampai dengan 0,692. Subtes keempat (position of shape yang terdiri dari 8 aitem, 6 aitem valid dengan angka korelasi 0,244 sampai 0,353. Subtes kelima (spatial relationship yang terdiri dari 7 aitem (untuk usia prasekolah aitem 8 tidak diberikan, 6 aitem valid dengan angka korelasi antara 0,16 sampai dengan 0,512. Reliabilitas subtes bergerak dari 0,476 – 0,820. Terdapatnya korelasi yang signifikan antara skor skala subtes dengan skor total dengan rentang korelasi 0,406 – 0,754 menunjukkan bahwa semua subtes yang terdapat dalam tes Frostig menunjukkan relevansi untuk menggambarkan skor total kemampuan persepsi visual.

  9. PENGEMBANGAN SISTEM TES DIAGNOSTIK KESULITAN BELAJAR BERBASIS WEB MAHASISWA JURUSAN TEKNIK MESIN

    Directory of Open Access Journals (Sweden)

    Soffan Nurhaji

    2016-07-01

    Full Text Available Penelitian ini bertujuan untuk: (a Merancang sistem tes diagnostik kesulitan belajar mahasiswa jurusan pendidikan teknik mesin, dan, dan (b mengembangkan sistem tes diagnostik kesulitan belajar Mahasiswa. Penelitian ini menggunakan pendekatan Research and Development dengan perangkat lunak. Model pengembangan yang digunakan dalam penelitian ini adalah model modifikasi linear sequential yang disebut juga sebagai classic life cycle atau model waterfall yang memiliki 4 langkah. Analisis kebutuhan sistem dan perancangan sistem telah dilakukan pada tahun kedua. Implementasi dan validasi program dilakukan pada tahun keempat. Validasi sistem dilakukan dengan angket yang diberikan kepada 6 dosen yang mengampu di jurusan teknik pendidikan mesin untuk melihat aspek kinerja, rancangan, dan aksesbilitas sistem. Analisis data validasi dilakukan dengan statistik deskriptif. Langkah terakhir, evaluasi pemanfaatan sistem, akan dilaksanakan pada tahun kelima. Sistem tes diagnostik kesulitan belajar akan dikembangkan dengan arsitektur web client-server. Sistem ini memiliki tiga kelompok pengguna, yaitu admin, dosen, dan mahasiswa. Hasil analisis aspek kinerja, rancangan, dan adaptabilitas sistem secara keseluruhan akan dianalisis dari angket yang mempunyai rata-rata penilaian yang diperoleh dari skala 1–4, sehingga termasuk kategori sangat baik. Karena itu sistem yang telah dikembangkan dapat digunakan pada penelitian lebih lanjut pada tahun keenam, yaitu evaluasi pemanfaatan sistem. 

  10. Performance of an X-ray single pixel TES microcalorimeter under DC and AC biasing

    International Nuclear Information System (INIS)

    Gottardi, L.; Kuur, J. van der; Korte, P. A. J. de; Den Hartog, R.; Dirks, B.; Popescu, M.; Hoevers, H. F. C.; Bruijn, M.; Borderias, M. Parra; Takei, Y.

    2009-01-01

    We are developing Frequency Domain Multiplexing (FDM) for the read-out of TES imaging microcalorimeter arrays for future X-ray missions like IXO. In the FDM configuration the TES is AC voltage biased at a well defined frequencies (between 0.3 to 10 MHz) and acts as an AM modulating element. In this paper we will present a full comparison of the performance of a TES microcalorimeter under DC bias and AC bias at a frequency of 370 kHz. In both cases we measured the current-to-voltage characteristics, the complex impedance, the noise, the X-ray responsivity, and energy resolution. The behaviour is very similar in both cases, but deviations in performances are observed for detector working points low in the superconducting transition (R/R N <0.5). The measured energy resolution at 5.89 keV is 2.7 eV for DC bias and 3.7 eV for AC bias, while the baseline resolution is 2.8 eV and 3.3 eV, respectively.

  11. Experimental investigation of thermal de-stratification in rock bed TES systems for high temperature applications

    International Nuclear Information System (INIS)

    Okello, Denis; Nydal, Ole J.; Banda, Eldad J.K.

    2014-01-01

    Highlights: • High thermal stratifications exists rock bed TES when charge with high temperature heat. • Faster thermal degradation occurs in highly stratified bed irrespective of the bed length. • Average rate of heat loss as a function of storage time increases with increasing average bed temperature. - Abstract: Solar energy fluctuates so much that it cannot promote continuous use. Integration of Thermal Energy Storage (TES) with solar energy collection devices has the potential of making solar energy available on demand. Thermal energy can be stored in a bed of rocks at temperatures suitable for applications like cooking, boiling space heating, etc. During charging, temperature stratification is observed in the bed. In a stratified system, if the heat is used immediately, then it is possible to extract heat at reasonably high temperature from the top. For cases where the system is to be used after sometime (later at night or the following morning), the high temperature heat at the top is observed to degrade as the system tries to establish thermal equilibrium irrespective of the bed height. The average rate of heat loss from the TES unit to the ambient is found to increase with increasing average bed temperatures

  12. Handbook on process and chemistry of nuclear fuel reprocessing. 3rd edition

    International Nuclear Information System (INIS)

    2015-03-01

    The fundamental data on spent nuclear fuel reprocessing and related chemistry was collected and summarized as a new edition of 'Handbook on Process and Chemistry of Nuclear Fuel Reprocessing'. The purpose of this handbook is contribution to development of the fuel reprocessing and fuel cycle technology for uranium fuel and mixed oxide fuel utilization. Contents in this book was discussed and reviewed by specialists of science and technology on fuel reprocessing in Japan. (author)

  13. Advances in the valorization of waste and by-product materials as thermal energy storage (TES) materials

    OpenAIRE

    Gutiérrez, Andrea; Miró, Laia; Gil, Antoni; Rodríguez Aseguinolaza, Javier; Barreneche Güerisoli, Camila; Calvet, Nicolas; Py, Xavier; Fernández Renna, Ana Inés; Grágeda, Mario; Ushak, Svetlana; Cabeza, Luisa F.

    2016-01-01

    Today, one of the biggest challenges our society must face is the satisfactory supply, dispatchability and management of the energy. Thermal Energy Storage (TES) has been identified as a breakthrough concept in industrial heat recovery applications and development of renewable technologies such as concentrated solar power (CSP) plants or compressed air energy storage (CAES). A wide variety of potential heat storage materials has been identified depending on the implemented TES method: sensibl...

  14. Production and evaluation of the recombinant antigen TES-30 of Toxocara canis for the immunodiagnosis of toxocariasis.

    Science.gov (United States)

    Olave, Ana M; Mesa, Jairo A; Botero, Jorge H; Patiño, Edwin B; García, Gisela M; Alzate, Juan F

    2016-03-03

    Toxocara canis is a pathogenic nematode of canines which can be accidentally transmitted to humans. Although serology is the most important diagnostic tool for this zoonosis, diagnostic kits use crude excretion/secretion antigens, most of them being glycoproteins which are not species-specific and may cross-react with antibodies generated against other parasites.  To produce the rTES-30 recombinant antigen of Toxocara canis and evaluate it in the immunodiagnosis of toxocariasis.  The gene that codes for TES-30 was cloned in the expression vector pET28a (+) using single-stranded oligonucleotides united by PCR. The protein rTES-30 was purified by Ni2+ affinity chromotography. Seroreactivity of rTES-30 was evaluated by immunoblot. Given that there is no gold standard test, the behaviour of the antigen was compared with the method that is routinely used to immunodiagnose toxocariasis, i.e., the conventional ELISA technique using excretion/secretion antigens.  The rTES-30 was produced from an Escherichia coli LB culture which yielded 2.25 mg/L of the antigen with a purity of 95%. The results obtained showed 73% (46/63) concordance of reactivity between the rTES-30 immunoblot and the conventional ELISA, and 100% concordance with the nonreactive sera (21). Nineteen of the 21 sera positive for other parasitoses reacted with ELISA, while only seven of these were positive with the rTES-30 immunoblot. Concordance between the ELISA and the immunoblot was moderate (kappa coefficient: 0.575; 95% CI: 0.41- 0.74).  The data presented show the potential of the rTES-30 inmunoblot for confirmation of possible ELISA positives, not only in epidemiological studies, but also as a candidate for the development of diagnostic tests for ocular toxocariasis in Colombia.

  15. Standard model for safety analysis report of fuel reprocessing plants

    International Nuclear Information System (INIS)

    1979-12-01

    A standard model for a safety analysis report of fuel reprocessing plants is established. This model shows the presentation format, the origin, and the details of the minimal information required by CNEN (Comissao Nacional de Energia Nuclear) aiming to evaluate the requests of construction permits and operation licenses made according to the legislation in force. (E.G.) [pt

  16. The regulations concerning the reprocessing business of spent fuels

    International Nuclear Information System (INIS)

    1978-01-01

    In compliance with ''The law for the regulations of nuclear source material, nuclear fuel material and reactors'' these regulations prescribe concerning reprocessing facilities: The procedures to apply for the approval of the design and method of construction and the approval of the change thereof; as well as the procedure to apply for the inspection of the facilities, and details of the inspection (in sections 2-6). After that, the regulations require the enterpriser of reprocessing business to keep necessary records and take necessary measures for safety concerning the facilities, operation of reprocessing equipments, and transportation, storage on disposal of used fuel, materials separated therefrom or materials contaminated by either of them (in sections 8-16). Further, the regulations prescribe the procedure to apply for the approval of the safety rule required to the enterpriser of reprocessing business by above mentioned law and specifies items which should be included into the rule (section 17). Moreover, the regulations require the enterpriser to submit reports of each use of the internationally controllled material and specifies the items which should be included into these reports (section 19). (Matsushima, A.)

  17. Technical specifications on the welding in fuel reprocessing plants

    Energy Technology Data Exchange (ETDEWEB)

    Karino, Motonobu; Uryu, Mitsuru; Matsui, N.; Nakazawa, Fumio; Imanishi, Makoto; Koizumi; Kazuhiko; Sugawara, Junichi; Tanaka, Hideo

    1999-04-01

    The past specifications SGN of the welding in JNC was reexamined for the reprocessing plants in order to further promote the quality control. The specification first concerns the quality of raw materials, items of the quality tests, material management, and qualification standards of the welders. It extends over details of the welding techniques, welding design, welding testings, inspection and the judgment standards. (H. Baba)

  18. Inspiration fra New York - udforskende læreprocesser

    DEFF Research Database (Denmark)

    Jørgensen, Lone Tang

    2017-01-01

    for tilrettelæggelse af læreprocesserne. Med udgangspunkt i Deweys ideer om skolen, baseret på den eksperimentelle metode, præsenteres Paula Rogovins arbejde på Manhattan New School i New York som et eksempel på, hvordan arbejdet med udforskende læreprocesser kan tilrettelægges....

  19. Reprocessing of spent nuclear fuel; Prerada isluzenog nuklearnog goriva

    Energy Technology Data Exchange (ETDEWEB)

    Gal, I [Institute of Nuclear Sciences Boris Kidric, Laboratorija za visoku aktivnost, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    This report covers: chemical-technology investigation of modified purex process for reprocessing of spent fuel; implementation of the procedure for obtaining plutonium peroxide and oxalate; research in the field of uranium, plutonium, and fission products separation by inorganic ion exchangers and extraction by organic solutions; study of the fission products in the heavy water RA reactor.

  20. Status of project design work for a German reprocessing plant

    International Nuclear Information System (INIS)

    Lang, K.; Zuehlke, P.

    1976-01-01

    A reprocessing plant will be built within the framework of a comprehensive waste management center planned by the Federal Government to treat the fuel elements unloaded from German nuclear power stations. On the basis of an annual throughput of 1,400 te of uranium averaged over the life of the plant, the center will be able to serve between 45,000 and 50,000 MWe of installed nuclear generating capacity. A comprehensive conceptual design study of the reprocessing plant to be built has been completed on the basis of the operating experience accumulated at the Karlsruhe reprocessing plant and the development work carried out by the Karlsruhe Nuclear Research Center and in the light also of an intensive exchange of experience with British and French reprocessing companies within the framework of United Reprocessors GmbH. This conceptual design study is the foundation for the preliminary project to be carried out on a collaborative basis by KEWA and PWK. (orig.) [de

  1. Reprocessing of spent nuclear fuels. Status and trends

    International Nuclear Information System (INIS)

    Hultgren, Aa.

    1993-01-01

    The report gives a short review of the status for industrial reprocessing and recycling of Uranium/Plutonium. The following countries are covered: Belgium, France, Germany, Great Britain, India, Japan, Russia, USA. Different fuel cycle strategies are accounted for, and new developments outlined. 116 refs, 27 figs, 12 tabs

  2. Implications of ICPR 60 for nuclear fuel reprocessing in france

    International Nuclear Information System (INIS)

    Mathieu, P.

    1992-01-01

    The ICRP 60 publication intends to guide the regulatory agencies on the main rules and principle of protection. The text contains recommendations for practices and for emergencies. The following report intends to develop the possible consequences of the publication for the reprocessing of spent fuel as managed by COGEMA in the plants of La Hague and Marcoule. (author)

  3. The economic and environmental benefits of reprocessing and recycle

    International Nuclear Information System (INIS)

    Masters, R.

    1977-01-01

    Recently published reports and papers on the economic, environmental and resource conservation benefits of reprocessing and the recycle of plutonium in thermal reactors provide an important background to the essentially political discussions in the United States on non-proliferation. Some of the main arguments and conclusions are presented. (author)

  4. Air conditioning facilities in a fuel reprocessing plant

    International Nuclear Information System (INIS)

    Kawasaki, Michitaka; Oka, Tsutomu

    1987-01-01

    Reprocessing plants are the facilities for separating the plutonium produced by nuclear reaction and unconsumed remaining uranium from fission products in the spent fuel taken out of nuclear reactors and recovering them. The fuel reprocessing procedure is outlined. In order to ensure safety in handling radioactive substances, triple confinement using vessels, concrete cells and buildings is carried out in addition to the prevention of criticality and radiation shielding, and stainless steel linings and drip trays are installed as occasion demands. The ventilation system in a reprocessing plant is roughly divided into three systems, that is, tower and tank ventilation system to deal with offgas, cell ventilation system for the cells in which main towers and tanks are installed, and building ventilation system. Air pressure becomes higher from tower and tank system to building system. In a reprocessing plant, the areas in a building are classified according to dose rate. The building ventilation system deals with green and amber areas, and the cell ventilation system deals with red area. These three ventilation systems are explained. Radiation monitors are installed to monitor the radiation dose rate and air contamination in working places. The maintenance and checkup of ventilation systems are important. (Kako, I.)

  5. Decontamination and decommissioning of the West Valley Reprocessing Plant

    International Nuclear Information System (INIS)

    Daugherty, H.F.; Keel, R.

    1986-11-01

    This report presents the decontamination and decommissioning (D and D) activities at the West Valley Nuclear Fuel Reprocessing Plant through September 1, 1986. The topics addressed are: D and D of areas for reuse by the Liquid Waste Treatment System (LWTS); D and D of areas for reuse as High Level Waste (HLW) canister storage; and technologies developed in D and D work

  6. Reasons for and against reprocessing of spent fuel elements

    Energy Technology Data Exchange (ETDEWEB)

    Gries, W

    1983-06-01

    In the following the reasons for and against the main methods of waste disposal are compared. The author examines the advantages and disadvantages of waste disposal by reprocessing of spent fuel assemblies or by immediate ultimate storage. To get a general idea the pros and cons are arranged and analysed according to the following subjects: - technology/science, - safety/environment, - profitability, - political aspects.

  7. Reprocessing of spent nuclear fuel; Prerada isluzenog nuklearnog goriva

    Energy Technology Data Exchange (ETDEWEB)

    Gal, I [Institute of Nuclear Sciences Boris Kidric, Laboratorija za hemiju visoke aktivnosti, Vinca, Beograd (Serbia and Montenegro)

    1964-12-15

    This volume contains the following reports: Experimental facility for testing and development of pulsed columns and auxiliary devices; Chemical-technology study of the modified 'Purex' process; Chemical and radiometric control analyses; Chromatographic separation of rare earth elements on paper treated by di-n butylphosphate; Preliminary study of some organic nitrogen extracts significant in fuel reprocessing.

  8. General criteria for the project of nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    1979-01-01

    Recommendations are presented establishing the general criteria for the project of nuclear fuel reprocessing plants to be licensed according to the legislation in effect. They apply to all the plant's systems, components and structures which are important to operation safety and to the public's health and safety. (F.E.) [pt

  9. Multi-purpose simulator 'MR TRIOS' for reprocessing plant

    International Nuclear Information System (INIS)

    Mitsui, Takeshi; Ariyoshi, Masahiro

    1993-01-01

    MHI(Mitsubishi Heavy Industries, Ltd.) has developed MR TRIOS(Mitsubishi Reprocessing plant TRansient simulator of Integrated process for Operation Support), the realtime dynamic simulator, for multipurpose use to support the Reprocessing Plant operation in various aspects. MR TRIOS integrates the simulation models of the unit process in reprocessing plant, including shearing, dissolution, NO x absorption, accountability and adjustment and co-decontamination process, where each simulation model has two kinds of models, one is Process and the other is Control System. MR TRIOS can simulate the process behavior of the above listed unit process in an integrated manner as well as independently. It is realized by MR CONTROL, the simulator control program developed by MHI. We can get from MR TRIOS the real-time process values, such as temperature, pressure, density, flow rate and concentration of eminent nuclides etc. enabling the evaluation of the process dynamic characteristics under various operating conditions. MR TRIOS has been proved to be an effective tool for the comprehensive study of the process and system dynamics, for operation technique improvements and for training. In this report we will show the introductory outline of multi-purpose simulator 'MR TRIOS' for reprocessing plant and also show the possibility to clarify the fundamental technical requirement to realize the effective material accountancy measure for Head-end Area. (author)

  10. Radiation exposures in reprocessing facilities at the Savannah River Plant

    International Nuclear Information System (INIS)

    Hayes, G.; Caldwell, R.D.; Hall, R.M.

    1979-06-01

    Two large reprocessing facilities have been operating at the Savannah River Plant since 1955. The plant, which is near Aiken, South Carolina, is operated for the US Department of Energy by the Du Pont Company. The reprocessing facilities have a work force of approximately 1,800. The major processes in the facilities are chemical separations of irradiated material, plutonium finishing, and waste management. This paper presents the annual radiation exposure for the reprocessing work force, particularly during the period 1965 through 1978. It also presents the collective and average individual annual exposures for various occupations including operators, mechanics, electricians, control laboratory technicians, and health physicists. Periodic and repetitive work activities that result in the highest radiation exposures are also described. The assimilation of radionuclides, particularly plutonium, by the work force is reviewed. Methods that have been developed to minimize the exposure of reprocessing personnel are described. The success of these methods is illustrated by experience - there has been no individual worker exposure of greater than 3.1 rems per year and only one plutonium assimilation greater than the maximum permissible body burden during the 24 years of operation of the facilities

  11. Summary of the status of the NFS reprocessing plant

    International Nuclear Information System (INIS)

    Clark, J.R.

    The modification program at the West Valley, New York, reprocessing plant is described. The program involves expansion, improving the plant's on-stream factor and reducing the occupational exposures, installing natural phenomena protection, and improving effluent control and waste management. Licencing requirements and their effects on scheduling are discussed. (E.C.B.)

  12. Information disclosure of troubles occurring at Rokkasho Reprocessing Plant

    International Nuclear Information System (INIS)

    Yamada, Tatsuya; Yoneyama, Mitsuru; Shinozaki, Yoshinori

    2005-01-01

    At Rokkasho Reprocessing Plant (RRP), efforts are made so that troubles occurred are promptly reported and announced publicly, and for minor troubles, etc., announcement to the society is made through the web-site and publicity magazines, so as to assure the transparency of the business. (author)

  13. Data used for safety assessment of reprocessing facilities

    International Nuclear Information System (INIS)

    Nomura, Yasushi; Suzuki, Atsuyuki; Kanagawa, Akira

    1990-08-01

    For safety assessment of a reprocessing facility, it is important to know performance of radioactive materials in their accidental release and transfer. Accordingly, it is necessary to collect and prepare data for use in analyses for their performance. In JAERI, experiments such as for data acquisition, for source-term evaluation and for radioactive material transfer, are now planned to be performed. Prior to these experiments, it is decided to investigate data in use for accidental safety assessment of reprocessing plants and their based experimental data, thus to make it possible to recommend reasonable values for safety analysis parameters by evaluating the investigated results, to select the experimental items, to edit a safety assessment handbook and so on. In this line of objectives, JAERI rewarded a two-year contract of investigation to Nuclear Safety Research Association, to make a working group under a special committee on data investigation for reprocessing facility safety assessment. This report is a collection of results reviewed and checked by the working group. The contents consist of two parts, one for investigation and review of data used for safety assessment of domestic or oversea reprocessing facilities, and the other for investigation, review and evaluation of ANSI recommended American standard data reported by E. Walker together with their based experimental data resorting to the original referred reports. (author)

  14. Ventilating system for reprocessing of nuclear fuel rods

    International Nuclear Information System (INIS)

    Szulinski, M.J.

    1981-01-01

    In a nuclear facility such as a reprocessing plant for nuclear fuel rods, the central air cleaner discharging ventilating gas to the atmosphere must meet preselected standards not only as to the momentary concentration of radioactive components, but also as to total quantity per year. In order to comply more satisfactorily with such standards, reprocessing steps are conducted by remote control in a plurality of separate compartments. The air flow for each compartment is regulated so that the air inventory for each compartment has a slow turnover rate of more than a day but less than a year, which slow rate is conveniently designated as quasihermetic sealing. The air inventory in each such compartment is recirculated through a specialized processing unit adapted to cool and/or filter and/or otherwise process the gas. Stale air is withdrawn from such recirculating inventory and fresh air is injected (eg., By the less than perfect sealing of a compartment) into such recirculating inventory so that the air turnover rate is more than a day but less than a year. The amount of air directed through the manifold and duct system from the reprocessing units to the central air cleaner is less than in reprocessing plants of conventional design

  15. Development of centrifugal contactor for FBR fuel reprocessing

    International Nuclear Information System (INIS)

    Washiya, Tadahiro; Takeuchi, Masayuki; Suganuma, Takashi; Aose, Shinichi; Ogino, Hideki

    2003-01-01

    In the Feasibility Study on Commercialized Fast Reactor Cycle Systems, the aqueous reprocessing technology is nominated as a candidate for future reprocessing system, which supposes to apply a centrifugal contactor in the extraction process. For the reprocessing plant, the centrifugal contactor has great advantages such as reducing solvent degradation, improving of equipment utilization rate, compact designing of equipment layout and critical safety domination. From these advantages, the centrifugal contactor is crucial equipment in the aqueous reprocessing process. Since 1985, JNC has been developing the centrifugal contactor. The single unit development has been accomplished and basic characteristics such as extraction performance, fluidic performance and remote maintenance performance have been determined. A durability test has been conducted for high longevity, with consideration given to the nitric acid mist and estimation of the equipment lifetime. System test equipment with centrifugal contactors of engineering scale was installed, and uranium test was conducted. Up to now, a standard flow sheet test in the extraction process and mal-operation test assuming the one stage shutdown condition have been performed. (author)

  16. West Valley Reprocessing Plant. Safety analysis plant, supplement 18

    International Nuclear Information System (INIS)

    1975-01-01

    Supplement 18 contains the following additions to Appendix II--5.0 Geology and Seismology: Section 12 ''Seismic Investigations for Spent Fuel Reprocessing Facility at West Valley, New York,'' October 20, 1975, and Section 13 ''Earthquake Return Period Analysis at West Valley, New York, for Nuclear Fuel Services, Inc.'' November 5, 1975

  17. Radiation exposures in reprocessing facilities at the Savannah River Plant

    International Nuclear Information System (INIS)

    Hayes, G.; Caldwell, R.D.; Hall, R.M.

    1979-01-01

    Two large reprocessing facilities have been operating at the Savannah River Plant since 1955. The plant, which is near Aiken, South Carolina, is operated for the U.S. Department of Energy by the Du Pont Company. The reprocessing facilities have a work force of approximately 1,800. The major processes in the facilities are chemical separations of irradiated material, plutonium finishing, and waste management. This paper presents the annual radiation exposure for the reprocessing work force, particularly during the period 1965 through 1978. It also presents the collective and average individual annual exposures for various occupations including operators, mechanics, electricians, control laboratory technicians, and health physicists. Periodic and repetitive work activities that result in the highest radiation exposures are also described. The assimilation of radionuclides, particularly plutonium, by the work force is reviewed. Methods that have been developed to minimize the exposure of reprocessing personnel are described. The success of these methods is illustrated by experience - there has been no individual worker exposure of greater than 3.1 rems per year and only one plutonium assimilation greater than the maximum permissible body burden during the 24 years of operation of the facilities

  18. Nuclear accountability data at the EUREX reprocessing plant

    International Nuclear Information System (INIS)

    Ilardi, S.; Pozzi, F.

    1976-01-01

    In the present work the physical inventory's and fissile material balance's data, which have been collected during the irradiated MTR fuel reprocessing campaign at the EUREX plant in Saluggia (VC), are reported, together with the most important procedures of fissile material accountability

  19. Melter operation results in chemical test at Rokkasho Reprocessing Plant

    International Nuclear Information System (INIS)

    Kanehira, Norio; Yoshioka, Masahiro; Muramoto, Hitoshi; Oba, Takaaki; Takahashi, Yuji

    2005-01-01

    Chemical Test of the glass melter system of the Vitrification Facility at Rokkasho Reprocessing Plant (RRP) was performed. In this test, basic performance of heating-up of the melter, melting glass, pouring glass was confirmed using simulated materials. Through these tests and operation of all modes, good results were gained, and training of operators was completed. (author)

  20. Remote maintenance lessons learned on prototypical reprocessing equipment

    International Nuclear Information System (INIS)

    Kring, C.T.; Schrock, S.L.

    1990-01-01

    A major objective of the Consolidated Fuel Reprocessing Program at the Oak Ridge National Laboratory is to develop and demonstrate the technology required to reprocess spent nuclear fuel. The Fuel Recycle Division, over the past 16 years, has undertaken this objective by designing and testing prototypical hardware representing essentially every major equipment item currently included in most fuel reprocessing plant conceptual designs. These designs are based on total remote maintenance to increase plant availability and reduce radiation exposure to plant operators. The designs include modular equipment to facilitate maintainability and the remote manipulation necessary to accomplish maintenance tasks. Prototypic equipment has been installed and tested in a cold mock-up of a reprocessing hot cell, called the remote operations and maintenance demonstration facility. The applied maintenance concept utilizes the dexterity and mobility of bridge-mounted, force-reflecting servomanipulators. Prototypic processing equipment includes a remote disassembly system, a remote shear system, a rotary dissolver, a remote automated sampler system, removable equipment racks to support chemical process equipment items, and the advanced servomanipulators. Each of these systems and a brief description of functions are discussed

  1. Materials management in an internationally safeguarded fuels reprocessing plant

    International Nuclear Information System (INIS)

    Hakkila, E.A.; Cobb, D.D.; Dayem, H.A.; Dietz, R.J.; Kern, E.A.; Markin, J.T.; Shipley, J.P.; Barnes, J.W.; Scheinman, L.

    1980-04-01

    The first volume of this report summarizes the results and conclusions for this study of conventional and advanced nuclear materials accounting systems applicable for both large (1500 MTHM/y) and small (210 MTHM/y) spent-fuel reprocessing facilities subject to international verification

  2. Spent fuel reprocessing system security engineering capability maturity model

    International Nuclear Information System (INIS)

    Liu Yachun; Zou Shuliang; Yang Xiaohua; Ouyang Zigen; Dai Jianyong

    2011-01-01

    In the field of nuclear safety, traditional work places extra emphasis on risk assessment related to technical skills, production operations, accident consequences through deterministic or probabilistic analysis, and on the basis of which risk management and control are implemented. However, high quality of product does not necessarily mean good safety quality, which implies a predictable degree of uniformity and dependability suited to the specific security needs. In this paper, we make use of the system security engineering - capability maturity model (SSE-CMM) in the field of spent fuel reprocessing, establish a spent fuel reprocessing systems security engineering capability maturity model (SFR-SSE-CMM). The base practices in the model are collected from the materials of the practice of the nuclear safety engineering, which represent the best security implementation activities, reflect the regular and basic work of the implementation of the security engineering in the spent fuel reprocessing plant, the general practices reveal the management, measurement and institutional characteristics of all process activities. The basic principles that should be followed in the course of implementation of safety engineering activities are indicated from 'what' and 'how' aspects. The model provides a standardized framework and evaluation system for the safety engineering of the spent fuel reprocessing system. As a supplement to traditional methods, this new assessment technique with property of repeatability and predictability with respect to cost, procedure and quality control, can make or improve the activities of security engineering to become a serial of mature, measurable and standard activities. (author)

  3. 9 CFR 114.18 - Reprocessing of biological products.

    Science.gov (United States)

    2010-01-01

    ... for all tests conducted shall be submitted to Animal and Plant Health Inspection Service. The licensee... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Reprocessing of biological products. 114.18 Section 114.18 Animals and Animal Products ANIMAL AND PLANT HEALTH INSPECTION SERVICE...

  4. TRMM Version 7 Level 3 Gridded Monthly Accumulations of GPROF Precipitation Retrievals

    Science.gov (United States)

    Stocker, E. F.; Kelley, O. A.

    2012-01-01

    In July 2011, improved versions of the retrieval algorithms were approved for TRMM. All data starting with June 2011 are produced only with the version 7 code. At the same time, version 7 reprocessing of all TRMM mission data was started. By the end of August 2011, the 14+ years of the reprocessed mission data became available online to users. This reprocessing provided the opportunity to redo and enhance upon an analysis of V7 impacts on L3 data accumulations that was presented at the 2010 EGU General Assembly. This paper will discuss the impact of algorithm changes made in th GPROF retrieval on the Level 2 swath products. Perhaps the most important change in that retrieval was to replacement of a model based a priori database with one created from Precipitation Radar (PR) and TMI brightness temperature (Tb) data. The radar pays a major role in the V7 GPROF (GPROF2010) in determining existence of rain. The level 2 retrieval algorithm also introduced a field providing the probability of rain. This combined use of the PR has some impact on the retrievals and created areas, particularly over ocean, where many areas of low-probability precipitation are retrieved whereas in version 6, these areas contained zero rain rates. This paper will discuss how these impacts get translated to the space/time averaged monthly products that use the GPROF retrievals. The level 3 products discussed are the gridded text product 3G68 and the standard 3A12 and 3B31 products. The paper provides an overview of the changes and explanation of how the level 3 products dealt with the change in the retrieval approach. Using the .25 deg x .25 degree grid, the paper will show that agreement between the swath product and the level 3 remains very high. It will also present comparisons of V6 and V7 GPROF retrievals as seen both at the swath level and the level 3 time/space gridded accumulations. It will show that the various L3 products based on GPROF level 2 retrievals are in close agreement. The

  5. Production of Toxocara cati TES-120 Recombinant Antigen and Comparison with its T. canis Homolog for Serodiagnosis of Toxocariasis

    Science.gov (United States)

    Zahabiun, Farzaneh; Sadjjadi, Seyed Mahmoud; Yunus, Muhammad Hafiznur; Rahumatullah, Anizah; Moghaddam, Mohammad Hosein Falaki; Saidin, Syazwan; Noordin, Rahmah

    2015-01-01

    Toxocariasis is a cosmopolitan zoonotic disease caused by the infective larvae of Toxocara canis and T. cati. Diagnosis in humans is usually based on clinical symptoms and serology. Immunoglobulin G (IgG)-enzyme-linked immunosorbent assay kits using T. canis excretory–secretory (TES) larval antigens are commonly used for serodiagnosis. Differences in the antigens of the two Toxocara species may influence the diagnostic sensitivity of the test. In this study, T. cati recombinant TES-120 (rTES-120) was cloned, expressed, and compared with its T. canis homolog in an IgG4-western blot. The diagnostic sensitivity and specificity of T. cati rTES-120 were 70% (33/47) and 100% (39/39), respectively. T. canis rTES-120 showed 57.4% sensitivity and 94.4% specificity. When the results of assays using rTES-120 of both species were considered, the diagnostic sensitivity was 76%. This study shows that using antigens from both Toxocara species may improve the serodiagnosis of toxocariasis. PMID:26033026

  6. Development of safety evaluation technology for fire and explosion in reprocessing plant

    International Nuclear Information System (INIS)

    Miura, Akihiko

    2005-01-01

    Based on some lessons learned from the accidents in the reprocessing plant all over the world, Japan Nuclear Cycle Development Institute (JNC) has researched and developed the safety technologies for the reprocessing plants and its related facilities. This paper describes some accidental information around the reprocessing plants and its related research activities in JNC. (author)

  7. Impact of the Tokai reprocessing plant on the workers and on the surrounding environment

    International Nuclear Information System (INIS)

    Tago, I.

    1996-01-01

    The Tokai reprocessing plant began operation in September 1977 to establish oxide fuel reprocessing technology in Japan. Its designed capacity is about 0.7 metric tons of uranium per day. This report gives an example of the evaluation of the health and environmental aspects of a reprocessing plant. (author)

  8. Optimization of the sizes and dates of starting up of reprocessing plants

    International Nuclear Information System (INIS)

    Nagashima, Kikusaburo

    1977-01-01

    It is desirable to complete the nuclear fuel cycle domestically for promoting nuclear power generation in Japan, and the reprocessing of spent fuel is indispensable. However, the capacity of the reprocessing plant in PNC and the reprocessing by the commissioning to foreign countries will be insufficient by the latter half of 1980s. In the planning of the second reprocessing plant in Japan, the following problems remain yet to be solved. The international regulation and the laws in Japan regarding the storage and transport of spent fuel, the disposal of radioactive wastes, and the recycling of plutonium must be established. The consensus of the public on the necessity and the safety of fuel reprocessing must be obtained. The technical investigation about fuel reprocessing and related business must be carried out sufficiently, including the necessity of introducing the technology from abroad. The economy and various conditions for industrializing fuel reprocessing must be studied. The economy of fuel reprocessing plants, the reprocessing cost taking escalation into account, mean reprocessing cost, the optimization of the time of starting full operation and the time of starting-up, the rise of reprocessing cost due to the escalation of operational cost are explained. Numerical calculation was carried out about the second reprocessing plant in Japan, and the results are examined. (Kako, I.)

  9. Pengembangan tes kemampuan literasi sains pada materi momentum dan impuls dengan Analisis Item Response Theory (IRT

    Directory of Open Access Journals (Sweden)

    Della Apriyani Kusuma Putri

    2018-04-01

    Full Text Available Kemampuan literasi sains adalah suatu kemampuan yang memungkinkan seseorang untuk membuat suatu keputusan dengan pengetahuan konsep dan proses sains yang dimilikinya. Berbagai macam permasalahan yang terjadi di era globalisasi ini menuntut siswa untuk tidak hanya cakap dalam aspek kognitif tapi juga mampu memberi keputusan untuk memecahkan permasalahan, sehingga dapat dikatakan bahwa kemampuan literasi sains adalah kemampuan yang penting dan harus dimiliki siswa. Oleh karena itu, dibutuhkan instrumen untuk mengukur kemampuan literasi sains. hal inilah yang mendasari peneliti mengembangkan instrumen kemampuan literasi sains. Tujuan penelitian ini adalah untuk mengembangkan dan mengetahui karakteristik tes kemampuan literasi sains fisika siswa SMA pada materi momentum dan impuls berdasarkan aspek literasi sains yang dikemukakan oleh Gormally. Metode penelitian yang diterapkan adalah penelitian dan pengembangan (Research and Development yaitu metode penelitian yang digunakan untuk menghasilkan produk tertentu, dan menguji keefektifan produk tersebut. Sebelum diuji coba tes telah divalidasi oleh tiga orang validator dan menghasilkan kesimpulan bahwa tes cukup baik dan dapat diuji coba. Hasil analisis menggunakan Item Response Theory menunjukkan bahwa model 3PL adalah model yang sesuai dengan karakteristik tes. Sedangkan karakteristik tes yang meliputi daya pembeda, tingkat kesukaran, dan faktor tebakan termasuk dalam kategori baik. Science literacy skills is an ability that allows one to make a decision with the knowledge of the concepts and processes of science has. A wide variety of problems that occur in a globalized world requires students to not only proficient in cognitive but also able to make a decision to solve the problem, so it can be said that the ability of science literacy is an important capability and must be owned by the students. Therefore, the instrument is required to measure the ability of science literacy. This problem is

  10. Retrieval and satellite intercomparison of O3 measurements from ground-based FTIR Spectrometer at Equatorial Station: Addis Ababa, Ethiopia

    Directory of Open Access Journals (Sweden)

    T. von Clarmann

    2013-02-01

    Full Text Available Since May 2009, high-resolution Fourier Transform Infrared (FTIR solar absorption spectra have been recorded at Addis Ababa (9.01° N latitude, 38.76° E longitude, 2443 m altitude above sea level, Ethiopia. The vertical profiles and total column amounts of ozone (O3 are deduced from the spectra by using the retrieval code PROFFIT (V9.5 and regularly determined instrumental line shape (ILS. A detailed error analysis of the O3 retrieval is performed. Averaging kernels of the target gas shows that the major contribution to the retrieved information comes from the measurement. The degrees of freedom for signals is found to be 2.1 on average for the retrieval of O3 from the observed FTIR spectra. The ozone Volume Mixing Ratio (VMR profiles and column amounts retrieved from FTIR spectra are compared with the coincident satellite observations of Microwave Limb Sounding (MLS, Michelson Interferometer for Passive Atmospheric Sounding (MIPAS, Tropospheric Emission Spectrometer (TES, Ozone Monitoring Instrument (OMI, Atmospheric Infrared Sounding (AIRS and Global Ozone Monitoring Experiment (GOME-2 instruments. The mean relative differences in ozone profiles of FTIR from MLS and MIPAS are generally lower than 15% within the altitude range of 27 to 36 km, whereas difference from TES is lower than 1%. Comparisons of measurements of column amounts from the satellite and the ground-based FTIR show very good agreement as exhibited by relative differences within +0.2% to +2.8% for FTIR versus MLS and GOME-2; and −0.9 to −9.0% for FTIR versus OMI, TES and AIRS. The corresponding standard deviations are within 2.0 to 2.8% for FTIR versus MLS and GOME-2 comparisons whereas that of FTIR versus OMI, TES and AIRS are within 3.5 to 7.3%. Thus, the retrieved O3 VMR and column amounts from a tropical site, Addis Ababa, is found to exhibit very good agreement with all coincident satellite observations over an approximate 3-yr period.

  11. Structure retrieval in HREM

    International Nuclear Information System (INIS)

    Gribelyuk, M.A.

    1991-01-01

    A new iteration method for direct structure retrieval starting from the exit plane-wave function Ψ e (r) is proposed and tested on models. The imaginary part of the potential cannot be retrieved. The effects of the limited resolution of Ψ e (r) as well as neglect of high-order Laue-zone effects and the choice of the starting potential on the result are discussed. The procedure is found to be preferable to that based on the subsequent approximation method with respect to a higher convergence rate. It is shown that an error as low as 10% may be obtained for the real part of the retrieved potential up to vertical strokeσV(r)tvertical stroke<5. (orig.)

  12. Interactive Information Retrieval

    DEFF Research Database (Denmark)

    Borlund, Pia

    2013-01-01

    The paper introduces the research area of interactive information retrieval (IIR) from a historical point of view. Further, the focus here is on evaluation, because much research in IR deals with IR evaluation methodology due to the core research interest in IR performance, system interaction...... and satisfaction with retrieved information. In order to position IIR evaluation, the Cranfield model and the series of tests that led to the Cranfield model are outlined. Three iconic user-oriented studies and projects that all have contributed to how IIR is perceived and understood today are presented......: The MEDLARS test, the Book House fiction retrieval system, and the OKAPI project. On this basis the call for alternative IIR evaluation approaches motivated by the three revolutions (the cognitive, the relevance, and the interactive revolutions) put forward by Robertson & Hancock-Beaulieu (1992) is presented...

  13. Introduction to information retrieval

    CERN Document Server

    Manning, Christopher D; Schütze, Hinrich

    2008-01-01

    Class-tested and coherent, this textbook teaches classical and web information retrieval, including web search and the related areas of text classification and text clustering from basic concepts. It gives an up-to-date treatment of all aspects of the design and implementation of systems for gathering, indexing, and searching documents; methods for evaluating systems; and an introduction to the use of machine learning methods on text collections. All the important ideas are explained using examples and figures, making it perfect for introductory courses in information retrieval for advanced un

  14. Information Retrieval Evaluation

    CERN Document Server

    Harman, Donna

    2011-01-01

    Evaluation has always played a major role in information retrieval, with the early pioneers such as Cyril Cleverdon and Gerard Salton laying the foundations for most of the evaluation methodologies in use today. The retrieval community has been extremely fortunate to have such a well-grounded evaluation paradigm during a period when most of the human language technologies were just developing. This lecture has the goal of explaining where these evaluation methodologies came from and how they have continued to adapt to the vastly changed environment in the search engine world today. The lecture

  15. Development of retrievability plans

    International Nuclear Information System (INIS)

    Richardson, P.J.

    1999-03-01

    It has become clear, from monitoring of many national programmes for siting of final repositories for radioactive waste disposal, that the potential or otherwise for retrievability of emplaced wastes is the one issue in particular which is repeatedly raised during public consultation and interaction. Although even those repositories which may be constructed over the next decades will operate for many decades more and be sealed only after a long-term monitoring phase, there is little operational pressure to finalise retrievability concepts. However, as siting processes require detailed conceptual designs to be developed, as do the associated safety assessment exercises, it is becoming increasingly recognised that the potential for retrieval must be examined now. This report is the culmination of a short project carried out for the Swedish National Co-ordinator for Nuclear Waste Disposal to examine the situation as regards the development and possible implementation of retrievability as an integral part of a disposal concept for nuclear waste. Because of the short work period involved, it can at best be only an overview, designed to provide a broad picture of current plans. The Swedish Nuclear Power Inspectorate has begun to examine the issue, and a report is due later in 1999. A major collaborative investigation, which began in March 1998, is also currently underway under the auspices of the EU, but only involves implementing agencies from the various Member States. This report is intended to serve as background to these other studies when they appear. Utilising currently available information, as well as personal contacts, those countries currently examining retrievability or reversibility of disposal in some form have been identified. Information regarding these proposals has been collated, and contact made with relevant agencies and national regulatory bodies where possible. The report includes some review of the technical aspects of retrievability, with especial

  16. Analysis and study of spent fuel reprocessing technology from birth to present

    International Nuclear Information System (INIS)

    Takahashi, Keizo

    2006-01-01

    As for the nuclear fuel reprocessing of the spent fuel, although there was argument of pros and cons, it was decided to start Rokkasho reprocessing project further at the Japan Atomic Energy Commission of ''Long-Term Program for Research, Development and Utilization of Nuclear Energy'' in year 2004. The operation of Tokai Reprocessing is going steadily to reprocess spent fuel more than 1,100 tons. In this paper, history, present status and future of reprocessing technology is discussed focusing from military Pu production, Magnox fuel reprocessing to oxide fuel reprocessing. Amount of reprocessed fuel are estimated based on fuel type. Then, history of reprocessing, US, UK, France, Germany, Russian, Belgian and Japan is presented and compared on technology, national character, development organization, environmental protection, and high active waste vitrification. Technical requirements are increased from Pu production fuel, Magnox fuel and oxide fuel mainly because of higher burnup. Reprocessing technology is synthetic of engineering and accumulation of operational experience. The lessons learned from the operational experience of the world will be helpful for establishment of nuclear fuel reprocessing technology in Japan. (author)

  17. Foreign Body Retrieval

    Medline Plus

    Full Text Available Toggle navigation Test/Treatment Patient Type Screening/Wellness Disease/Condition Safety En Español More Info Images/Videos About Us News Physician Resources Professions Site Index A-Z Foreign Body Retrieval Foreign ...

  18. Information Retrieval Models

    NARCIS (Netherlands)

    Hiemstra, Djoerd; Göker, Ayse; Davies, John

    2009-01-01

    Many applications that handle information on the internet would be completely inadequate without the support of information retrieval technology. How would we find information on the world wide web if there were no web search engines? How would we manage our email without spam filtering? Much of the

  19. Energy Storage and Retrieval

    Indian Academy of Sciences (India)

    Annual Meetings · Mid Year Meetings · Discussion Meetings · Public Lectures · Lecture Workshops · Refresher Courses · Symposia · Live Streaming. Home; Journals; Resonance – Journal of Science Education; Volume 1; Issue 6. Energy Storage and Retrieval The Secondary Battery Route. A K Shukla P Vishnu Kamath.

  20. Foreign Body Retrieval

    Medline Plus

    Full Text Available ... Foreign Body Retrieval Sponsored by Please note RadiologyInfo.org is not a medical facility. Please contact your ... links: For the convenience of our users, RadiologyInfo .org provides links to relevant websites. RadiologyInfo.org , ACR ...

  1. Utah Text Retrieval Project

    Energy Technology Data Exchange (ETDEWEB)

    Hollaar, L A

    1983-10-01

    The Utah Text Retrieval project seeks well-engineered solutions to the implementation of large, inexpensive, rapid text information retrieval systems. The project has three major components. Perhaps the best known is the work on the specialized processors, particularly search engines, necessary to achieve the desired performance and cost. The other two concern the user interface to the system and the system's internal structure. The work on user interface development is not only concentrating on the syntax and semantics of the query language, but also on the overall environment the system presents to the user. Environmental enhancements include convenient ways to browse through retrieved documents, access to other information retrieval systems through gateways supporting a common command interface, and interfaces to word processing systems. The system's internal structure is based on a high-level data communications protocol linking the user interface, index processor, search processor, and other system modules. This allows them to be easily distributed in a multi- or specialized-processor configuration. It also allows new modules, such as a knowledge-based query reformulator, to be added. 15 references.

  2. The Knowledge Retrieval Matrix

    DEFF Research Database (Denmark)

    Gammelgaard, Jens; Ritter, Thomas

    2004-01-01

    AbstractPrevious discussions of knowledge transfer within multinational corporations tended tofocus on the process as an isolated phenomenon and on the factors that impede the process.Less attention has been given to how the individual knowledge worker retrieves or identifies,and then decodes kno...

  3. Music Information Retrieval.

    Science.gov (United States)

    Downie, J. Stephen

    2003-01-01

    Identifies MIR (Music Information Retrieval) computer system problems, historic influences, current state-of-the-art, and future MIR solutions through an examination of the multidisciplinary approach to MIR. Highlights include pitch; temporal factors; harmonics; tone; editorial, textual, and bibliographic facets; multicultural factors; locating…

  4. Information Retrieval in Physics.

    Science.gov (United States)

    Herschman, Arthur

    Discussed in this paper are the information problems in physics and the current program of the American Institute of Physics (AIP) being conducted in an attempt to develop an information retrieval system. The seriousness of the need is described by means of graphs indicating the exponential rise in the number of physics publications in the last…

  5. Review of Design Data for Safety Assessment of Tokai Reprocessing Plant. Control of hydrogen gas produced by radiolysis of reprocessing solutions at Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Omori, E.; Surugaya, N.; Takaya, A.; Nakamura, H.; Maki, A.; Yamanouchi, T.

    1999-10-01

    Radioactive materials in aqueous solution at a nuclear fuel reprocessing plant causes radiolytic generation of several gases including hydrogen. Hydrogen accumulating in equipment can be an explosion hazard. In such plants, though the consideration in the design has been fundamentally made in order to remove the ignition source from the equipment, the hydrogen concentration in the equipment should not exceed the explosion threshold. It is, therefore, desired to keep the hydrogen concentration lower than the explosion threshold by dilution with the air introduced into equipment, from the viewpoint which previously prevents the explosion. This report describes the calculation of hydrogen generation, evaluation of hydrogen concentration under abnormal operation and consideration of possible improvement at Tokai Reprocessing Plant. The amount of hydrogen generation was calculated for each equipment from available data on radiolysis induced by radioactive materials. Taking into consideration for abnormal condition that is single failure of air supply and loss of power supply, the investigation was made on the method for controlling so that the hydrogen concentration may not exceed the explosion threshold. Possible means which can control the concentration of hydrogen gas under the explosion threshold have been also investigated. As the result, it was found that hydrogen concentration of most equipment was kept under the explosion threshold. It was also shown that improvement of the facility was necessary on the equipment in which the concentration of the hydrogen may exceed the explosion threshold. Proposals based on the above results are also given in this report. The above content has been described in 'Examination of the hydrogen produced by the radiolysis' which is a part of 'Reviews of Design Data for Safety Assessment of Tokai Reprocessing Plant' (JNC TN8410 99-002) published in February 1999. This report incorporates the detail evaluation so that operation

  6. Retrievability, ethics and democracy

    International Nuclear Information System (INIS)

    Jensen, M.; Westerlind, M.

    2000-01-01

    Ethics is always a social concern, an integrated part of laws and regulations. Treatment of ethics as a separate part in the decision making process is therefore always debatable. It cannot be introduced as an extraneous component to compensate for, or to improve, a morally flawed practice, and the margin for unethical practices is strongly circumscribed by regulation in the nuclear field, internationally. However, a discussion on different stakeholders and their different ethical concerns should always be welcome. One example is the implementer's views on ethics. Even if they are in complete parity with existing legal and regulatory goals, the goals may still represent the implementer's own motives and choices. Also, stakeholders may view the laws or regulations as unfair. In making the critique, the stakeholder simply formulates a separate political standpoint. Finally, an alternative discussion is to place existing regulations into an ethical perspective - adding a new dimension to the issues. Retrievability for high level waste repositories is often in focus in ethical discussions. Unfortunately, it is used in many ways and has become an unclear term. It may cover anything from planned recuperation to the property of waste being retrievable in years or tens of years, or in the distant time range of hundreds or thousands of years. The term retrievability is often proposed to cover mainly positive qualities such as the option of later changes to the repository or a new disposal concept. However, as ICRP and others have pointed out, it also implies the possibility of: i) operational exposures, ii) continuing risks of accidental releases, iii) financial provisions to cover operating costs and iv) continuing reliance on institutional control, thus imposing some burdens to future generations. In a certain sense, anything can be retrieved from any repository. There is therefore a need for a clear and operable definition of retrievability requirements, including the

  7. Status of the development on simulation technology for pyrochemical reprocessing

    International Nuclear Information System (INIS)

    Arie, Kazuo; Kawabe, Akihiro; Fujita, Reiko; Yamamura, Tsutomu; Sato, Yuzuru; Goto, Takuya; Minato, Kazuo; Tosaka, Ikuo; Amano, Osamu; Yamamoto, Kazuhiko

    2005-01-01

    The computerized simulation technique of element behaviors in pyrochemical reprocessing is largely useful to raise the efficiency in development of pyrochemical reprocessing technique and moreover to operate reasonably practical plans in the near future. The simulation code SPR1.0 has currently been developed, which can simultaneously analyze the electrochemical and chemical reactions and can deal generally also with many elements of study. It was found from some trial calculations that this code can analyze an electrolytic behavior of MOX. The present study was performed by Toshiba Co., Ltd. together with Tohoku University. and Kyoto University as entrusted from Japan Atomic Power Company Co., Ltd. in cooperation with JAERI, Tohoku Electric Power Co., Inc. and Tokyo Electric Power Co., Inc. (M.H.)

  8. Status of development on simulation technology for pyrochemical reprocessing

    International Nuclear Information System (INIS)

    Arie, Kazuo; Mizuguchi, Koji; Fujita, Reiko

    2004-01-01

    Simulation techniques for the elemental behaviors in the pyrochemical reprocessing process of spent nuclear fuels are important for fuel reprocessing and future power station development. The authors developed a simulation code SPR1.0 which can analyze co-occurring electrochemical and chemical reactions simultaneously and which is applicable to know the behavior of any element in the system. The present report describes the status of the code development, the database for fundamental electrochemical reactions, and verification of the code. The code employs TRIAS code for electrochemical reactions and SOLGASMIX-PV for chemical reactions. Electrolytic process for MOX (mixed oxide) fuels with different Pu redox ratios were simulated using the present code and the effect of introducing iron ions was studied. The prospect of future development is also described. (S. Ohno)

  9. Report of the study grou: Data Processing in Reprocessing Plants

    International Nuclear Information System (INIS)

    1976-08-01

    A study group to examine Data Processing in Spent Fuel Reprocessing Plants was created at the request of the Head of Productions and entrusted to the Director of the La Hague Centre. The groupe was made up of engineers working in different fields: piloting, architecture, building outfits, services etc. To begin with the group examined the solutions proposed by the La Hague Centre for the replacement of data processing units in service at the time but too old and unreliable to meet the safety rules laid down. Secondly, as a contribution towards France's heritage in the fuel reprocessing field, the group investigated systems and configurations for possible application to the equipment of future plants. The results of these studies were submitted in January 1974 [fr

  10. Remotex and servomanipulator needs in nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    Garin, J.

    1981-01-01

    Work on the conceptual design of a pilot-scale plant for reprocessing breeder reactor fuels is being performed at Oak Ridge National Laboratory. The plant design will meet all current federal regulations for repocessing plants and will serve as prototype for future production plants. A unique future of the concept is the incorporation of totally remote operation and maintenance of the process equipment within a large barn-like hot cell. This approach, caled Remotex, utilizes servomanipulators coupled with television viewing to extend man's capabilities into the hostile cell environment. The Remotex concept provides significant improvements for fuel reprocessing plants and other nuclear facilities in the areas of safeguarding nuclear materials, reducing radiation exposure, improving plant availability, recovering from unplanned events, and plant decommissioning

  11. The safety of the reprocessing plant of Cogema La Hague

    International Nuclear Information System (INIS)

    Ledermann, P.

    1997-01-01

    The risks associated to the operation of a reprocessing plant come from the important quantities of radioactive matter. To insure the reprocessing safety consists in keeping, in any circumstance, the containment of radioactive matter. That this objective that leads the safety at any step of the factory life. Three risks families are listed: the risks from nuclear origin, associated to the specific physico-chemical behaviours of radioactive matter (dispersion and criticality, thermal risks and risks bound to the hydrogen production); the second family is the group of internal risks resulting from the industrial activity (chemical risks, fire risks, dysfunctions of electric installations or falls of loads); the last family is the group of external risks resulting from the impact of events reaching the site where are established the installations (risks associated to climatic conditions, risks associated to surrounding activities such explosions, fires, impact resulting from the fall of a tourism plane or road transport of hazardous matter). (N.C.)

  12. The measurement of neptunium in fast reactor fuel reprocessing

    International Nuclear Information System (INIS)

    Mair, M.A.; Savage, D.J.; Kyffin, T.W.

    1986-02-01

    Analytical techniques have been developed to measure neptunium in the feed, waste and product streams of a fast reactor fuel reprocessing plant. The estimated level of one microgram per milligram of plutonium in some solutions presented severe separation and measurement problems. An initial separation stage was essential, and both ion exchange and solvent extraction using thenoyltrifluoroacetone were studied. The redox chemistry of neptunium necessary to achieve good separation is considered. Spectrophotometry measurement of the stable neptunium/arsenazo III complex was selected for the final neptunium determination with additional analysis by radiometric methods. Incomplete recovery of neptunium during the separation stages necessitated yield measurements, using either neptunium-237 as an internal standard or the short lived gamma active neptunium-239 isotope as a tracer. The distribution of neptunium between the waste and product streams is discussed, in relation to the chemistry of neptunium in the reprocessing plant. (author)

  13. Nuclear energy without waste reprocessing in West Germany?

    International Nuclear Information System (INIS)

    Ebert, K.

    1989-01-01

    The decision to discontinue construction of the Wackersdorf waste reprocessing plant has been an item of public interest for only a short period; even supporters of nuclear power seemed to have been just relieved that this controversial project was off the agenda, and done with. So only little was to be heard from experts about the facts, background, and consequences of this decision. The author of the article in hand is head of the Hot Chemistry Institute of the Karlsruhe Nuclear Research Centre and therefore has been a leading scientist in the development of reprocessing technology. He presents from his point of view the facts and reasons leading to the decision, and explains the possible consequences for the F.R.G. (orig./RB) [de

  14. Reprocessable thermosets for sustainable three-dimensional printing.

    Science.gov (United States)

    Zhang, Biao; Kowsari, Kavin; Serjouei, Ahmad; Dunn, Martin L; Ge, Qi

    2018-05-08

    Among all three-dimensional (3D) printing materials, thermosetting photopolymers claim almost half of the market, and have been widely used in various fields owing to their superior mechanical stability at high temperatures, excellent chemical resistance as well as good compatibility with high-resolution 3D printing technologies. However, once these thermosetting photopolymers form 3D parts through photopolymerization, the covalent networks are permanent and cannot be reprocessed, i.e., reshaped, repaired, or recycled. Here, we report a two-step polymerization strategy to develop 3D printing reprocessable thermosets (3DPRTs) that allow users to reform a printed 3D structure into a new arbitrary shape, repair a broken part by simply 3D printing new material on the damaged site, and recycle unwanted printed parts so the material can be reused for other applications. These 3DPRTs provide a practical solution to address environmental challenges associated with the rapid increase in consumption of 3D printing materials.

  15. The refurbishment of the D1206 fuel reprocessing plant

    International Nuclear Information System (INIS)

    Bailey, G.

    1988-01-01

    The term decommissioning can be applied not only to reactors but to any nuclear plant, laboratory, building or part of a building that may have been associated with radioactive material and needs to be restored to clean conditions. In this case the decommissioning and reconstruction of the Dounreay Fast Reactor fuel reprocessing plant, so that plutonium oxide could be reprocessed as well as enriched uranium fuel, is described. The work included improving containment and shielding, building a new head-end treatment cave for the more complex and larger fuel elements, improving the ventilation and constructing a new dissolver. In this paper the breakdown cave and dissolver cell are described and compared and the work done explained. (U.K.)

  16. Noble gas atmospheric monitoring for international safeguards at reprocessing plants

    International Nuclear Information System (INIS)

    Nakhleh, C.W.; Poths, J.; Stanbro, W.D.; Perry, R.T. Jr.; Wilson, W.B.; Fearey, B.L.

    1997-01-01

    The use of environmental sampling is a major component of the improvements of International Atomic Energy Agency safeguards being carried out under Program 93+2. Nonradioactive noble gas isotopic measurements in the effluent stream of large reprocessing facilities may provide useful confirmatory information on the burnup and reactor type of the spent fuel undergoing reprocessing. The authors have taken and analyzed stack samples at an operating facility. The data show clear fission signals. The authors are currently applying a maximum-likelihood estimation procedure to determine the fuel burnup from these data. They anticipate that the general features involved in the table noble gas problem--selection of appropriate signals, measurement of those signals under realistic conditions, and inverse calculation of parameters of interest from the environmental data--will be present in all environmental sampling problems. These methods should therefore be widely applicable

  17. Experience of iodine removal in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Kikuchi, K.; Komori, Y.; Takeda, K.

    1985-01-01

    In the Tokai reprocessing plant about 170 ton of irradiated fuels have been processed since the beginning of hot operations in 1977. There was no effective equipment for iodine removal from the off-gas except for alkaline scrubbers when the plant construction was completed. In order to reduce the iodine discharge to the atmosphere, silver-exchanged zeolite (AgX) filters were installed additionally in 1979 and 1980, and they have been effective. However, those decontamination factors (DFs) were not as high as expected, and increasing the reprocessing amount of spent fuels it became necessary to lower the iodine discharge to the atmosphere. Therefore, other iodine removal equipment is planned to be installed in the plant. Concerning these investigations and development of iodine removal techniques, the iodine concentration of actual off-gases was measured and useful data were obtained

  18. Status of CSR RL06 GRACE reprocessing and preliminary results

    Science.gov (United States)

    Save, H.

    2017-12-01

    The GRACE project plans to re-processes the GRACE mission data in order to be consistent with the first gravity products released by the GRACE-FO project. The RL06 reprocessing will harmonize the GRACE time-series with the first release of GRACE-FO. This paper catalogues the changes in the upcoming RL06 release and discusses the quality improvements as compared to the current RL05 release. The processing and parameterization changes as compared to the current release are also discussed. This paper discusses the evolution of the quality of the GRACE solutions and characterize the errors over the past few years. The possible challenges associated with connecting the GRACE time series with that from GRACE-FO are also discussed.

  19. Reprocessing seismic data: better results below diabase sills

    Energy Technology Data Exchange (ETDEWEB)

    Makler, Marisa [Halliburton Servicos Ltda., Rio de Janeiro, RJ (Brazil); Pellizzon, Marcela

    2008-07-01

    The effect of the diabase sills in the seismic data processing has been studied in the last twenty years. These rocks strongly influence the exploratory activities in a basin, because the diabase disturbs the sign and generates multiple and spherical divergence, increasing the exploratory risk in these areas. In the present work a method of 2D seismic reprocessing will be presented using Prestack Kirchhoff Time Migration in an older seismic data of Solimoes basin. The objective of this paper is to show the high results on the reprocessing seismic data below the diabase sills. The 2D lines processed give relevant improvement of the quality of signal, showing better the faults zones and preserving the geological structures than the older data. (author)

  20. Historical fuel reprocessing and HLW management in Idaho

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  1. Continuous chemical cold traps for reprocessing off-gas purification

    International Nuclear Information System (INIS)

    Henrich, E.; Bauder, U.; Steinhardt, H.J.; Bumiller, W.

    1985-01-01

    Absorption of nitrogen oxides and iodine from simulated reprocessing plant off-gas streams has been studied using nitric acid and nitric acid/hydrogen peroxide mixtures at low temperatures. The experiments were carried out at the laboratory and on the engineering scale. The pilot plant scale column has 0.8 m diameter and 16 absorption plates at 0.2 m spacing. Cooling coils on the plates allow operating temperatures down to -60 0 C. The NO concentration in the feed gas usually has been 1% by volume and the flow rate 4-32 m 3 (STP) per hour. The iodine behavior has been studied using I-123 tracer. Results of the study are presented. The chemistry of the processes and the advantages and disadvantages in correlation to the various applications for an off-gas purification in a reprocessing plant are compared and discussed. The processes are compatible with the PUREX process and do not produce additional waste

  2. Decommissioning and dismantling of the reprocessing plant Karlsruhe

    International Nuclear Information System (INIS)

    Eiben, K.; Fritz, P.

    1995-01-01

    Reprocessing activities were discontinued in late 1990. The facility was drained and rinsed, and 80 m3 of HLWC have since been stored in special tanks, awaiting vitrification. Decommissioning work is scheduled to proceed in six phases. The reprocessing areas of the facility will be prepared for release from radiological control and dismantled in the first phase. The remaining facilities can be deregulated, and storage tanks dismantled, only after termination of phase 1. The goal of the following phase is clearance from radiological control of all controlled areas, and the last phase is to cover dismantling of all buildings and restoration of a green field site. The overall costs of these activities are estimated to amount to DM 1.657 million. The article explains the contents of the first permits for decommissioning as well as the documents prepared for planning of work and licence application. (orig./HP) [de

  3. Evaluation of subcritical hybrid systems loaded with reprocessed fuel

    International Nuclear Information System (INIS)

    Velasquez, Carlos E.; Barros, Graiciany de P.; Pereira, Claubia; Veloso, Maria Auxiliadora F.; Costa, Antonella L.

    2015-01-01

    Highlights: • Accelerator driven systems (ADS) and fusion–fission systems are investigated for transmutation and fuel regeneration. • The calculations were performed using Monteburns code. • The results indicate the most suitable system for achieve transmutation. - Abstract: Two subcritical hybrid systems containing spent fuel reprocessed by Ganex technique and spiked with thorium were submitted to neutron irradiation of two different sources: ADS (Accelerator-driven subcritical) and Fusion. The aim is to investigate the nuclear fuel evolution using reprocessed fuel and the neutronic parameters under neutron irradiation. The source multiplication factor and fuel depletion for both systems were analysed during 10 years. The simulations were performed using MONTEBURNS code (MCNP/ORIGEN). The results indicate the main differences when irradiating the fuel with different neutron sources as well as the most suitable system for achieving transmutation

  4. Safety aspects in fuel reprocessing and radioactive waste management

    International Nuclear Information System (INIS)

    Agarwal, K.

    2018-01-01

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

  5. Chemical engineering in fuel reprocessing. The French experience

    International Nuclear Information System (INIS)

    Viala, M.; Sombret, C.; Bernard, C.; Miquel, P.; Moulin, J.P.

    1992-01-01

    Reprocessing is the back-end of the nuclear fuel cycle, designed to recover valuable fissile materials, especially plutonium, and to condition safely all the wastes ready for disposal. For its new commercial reprocessing plants (UP 3 and UP 2 800) COGEMA decided to include many engineering innovations as well as new processes and key-components developed by CEA. UP 3 is a complete new plant with a capacity of 800 t/y which was put in operation in August 1990. UP 2 800 is an extension of the existing UP 2 facility, designed to achieve the same annual capacity of 800 t/y, to be put in operation at the end of 1993 by the commissioning of a new head-end and highly active chemical process facilities

  6. Remote maintenance in TOR fast reactor fuel reprocessing facility

    International Nuclear Information System (INIS)

    Eymery, R.; Constant, M.; Malterre, G.

    1986-11-01

    The TOR facility which is undergoing commissioning tests has a capacity of 5 T. HM/year which is enough for reprocessing all the Phenix fuel, with an excess capacity which is to be used for other fast reactors fuels. It is the result of enlargement and renovation of the old Marcoule pilot facility. A good load factor is expected through the use of equipment with increased reliability and easy maintenance. TOR will also be used to test new equipment developed for the large breeder fuel reprocessing plant presently in the design stage. The latter objective is specifically important for the parts of the plant involving mechanical equipment which are located in a new building: TOR 1. High reliability and flexibility will be obtained in this building thanks to the attention given to the integrated remote handling system [fr

  7. Concept of a tritium extraction facility for a reprocessing plant

    International Nuclear Information System (INIS)

    Tunaboylu, K.; Paulovic, M.; Ulrich, D.

    1991-01-01

    There are several alternatives for reducing the release of tritium to the environment originating from the wastewater of a reprocessing plant. Such alternatives, which are applicable for sites not located by the sea or by large rivers, are limited to either injection of tritiated wastewater into suitable deep geological formations, or final disposal into a deep underground repository after adequate treatment similar to other low and intermediate active waste. Removal of tritium from the wastewater by enrichment represents a further feasible option of the second alternative, which allows reduction of the huge volume of tritiated water to be treated before disposal. A significant volume reduction increases the safety of the subsequent steps such as transport, interim storage and final disposal of tritiated waste, furthermore, decreases the corresponding overall waste management cost. The projected Wackersdorf reprocessing plant has been considered as a reference for assessing the permitted tritium releases and other site characteristics. (orig.)

  8. Abnormal reactions in a evaporator in a fuel reprocessing plant

    International Nuclear Information System (INIS)

    Kida, Takashi; Umeda, Miki; Sugikawa, Susumu

    2003-01-01

    In order to evaluate a self-accelerated reaction in an evaporator in a fuel reprocessing plant due to organic-nitric acid reactions, a development of a calculation code is under way. Mock-up tests were performed to investigate the fluid dynamic behavior of the organic solvent in the evaporator. Based on these results, the model of the calculation code was constructed. This report describes the results of mock-up tests and the model of the calculation code. (author)

  9. Retention of gaseous fission products in reprocessing LMFBR fuels

    International Nuclear Information System (INIS)

    Burch, W.D.; Yarbro, O.O.; Groenier, W.S.; Stephenson, M.J.

    1976-05-01

    The report is devoted to status of the development programme at the Oak Ridge National Laboratory on methods for retaining iodine-131 and 129, Krypton-85, Tritium and Carbon-14 in reprocessing LMFBR fuels. The Iodox process, Fluorocarbon absorption process and Voloxidation process are described for retention of iodine, Krypton-85 and Tritium, respectively. Flowsheets for the different processes are given and results of experimental runs in small engineering-scale equipment are reported

  10. Waste Incidental to Reprocessing Evaluation for Disposing Saltcake to Saltstone

    International Nuclear Information System (INIS)

    Jones, R.T.

    2002-01-01

    This Waste Incidental to Reprocessing Evaluation is performed in accordance with Department of Energy Order 435.1, Radioactive Waste Management. This evaluation is performed in order to determine whether saltcake currently stored in the Tank Farms, when separated from supernate, meets WIR requirements and can therefore be managed as Low Level Waste and disposed in the Saltstone Production and Disposal Facility in Z-Area

  11. Safety assessment of UP3-A reprocessing plant

    International Nuclear Information System (INIS)

    Mercier, J.P.; Guezenec, J.Y.; Poirier, M.C.

    1992-02-01

    This presentation describes how the safety assessment was made of UP3-A plant of the La Hague establishment for the building permit and operating license within the context of French nuclear regulations and the national debate on the need for reprocessing. Other factors discussed are how the public was involved, how the regulations were improved in the process and what the different stages of commissioning consisted of. (author)

  12. Assembly of laboratory line for nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Fidler, J.; Chotivka, V.

    1979-01-01

    The dismantling of a laboratory line for spent fuel reprocessing after the termination of the research programme and the procedures for hot and semi-hot cell decontamination are described. The equipment was mostly disassembled in smaller parts which were then decontaminated by wiping them with cotton wool soaked in detergent and citric acid, varnished with two-component epoxi varnish, wrapped into multiple polyethylene foils, sealed in PVC bags and thus ready for transport. (B.S.)

  13. Potential fire or explosion risks in reprocessing plants

    International Nuclear Information System (INIS)

    Lefort, G.

    1983-05-01

    Installation for reprocessing are large chemical plants handling large quantities of inflammable solvents and products allowing large risk of fire. Further, the chemical process involves the use of oxidizer and reducer agents which can have a very strong chemical activity and by certain circumstances create overpressures or large explosions. This paper shows the principal radioactive consequences we can retain in safety analyses. As an example the combustion phenomenon involved in a solid waste storage silo with irradiated uranium traces is described [fr

  14. The safety of the new reprocessing plants of La Hague

    International Nuclear Information System (INIS)

    Devillers, C.; Dubois, G.

    1987-09-01

    In this document the authors show the main guiding lines on which is based the safety of the new reprocessing plant of La Hague. They are: - the objectives: to limit the impacts on workers and environment - the methods: safety analysis based on the checking and evaluation of significant risks. - the means: to make a safety plant by the use of quality assurance in the conception and in the plant construction [fr

  15. Economic evaluation of reprocessing and thermal reactor recycle

    International Nuclear Information System (INIS)

    Marshall, W.

    This paper provides a summing up of the discussions on economic aspects in WG4. These discussions also took account of the strategic, ecological and public acceptance factors intimately involved. Tentative conclusions are put forward as a basis for discussion. Reprocessing may take place for reasons other than just strictly economic ones. The decisions facing various countries are rationalized by considering their reactions to the range of possible uranium prices and fast reactor costs in the future

  16. The reasons for and against reprocessing of spent fuel elements

    International Nuclear Information System (INIS)

    Gries, W.

    1983-01-01

    In the following the reasons for and against the main methods of waste disposal are compred. The author examines the advantages and disadvantages of waste disposal by reprocessing of spent fuel assemblies or by immediate ultimate storage. To get a general idea the pros and cons are arranged and analysed according to the following subjects: - technology/science, - safety/environment, - profitability, - political aspects. (orig./UA) [de

  17. Status of power reactor fuel reprocessing in India

    International Nuclear Information System (INIS)

    Kansra, V.P.

    1999-01-01

    Spent fuel reprocessing in India started with the commissioning of the Trombay Plutonium Plant in 1964. This plant was intended for processing spent fuel from the 40 MWth research reactor CIRUS and recovering plutonium required for the research and development activities of the Indian Atomic Energy programme. India's nuclear energy programme aims at the recycle of plutonium in view of the limited national resources of natural uranium and abundant quantities of thorium. This is based on the approach which aims at separating the plutonium from the power reactor spent fuel, use it in the fast reactors to breed 233 U and utilise the 233 U generated to sustain a virtually endless source of power through thorium utilisation. The separated plutonium is also being utilised to fabricate MOX fuel for use in thermal reactors. Spent fuel treatment and extracting plutonium from it makes economic sense and a necessity for the Indian nuclear power programme. This paper describes the status and trends in the Indian programme for the reprocessing of power reactor fuels. The extraction of plutonium can also be seen as a far more positive approach to long-term waste management. The closed cycle approach visualised and pursued by the pioneers in the field is now steadily moving India towards the goal of a sustainable source of power through nuclear energy. The experience in building, operating and refurbishing the reprocessing facilities for uranium and thorium has resulted in acquiring the technological capability for designing, constructing, operating and maintaining reprocessing plants to match India's growing nuclear power programme. (author)

  18. Methods for separating actinides from reprocessing and refabrication plant wastes

    International Nuclear Information System (INIS)

    Tedder, D.W.; Finney, B.C.; Blomeke, J.O.

    1979-01-01

    Chemical processing flowsheets have been developed to partition actinides from all actinide-bearing LWR fuel reprocessing and refabrication plant wastes. These wastes include high-activity-level liquids, scrap recovery liquors, HEPA filters and incinerator ashes, and chemical salt wastes such as sodium carbonate scrub solutions, detergent cleanup streams, and alkaline off-gas scrubber liquors. The separations processes that were adopted for this study are based on solvent extraction, cation exchange chromatography, and leaching with Ce 4+ -HNO 3 solution

  19. Eye Movement Desensitization and Reprocessing for Adolescent Depression

    OpenAIRE

    Bae, Hwallip; Kim, Daeho; Park, Yong Chon

    2008-01-01

    While cognitive behavior therapy is considered to be the first-line therapy for adolescent depression, there are limited data on whether other psychotherapeutic techniques are also effective in treating adolescents with depression. This report suggests the potential application of eye movement desensitization and reprocessing (EMDR) for treatment of depressive disorder related, not to trauma, but to stressful life events. At present, EMDR has only been empirically validated for only trauma-re...

  20. Roles of programmable logic controllers in fuel reprocessing plants

    International Nuclear Information System (INIS)

    Mishra, Hrishikesh; Balakrishnan, V.P.; Pandya, G.J.

    1999-01-01

    Fuel charging facility is another application of Programmable Logic Controllers (PLC) in fuel reprocessing plants, that involves automatic operation of fuel cask dolly, charging motor, pneumatic doors, clutches, clamps, stepper motors and rod pushers in a pre-determined sequence. Block diagram of ACF system is given for underlining the scope of control and interlocks requirements involved for automation of the fuel charging system has been provided for the purpose at KARP Plant, Kalpakkam