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Sample records for elaborated reprocessing separation

  1. 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)

  2. Ion chromatographic separation for analysis of radiostrontium in nuclear reprocessing solutions of high ionic strength

    International Nuclear Information System (INIS)

    Lamb, J.D.; Nordmeyer, F.R.; Drake, P.A.; Elder, M.P.; Miles, R.W.

    1989-01-01

    An ion chromatography (IC)-based method was developed for Sr 2+ concentration and separation showing high recoveries of strontium. This procedure permits complete automation. One of the potential weaknesses of the IC approach to sample preconcentration, i.e. sensitivity to solutions of high acid content, common in nuclear reprocessing solution, has been overcome by a novel application of acid suppression technology. (author) 12 refs.; 8 figs.; 3 tabs

  3. Trivalent lanthanide/actinide separation in the spent nuclear fuel wastes' reprocessing

    International Nuclear Information System (INIS)

    Narbutt, J.; Krejzler, J.

    2006-01-01

    Separation of trivalent actinides, in particular americium and curium, from lanthanides is an important step in an advanced partitioning process for future reprocessing of spent nuclear fuels. Since the trivalent actinides and lanthanides have similar chemistries, it is rather difficult to separate them from each other. The aim of presented work was to study solvent extraction of Am(III) and Eu(III) in a system containing diethylhemi-BTP (6-(5,6-diethyl-1,2,4-triazin-3-yl)-2,2'-bipyridine) and COSAN (protonated bis(chlorodicarbollido)cobalt(III)). The system was chosen by several groups working in the integrated EC research Project EUROPART. Several physicochemical properties of the extraction system were analyzed and discussed

  4. Separation of krypton from dissolver off-gas of a reprocessing plant using preparative gas chromatography

    International Nuclear Information System (INIS)

    Matoni, M.

    1984-02-01

    Kr-85 can be separated from the pre-purified purge air in the final processing step of the purification phase for dissolver off-gases of a reprocessing plant with the aid of preparative gas chromatography. Activated carbon adsorbers in combination with helium as carrier gas permits maximum gas mixture through-flow. A separation temperature of 30 0 C is considered optimal. An adsorbent volume of 40 dm 3 is necessary for processing the residual gas flow of 2.5 Nm 3 /h; the adsorbent is divided between 2 columns linked in series each of which are 2 m long with an internal diameter of 100 mm. The helium flow required is five times greater than the off-gas flow. The degree of purity for krypton is greater than 90% for a decontamination factor of greater than 1000. (orig./HP) [de

  5. Separation systems for the nuclear industry: from system elaboration to its validation in radioactive environment

    International Nuclear Information System (INIS)

    Draye, Micheline

    2004-01-01

    My research deals with the end of the electronuclear cycle and aims to design, create, assess and/or improve various separation Systems for spent nuclear fuel reprocessing. The range of roads explored is large from liquid-liquid extraction, tp membrane processes, through solid-liquid extraction. Beyond the development of various concepts for targeted radionuclides separation, the Systems efficiency and stability were studied. Evaluation of irradiation dose on separations was examined based on the needs of the nuclear industry. As an example, after highlighting the great potential of DCH18C6 for the development of a new nuclear fuel reprocessing process, we determined the structure of its degradation products using a suite of analytical techniques (FTIR, NMR, CG-MS and X-ray diffraction). Considering the increasing precautions taken by the nuclear industry, we deem it necessary to expand our investigations into organic stereochemistry of extracting ligands. We determined the stereochemistry of the DCH18C6 radiolysis products. Despite the capacity of the structural analytical techniques used and previously quoted, we synthesized each possible structure to assess ail the proposed fragments. These syntheses allowed us to evaluate the degradation products interference during potential DCH18C6 industrial use and to conclude that its great extraction capabilities and its remarkable chemical and radiochemical stability make the DCH18C6 a reliable candidate for the spent nuclear fuel reprocessing. To vary the available analytical techniques and to develop more relevant scientific approaches, some of the described work was conducted as a part of national and/or international collaborations. In this context, the study of the poly(4-vinylpyridine) (P4VP) resin stability in radioactive medium allowed us to establish a scientific collaboration with the 'Nuclear Physic Institute of Lyon' for the use of a surface analysis fine technique, the Time of Flight

  6. Silver iodide reduction in aqueous solution: application to iodine enhanced separation during spent nuclear fuels reprocessing

    International Nuclear Information System (INIS)

    Badie, Jerome

    2002-01-01

    Silver iodide is a key-compound in nuclear chemistry either in accidental conditions or during the reprocessing of spent nuclear fuel. In that case, the major part of iodine is released in molecular form into the gaseous phase at the time of dissolution in nitric acid. In French reprocessing plants, iodine is trapped in the dissolver off-gas treatment unit by two successive steps: the first consists in absorption by scrubbing with a caustic soda solution and in the second, residual iodine is removed from the gaseous stream before the stack by chemisorption on mineral porous traps made up of beds of amorphous silica or alumina porous balls impregnated with silver nitrate. Reactions of iodine species with the impregnant are assumed to lead to silver iodide and silver iodate. Enhanced separation policy would make necessary to recover iodine from the filters by silver iodide dissolution during a reducing treatment. After a brief silver-iodine chemical bibliographic review, the possible reagents listed in the literature were studied. The choice has been made to use ascorbic acid and hydroxylamine. An experimental work on silver iodide reduction by this two compounds allowed us to determinate reaction products, stoichiometry and kinetics parameters. Finally, the process has been initiated on stable iodine loaded filters samples. (author) [fr

  7. The Nuclear Energy Advanced Modeling and Simulation Safeguards and Separations Reprocessing Plant Toolkit

    Energy Technology Data Exchange (ETDEWEB)

    McCaskey, Alex [ORNL; Billings, Jay Jay [ORNL; de Almeida, Valmor F [ORNL

    2011-08-01

    This report details the progress made in the development of the Reprocessing Plant Toolkit (RPTk) for the DOE Nuclear Energy Advanced Modeling and Simulation (NEAMS) program. RPTk is an ongoing development effort intended to provide users with an extensible, integrated, and scalable software framework for the modeling and simulation of spent nuclear fuel reprocessing plants by enabling the insertion and coupling of user-developed physicochemical modules of variable fidelity. The NEAMS Safeguards and Separations IPSC (SafeSeps) and the Enabling Computational Technologies (ECT) supporting program element have partnered to release an initial version of the RPTk with a focus on software usability and utility. RPTk implements a data flow architecture that is the source of the system's extensibility and scalability. Data flows through physicochemical modules sequentially, with each module importing data, evolving it, and exporting the updated data to the next downstream module. This is accomplished through various architectural abstractions designed to give RPTk true plug-and-play capabilities. A simple application of this architecture, as well as RPTk data flow and evolution, is demonstrated in Section 6 with an application consisting of two coupled physicochemical modules. The remaining sections describe this ongoing work in full, from system vision and design inception to full implementation. Section 3 describes the relevant software development processes used by the RPTk development team. These processes allow the team to manage system complexity and ensure stakeholder satisfaction. This section also details the work done on the RPTk ``black box'' and ``white box'' models, with a special focus on the separation of concerns between the RPTk user interface and application runtime. Section 4 and 5 discuss that application runtime component in more detail, and describe the dependencies, behavior, and rigorous testing of its constituent components.

  8. A review of the separation and immobilisation of krypton arising from nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Judd, S.J.

    1992-01-01

    The techniques for the separation and immobilisation of 85 Kr are reviewed. Particular attention is paid to processes currently available or undergoing development on the technical to industrial scale. Of the separation processes, cryogenic distillation has reached the most advanced stage of development, with a pilot facility already undergoing radioactive demonstration. The PNC Kr-recovery pilot plant, which has a off-gas flow capacity of 110 m 3 hr -1 (approximately 1/4 the scale of THORP), is currently undergoing tests at Tokai Mura. Low-temperature absorption and adsorption processes have also reached the pilot plant stage but have yet to undergo radiological tests. The separated krypton has been conventionally stored as the compressed gas in cylinders, but progress made in encapsulation techniques suggest that more secure immobilisation can be achieved by encapsulation within a metal or zeolite matrix. Processes based on the implantation of krypton in a metal or metal alloy have been demonstrated on the technical scale with the radioactive gas. It is concluded that the technology for the separation, isolation and immobilisation of radioactive krypton is available only on a reduced scale compared with THORP. The investment cost of a 85 Kr management facility for THORP, based on cryogenic distillation followed by immobilisation by implantation in metal and assuming a 20 year plant life, is estimated at 51-57M pounds. The cost of prepurification of the off-gas stream is included in this figure. Accompanying operating costs, including those incurred by disposal of the encapsulate in geological formations, are estimated at 2.2-3.3 M pounds per annum. Further development work under radioactive conditions is still required prior to the application of existing technology to full-scale fuel reprocessing plant. (author)

  9. Simulation codes of chemical separation process of spent fuel reprocessing. Tool for process development and safety research

    International Nuclear Information System (INIS)

    Asakura, Toshihide; Sato, Makoto; Matsumura, Masakazu; Morita, Yasuji

    2005-01-01

    This paper reviews the succeeding development and utilization of Extraction System Simulation Code for Advanced Reprocessing (ESSCAR). From the viewpoint of development, more tests with spent fuel and calculations should be performed with better understanding of the physico-chemical phenomena in a separation process. From the viewpoint of process safety research on fuel cycle facilities, it is important to know the process behavior of a key substance; being highly reactive but existing only trace amount. (author)

  10. Issues for Conceptual Design of AFCF and CFTC LWR Spent Fuel Separations Influencing Next-Generation Aqueous Fuel Reprocessing

    International Nuclear Information System (INIS)

    D. Hebditch; R. Henry; M. Goff; K. Pasamehmetoglu; D. Ostby

    2007-01-01

    In 2007, the U.S. Department of Energy (DOE) published the Global Nuclear Energy Partnership (GNEP) strategic plan, which aims to meet US and international energy, safeguards, fuel supply and environmental needs by harnessing national laboratory R and D, deployment by industry and use of international partnerships. Initially, two industry-led commercial scale facilities, an advanced burner reactor (ABR) and a consolidated fuel treatment center (CFTC), and one developmental facility, an advanced fuel cycle facility (AFCF) are proposed. The national laboratories will lead the AFCF to provide an internationally recognized R and D center of excellence for developing transmutation fuels and targets and advancing fuel cycle reprocessing technology using aqueous and pyrochemical methods. The design drivers for AFCF and the CFTC LWR spent fuel separations are expected to impact on and partly reflect those for industry, which is engaging with DOE in studies for CFTC and ABR through the recent GNEP funding opportunity announcement (FOA). The paper summarizes the state-of-the-art of aqueous reprocessing, gives an assessment of engineering drivers for U.S. aqueous processing facilities, examines historic plant capital costs and provides conclusions with a view to influencing design of next-generation fuel reprocessing plants

  11. Low-temperature technology for the separation of krypton in reprocessing plants under nuclear conditions

    International Nuclear Information System (INIS)

    Gutowski, H.; Schroeder, E.

    1979-01-01

    The present status of the design work aiming at an Installation for the Purification of Dissolver Off-gas (AZUR) is outlined. The technological measures taken to cope with the problems resulting from the specific nuclear conditions are described in detail. The demonstration of a high availability of this technology in hot operation will be an important step towards the realisation of a fuel reprocessing plant. (orig.) [de

  12. 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

  13. Basic research on separation control of long life nuclides in fuel reprocessing processes

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Atsuyuki; Usami, Go [Tokyo Univ. (Japan). Faculty of Engineering; Maeda, Mitsuru; Fujine, Sachio; Uchiyama, Gunzo; Kihara, Takehiro; Asakura, Toshihide; Hotoku, Shinobu

    1996-01-01

    The behavior of technetium (Tc) in nuclear fuel reprocessing processes has become the subject to be elucidated in the transition to distribution process by coextraction and the catalytic action in distribution process. In order to forecast or control the behavior of Tc in reprocessing processes, it is necessary to understand that at which valence Tc exists stably in respective processes. Tc is stable at 7 valence in nitric acid solution expected in reprocessing. In this research, the reaction speed of the oxidation and reduction reactions of rhenium (Re) which simulates Tc was measured by laser Raman spectroscopy which can do high speed analysis of valence. The experimental method is explained. The Raman spectra of Re in the experimental system of this research were measured in perchloric acid solution and nitric acid solution, and compared with the values in literatures. As the result, the validity of this research was assured. It was confirmed that Re(7) was not reduced by sulfamic acid and ascorbic acid. Re(7) was reduced by thiocyanic acid once, but was oxidized again by the reaction of thiocyanic acid and nitric acid. (K.I.)

  14. Separation of actinides and lanthanides from nuclear power reactor fuel reprocessing waste by bidentate organophosphorous extractant

    International Nuclear Information System (INIS)

    Zhao Hugen; Fu Lichun; Wei Xiufang; Liu Suying; Ye Guoan; Yang Liucheng; Jiang Jincai

    1990-01-01

    A multistage countercurrent extraction process is developed for the removal and recovery of actinides and lanthanides by 30(V)% bidentate organophosphorous extractant DHDECMP in diethyl benzene from 3 mol/l nitric acid solution of simulated nuclear power reactor fuel reprocessing waste. In the R-A extraction cycle (6 extraction stages and 2 scrub stages), the recovery efficiency for U, Np. Pu, Am and Gd is 99.95%, 99.40%, 99.95% 99.99% and 99.70% respectively, and the decontamination factor for fission product elements is DF Zr > 3.6 x 10 3 , DF Nb > 3.7 x 10 3 , DF Ru = 6.8, DF Cs > 3.9 x 10 3 and DF Sr > 2.8 x 10 3 respectively. In the R-B cycle (6 stripping stages) for the stripping of Pu , Am and Gd from organic phase, the stripping efficiency for Pu, Am and Gd is 96.58%, >99.65% and > 99.70% respectively. Finally, in the R-C cycle (6 stripping stages) for the stripping of Np and U, the stripping efficiency for Np is 99.95% whereas that for U is 98.02%

  15. A computer code for calculation of solvent-extraction separation in a multicomponent system with reference to nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Carassiti, F.; Liuzzo, G.; Morelli, A.

    1982-01-01

    Nuclear technology development pointed out the need for a new assessment of the fuel cycle back-end. Treatment and disposal of radioactive wastes arising from nuclear fuel reprocessing is known as one of the problems not yet satisfactorily solved, together with separation process of uranium and plutonium from fission products in highly irradiated fuels. Aim of this work is to present an improvement of the computer code for solvent extraction process calculation previously designed by the authors. The modeling of the extraction system has been modified by introducing a new method for calculating the distribution coefficients. The new correlations were based on deriving empirical functions for not only the apparent equilibrium constants, but also the solvation number. The mathematical model derived for calculating separation performance has been then tested for up to ten components and twelve theoretical stages with minor modifications to the convergence criteria. Suitable correlations for the calculation of the distribution coefficients of Uranium, Plutonium, Nitric Acid and fission products were constructed and used to successfully simulate several experimental conditions. (Author)

  16. Treatment and separation of radioactive fission products tritium, rare gases and iodine in nuclear fuel reprocessing plants

    Energy Technology Data Exchange (ETDEWEB)

    Schnez, H.

    1975-07-15

    Rare gases must be separated from the process off-gases of the head-end of the Purex and Thorex processes. To achieve high decontamination factors, the quantity of off-gas should be kept as low as possible. For rare gas separation, there are two possible methods of routing the off-gas: (a) the open flushing gas circuit, in which the purified off-gas (generally air) is passed off via the stack and (b) the closed circuit in which the off-gas (nitrogen or rare gases) is recycled to the dissolver after purification. Tritium must not be entrained into the second extraction cycle or be emitted with off-gases in the form of water vapor (HTO) or HT, but must remain completely in the aqueous phase. Most of the process water is recycled, as a result of which the tritium becomes concentrated in it. This tritiated water is then subjected to tritium rectification at a suitable point in the process. Iodine is very difficult to isolate to a small number of process stages. Present aim is to release the iodine in the dissolver stage into the off-gas, so as to prevent it being entrained into the extraction part. By the injection of hot nitrogen or water vapor into the dissolver or into iodine-containing condensates, all of the iodine is passed into the gaseous phase. Scrubbers can also be used together with iodine-containing condensates to adjust the scrubbing solution. Capital cost of separation plants account for 1 to 10 percent of the total cost of the reprocessing installation, and even more if a sophisticated tritium separation system is required. (DLC)

  17. Carbon dioxide-krypton separation and radon removal from nuclear-fuel-reprocessing off-gas streams

    International Nuclear Information System (INIS)

    Hirsch, P.M.; Higuchi, K.Y.; Abraham, L.

    1982-07-01

    General Atomic Company (GA) is conducting pilot-plant-scale tests that simulate the treatment of radioactive and other noxious volatile and gaseous constituents of off-gas streams from nuclear reprocessing plants. This paper reports the results of engineering-scale tests performed on the CO 2 /krypton separation and radon holdup/decay subsystems of the GA integrated off-gas treatment system. Separation of CO 2 from krypton-containing gas streams is necessary to facilitate subsequent waste processing and krypton storage. Molecular sieve 5A achieved this separation in dissolver off-gas streams containing relatively low krypton and CO 2 concentrations and in krypton-rich product streams from processes such as the krypton absorption in liquid carbon dioxide (KALC) process. The CO 2 /krypton separation unit is a 30.5-cm-diameter x 1.8-m-long column containing molecular sieve 5A. The loading capacity for CO 2 was determined for gas mixtures containing 250 ppM to 2.2% CO 2 and 170 to 750 ppM krypton in either N 2 or air. Gas streams rich in CO 2 were diluted with N 2 to reduce the temperature rise from the heat of adsorption, which would otherwise affect loading capacity. The effluent CO 2 concentration prior to breakthrough was less than 10 ppM, and the adsorption capacity for krypton was negligible. Krypton was monitored on-line with a time-of-flight mass spectrometer and its concentration determined quantitatively by a method of continuous analysis, i.e., selected-ion monitoring. Radon-220 was treated by holdup and decay on a column of synthetic H-mordenite. The Rn-220 concentration was monitored on-line with flow-through diffused-junction alpha detectors. Single-channel analyzers were utilized to isolate the 6.287-MeV alpha energy band characteristic of Rn-220 decay from energy bands due to daughter products

  18. Carbon dioxide-krypton separation and radon removal from nuclear-fuel-reprocessing off-gas streams

    Energy Technology Data Exchange (ETDEWEB)

    Hirsch, P.M.; Higuchi, K.Y.; Abraham, L.

    1982-07-01

    General Atomic Company (GA) is conducting pilot-plant-scale tests that simulate the treatment of radioactive and other noxious volatile and gaseous constituents of off-gas streams from nuclear reprocessing plants. This paper reports the results of engineering-scale tests performed on the CO/sub 2//krypton separation and radon holdup/decay subsystems of the GA integrated off-gas treatment system. Separation of CO/sub 2/ from krypton-containing gas streams is necessary to facilitate subsequent waste processing and krypton storage. Molecular sieve 5A achieved this separation in dissolver off-gas streams containing relatively low krypton and CO/sub 2/ concentrations and in krypton-rich product streams from processes such as the krypton absorption in liquid carbon dioxide (KALC) process. The CO/sub 2//krypton separation unit is a 30.5-cm-diameter x 1.8-m-long column containing molecular sieve 5A. The loading capacity for CO/sub 2/ was determined for gas mixtures containing 250 ppM to 2.2% CO/sub 2/ and 170 to 750 ppM krypton in either N/sub 2/ or air. Gas streams rich in CO/sub 2/ were diluted with N/sub 2/ to reduce the temperature rise from the heat of adsorption, which would otherwise affect loading capacity. The effluent CO/sub 2/ concentration prior to breakthrough was less than 10 ppM, and the adsorption capacity for krypton was negligible. Krypton was monitored on-line with a time-of-flight mass spectrometer and its concentration determined quantitatively by a method of continuous analysis, i.e., selected-ion monitoring. Radon-220 was treated by holdup and decay on a column of synthetic H-mordenite. The Rn-220 concentration was monitored on-line with flow-through diffused-junction alpha detectors. Single-channel analyzers were utilized to isolate the 6.287-MeV alpha energy band characteristic of Rn-220 decay from energy bands due to daughter products.

  19. 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.

  20. The uranium and thorium separation in the chemical reprocessing of the irradiated fuel of thorium and uranium mixed oxides

    International Nuclear Information System (INIS)

    Oliveira, E.F. de.

    1984-09-01

    A bibliographic research has been carried out for reprocessing techniques of irradiated thorium fuel from nuclear reactors. The Thorex/Hoechst process has been specially considered to establish a method for reprocessing thorium-uranium fuel from PWR. After a series of cold tests performed in laboratory it was possible to set the behavior of several parameters affecting the Thorex/Hoechst process. Some comments and suggestions are presented for modifications in the process flosheet conditions. A discussion is carried out for operational conditions such as the aqueous to organic flow ratio the acidity of strip and scrub solutions in the process steps for thorium and uranium recovery. The operation diagrams have been constructed using equilibrium experimental data which correspond to conditions observed in laboratory. (Author) [pt

  1. A technical review of liquid/liquid and solid/liquid separation equipment in the field of nuclear-fuel reprocessing

    International Nuclear Information System (INIS)

    Vassallo, G.

    1981-01-01

    Liquid/liquid extraction is generally accepted as the preferred method in nuclear-fuel reprocessing. However, although many types of liquid/liquid contactors are available, only a few meet the stringent specifications set by the nuclear industry. This report discusses the criteria for contactor selection and then reviews the most important types, namely packed columns, pulsed columns, mixer-setters and centrifugal contactors. Finally, a short section concerned with solid/liquid separations is included because of the possible deleterious effects caused by solids in liquid/liquid contactors

  2. Elaboration of a model of the nuclear fragmentation and application to the method of isotopic separation of projectile fragments

    International Nuclear Information System (INIS)

    Gaimard, J.J.

    1990-10-01

    In this thesis the experimental results on the cross sections for the production of 36 P in the fragmentation of 403 MeV/u 40 Ar on a carbon target are presented. Furthermore some models of the nuclear fragmentation are elaborated and compared by means of experimental data for the production of gold and cerium isotopes in the reaction 12 C+ 209 Bi at 400 MeV/u, of chlorine, sulfur, aluminium, magnesium, and oxygen isotopes in the reactions 40 Ar+ 12 C at 600 MeV/u and 48 Ca+ 9 Be at 212 MeV/u, and of cobalt, manganese, vanadium, and scandium isotopes together with the charge distributions for A=43 and A=44 in the reactions 40 Ar+ 64 Cu at 2 GeV/u and 56 Fe+ 12 C at 600 MeV/u. (HSI)

  3. 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

  4. Development of Kr-85 separation methods from the waste gas of large reprocessing plants: results for the prototype experimental plants Adamo and Kreta

    International Nuclear Information System (INIS)

    Ammon, R.V.; Bumiller, W.; Hutter, E.; Neffe, G.

    1979-01-01

    The concept followed at the Nuclear Research Centre, of the separation of radioactive Kr from reprocessing plant waste gas, provides for the low temperature rectification (TTR) of the liquefied gas mixture as the last stage of the whole waste gas purification line. As the first step in testing this concept, the KRETA test plant was erected; this was designed for a throughput of 50 Nm 3 /h of a synthetic, ie, cold gas mixture. Thus the plant was about 1/4 to 1/6 th the scale of the large reprocessing plant. Details were reported in the PNS annual colloquium of 1975. This plant has now been operating well for a year: a report is presented on the results. The present operation of the KRETA and the ADAMO (adsorption plant) test facilities has shown that the rectification of the ternary system N 2 -Kr-Xe is possible if certain limit concentrations of Kr And Xe are contained in the feed gas. If the Xe concentration is less than 900 ppm the waste gas can be fed in unaltered; if it is more then Kr must be added in order to increase the Kr/Xe ratio. The Kr return fraction as is provided for in the AZUR project, could be simulated by variations of the feed gas. (author)

  5. 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

  6. Determination of 230Th (Ionium) in uranium ores and wastes from uranium reprocessing. IV. Calculation of ionium separation yield

    International Nuclear Information System (INIS)

    Galiano Sedano, J. A.; Acena Barrenechea, M. L.

    1974-01-01

    For determining ionium ( 2 30Th) in minerals and uranium processing wastes by precipitation with fluorhidric acid, using lanthanum as carrier, and selective extraction with tenoytrifluoroacetone (TTA) followed by radiometric determination of the isolated nuclide, it is necessary the use of a tracer since the chemical yield of the separation ranges between wide limits. In this paper, the use of the beta-emitter 2 34Th as the most convenient tracer is discussed. Equations are derived for correcting for counting errors introduced by other thorium isotopes which are present either in the sample or in the tracer, as well as for calculating the chemical yield of the separation. These equations have been experimentally checked by ionium determinations carried out with different types of samples. (Author) 18 refs

  7. Strategy and current state of research on enhanced iodine separation during spent fuel reprocessing by the Purex process

    Energy Technology Data Exchange (ETDEWEB)

    Devisme, F.; Juvenelle, A.; Touron, E. [CEA Valrho, Dir. de l' Energie Nucleaire, DEN/DRCP, 30 - Marcoule (France)

    2001-07-01

    An enhanced separation process designed to recover and purify molecular iodine desorbed during dissolution is described in the context of {sup 129}I management in the Purex process for transmutation or interim storage. It involves reducing acid scrubbing with hydroxyl-ammonium nitrate followed by oxidation with hydrogen peroxide to obtain selective desorption. The stoichiometry and kinetics are determined for each step and an experimental validation program is now in progress using a small pilot facility equipped with a scrubbing column. The technical feasibility of the process has already been demonstrated: room-temperature scrubbing with a HAN solution (0,5 mol.L{sup -1}) at a pH of about 5 results in 99% iodine trapping efficiency; the subsequent desorption yield is 99,5%. (author)

  8. 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

  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. 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)

  12. 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.)

  13. 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

  14. Nuclear Fuel Reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Michael F. Simpson; Jack D. Law

    2010-02-01

    This is an a submission for the Encyclopedia of Sustainable Technology on the subject of Reprocessing Spent Nuclear Fuel. No formal abstract was required for the article. The full article will be attached.

  15. Choosing a reprocessing method.

    Science.gov (United States)

    Bolding, Barbara

    2004-06-01

    The choice of a reprocessing method depends on many factors and there is no one perfect method that suits all situations. The needs of patients, staff and the healthcare facility, as well as the types of products available at any given time, will all influence the decision. And that decision will not be final. Products change as do consumer needs. As a result the reprocessing decision will need to be reviewed, on a regular basis, in order to ensure that it remains current.

  16. AKUT: a process for the separation of aerosols, krypton, and tritium from burner off-gas in HTR-fuel reprocessing

    International Nuclear Information System (INIS)

    Laser, M.; Barnert-Wiemer, H.; Beaujean, H.; Merz, E.; Vygen, H.

    1975-01-01

    The AKUT process consists of the following process steps: (1) aerosol retention by an electrostatic separator followed by HEPA filters, (2) oxidation of CO with O 2 or reaction of excess O 2 with CO, respectively, (3) compression, (4) scrubbing and/or liquefaction, (5) separation of krypton by distillation, and (6) separation of tritiated water and iodine by adsorption or chemical reaction. Liquefied off-gas with low permanent gas content resulting from graphite burning with oxygen may be distilled at ambient temperature. Off-gas with higher permanent gas content from burning with oxygen enriched air must be processed at lower temperature. The ambient temperature flow sheet is preferable from an economic as well as safety point of view. (U.S.)

  17. 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

  18. 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)

  19. 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''

  20. 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.)

  1. 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

  2. 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

  3. 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.)

  4. 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)

  5. 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

  6. Elaborating on Threshold Concepts

    Science.gov (United States)

    Rountree, Janet; Robins, Anthony; Rountree, Nathan

    2013-01-01

    We propose an expanded definition of Threshold Concepts (TCs) that requires the successful acquisition and internalisation not only of knowledge, but also its practical elaboration in the domains of applied strategies and mental models. This richer definition allows us to clarify the relationship between TCs and Fundamental Ideas, and to account…

  7. 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

  8. 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

  9. 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

  10. Reprocessing in Luminous Disks

    Science.gov (United States)

    Bell, K. Robbins; DeVincenzi, Donald L. (Technical Monitor)

    1999-01-01

    We develop and investigate a procedure that accounts for disk reprocessing of photons that originate in the disk itself. Surface temperatures and simple, black body spectral energy distributions (SEDs) of protostellar disks are calculated. In disks that flare with radius, reprocessing of stellar photons results in temperature profiles considerably shallower than r(sup -3/4). Including the disk as a radiation source (as in the case of actively secreting disks) along with the stellar source further flattens the temperature profile. Disks that flare strongly near the star and then smoothly curve over and become shadowed at some distance ("decreasing curvature" disks) exhibit nearly power-law temperature profiles which result in power-law infrared SEDs with slopes in agreement with typical observations of young stellar objects. Disk models in which the photospheric thickness is controlled by the local opacity and in which the temperature decreases with radius naturally show this shape. Uniformly flaring models do not match observations as well; progressively stronger reprocessing at larger radii leads to SEDs that flatten toward the infrared or even have a second peak at the wavelength corresponding (through the Wien law) to the temperature of the outer edge of the disk. In FU Orionis outbursting systems, the dominant source of energy is the disk itself. The details of the reprocessing depend sensitively on the assumed disk shape and emitted temperature profile. The thermal instability outburst models of Bell Lin reproduce trends in the observed SEDs of Fuors with T varies as r(sup -3/4) in the inner disk (r approx. less than 0.25au corresponding to lambda approx. less than 10 microns) and T varies as r(sup -1/2) in the outer disk. Surface irradiation during outburst and quiescence is compared in the region of planet formation (1 - 10 au). The contrast between the two phases is diminished by the importance of the reprocessing of photons from the relatively high mass

  11. EDRP public local inquiry, UKAEA/BNFL precognition on: PFR fuel reprocessing and radioactive waste management at Dounreay

    International Nuclear Information System (INIS)

    Pugh, O.

    1986-01-01

    A description of PFR fuel reprocessing at Dounreay is given, including brief details of fuel assembly transport, dismantling, chemical separation processes and reprocessing experience. The origin of radioactive wastes from PFR reprocessing, and the types of radioactive waste are outlined. The management of radioactive waste, including storage, treatment and disposal is described. (U.K.)

  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. Reprocessing RERTR silicide fuels

    International Nuclear Information System (INIS)

    Rodrigues, G.C.; Gouge, A.P.

    1983-05-01

    The Reduced Enrichment Research and Test Reactor Program is one element of the United States Government's nonproliferation effort. High-density, low-enrichment, aluminum-clad uranium silicide fuels may be substituted for the highly enriched aluminum-clad alloy fuels now in use. Savannah River Laboratory has performed studies which demonstrate reprocessability of spent RERTR silicide fuels at Savannah River Plant. Results of dissolution and feed preparation tests and solvent extraction processing demonstrations with both unirradiated and irradiated uranium silicide fuels are presented

  14. 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

  15. 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

  16. 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)

  17. 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

  18. 1. round table - Spent fuels composition. Back-end of the fuel cycle and reprocessing, plutonium and other nuclear materials management. 2. round table - Separation-transmutation. 3. round table - Scenarios for a long term inventory of nuclear materials and wastes

    International Nuclear Information System (INIS)

    2005-01-01

    The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprises 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is the synthesis of the round table debates which took place at Paris on the reprocessing of spent fuels. Three aspects are discussed: the risks linked with the recovery of valorizable materials, the economical viability of the separation/transmutation option, and the future of the nuclear option in the French energy policy. Six presentations (transparencies) are attached with these proceedings which treat of: the reprocessing/recycling to the test, perspectives of future wastes, present day wastes/valorizable materials and future scenarios, critical analysis scenarios, why reprocessing spent fuels?, processing of spent fuels and recycling, separation and transmutation of long-lived radioactive wastes, thorium-uranium cycle. (J.S.)

  19. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Hanzawa, Masatoshi; Morioka, Nobuo [Advanced Systems Center, Mitsubishi Materials Corp., Tokyo (Japan); Fumoto, Hiromichi [Strategical Planning Dept., Energy and Ecosystem Business Company, Mitsubishi Materials Corp., Tokyo (Japan); Nishimura, Kenji; Chikazawa, Takahiro [Energy and Ecosystem Laboratories, Mitsubishi Materials Corp., Naka, Ibaraki (Japan)

    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)

  1. 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

  2. Material control for a reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

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

    1976-08-15

    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.

  3. 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

  4. Application of steric exclusion chromatography for the separation of degradation products of the solvent used for the reprocessing of the nuclear fuels; Application de la chromatographie d`exclusion sterique a la separation de produits de degradation du solvant du retraitement des combustibles nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Pozo, C.

    1993-08-01

    The solvent, used in France in Purex reprocessing plants at La Hague is tributylphosphate (TBP) diluted to 30% with a mixture of branched alkanes, for which the main component is branched dodecane (70%). In order to minimize volumes of organic wastes, we have to maintain Purex solvent qualities and to get rid of degradation products. The subject of this memoir concerns among all the degradation products the heaviest molecules. The separation and the identification of these products have been carried out by preparative steric exclusion chromatography, followed by the analysis of the samples by various analytical methods. An inactive residue containing heavy degradation products was prepared according to the process used in the UP3 La Hague plant. The Analysis of this residue using steric exclusion chromatography and GPC/MS methods, shows the presence of three families of compounds heavier than TBP: the ``dimers of TBP`` (provided from the addition of two molecules of TBP), the ``TBP-alkanes`` (the main molecule is the result of the addition of dodecane with TBP), and ``the functionalized TBP`` (hydroxyled TBP, nitrous TBP, nitrated TBP). Plutonium (IV) retention tests were made on the various fractions generated by steric chromatography. They showed that ``the dimers of TBP`` and ``the functionalized TBP`` families are responsible for that retention. These results confirm the good efficiency of the solvent distillation system operated in UP3 plant which allow the elimination of heavy degradation products of the solvent with the residue and then restore excellent extracting properties for the recycled solvent. (author). 35 figs., 69 refs., 15 tabs.

  5. Irradiated fuel reprocessing

    International Nuclear Information System (INIS)

    Ruiz, C.P.; Peterson, J.P. Jr.

    1977-01-01

    A process for separately recovering uranium, plutonium and neptunium substantially free of fission products from irradiated nuclear fuel is presented in which the fuel is dissolved in a strong mineral acid forming an aqueous dissolved nuclear fuel solution and treated to separate the uranium, plutonium and neptunium therefrom substantially free of said fission products by the sequential steps of solvent extraction, ion exchange and fluorination. The process has an improvement comprising the addition of a sufficient quantity of an additive of a stable metallic complex to the aqueous dissolved nuclear fuel solution prior to solvent extraction. This achieves improved purity of the separated uranium, plutonium and neptunium

  6. Spent fuel reprocessing method

    International Nuclear Information System (INIS)

    Shoji, Hirokazu; Mizuguchi, Koji; Kobayashi, Tsuguyuki.

    1996-01-01

    Spent oxide fuels containing oxides of uranium and transuranium elements are dismantled and sheared, then oxide fuels are reduced into metals of uranium and transuranium elements in a molten salt with or without mechanical removal of coatings. The reduced metals of uranium and transuranium elements and the molten salts are subjected to phase separation. From the metals of uranium and transuranium elements subjected to phase separation, uranium is separated to a solid cathode and transuranium elements are separated to a cadmium cathode by an electrolytic method. Molten salts deposited together with uranium to the solid cathode, and uranium and transuranium elements deposited to the cadmium cathode are distilled to remove deposited molten salts and cadmium. As a result, TRU oxides (solid) such as UO 2 , Pu 2 in spent fuels can be reduced to U and TRU by a high temperature metallurgical method not using an aqueous solution to separate them in the form of metal from other ingredients, and further, metal fuels can be obtained through an injection molding step depending on the purpose. (N.H.)

  7. Corrosion aspects in reprocessing technology

    International Nuclear Information System (INIS)

    Fauvet, P.; Pinard Legry, G.

    1992-01-01

    This paper presents two examples illustrating the importance of the physicochemical conditions existing at the metal-medium interface on the corrosion behaviour of materials utilized in spent fuel reprocessing plants: corrosion of a stainless steel in the presence of nitric acid condensates, which is much more severe than in the liquid bulk; behaviour of zirconium, which has an outstanding corrosion resistance in nitric acid, but may suffer depassivation in drastic conditions (not existing in reprocessing plants), with the consequence of a loss of the protective effect of the zirconia passive layer

  8. Gloves Reprocessing: Does It Really Save Money?

    OpenAIRE

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

    2015-01-01

    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 glov...

  9. 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

  10. 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

  11. Reprocessing of reusable medical devices.

    Science.gov (United States)

    Malchesky, P S; Chamberlain, V C; Scott-Conner, C; Salis, B; Wallace, C

    1995-01-01

    Advances in medical science and, in particular, minimally invasive surgical and diagnostic procedures have stimulated the development of new and improved medical devices. This has been made possible because of developments in engineering and material sciences. The design of devices for reusability is particularly important in an effort to provide cost effective healthcare. Concerns and issues include the ability to safely and effectively reprocess the devices, infection prevention and control, safety of the patient and healthcare worker, environmental concerns, and effective use of resources. From an infection prevention point of view, present requirements are based upon the intended use of the devices. Critical devices require sterilization. Semi-critical devices require, as a minimum, high level disinfection. Sterilization is, however, preferred whenever possible. Before sterilization or disinfection, devices should be cleaned adequately. Device designs should be readily amenable to cleaning and sterilization. In the past, design requirements focused primarily on the clinical user and device functionality, with reuse considerations left to the user. In the current market, the customer is redefined and, for reusable medical devices, includes all those associated with the device through the reprocessing procedure. In addition, regulations require that manufacturers give detailed instructions for reprocessing medical devices. The device users have the obligation to follow reprocessing instructions. Many choices exist today in device designs, including disposable or reusable devices. The user needs to balance cost versus convenience and reprocessing requirements for reusables. Current trends are to reuse more devices, including many of which were meant to be disposable. Cost effective designs can best be achieved when the user and manufacturer work together on the design.(ABSTRACT TRUNCATED AT 250 WORDS)

  12. 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

  13. 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

  14. Economics and resources analysis of the potential use of reprocessing options by the current Spanish nuclear reactor park

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez-Velarde, F.; Merino Rodriguez, I.; Gonzalez-Romero, E.

    2014-07-01

    Reprocessing of irradiated nuclear fuel serves multiple purposes, from Pu separation and recovery for MOX fuel fabrication to reduction of high level waste volume, and is nowadays being implemented in several countries like France, Japan, Russia or United Kingdom. This work is aimed at exploring the possibility (in resources and economic terms) of implementing reprocessing for MOX fabrication in Spain. (Author)

  15. The integral fast reactor fuels reprocessing laboratory at Argonne National Laboratory, Illinois

    International Nuclear Information System (INIS)

    Wolson, R.D.; Tomczuk, Z.; Fischer, D.F.; Slawecki, M.A.; Miller, W.E.

    1986-09-01

    The processing of Integral Fast Reactor (IFR) metal fuel utilizes pyrochemical fuel reprocessing steps. These steps include separation of the fission products from uranium and plutonium by electrorefining in a fused salt, subsequent concentration of uranium and plutonium for reuse, removal, concentration, and packaging of the waste material. Approximately two years ago a facility became operational at Argonne National Laboratory-Illinois to establish the chemical feasibility of proposed reprocessing and consolidation processes. Sensitivity of the pyroprocessing melts to air oxidation necessitated operation in atmosphere-controlled enclosures. The Integral Fast Reactor Fuels Reprocessing Laboratory is described

  16. Modernization of SNF WWER-440 reprocessing at RPA 'Mayak'

    International Nuclear Information System (INIS)

    Fedorov, Yuri S.; Anisimov, Oleg P.; Zilberman, Boris Ya.; Ryabkov, Dmitry V.; Kirillov, Sergey N.; Kolupaev, Dmitry N.; Logunov, Mikhail V.; Kudryavtsev, Evgeny G.; Khaperskaya, Anjilika V.

    2011-01-01

    RT-1 plant for SNF WWER-440 reprocessing situated at the RPA 'Mayak' has been in operation for more than 30 years. During this time the requirements to the radioactive waste management has become more rigid. In this respect the results of our earlier works directed on improvement of RT-1 technology and on creation of the Experimental and Demonstration Center at the Mining-Chemical Combine were thoroughly analyzed and revised. As a result, the variants of SNF reprocessing improvement were developed aimed at termination of the liquid process radioactive waste disposal and its compatibility with existing infrastructure of PT-1 plant. Chosen promising approaches are: implementation of the SNF voloxidation after fuel assembly cutting in order to remove tritium before fuel dissolution, separation of the evaporation processes of HLW generated in NPP SNF reprocessing and that of highly enriched aluminum-based SNF for subsequent vitrification of the bottoms of the first process as a borosilicate glass and direction of the second one to long-lived radionuclide partitioning in order to provide further cementation of the excess aluminum. Modernization of the process units of the RT-1 plant would provide SNF reprocessing within the limits of modern ecological requirements. (author)

  17. 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.)

  18. 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

  19. 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.)

  20. 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

  1. Solvent distillation studies for a purex reprocessing plant

    International Nuclear Information System (INIS)

    Ginisty, C.; Guillaume, B.

    1990-01-01

    A distillation system has been developed for regeneration of Purex solvent and will be implemented for the first time in a reprocessing plant. The results are described and analyzed, with emphasis on laboratory experiments which were made with a radioactive plant solvent. Particularly the distillation provides a good separation of solvent degradation products, which was verified by measurements of interfacial tension and plutonium or ruthenium retention. 16 refs., 3 figs., 5 tabs

  2. Irradiated uranium reprocessing, Final report I-VI, Part VI - Separation of uranium, plutonium and fission products from HNO3 solution on the zirconium phosphate (part I), Adsorption equilibrium and kinetics

    International Nuclear Information System (INIS)

    Gal, I.; Ruvarac, A.

    1961-12-01

    Separation of uranium, plutonium and long-lived fission products was investigated on a inorganic ion exchanger. Zirconium phospate was chosen for this purpose because its ion exchanger properties were well known. This report deals with the study of equilibrium and kinetics of the adsorption

  3. 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

  4. 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.)

  5. 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.

  6. SPIRIT 2013 explanation and elaboration

    DEFF Research Database (Denmark)

    Chan, An-Wen; Tetzlaff, Jennifer M; Gøtzsche, Peter C

    2013-01-01

    (Standard Protocol Items: Recommendations for Interventional Trials). The SPIRIT Statement provides guidance in the form of a checklist of recommended items to include in a clinical trial protocol. This SPIRIT 2013 Explanation and Elaboration paper provides important information to promote full...... understanding of the checklist recommendations. For each checklist item, we provide a rationale and detailed description; a model example from an actual protocol; and relevant references supporting its importance. We strongly recommend that this explanatory paper be used in conjunction with the SPIRIT Statement...

  7. 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

  8. 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

  9. 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

  10. Gadow's relational narrative: an elaboration.

    Science.gov (United States)

    Hess, Joanne D

    2003-07-01

    Nurse philosopher Sally Gadow (1999) has proposed the relational narrative between patient and nurse as a 'postmodern turn' for nursing ethics. She has conceptualized this moral approach as the construction by patient and nurse of a coauthored narrative describing the good they are seeking, as well as the means to achieve this good. The purpose of this article is to provide an elaboration of Gadow's seminal conceptualization of relational narrative based on her writings and those of other philosophers. The article will further develop relational narrative's foundations in relationship and narrative and will explore engagement as a dimension essential to its creation and growth. The elaboration first builds on the notion of relationship as foundational to this postmodern moral perspective. Narrative then is advanced as being at the heart of the patient-nurse relationship and their relational narrative, based on an exploration of narrative's role in the moral realm as an epistemology for patient and nurse. Finally, the dialogic and embodied engagement expressed by a relational narrative is developed as a critical element of the ethic.

  11. 1. round table - Spent fuels composition. Back-end of the fuel cycle and reprocessing, plutonium and other nuclear materials management. 2. round table - Separation-transmutation. 3. round table - Scenarios for a long term inventory of nuclear materials and wastes; 1. table ronde - La composition des combustibles uses. L'aval du combustible et le retraitement, la gestion du plutonium et des autres matieres nucleaires. 2. table ronde - Separation-transmutation. 3. table ronde - Scenarii pour un inventaire des matieres et des dechets nucleaires a LT

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprises 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is the synthesis of the round table debates which took place at Paris on the reprocessing of spent fuels. Three aspects are discussed: the risks linked with the recovery of valorizable materials, the economical viability of the separation/transmutation option, and the future of the nuclear option in the French energy policy. Six presentations (transparencies) are attached with these proceedings which treat of: the reprocessing/recycling to the test, perspectives of future wastes, present day wastes/valorizable materials and future scenarios, critical analysis scenarios, why reprocessing spent fuels?, processing of spent fuels and recycling, separation and transmutation of long-lived radioactive wastes, thorium-uranium cycle. (J.S.)

  12. Radioactive Iodine and Krypton Control for Nuclear Fuel Reprocessing Facilities

    Directory of Open Access Journals (Sweden)

    Nick R. Soelberg

    2013-01-01

    Full Text Available The removal of volatile radionuclides generated during used nuclear fuel reprocessing in the US is almost certain to be necessary for the licensing of a reprocessing facility in the US. Various control technologies have been developed, tested, or used over the past 50 years for control of volatile radionuclide emissions from used fuel reprocessing plants. The US DOE has sponsored, since 2009, an Off-gas Sigma Team to perform research and development focused on the most pressing volatile radionuclide control and immobilization problems. In this paper, we focus on the control requirements and methodologies for 85Kr and 129I. Numerous candidate technologies have been studied and developed at laboratory and pilot-plant scales in an effort to meet the need for high iodine control efficiency and to advance alternatives to cryogenic separations for krypton control. Several of these show promising results. Iodine decontamination factors as high as 105, iodine loading capacities, and other adsorption parameters including adsorption rates have been demonstrated under some conditions for both silver zeolite (AgZ and Ag-functionalized aerogel. Sorbents, including an engineered form of AgZ and selected metal organic framework materials (MOFs, have been successfully demonstrated to capture Kr and Xe without the need for separations at cryogenic temperatures.

  13. 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.)

  14. 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

  15. 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)

  16. Density and volume measurements of reprocessing plant feed

    International Nuclear Information System (INIS)

    Platzer, R.; Carrier, M.; Neuilly, M.; Dedaldechamp, P.

    1985-05-01

    A theoretical study of the phenomenon of gas bubbles formation within a liquid led to an adaptation of the differential pressure bubbling technique for the measurement of liquid levels and densities in tanks. Experiments, carried out on a 800 liters tank with water and uranyl nitrate solutions had the double aim to study the precision attainable on volume and density measurements and to design a method for corrections of influencing factors. In parallel, procedures for transfer of known volumes through the use of siphons and for tank calibration by liquid level measurement are also investigated. The paper presents the first results obtained so far and the conclusions to be drawn for the elaboration of calibration and exploitation procedures suitables for use in reprocessing plants. The demonstration to transfer mass of solution with an accuracy of 0.1% is made [fr

  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. Reprocessing of PLA/Graphene Nanoplatelets Nanocomposites

    Directory of Open Access Journals (Sweden)

    Luigi Botta

    2017-12-01

    Full Text Available This work reports a study on the effect of multiple reprocessing on the properties of poly(lactic acid (PLA filled with graphene nanoplatelets (GnP compared to the melt reprocessed neat polymeric matrix. In particular, morphological, X-Ray Diffraction and Micro-Raman analyses, intrinsic viscosity measurements, thermal, rheological and mechanical tests were carried out on materials reprocessed up five times by means of a single screw extruder. The results indicated that the presence of GnP decreased the degradation rate as a function of the reprocessing cycles in comparison with the neat PLA that, on the contrary, showed a more drastic reduction of the molecular weight. Moreover, the reprocessing improved the particle dispersion and reduced the presence of GnP aggregates.

  19. 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)

  20. Pyro-electrochemical reprocessing of irradiated MOX fast reactor fuel, testing of the reprocessing process with direct MOX fuel production

    International Nuclear Information System (INIS)

    Kormilitzyn, M.V.; Vavilov, S.K.; Bychkov, A.V.; Skiba, O.V.; Chistyakov, V.M.; Tselichshev, I.V.

    2000-01-01

    One of the advanced technologies for fast reactor fuel recycle is pyro-electrochemical molten salt technology. In 1998 we began to study the next phase of the irradiated oxide fuel reprocessing new process MOX → MOX. This process involves the following steps: - Dissolution of irradiated fuel in molten alkaline metal chlorides, - Purification of melt from fission products that are co-deposited with uranium and plutonium oxides, - Electrochemical co-deposition of uranium and plutonium oxides under the controlled cathode potential, - Production of granulated MOX (crushing,salt separation and sizing), and - Purification of melt from fission products by phosphate precipitation. In 1998 a series of experiments were prepared and carried out in order to validate this process. It was shown that the proposed reprocessing flowsheet of irradiated MOX fuel verified the feasibility of its decontamination from most of its fission products (rare earths, cesium) and minor-actinides (americium, curium)

  1. Application of a room temperature ionic liquid for nuclear spent fuel reprocessing: speciation of trivalent europium and solvatation effects; Application d'un liquide ionique basse temperature pour les procedes de separation: speciation de l'europium trivalent et effets solvatation

    Energy Technology Data Exchange (ETDEWEB)

    Moutiers, G.; Mekki, S. [CEA Saclay, Dept. de Physico-Chimie, Service de Chimie Physique, 91 - Gif sur Yvette (France); Billard, I. [IN2P3/CNRS, 69 - Villeurbanne (France)

    2007-07-01

    One of the solutions proposed for the optimization of the long term storage and conditioning of spent nuclear fuel is to separate actinide and lanthanide both from each other and from other less radioactive metallic species. The industrial proposed processes, based on liquid liquid extraction steps, involve solvents with non negligible vapour pressure and may generate contaminated liquid wastes that will have to be reprocessed. During the last decade, some room-temperature ionic liquids have been studied and integrated into industrial processes. The interest on this class of solvent came out from their 'green' properties (non volatile, non flammable, recyclable, etc...), but also from the variability of their physico-chemical properties (stability, hydrophobicity, viscosity) as a function of the RTIL chemical composition. Indeed, it has been shown that classical chemical industrial processes could be transferred into those media, even more improved, while a certain number of difficulties arising from using traditional solvent can be avoided. In this respect, it could be promising to investigate the ability to use room temperature ionic liquid into the spent nuclear fuel reprocessing field. The aim of this this study is to test the ability of the specific ionic liquid bumimTf{sub 2}N to allow trivalent europium extraction. The choice of this metal is based on the chemical analogy with trivalent minor actinides Curium and Americium which are contributing the greatest part of the long-lived high level radioactive wastes. Handling these elements needs to be very cautious for the safety and radioprotection aspect. Moreover, europium is a very sensitive luminescent probe to its environment even at the microscopic scale. The report is structured with four parts. In a first chapter, we present the main physico-chemical properties of an imidazolium-based ionic liquid family, and then we choose the ionic liquid bumimTf{sub 2}N for the whole thesis and start with

  2. 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)

  3. A survey of methods to immobilize tritium and carbon-14 arising from a nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Taylor, P.

    1991-02-01

    This report reviews the literature on methods to separate and immobilize tritium ( 3 H) and carbon-14 ( 14 C) released from U0 2 fuel in a nuclear fuel reprocessing plant. It was prepared as part of a broader review of fuel reprocessing waste management methods that might find future application in Canada. The calculated inventories of both 3 H and 14 C in used fuel are low; special measures to limit releases of these radionuclides from reprocessing plants are not currently in place, and may not be necessary in future. If required, however, several possible approaches to the concentration and immobilization of both radionuclides are available for development. Technology to control these radionuclides in reactor process streams is in general more highly developed than for reprocessing plant effluent, and some control methods may be adaptable to reprocessing applications

  4. 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.

  5. An overview on dry reprocessing of irradiated nuclear fuels

    International Nuclear Information System (INIS)

    Ouyang Yinggen

    2002-01-01

    Although spent nuclear fuels have been reprocessed successfully for many years by the well-know Purex process based on solvent extraction, other reprocessing method which do not depend upon the use of organic solvents and aqueous media appear to have important potential advantage. There are two main non-aqueous methods for the reprocessing of spent fuel: fluoride-volatility process and pyro-electrochemical process. The presence of a poser in the process is that PuF 6 is obviously thermodynamically stable only in the presence of a large excess of fluorine. Pyro-electrochemical process is suited to processing metallic, oxide and carbide fuels. First, the fuel is dissolved in fresh salts, then, electrodes are introduced into the bath, U and Pu are deposited on the cathode, third, separation and refinement U and Pu are deposited on the cathode. There is a couple of contradictions in the process that are not in harmonious proportion in the fields on the nuclear fuel is dissolved the ability in the molten salt and corrosiveness of the molten salt for equipment used in the process

  6. 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

  7. Energies and media nr 30. Conditions for the nuclear sector. The fuel cycle and wastes. The usefulness of fuel reprocessing. Wastes

    International Nuclear Information System (INIS)

    2009-10-01

    After some comments on recent events in the nuclear sector in different countries (energy policy and projects in the USA, Europe, China, India, Russia), this issue proposes some explanations on the nuclear fuel cycle and on nuclear wastes: involved processes and products from mining to reprocessing and recycling, usefulness of reprocessing (future opportunities of fast neutron reactors, present usefulness of reprocessing with the recycling of separated fissile materials), impact of reprocessing on the environment in La Hague (gas and liquid releases, release standard definition), and the destiny of wastes

  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. 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.

  10. 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

  11. 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

  12. 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)

  13. Solvent extraction in nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Chesne, A.

    1980-09-01

    The author reviews the chief aspects of solvent extraction in reprocessing, including choice of the solvent, general description of the Purex process, and extractor technology, while emphasizing the specific character of nuclear fuels

  14. Kerosene fires in reprocessing plants

    International Nuclear Information System (INIS)

    Lindner, W.

    1990-08-01

    The thermodynamic and radiological consequences of accidental kerosene fires in have been investigated and analyzed. The burning rate of kerosene fires depends mainly on the burning area and in closed containments on the available oxygen and the ventilation rate in the cells of the reprocessing plants. Maximum burning rates of 150 kg/m 2 xh were measured. Burning kerosene-TBP mixtures produce large amounts of airborne soot. These particles agglomerate very fast to chainlike aerosols. The soot formation rate depends on TBP concentration and can be 10% of the organic layer. The smoke production has a maximum at the end of combustion. Uranium containing TBP releases radioactive particles during fires. The release rate depends on the uranium concentration in the organic liquid and might be up to 10% at the uranium solved in the organic liquid. Special safety filters were developed and tested under accident conditions. Multilayer sandbed filters have filtration efficiencies as high as HEPA filters and proved to have high resistivity against pressure, temperature, and chemicals. (orig.) [de

  15. 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

  16. 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

  17. Behavior of Nb fission product during nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Gue, J.P.

    1977-02-01

    Investigations on niobium fission product behavior in nitric acid and tributyl phosphate media have been carried out in order to explain the difficulties encountered in separating this element from fissile materials during spent nuclear fuel reprocessing. The studies have shown that in nitric acid solution, pentavalent niobium has a colloidal hydroxide form. The so-obtained sols were characterized by light scattering, electronic microscopy, electrophoresis and ultracentrifugation methods. In heterogeneous extracting media containing tributyl phosphate and dibutyl phosphoric acid the niobium hydroxide sols could be flocculated by low dibutyl phosphoric acid concentration or extracted into the organic phase containing an excess of dibutyl phosphoric acid [fr

  18. 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)

  19. Safeguarding large size reprocessing facilities, a challenge?

    International Nuclear Information System (INIS)

    Regnier, J.; Saverot, P.

    1994-01-01

    Safeguard implementation has evolved over years for relatively simple beginning in first reprocessing plants such as UP-2 in France and Tokai-mura in Japan to the high level technical sophistication in the large size COGEMA reprocessing plant which is fully automated for safety, security and efficiency. The increase of size, complexity and automation has resulted in the legitimate feeling of frustration from inspectorate, national authority and operators. In 1980s, increased emphasis was placed on the formalization of safeguard techniques, methods and equipment to face the challenge of safeguarding effectively and efficiently new large size reprocessing plants. Safeguard approaches, technical capability, facility practices, safeguard measures, inspection procedures, and effectiveness evaluation were developed, reviewed and implemented. The general solutions for facing the challenge, the La Hague reprocessing complex, the research and development for safeguard equipment and so on are described. The safeguard scheme designed by EURATOM in agreement with COGEMA for the La Hague reprocessing complex, based on a modern, complete and extensive C/S and nuclear material accountancy system, has proved to be efficient and effective. Large commercial reprocessing plants can be effectively safeguarded despita their high degree of automation. (K.I.)

  20. 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)

  1. Menyoal Elaboration Likelihood Model (ELM dan Teori Retorika

    Directory of Open Access Journals (Sweden)

    Yudi Perbawaningsih

    2012-06-01

    Full Text Available Abstract: Persuasion is a communication process to establish or change attitudes, which can be understood through theory of Rhetoric and theory of Elaboration Likelihood Model (ELM. This study elaborates these theories in a Public Lecture series which to persuade the students in choosing their concentration of study. The result shows that in term of persuasion effectiveness it is not quite relevant to separate the message and its source. The quality of source is determined by the quality of the message, and vice versa. Separating the two routes of the persuasion process as described in the ELM theory would not be relevant. Abstrak: Persuasi adalah proses komunikasi untuk membentuk atau mengubah sikap, yang dapat dipahami dengan teori Retorika dan teori Elaboration Likelihood Model (ELM. Penelitian ini mengelaborasi teori tersebut dalam Kuliah Umum sebagai sarana mempersuasi mahasiswa untuk memilih konsentrasi studi studi yang didasarkan pada proses pengolahan informasi. Menggunakan metode survey, didapatkan hasil yaitu tidaklah cukup relevan memisahkan pesan dan narasumber dalam melihat efektivitas persuasi. Keduanya menyatu yang berarti bahwa kualitas narasumber ditentukan oleh kualitas pesan yang disampaikannya, dan sebaliknya. Memisahkan proses persuasi dalam dua lajur seperti yang dijelaskan dalam ELM teori menjadi tidak relevan.

  2. 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)

  3. Silicon behaviour during reprocessing of uranium silicide fuel by the PUREX process

    International Nuclear Information System (INIS)

    Touron, E.; Cheroux, L.

    2001-01-01

    Uranium silicide nuclear fuel is substantially different from power reactor fuel. Reprocessing of spent U 3 Si 2 fuel is a promising alternative to storage in order to reduce the waste volume and improve containment while separating reusable material from the waste. Among the possible spent fuel reprocessing scenarios, a study of dissolution of U 3 Si 2 fuel components in acidic media has shown that the PUREX process is applicable with a few modifications in the initial process steps. This study provided valuable data on several aspects of silicon behavior in nitric acid media, and suggests that the presence of silicon does not hinder the extraction of reusable materials. (author)

  4. Risk of infections associated with improperly reprocessed transrectal ultrasound-guided prostate biopsy equipment.

    Science.gov (United States)

    Lessa, Fernanda; Tak, Sangwoo; Devader, Shannon R; Goswami, Rekha; Anderson, Mary; Williams, Ian; Gensheimer, Kathleen F; Srinivasan, Arjun

    2008-04-01

    A hospital discovered a lapse in the reprocessing procedures for transrectal ultrasound-guided prostate biopsy equipment. An investigation was initiated to assess the risks of transmission of hepatitis B virus (HBV), hepatitis C virus (HCV), human immunodeficiency virus (HIV), and bacteria during prostate biopsies. We offered testing for HBV, HCV, and HIV infection to patients who had undergone prostate biopsies from January 30, 2003, through January 27, 2006. We reviewed their medical records and obtained information on the reprocessing procedures that were in use at the time for the prostate biopsy equipment. A healthcare facility in Maine. Of the 528 patients exposed to improperly reprocessed prostate biopsy equipment, none tested positive for HIV or HCV. Sixteen patients (3%) tested positive for past HBV infection but had no prebiopsy HBV serologic test results available (ie, transmission from improperly reprocessed biopsy equipment was possible), and 11 (2%) had evidence of postbiopsy bacterial infections. The number of cases of HBV and bacterial infections were within reported ranges for this population and were not clustered in time. Review of the reprocessing procedures in use at the time revealed that the manufacturer-recommended brushes for cleaning the reusable biopsy needle guide were never used. Brushes did not come with the equipment and had to be ordered separately. Despite the lack of evidence of pathogen transmission in this investigation, it is critical to review the manufacturer's reprocessing recommendations and to establish appropriate procedures to avert potential pathogen transmission and subsequent patient concerns. This investigation provides a better understanding of the risks associated with improperly reprocessed transrectal ultrasound prostate biopsy equipment and serves as a methodologic tool for future investigations.

  5. REMARK checklist elaborated to improve tumor prognostician

    Science.gov (United States)

    Experts have elaborated on a previously published checklist of 20 items -- including descriptions of design, methods, and analysis -- that researchers should address when publishing studies of prognostic markers. These markers are indicators that enable d

  6. About the elaboration of pure uranium dicarbide

    International Nuclear Information System (INIS)

    Besson, J.; Blum, P.; Guinet, Ph.; Spitz, J.

    1963-01-01

    In order to develop methods for the elaboration of as pure as possible uranium dicarbide, the authors report the study of different elaboration processes based on the reaction between uranium and carbon, or between uranium and hydrocarbon, or between uranium oxide and carbon. They finally choose a method which comprises an arc-induced fusion of a mixture of uranium dioxide and carbon. The fusion process is described. The influence of thermal treatments is discussed as well as the graphite electrode carburization

  7. 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)

  8. 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

  9. 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

  10. Removal of actinides from high-level wastes generated in the reprocessing of commercial fuels

    International Nuclear Information System (INIS)

    Bond, W.D.; Leuze, R.E.

    1975-09-01

    Progress is reported on a technical feasibility study of removing the very long-lived actinides (uranium, neptunium, plutonium, americium, and curium) from high-level wastes generated in the commercial reprocessing of spent nuclear fuels. The study was directed primarily at wastes from the reprocessing of light water reactor (LWR) fuels and specifically to developing satisfactory methods for reducing the actinide content of these wastes to values that would make 1000-year-decayed waste comparable in radiological toxicity to natural uranium ore deposits. Although studies are not complete, results thus far indicate the most promising concept for actinide removal includes both improved recovery of actinides in conventional fuel reprocessing and secondary processing of the high-level wastes. Secondary processing will be necessary for the removal of americium and curium and perhaps some residual plutonium. Laboratory-scale studies of separations methods that appear most promising are reported and conceptual flowsheets are discussed. (U.S.)

  11. Population dose from LWR fuel reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Schubert, J.F.; Cooper, R.E.; Watts, J.R.; Bailey, C.E.

    1979-01-01

    The inhalation, submersion, and food ingestion dose to the regional and US population are calculated for estimated releases of radionuclides from a hypothetical LWR nuclear fuel reprocessing plant located in southeastern United States. A mathematical transport, diffusion, and deposition model was used to obtain the air concentrations and ground deposition of the various radionuclides emitted to the atmosphere from the reprocessing facility. The global population dose from atmospheric submersion was also calculated for /sup 3/H, /sup 14/C, and /sup 85/Kr. The total exposure to persons living in the region of the plant would be 0.2% of background.

  12. 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

  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. Keeping control of reprocessing plant construction

    International Nuclear Information System (INIS)

    Jackson, K.G.

    1991-01-01

    Keeping control of reprocessing plant construction is a function of the traditional skills in project management, about which much has been written, but is critically dependent upon the selection of strategies and systems which will provide an appropriate infrastructure of policies, procedures, specifications, information, skills and community relations. (author)

  15. Limitation of radioactive emissions from reprocessing plants

    International Nuclear Information System (INIS)

    Bonka, H.; Hesel, D.; Schmidtlein, P.; Schwarz, G.; Wagner, O.; Edelhauser, H.

    1977-01-01

    In the reprocessing plants, all radioactive material contained in the fuel elements is released. Because of that the retention facilities must be designed so effectively that only very small quantities of radioactive material are emitted from the plant. Among the numerous radioactive materials obtained in the reprocessing plant especially the retention of 3 H, 14 C, 85 Kr, 129 I, 131 I and the actinides requires considerable technological effort and financial expenditure. The emission of nuclides significant for the reprocessing plants must also be considered under long-term aspects of radiation protection, because these nuclides are mainly long-lived isotopes. Due to local and global points of view at least 90% of 3 H and 85 Kr and more than 99% of 129 I and 131 I ought to be retained. Most of the 14 C can be extracted along with the 85 Kr control-system. The emission-rate of the total α-emitting actinides from one plant should not exceed 0.1 Ci/a. The collective dose to the world population is a further criterium for the limitation of the emission from reprocessing plants. On consideration of the collective dose to the world population 14 C has the greatest significance among the above-named radionuclides. It is, however, extremely difficult to derive unambiguous criterion for the retention of different radioactive materials out of the collective doses which will finally be accepted by the general public

  16. 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

  17. 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...

  18. Chemistry of materials relevant to aqueous reprocessing and waste management

    International Nuclear Information System (INIS)

    Srinivasan, T.G.

    2012-01-01

    Nuclear energy option will be an inevitable one with the fossil fuels depleting fast and present coal and oil based thermal power generation resulting in unwanted green house gas emission. The utilisation of the fissile resources will be more effective with closed fuel cycle option wherein the spent reactor fuel is reprocessed and the unused uranium and plutonium formed during the reactor operation is recovered and re-used. Of the aqueous and non-aqueous routes available to reprocess the spent nuclear fuels, aqueous reprocessing method of recovering the valuable uranium and plutonium by the PUREX process is in vogue for the past six decades. The process involves chopping the fuel into small lengths, leaching uranium and plutonium with concentrated nitric acid under reflux, conditioning the dissolver solution with respect to acidity and valency of U and Pu, solvent extraction with 30%TBP/n-DD to selectively extract U(VI) and Pu(IV) leaving most of the fission products into the raffinate, partitioning plutonium from uranium and reconversion of U and Pu into oxide forms after further purification. Many reagents are used to achieve near quantitative recovery of both uranium and plutonium (>99.9%) and with high decontamination factors (>10 7 ) from highly radioactive fission products. Nevertheless, the chemistry of several reagents used and the chemical processes that take place during the entire course of reprocessing and waste management operations are yet to be fully understood and gives a lot of scope for further improvements. Some examples where research requires concerted efforts are, 1) development of new extractants conforming to CHON principle, with acceptable physical properties, high stability, selectivity and resistance to third phase formation, 2) new partitioning reagents and processes which offer good efficiency and kinetics for uranium/plutonium reduction, 3) understanding the chemistry of troublesome fission products such as Tc, Ru and Zr, 4

  19. Innovative Separations Technologies

    Energy Technology Data Exchange (ETDEWEB)

    J. Tripp; N. Soelberg; R. Wigeland

    2011-05-01

    Reprocessing used nuclear fuel (UNF) is a multi-faceted problem involving chemistry, material properties, and engineering. Technology options are available to meet a variety of processing goals. A decision about which reprocessing method is best depends significantly on the process attributes considered to be a priority. New methods of reprocessing that could provide advantages over the aqueous Plutonium Uranium Reduction Extraction (PUREX) and Uranium Extraction + (UREX+) processes, electrochemical, and other approaches are under investigation in the Fuel Cycle Research and Development (FCR&D) Separations Campaign. In an attempt to develop a revolutionary approach to UNF recycle that may have more favorable characteristics than existing technologies, five innovative separations projects have been initiated. These include: (1) Nitrogen Trifluoride for UNF Processing; (2) Reactive Fluoride Gas (SF6) for UNF Processing; (3) Dry Head-end Nitration Processing; (4) Chlorination Processing of UNF; and (5) Enhanced Oxidation/Chlorination Processing of UNF. This report provides a description of the proposed processes, explores how they fit into the Modified Open Cycle (MOC) and Full Recycle (FR) fuel cycles, and identifies performance differences when compared to 'reference' advanced aqueous and fluoride volatility separations cases. To be able to highlight the key changes to the reference case, general background on advanced aqueous solvent extraction, advanced oxidative processes (e.g., volumetric oxidation, or 'voloxidation,' which is high temperature reaction of oxide UNF with oxygen, or modified using other oxidizing and reducing gases), and fluorination and chlorination processes is provided.

  20. 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

  1. Effects of reprocessing on nanoalumina polymer composites

    Science.gov (United States)

    Huang, Chunchia

    The life cycle of reprocessed polymer nanocomposites is a critical factor associated with their growing use, but the limited work on reprocessing of nanocomposites has focused solely on the effects of organoclays. This research investigated of the structure and property changes during reprocessing of polypropylene (PP) and polycarbonate (PC) nanocomposites with 3 wt. % nanoalumina. Neat PP and PC were used as controls. Reprocessing of the neat polymers and nanocomposites produced no indication of oxidation (in FTIR), no changes in the glass transition temperature of PC and the melting temperatures of PP, and no changes in thermal stability (as measured using thermogravimetric analysis). Significant decreases, however, occurred in the melt viscosity of the materials. The introduction of nanoalumina during twin screw extrusion also produced a significant decrease in the viscosity and a 10°C decrease in the glass transition temperature of the PC nanocomposite. Color changes did not correspond to the chain scission in PP and PC; neat PP and PP composite yellowed, neat PC turned brown, and the PC nanocomposite did not change color. Dispersion of the nanoalumina in both PP and PC improved with repeated reprocessing, the crystallinity in the PP/nanoalumina composites remained constant. The Young's moduli of both the PP and PP/A12O3 nanocomposite were similar, whereas the Young's modulus values of the PC/A1 2O3 nanocomposite was slighted lower than that of the neat PC. In contrast, the elongations at break of the PP/A12O3 and PC/A12O3 nanocomposites were, respectively, 50% and 16% of the values measured for the neat resins. All modulus and elongation at break values, however, remained constant over five reprocessing cycles. This behavior suggests that the major degradation mechanism during reprocessing of neat PP and PP nanocomposites was thermal-mechanical polymer chain scission and that the nanoalumina enhanced this degradation in the PC/nanoalumina. This additional

  2. 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

  3. 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)

  4. Novel finishing concepts within BNFL'S advanced reprocessing programme

    International Nuclear Information System (INIS)

    Hobbs, J.W.; Booth, R.; Lawson, S.; Parkes, P.

    2000-01-01

    New methods of converting actinide nitrate solutions to oxide and fabricating the products from the reprocessing of high burn up and MOX fuels are necessary for the next generation of fuel cycle facilities in order to meet dose criteria and cost reduction targets. Options to support this include never fully separating the plutonium from the uranium and reducing decontamination factors. The product stream from such a reprocessing plant will require a finishing route capable of significant levels of automation and dose minimization. Casting of molten uranyl nitrate into pellets followed by de-nitration under vacuum has been investigated as a novel way of manufacturing oxide fuel pellets. Pellets were successfully cast over a range of temperatures and de-nitrated. Incorporation of uranium oxide into the melt was investigated to increase the density of the cast pellet. It has been demonstrated that it is possible to produce extrudates from powder and molten magnesium nitrate mixtures. Results of a preliminary study of the flow behaviour during extrusion of magnesium nitrate simulant loaded with alumina powder are also discussed. (authors)

  5. R and D of On-line Reprocessing Technology for Molten-Salt Reactor Systems

    International Nuclear Information System (INIS)

    Uhlir, Jan; Tulackova, Radka; Chuchvalcova Bimova, Karolina

    2006-01-01

    The Molten Salt Reactor (MSR) represents one of promising future nuclear reactor concept included in the Generation IV reactors family. The reactor can be operated as the thorium breeder or as the actinide transmuter. However, the future deployment of Molten-Salt Reactors will be significantly dependent on the successful mastering of advanced reprocessing technologies dedicated to their fuel cycle. Here the on-line reprocessing technology connected with the fuel circuit of MSR is of special importance because the reactor cannot be operated for a long run without the fuel salt clean-up. Generally, main MSR reprocessing technologies are pyrochemical, majority of them are fluoride technologies. The proposed flow-sheets of MSR on-line reprocessing are based on a combination of molten-salt / liquid metal extraction and electro-separation processes, which can be added to the gas extraction process already verified during the MSRE project in ORNL. The crucial separation method proposed for partitioning of actinides from fission products is based on successive Anodic dissolution and Cathodic deposition processes in molten fluoride media. (authors)

  6. Radiotreated cocoa powder for frozen elaboration

    International Nuclear Information System (INIS)

    Rodriguez Jorge, M.; Alvarez Gil, M.; Prieto Miranda, E.; Morales Valladares, M.

    1995-01-01

    The aim of the present papers is to study the possibilities of 2.0 kGy gamma radiotreated cocoa powder to be used in the elaboration of powder mixture for the preparation of chocolate frozen. Three industrial productions were carried out. Microbiological and organoleptic evaluations of the final product were performed. The results showed that the use of radurized cocoa powder in the frozen elaboration is feasible. A good hygienic quality of this product was obtained and no organoleptic alterations were detected [es

  7. Elaborative Retrieval: Do Semantic Mediators Improve Memory?

    Science.gov (United States)

    Lehman, Melissa; Karpicke, Jeffrey D.

    2016-01-01

    The elaborative retrieval account of retrieval-based learning proposes that retrieval enhances retention because the retrieval process produces the generation of semantic mediators that link cues to target information. We tested 2 assumptions that form the basis of this account: that semantic mediators are more likely to be generated during…

  8. Analysis of nuclear proliferation resistance reprocessing and recycling technologies

    International Nuclear Information System (INIS)

    Paviet-Hartmann, Patricia; Cerefice, Gary; Stacey, Marcela; Bakhtiar, Steven

    2011-01-01

    The PUREX process has been progressively and continuously improved during the past three decades, and these improvements account for successful commercialization of reprocessing in a few countries. The renewed interest in nuclear energy and the international growth of nuclear electricity generation do not equate - and should not be equated - with increasing proliferation risks. Indeed, the nuclear renaissance presents a unique opportunity to enhance the culture of non-proliferation. With the recent revival of interest in nuclear technology, technical methods for prevention of nuclear proliferation are being revisited. Robust strategies to develop new advanced separation technologies are emerging worldwide for sustainability and advancement of nuclear energy with enhanced proliferation resistance. On the other hand, at this moment, there are no proliferation resistance advanced technologies. Until now proliferation resistance as it applies to reprocessing has been focused on not separating a pure stream of weapons-usable plutonium. France, as an example, has proposed a variant of the PUREX process, the COEX TM process, which does not result on a pure plutonium product stream. A further step is to implement a process based on group extraction of actinides and fission products associated with a homogeneous recycling strategy (UNEX process in the US, GANEX process in France). Such scheme will most likely not be deployable on an industrial scale before 2030 or so because it requires intensive R and D and robust flowsheets. Finally, future generation recycling schemes will handle the used nuclear fuel in fast neutron reactors. This means that the plutonium throughput of the recycling process may increase. The need is obvious for advanced aqueous recycling technologies that are intrinsically more proliferation resistant than the commercial PUREX process. In this paper, we review the actual PUREX process along with the advanced recycling technologies that will enhance

  9. Analysis of nuclear proliferation resistance reprocessing and recycling technologies

    International Nuclear Information System (INIS)

    Paviet-Hartmann, Patricia; Stacey, Marcela Riveros; Bakhtiar, Steven; Cerefice, Gary

    2011-01-01

    The PUREX process has been progressively and continuously improved during the past three decades, and these improvements account for successful commercialization of reprocessing in a few countries. The renewed interest in nuclear energy and the international growth of nuclear electricity generation do not equate - and should not be equated - with increasing proliferation risks. Indeed, the nuclear renaissance presents a unique opportunity to enhance the culture of non-proliferation. With the recent revival of interest in nuclear technology, technical methods for prevention of nuclear proliferation are being revisited. Robust strategies to develop new advanced separation technologies are emerging worldwide for sustainability and advancement of nuclear energy with a decrease in proliferation risks. On the other hand, at this moment, advanced technologies with reduced proliferation risks are being developed. Until now proliferation resistance as it applies to reprocessing has been focused on not separating a pure stream of weapons-usable plutonium. France, as an example, has proposed a variant of the PUREX process, the COEX TM process, which does not result on a pure plutonium product stream. A further step is to implement a process based on group extraction of actinides and fission products associated with a homogeneous recycling strategy (UNEX process in the U.S., GANEX process in France). Such scheme will most likely not be deployable on an industrial scale before 2030 or so because it requires intensive R and D and robust flow-sheets. Finally, future generation recycling schemes will likely handle the used nuclear fuel in fast neutron reactors. This means that the plutonium throughput of the recycling process may increase. The need is obvious for advanced aqueous recycling technologies that have less proliferation risk than the commercial PUREX process. In this paper, we review the actual PUREX process along with the advanced recycling technologies that will

  10. Analysis of nuclear proliferation resistance reprocessing and recycling technologies

    Energy Technology Data Exchange (ETDEWEB)

    Patricia Paviet-Hartmann; Gary Cerefice; Marcela Stacey; Steven Bakhtiar

    2011-05-01

    The PUREX process has been progressively and continuously improved during the past three decades, and these improvements account for successful commercialization of reprocessing in a few countries. The renewed interest in nuclear energy and the international growth of nuclear electricity generation do not equate – and should not be equated -with increasing proliferation risks. Indeed, the nuclear renaissance presents a unique opportunity to enhance the culture of non-proliferation. With the recent revival of interest in nuclear technology, technical methods for prevention of nuclear proliferation are being revisited. Robust strategies to develop new advanced separation technologies are emerging worldwide for sustainability and advancement of nuclear energy with enhanced proliferation resistance. On the other hand, at this moment, there are no proliferation resistance advanced technologies. . Until now proliferation resistance as it applies to reprocessing has been focused on not separating a pure stream of weapons-usable plutonium. France, as an example, has proposed a variant of the PUREX process, the COEX TM process, which does not result on a pure plutonium product stream. A further step is to implement a process based on group extraction of actinides and fission products associated with a homogeneous recycling strategy (UNEX process in the US, GANEX process in France). Such scheme will most likely not be deployable on an industrial scale before 2030 or so because it requires intensive R&D and robust flowsheets. Finally, future generation recycling schemes will handle the used nuclear fuel in fast neutron reactors. This means that the plutonium throughput of the recycling process may increase. The need is obvious for advanced aqueous recycling technologies that are intrinsically more proliferation resistant than the commercial PUREX process. In this paper, we review the actual PUREX process along with the advanced recycling technologies that will enhance

  11. 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.

  12. 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

  13. 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)

  14. 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

  15. 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

  16. Integrated international safeguards concepts for fuel reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    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.

  17. Incident analysis for the large reprocessing plant

    International Nuclear Information System (INIS)

    Avenhaus, R.; Nagel, K.

    1979-01-01

    In the report period the analysis of important incidents in the extraction area has been started in caloboration with WAK (= Karlsruhe Reprocessing Plant) representatives. Ignition sources, ignitable substances, possible fires and the possible propagation of these fires within and beyond the cells were reviewed. The detailed analysis for a special incident was started. A fault tree was constructed for the conditions leading to an oxyhydrogen explosion in the 2 BX battery. (orig./RW) [de

  18. High temperature gas-cooled reactor (HTGR) graphite pebble fuel: Review of technologies for reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Mcwilliams, A. J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-09-08

    This report reviews literature on reprocessing high temperature gas-cooled reactor graphite fuel components. A basic review of the various fuel components used in the pebble bed type reactors is provided along with a survey of synthesis methods for the fabrication of the fuel components. Several disposal options are considered for the graphite pebble fuel elements including the storage of intact pebbles, volume reduction by separating the graphite from fuel kernels, and complete processing of the pebbles for waste storage. Existing methods for graphite removal are presented and generally consist of mechanical separation techniques such as crushing and grinding chemical techniques through the use of acid digestion and oxidation. Potential methods for reprocessing the graphite pebbles include improvements to existing methods and novel technologies that have not previously been investigated for nuclear graphite waste applications. The best overall method will be dependent on the desired final waste form and needs to factor in the technical efficiency, political concerns, cost, and implementation.

  19. 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.)

  20. [Elaboration and critical evaluation of clinical guidelines].

    Science.gov (United States)

    García Villar, C

    2015-11-01

    Clinical guidelines are documents to help professionals and patients select the best diagnostic or therapeutic option. Elaborating guidelines requires an efficient literature search and a critical evaluation of the articles found to select the most appropriate ones. After that, the recommendations are formulated and then must be externally evaluated before they can be disseminated. Even when the guidelines are very thorough and rigorous, it is important to know whether they fulfill all the methodological requisites before applying them. With this aim, various scales have been developed to critically appraise guidelines. Of these, the AGREE II instrument is currently the most widely used. This article explains the main steps in elaborating clinical guidelines and the main aspects that should be analyzed to know whether the guidelines are well written. Copyright © 2015 SERAM. Published by Elsevier España, S.L.U. All rights reserved.

  1. Geographic assistance of decontamination strategy elaboration

    International Nuclear Information System (INIS)

    Davydchuk, V.; Arapis, G.

    1996-01-01

    Those who elaborates the strategy of decontamination of vast territories is to take into consideration the heterogeneity of such elements of landscape as relief, lithology, humidity and types of soils and, vegetation, both on local and regional level. Geographic assistance includes evaluation of efficacy of decontamination technologies in different natural conditions, identification of areas of their effective application and definition of ecological damage, estimation of balances of the radionuclides in the landscapes to create background of the decontamination strategy

  2. 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)

  3. 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)

  4. 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)

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

    OpenAIRE

    Raval, Krutik Vipulbhai; Chaudhari, Rajeev; Khant, Shahil Rameshbhai; Joglekar, Omkar; Patel, Dipen

    2017-01-01

    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 inadequ...

  6. 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

  7. Transport and reprocessing of irradiated TRIGA fuel elements

    International Nuclear Information System (INIS)

    Staake, Theo R.

    1980-01-01

    This paper is intended to provide a review of the transport of irradiated TRIGA fuel elements, and the selection of the transport casks. The information presented is based on the experience TRANSNUKLEAR GmbH has gained over the last 14 years in the transport and reprocessing of irradiated MTR fuel elements. During this period over 2000 fuel elements were delivered to various destinations for reprocessing (about 1000 fuel elements - to European reprocessing plants (Eurochemic in Belgium, and CEA Marcoule in France), and, since 1977, over 1000 fuel elements - to the US-DOE Savannah River reprocessing plant)

  8. 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.)

  9. Simulations of Atmospheric Krypton-85 to Assess the Detectability of Clandestine Nuclear Reprocessing

    International Nuclear Information System (INIS)

    Ross, O.; Ahlswede, J.; Annewandter, R.; Kalinowski, M.B.; Rast, S.; Schluenzen, K.H.

    2010-01-01

    The results of this study were achieved in the project 'Simulation of Atmospheric Noble Gas Concentrations to Assess Sampling Procedures for the Detection of Clandestine Nuclear Reprocessing' (IAEA GER 1643) in the joint programme of IAEA and Federal Government of Germany. In the first year of the project the detectability of additional krypton-85 sources was investigated using atmospheric transport modelling. Krypton-85 is released into the air during reprocessing of spent nuclear fuel rods. Therefore the krypton-85 signature can possibly be used for the detection of undeclared plutonium separation. First, the global krypton-85 background produced by known reprocessing facilities from 1971 until 2006 was simulated with the atmospheric general circulation model ECHAM5 using annual emission data. The model results were evaluated by extensive comparison with measurements performed by the German Federal Office for Radiation Protection. Of particular interest for an assessment of the detectability of unknown sources is the background variability. The variability of concentrations is very high over central Europe, where the large reprocessing plants La Hague and Sellafield are located, and it is very low on the Southern Hemisphere, where no nuclear reprocessing takes place. The analysis of concentration time series on various time scales allows partly a distinction between fluctuations caused by the variability of the sources from variations due to atmospheric dynamics. Furthermore the detection sensitivity to a set of arbitrarily specified source locations is analysed with a Lagrangian particle dispersion model. This, in combination with the location specific background variability, is giving first benchmarks on the capability of using krypton-85 for IAEA Safeguards based on the Additional Protocols foreseeing environmental sampling. (author)

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. Elaboration of a Mn-Ni alloy

    International Nuclear Information System (INIS)

    Meny, L.

    1957-06-01

    The manganese-nickel alloy with a high manganese content is used to produce very low thickness sensors for the measurement of neutron flows in a reactor. The author reports the elaboration of such an alloy with a 75 per cent content of manganese and 25 per cent content of nickel, by using a powder metallurgy approach. Purity and homogeneity were looked for more than good mechanical properties. In this note, the author presents the alloy fabrication apparatus, and reports some properties of sheets produced with this alloy

  16. Reconstitution of Biosynthetic Machinery for the Synthesis of the Highly Elaborated Indole Diterpene Penitrem

    DEFF Research Database (Denmark)

    Liu, Chengwei; Tagami, Koichi; Minami, Atsushi

    2015-01-01

    Penitrem A is one of the most elaborated members of the fungal indole diterpenes. Two separate penitrem gene clusters were identified using genomic and RNA sequencing data, and 13 out of 17 transformations in the penitrem biosynthesis were elucidated by heterologous reconstitution of the relevant...

  17. Proceedings of the 4th status report of the Reprocessing and Waste Management Project (PWA) of November 5th, 1981

    International Nuclear Information System (INIS)

    1982-03-01

    The lectures presented to this meeting deal with the concept of waste disposal in the Federal Republic of Germany, the current state and results of the development work within the project 'Reprocessing and Waste Management'. The main efforts and technological programmes are described as well. Further lectures have been held on problems relating to a fuel reprocessing plant (dissolver-off-gas treatment, tritium separation, hydraulic studies on pulsating columns, electroreduction in the PUREX process, analytical procedures for process analyses). Moreover, materials problems have been discussed and the monitor development for criticality control, work for improving remote handling devices, and the reprocessing of a KNK II reactor mixed oxide fuel in the laboratory test plant MILLI. (RB) [de

  18. Environmental tritium monitoring around Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Yamato, A.

    1982-01-01

    The environmental tritium monitoring in the sea near Tokai Reprocessing Plant has been performed since 1977, the year of having started the hot test operation of the plant. On the other hand, atmospheric tritium monitoring was started almost at the same time as a research program instead of a routine program. This paper is a review for tritium monitoring in the sea and in the air around the Tokai Reprocessing Plant. The plant is located in Tokai Village, Ibaraki Prefecture, on the Pacific coast. It is based on the Purex process, and the nominal capacity is 210 tons per year. Around the TRP, there are four uranium fabrication facilities, five research reactors, two power reactors and other research facilities. About 173,000 inhabitants are within 10 km range from the plant. The authorized discharge limit of tritium is 200 Ci per day and 51,100 Ci per year in the sea. That in the atmosphere is 50 Ci per day and about 15,000 Ci per year. The tritium from the TRP was discharged mainly into the sea. The sea water samples were distilled, and the tritium concentration was measured by liquid scintillation counting. During three years of the hot operation of TRP, discharged tritium was about 7,000 Ci into the sea and about 140 Ci into the atmosphere. The tritium level has been maintained, and its significant increase was not observed. (Kako, I.)

  19. 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

  20. 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

  1. 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

  2. Improved measurement of aluminum in irradiated fuel reprocessed at the Savannah River Site

    International Nuclear Information System (INIS)

    Maxwell, S.L. III.

    1991-01-01

    At the Savannah River Site (SRS), irradiated fuel from research reactor operators or their contract fuel service companies is reprocessed in the H-Canyon Separations Facility. Final processing costs are based on analytical measurements of the amount of total metal dissolved. Shipper estimates for uranium and uranium-235 and measured values at SRS have historically agreed very well. There have occasionally been significant differences between shipper estimates for aluminum and the aluminum content determined at SRS. To minimize analytical error that might contribute to poor shipper-receiver agreement for the reprocessing of off-site fuel, a new analytical method to measure aluminum was developed by SRS Analytical Laboratories at the Central Laboratory Facilities. An EDTA (ethylenediaminetetraacetic acid) titration method, subject to dissolver matrix interferences, was previously used at SRS to measure aluminum in H-Canyon dissolver during the reprocessing of offsite fuel. The new method combines rapid ion exchange technology with direct current argon plasma spectrometry to enhance the reliability of aluminum measurements for off-site fuel. The technique rapidly removes spectral interferences such as uranium and significantly lowers gamma levels due to fission products. Aluminium is separated quantitatively by using an anion exchange technique that employs oxalate complexing, small particle size resin and rapid flow rates. The new method, which has eliminated matrix interference problems with these analyses and improved the quality of aluminum measurements, has improved the overall agreement between shipper-receiver values for offsite fuel processed SRS

  3. 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.

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

    African Journals Online (AJOL)

    increased upon reprocessing. Moreover, most of the pure excipients processed by direct compression had an increase in porosity after reprocessing. This implies an increase in the number of spaces between fine particles, increase of specific surface area and reduction of powder density keeping a large amount of air.

  6. On returned wastes accompanying commission of reprocessing to foreign countries

    International Nuclear Information System (INIS)

    Shimoda, Hideo

    1983-01-01

    The radioactive wastes generated accompanying the reprocessing of spent fuel from Japanese nuclear power stations entrusted to the reprocessing companies in Great Britain and France are expected to be returned to Japan from 1990 on. In Japan, the wastes generated from reprocessing are to be dealt with by reprocessing enterprises, but these returned wastes are returned to electric power companies who made the contract to entrust reprocessing, therefore they have become the problem of electric power companies themselves. It is investigated by establishing the expert committee in the Federation of Electric Power Companies, and obtaining assistance from Japan Atomic Energy Research Institute, Power Reactor and Nuclear Fuel Development Corp. and men of learn and experience. The reprocessing plan for spent fuel in Japan, the features of the new reprocessing contract, the tackling organization in electric power companies, the outline of the foreign reprocessing plants, the specification and quantity of the returned wastes, the long term scenario of the management of the returned wastes, the transportation, storage and disposal are described. (Kako, I.)

  7. 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.

  8. False Memories for Suggestions: The Impact of Conceptual Elaboration

    Science.gov (United States)

    Zaragoza, Maria S.; Mitchell, Karen J.; Payment, Kristie; Drivdahl, Sarah

    2011-01-01

    Relatively little attention has been paid to the potential role that reflecting on the meaning and implications of suggested events (i.e., conceptual elaboration) might play in promoting the creation of false memories. Two experiments assessed whether encouraging repeated conceptual elaboration, would, like perceptual elaboration, increase false…

  9. 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)

  10. 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)

  11. 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

  12. 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)

  13. 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

  14. Target identification procedure for plutonium reprocessing facilities

    International Nuclear Information System (INIS)

    Sacks, I.; Maimoni, A.; Adams, R.

    1977-06-01

    Lawrence Livermore Laboratory has developed, as a portion of the Nuclear Regulatory Commission Material Control Project, a methodology for identifying and ranking probable adversary targets in a plutonium reprocessing facility. This ranking is based on the ''atractiveness'' of the target material to an adversary. The basic subjective nature of this attractiveness has been made more rigorous and is based on the use of multiattribute utility theory and the inputs of knowledgeable experts. Once the attractive materials have been identified, the possible flow paths which could lead to diversion can be determined. A computer code has been developed which will automatically determine these flow paths from information contained within the plant process piping and instrumentation diagrams

  15. 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

  16. 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)

  17. 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

  18. 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.)

  19. Fully integrated safeguards and security for reprocessing plant monitoring

    International Nuclear Information System (INIS)

    Duran, Felicia Angelica; Ward, Rebecca; Cipiti, Benjamin B.; Middleton, Bobby D.

    2011-01-01

    Nuclear fuel reprocessing plants contain a wealth of plant monitoring data including material measurements, process monitoring, administrative procedures, and physical protection elements. Future facilities are moving in the direction of highly-integrated plant monitoring systems that make efficient use of the plant data to improve monitoring and reduce costs. The Separations and Safeguards Performance Model (SSPM) is an analysis tool that is used for modeling advanced monitoring systems and to determine system response under diversion scenarios. This report both describes the architecture for such a future monitoring system and present results under various diversion scenarios. Improvements made in the past year include the development of statistical tests for detecting material loss, the integration of material balance alarms to improve physical protection, and the integration of administrative procedures. The SSPM has been used to demonstrate how advanced instrumentation (as developed in the Material Protection, Accounting, and Control Technologies campaign) can benefit the overall safeguards system as well as how all instrumentation is tied into the physical protection system. This concept has the potential to greatly improve the probability of detection for both abrupt and protracted diversion of nuclear material.

  20. Alpha-contaminated waste from reprocessing of nuclear fuel

    International Nuclear Information System (INIS)

    Sumner, W.

    1982-01-01

    The anticipated alpha-waste production rates from the Barnwell Nuclear Fuel Reprocessing plant is discussed. The estimated alpha-waste production rate from the 1500 metric ton/year plant is about 85,000 ft 3 /year at the 10 nCi/g limit. Most of this waste is estimated to come from the separation facility, and the major waste sources were cladding, which was 27%, and low-level contact-handled general process trash, which was estimated at 32% of the total. It was estimated that 45% of the waste was combustible and 72% of the waste was compactible. These characteristics could have a significant impact on the final volumes as disposed. Changing the alpha-waste limit from 10 nCi/g to 100 nCi/g was estimated to reduce the amount of alpha waste produced by about 20%. Again, the uncertainty in this value obviously has to be substantial. One has to recognize that these estimates were just that; they were not based on any operating experience. The total plutonium losses to waste, including the high-level waste, was estimated to be 1.5%. The cladding waste was estimated to be contaminated with alpha emitters to the extent of 10 4 to 10 5 nCi/g

  1. Swift Monitoring of NGC 4151: Evidence for a Second X-Ray/UV Reprocessing

    Science.gov (United States)

    Edelson, R.; Gelbord, J.; Cackett, E.; Connolly, S.; Done, C.; Fausnaugh, M.; Gardner, E.; Gehrels, N.; Goad, M.; Horne, K.; McHardy, I.; Peterson, B. M.; Vaughan, S.; Vestergaard, M.; Breeveld, A.; Barth, A. J.; Bentz, M.; Bottorff, M.; Brandt, W. N.; Crawford, S. M.; Dalla Bontà, E.; Emmanoulopoulos, D.; Evans, P.; Figuera Jaimes, R.; Filippenko, A. V.; Ferland, G.; Grupe, D.; Joner, M.; Kennea, J.; Korista, K. T.; Krimm, H. A.; Kriss, G.; Leonard, D. C.; Mathur, S.; Netzer, H.; Nousek, J.; Page, K.; Romero-Colmenero, E.; Siegel, M.; Starkey, D. A.; Treu, T.; Vogler, H. A.; Winkler, H.; Zheng, W.

    2017-05-01

    Swift monitoring of NGC 4151 with an ˜6 hr sampling over a total of 69 days in early 2016 is used to construct light curves covering five bands in the X-rays (0.3-50 keV) and six in the ultraviolet (UV)/optical (1900-5500 Å). The three hardest X-ray bands (>2.5 keV) are all strongly correlated with no measurable interband lag, while the two softer bands show lower variability and weaker correlations. The UV/optical bands are significantly correlated with the X-rays, lagging ˜3-4 days behind the hard X-rays. The variability within the UV/optical bands is also strongly correlated, with the UV appearing to lead the optical by ˜0.5-1 days. This combination of ≳3 day lags between the X-rays and UV and ≲1 day lags within the UV/optical appears to rule out the “lamp-post” reprocessing model in which a hot, X-ray emitting corona directly illuminates the accretion disk, which then reprocesses the energy in the UV/optical. Instead, these results appear consistent with the Gardner & Done picture in which two separate reprocessings occur: first, emission from the corona illuminates an extreme-UV-emitting toroidal component that shields the disk from the corona; this then heats the extreme-UV component, which illuminates the disk and drives its variability.

  2. Swift Monitoring of NGC 4151: Evidence for a Second X-Ray/UV Reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Edelson, R. [University of Maryland, Department of Astronomy, College Park, MD 20742-2421 (United States); Gelbord, J. [Spectral Sciences Inc., 4 Fourth Avenue, Burlington, MA 01803 (United States); Cackett, E. [Department of Physics and Astronomy, Wayne State University, 666 W. Hancock Street, Detroit, MI 48201 (United States); Connolly, S.; McHardy, I. [University of Southampton, Highfield, Southampton, SO17 1BJ (United Kingdom); Done, C.; Gardner, E. [University of Durham, Center for Extragalactic Astronomy, Department of Physics, South Road, Durham, DH1 3LE (United Kingdom); Fausnaugh, M.; Peterson, B. M. [The Ohio State University, Department of Astronomy, 140 W 18th Avenue, Columbus, OH 43210 (United States); Gehrels, N. [Astrophysics Science Division, NASA Goddard Space Flight Center, Greenbelt, MD 20771 (United States); Goad, M.; Vaughan, S. [University of Leicester, Department of Physics and Astronomy, Leicester, LE1 7RH (United Kingdom); Horne, K. [SUPA Physics and Astronomy, University of St. Andrews, Fife, KY16 9SS Scotland (United Kingdom); Vestergaard, M. [Dark Cosmology Centre, Niels Bohr Institute, University of Copenhagen, Juliane Maries Vej 30, DK-2100 Copenhagen (Denmark); Breeveld, A. [Mullard Space Science Laboratory, University College London, Holmbury St. Mary, Dorking, Surrey RH5 6NT (United Kingdom); Barth, A. J. [Department of Physics and Astronomy, 4129 Frederick Reines Hall, University of California, Irvine, CA 92697 (United States); Bentz, M. [Department of Physics and Astronomy, Georgia State University, 25 Park Place, Suite 605, Atlanta, GA 30303 (United States); Bottorff, M. [Physics Department, Southwestern University, Georgetown, TX 78626 (United States); Brandt, W. N. [Department of Astronomy and Astrophysics, Eberly College of Science, 525 Davey Laboratory, The Pennsylvania State University, University Park, PA 16802 (United States); Crawford, S. M. [South African Astronomical Observatory, P.O. Box 9, Observatory 7935, Cape Town (South Africa); and others

    2017-05-01

    Swift monitoring of NGC 4151 with an ∼6 hr sampling over a total of 69 days in early 2016 is used to construct light curves covering five bands in the X-rays (0.3–50 keV) and six in the ultraviolet (UV)/optical (1900–5500 Å). The three hardest X-ray bands (>2.5 keV) are all strongly correlated with no measurable interband lag, while the two softer bands show lower variability and weaker correlations. The UV/optical bands are significantly correlated with the X-rays, lagging ∼3–4 days behind the hard X-rays. The variability within the UV/optical bands is also strongly correlated, with the UV appearing to lead the optical by ∼0.5–1 days. This combination of ≳3 day lags between the X-rays and UV and ≲1 day lags within the UV/optical appears to rule out the “lamp-post” reprocessing model in which a hot, X-ray emitting corona directly illuminates the accretion disk, which then reprocesses the energy in the UV/optical. Instead, these results appear consistent with the Gardner and Done picture in which two separate reprocessings occur: first, emission from the corona illuminates an extreme-UV-emitting toroidal component that shields the disk from the corona; this then heats the extreme-UV component, which illuminates the disk and drives its variability.

  3. Report of third regular inspection of Tokai reprocessing facilities, Power Reactor and Nuclear Fuel Development Corp

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    The reprocessing facilities passed the inspection before use on December 25, 1980, and started the full operation. Since then, this is the third regular inspection. It was begun on April 1, 1986, and finished on August 18, 1986, with the inspection of the rate of recovery of products. The reprocessing facilities which became the object of inspection were the facilities for accepting and storing spent fuel, the reprocessing facilities proper (the facilities of shearing, dissolution, separation, refining, denitration and recovery of acid and solvent), the facilities for storing products, measurement and control system, radioactive waste facilities, radiation control facilities and attached facilities (power, water, steam and testing). The main works carried out during the period of this regular inspection were the repair of an enriched uranium dissolution tank by welding, the renewal of a piping for a low activity waste liquid storing tank, and the removal of a washing tank. The total exposure dose in the first half of fiscal year 1986 was about 30.81 man-rem. (Kako, I.)

  4. Evaluation of methods for decladding LWR fuel for a pyroprocessing-based reprocessing plant

    International Nuclear Information System (INIS)

    Bond, W.D.; Mailen, J.C.; Michaels, G.E.

    1992-10-01

    The first step in reprocessing disassembled light-water reactor (LWR) spent fuel is to separate the zirconium-based cladding from the UO 2 fuel. A survey of decladding technologies has been performed to identify candidate decladding processes suitable for LWR fuel and compatible with downstream pyropr for separation of actinides and fission products. Technologies for the primary separation of Zircaloy cladding from oxide fuel and for secondary separations (in most cases, a further decontamination of the cladding) were reviewed. Because cutting of the fuel cladding is a necessary step in all flowsheet options, metal cutting technologies were also briefly evaluated. The assessment of decladding processes resulted in the identification of the three or four potentially attractive options that may warrant additional near-term evaluation. These options are summarized, and major strengths and issues of each option are discussed

  5. Evaluation of methods for decladding LWR fuel for a pyroprocessing-based reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Bond, W.D.; Mailen, J.C.; Michaels, G.E.

    1992-10-01

    The first step in reprocessing disassembled light-water reactor (LWR) spent fuel is to separate the zirconium-based cladding from the UO[sub 2] fuel. A survey of decladding technologies has been performed to identify candidate decladding processes suitable for LWR fuel and compatible with downstream pyropr for separation of actinides and fission products. Technologies for the primary separation of Zircaloy cladding from oxide fuel and for secondary separations (in most cases, a further decontamination of the cladding) were reviewed. Because cutting of the fuel cladding is a necessary step in all flowsheet options, metal cutting technologies were also briefly evaluated. The assessment of decladding processes resulted in the identification of the three or four potentially attractive options that may warrant additional near-term evaluation. These options are summarized, and major strengths and issues of each option are discussed.

  6. Evaluation of methods for decladding LWR fuel for a pyroprocessing-based reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Bond, W.D.; Mailen, J.C.; Michaels, G.E.

    1992-10-01

    The first step in reprocessing disassembled light-water reactor (LWR) spent fuel is to separate the zirconium-based cladding from the UO{sub 2} fuel. A survey of decladding technologies has been performed to identify candidate decladding processes suitable for LWR fuel and compatible with downstream pyropr for separation of actinides and fission products. Technologies for the primary separation of Zircaloy cladding from oxide fuel and for secondary separations (in most cases, a further decontamination of the cladding) were reviewed. Because cutting of the fuel cladding is a necessary step in all flowsheet options, metal cutting technologies were also briefly evaluated. The assessment of decladding processes resulted in the identification of the three or four potentially attractive options that may warrant additional near-term evaluation. These options are summarized, and major strengths and issues of each option are discussed.

  7. Method of reprocessing nuclear fuel using vacuum freeze-drying method

    International Nuclear Information System (INIS)

    Otsuka, Katsuyuki; Kondo, Isao.

    1989-01-01

    Solutions of plutonium nitrate and uranyl nitrate, spent solvents and liquid wastes separated by the treatment in the solvent extractant steps in the wet processing steps of re-processing plants or fuel fabrication plants are processed by means of freeze-drying under vacuum. Then, the solutions of plutonium nitrate and uranyl nitrate are separated into nitrates and liquid condensates and the spent solvents are freeze-dried. Thus, they are separated into tri-n-butyl phosphate, diester, monoester and n-dodecane and the liquid wastes are processed by means of freeze-drying and separated into liquids and residues. In this way, since sodium carbonate, etc. are not used, the amount of resultant liquid wastes is reduced and sodium is not contained in liquid wastes sent to an asphalt solidification step and a vitrification step, the processing steps can be simplified. (S.T.)

  8. 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

  9. Process monitoring in international safeguards for reprocessing plants: A demonstration

    Energy Technology Data Exchange (ETDEWEB)

    Ehinger, M.H.

    1989-01-01

    In the period 1985--1987, the Oak Ridge National Laboratory investigated the possible role of process monitoring for international safeguards applications in fuel reprocessing plants. This activity was conducted under Task C.59, ''Review of Process Monitoring Safeguards Technology for Reprocessing Facilities'' of the US program of Technical Assistance to the International Atomic Energy Agency (IAEA) Safeguards program. The final phase was a demonstration of process monitoring applied in a prototypical reprocessing plant test facility at ORNL. This report documents the demonstration and test results. 35 figs.

  10. 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

  11. 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.

  12. Predicting the behaviour of neptunium during nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Drake, V.A.

    1987-01-01

    Neptunium ions are subjected to changes in oxidation state in most of the extraction cycles of reprocessing. These reactions are often sufficiently fast to be significant but too slow to reach equilibrium within the residence time in a given contactor. The situation is further complicated by different extraction behaviours of the neptunium oxidation states into the reprocessing solvent. How experimental and theoretical analyses can be used to predict the route followed by neptunium in reprocessing, which is of practical importance in plant and waste management, is discussed. (author)

  13. Elaboration of fiber-reinforced metallic materials; Elaboration des materiaux metalliques renforces par des fibres

    Energy Technology Data Exchange (ETDEWEB)

    Martin, J.M. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1969-08-01

    A bibliographic study on the elaboration of fiber reinforced metallic materials is presented in three parts: the theory of fiber reinforcement of metals in summarized, with emphasis on the mechanical and geometric factors which govern the behaviour and the performances to be expected from a given composite material; a second part is devoted to the study of the physical and chemical factors related to the structural stability of the material. Finally, the various processes of fabrication of such composites are presented and discussed. (author) [French] Cette etude bibliographique de l'elaboration des materiaux metalliques renforces par des fibres, comprend trois parties. Dans la premiere partie, la theorie du renforcement des metaux par des fibres est resumee de maniere a mettre en lumiere les facteurs mecaniques et geometriques qui determinent le comportement et les performances que l'on peut attendre d'un composite donne. La seconde partie est consacree a l'etude des facteurs physico-chimiques qui determinent la stabilite structurale d'un composite. Enfin, la troisieme partie est constituee par l'expose des differentes methodes d'elaboration des composites. (auteur)

  14. THE ECONOMICS OF REPROCESSING vs. DIRECT DISPOSAL OF SPENT NUCLEAR FUEL

    International Nuclear Information System (INIS)

    Bunn, Matthew; Fetter, Steve; Holdren, John P.; Zwaan, Bob van der

    2003-01-01

    This report assesses the economics of reprocessing versus direct disposal of spent nuclear fuel. The breakeven uranium price at which reprocessing spent nuclear fuel from existing light-water reactors (LWRs) and recycling the resulting plutonium and uranium in LWRs would become economic is assessed, using central estimates of the costs of different elements of the nuclear fuel cycle (and other fuel cycle input parameters), for a wide range of range of potential reprocessing prices. Sensitivity analysis is performed, showing that the conclusions reached are robust across a wide range of input parameters. The contribution of direct disposal or reprocessing and recycling to electricity cost is also assessed. The choice of particular central estimates and ranges for the input parameters of the fuel cycle model is justified through a review of the relevant literature. The impact of different fuel cycle approaches on the volume needed for geologic repositories is briefly discussed, as are the issues surrounding the possibility of performing separations and transmutation on spent nuclear fuel to reduce the need for additional repositories. A similar analysis is then performed of the breakeven uranium price at which deploying fast neutron breeder reactors would become competitive compared with a once-through fuel cycle in LWRs, for a range of possible differences in capital cost between LWRs and fast neutron reactors. Sensitivity analysis is again provided, as are an analysis of the contribution to electricity cost, and a justification of the choices of central estimates and ranges for the input parameters. The equations used in the economic model are derived and explained in an appendix. Another appendix assesses the quantities of uranium likely to be recoverable worldwide in the future at a range of different possible future prices

  15. THE ECONOMICS OF REPROCESSING vs DIRECT DISPOSAL OF SPENT NUCLEAR FUEL

    Energy Technology Data Exchange (ETDEWEB)

    Matthew Bunn; Steve Fetter; John P. Holdren; Bob van der Zwaan

    2003-07-01

    This report assesses the economics of reprocessing versus direct disposal of spent nuclear fuel. The breakeven uranium price at which reprocessing spent nuclear fuel from existing light-water reactors (LWRs) and recycling the resulting plutonium and uranium in LWRs would become economic is assessed, using central estimates of the costs of different elements of the nuclear fuel cycle (and other fuel cycle input parameters), for a wide range of range of potential reprocessing prices. Sensitivity analysis is performed, showing that the conclusions reached are robust across a wide range of input parameters. The contribution of direct disposal or reprocessing and recycling to electricity cost is also assessed. The choice of particular central estimates and ranges for the input parameters of the fuel cycle model is justified through a review of the relevant literature. The impact of different fuel cycle approaches on the volume needed for geologic repositories is briefly discussed, as are the issues surrounding the possibility of performing separations and transmutation on spent nuclear fuel to reduce the need for additional repositories. A similar analysis is then performed of the breakeven uranium price at which deploying fast neutron breeder reactors would become competitive compared with a once-through fuel cycle in LWRs, for a range of possible differences in capital cost between LWRs and fast neutron reactors. Sensitivity analysis is again provided, as are an analysis of the contribution to electricity cost, and a justification of the choices of central estimates and ranges for the input parameters. The equations used in the economic model are derived and explained in an appendix. Another appendix assesses the quantities of uranium likely to be recoverable worldwide in the future at a range of different possible future prices.

  16. Pyrochemical reprocessing of molten salt fast reactor fuel: focus on the reductive extraction step

    Directory of Open Access Journals (Sweden)

    Rodrigues Davide

    2015-12-01

    Full Text Available The nuclear fuel reprocessing is a prerequisite for nuclear energy to be a clean and sustainable energy. In the case of the molten salt reactor containing a liquid fuel, pyrometallurgical way is an obvious way. The method for treatment of the liquid fuel is divided into two parts. In-situ injection of helium gas into the fuel leads to extract the gaseous fission products and a part of the noble metals. The second part of the reprocessing is performed by ‘batch’. It aims to recover the fissile material and to separate the minor actinides from fission products. The reprocessing involves several chemical steps based on redox and acido-basic properties of the various elements contained in the fuel salt. One challenge is to perform a selective extraction of actinides and lanthanides in spent liquid fuel. Extraction of actinides and lanthanides are successively performed by a reductive extraction in liquid bismuth pool containing metallic lithium as a reductive reagent. The objective of this paper is to give a description of the several steps of the reprocessing retained for the molten salt fast reactor (MSFR concept and to present the initial results obtained for the reductive extraction experiments realized in static conditions by contacting LiF-ThF4-UF4-NdF3 with a lab-made Bi-Li pool and for which extraction efficiencies of 0.7% for neodymium and 14.0% for uranium were measured. It was concluded that in static conditions, the extraction is governed by a kinetic limitation and not by the thermodynamic equilibrium.

  17. Overview of reductants utilized in nuclear fuel reprocessing/recycling

    Energy Technology Data Exchange (ETDEWEB)

    Patricia Paviet-Hartmann; Catherine Riddle; Keri Campbell; Edward Mausolf

    2013-10-01

    promises as a replacement for AHA. FHA undergoes hydrolysis to formic acid which is volatile, thus allowing the recycling of nitric acid. Unfortunately, FHA powder was not stable in the experiments we ran in our laboratory. In addition, AHA and FHA also decompose to hydroxylamine which may undergo an autocatalytic reaction. Other reductants are available and could be extremely useful for actinides separation. The review presents the current plutonium reductants used in used nuclear fuel reprocessing and will introduce innovative and novel reductants that could become reducers for future research on UNF separation.

  18. 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

  19. Energies and media nr 30. Conditions for the nuclear sector. The fuel cycle and wastes. The usefulness of fuel reprocessing. Wastes; Energies et medias no. 30. La conjoncture, pour le nucleaire. Le cycle du combustible et les dechets. L'utilite du retraitement des combustibles. Les dechets

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-10-15

    After some comments on recent events in the nuclear sector in different countries (energy policy and projects in the USA, Europe, China, India, Russia), this issue proposes some explanations on the nuclear fuel cycle and on nuclear wastes: involved processes and products from mining to reprocessing and recycling, usefulness of reprocessing (future opportunities of fast neutron reactors, present usefulness of reprocessing with the recycling of separated fissile materials), impact of reprocessing on the environment in La Hague (gas and liquid releases, release standard definition), and the destiny of wastes

  20. 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

  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. Reprocessing yields and material throughput: HTGR recycle demonstration facility

    Energy Technology Data Exchange (ETDEWEB)

    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. (28 tables, 18 figs.)

  3. (reprocessed)CAGE peaks - FANTOM5 | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available List Contact us FANTOM5 (reprocessed)CAGE peaks Data detail Data name (reprocessed)CAGE peaks DOI 10.18908/l...g38/mm10). Data file File name: (reprocessed)CAGE_peaks (Homo sapiens) File URL: ftp://ftp.biosciencedbc.jp/...archive/fantom5/datafiles/reprocessed/hg38_latest/extra/CAGE_peaks/ File size: 11 MB File name: (reprocessed...)CAGE_peaks (Mus musculus) File URL: ftp://ftp.biosciencedbc.jp/archive/fantom5/datafiles/reprocess...his Database Site Policy | Contact Us (reprocessed)CAGE peaks - FANTOM5 | LSDB Archive ...

  4. (reprocessed)CAGE_peaks_expression - FANTOM5 | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available List Contact us FANTOM5 (reprocessed)CAGE_peaks_expression Data detail Data name (reprocessed)CAGE_peaks_exp... (hg38/mm10). Data file File name: (reprocessed)CAGE_peaks_expression (Homo sapiens) File URL: ftp://ftp.bio...sciencedbc.jp/archive/fantom5/datafiles/reprocessed/hg38_latest/extra/CAGE_peaks_expression/ File size: 3.3 GB File name: (reprocess...tp.biosciencedbc.jp/archive/fantom5/datafiles/reprocessed/mm10_latest/extra/CAGE_peaks_expression/ File size...f This Database Site Policy | Contact Us (reprocessed)CAGE_peaks_expression - FANTOM5 | LSDB Archive ...

  5. 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

  6. Reprocessing in the United Kingdom. Part II

    International Nuclear Information System (INIS)

    Jackson, K.G.; Bonser, D.R.

    1994-01-01

    BNFL's Thermal Oxide Reprocessing Plant (THORP) was one of the largest construction projects in Europe. Similarly its control system is one of the most complex and comprehensive ever installed. This paper briefly reviews construction and then focuses on the organisation for, and challenges met in, commissioning the plant. In particular the way in which the regulatory interface was managed is described. Meanwhile liaison with the regulators was also taking place at a quite different level- for a battle was raging at a public relations and political level to secure revised discharge authorizations for the Sellafield Site which would allow THORP to operate. The uncertainty as to when THORP would be able to operate gave rise to unfamiliar project planning issues. This paper, describes the challenges and successes of the commissioning activities against the background of the regulatory interfaces and Greenpeace's activities. It is concluded that, in addition to the importance of the regulatory interface, which was well managed, it is essential that, with major and potentially controversial projects, the government itself must be assisted to help the nuclear industry. 2 tabs., 1 fig

  7. 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)

  8. Influence of the reprocessing on molten salt reactor behaviour

    OpenAIRE

    Merle-Lucotte, E.; Mathieu, L.; Heuer, D.; Billebaud, A.; Brissot, R.; Le Brun, C.; Liatard, E.; Loiseaux, J.M.; Méplan, O.; Nuttin, A.; Wilson, J.

    2005-01-01

    International audience; The Molten Salt Reactor is one of the systems studied as a Generation IV reactor. Its main characteristic is the strong coupling between neutronics and salt reprocessing. Such nuclear reactors use a liquid fuel which is also the coolant. Elements produced during the reactor's operation, like Fission Products (FP) or TransUranians, modify the neutronic balance of the reactor by capturing neutrons. As the fuel is liquid, samples can be extracted and reprocessed to remove...

  9. 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.

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

    Science.gov (United States)

    Raval, Krutik Vipulbhai; Chaudhari, Rajeev; Khant, Shahil Rameshbhai; Joglekar, Omkar; Patel, Dipen

    2017-01-01

    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.

  11. SYSTEMS ENGINEERING APPROACHES FOR IMPROVING REUSABLE MEDICAL EQUIPMENT REPROCESSING PROCESSES

    OpenAIRE

    JAMES C. BENNEYAN; CLAIRE BOND

    2013-01-01

    Hospital reusable medical equipment (RME) includes any items that are intended to be reprocessed and reused indefinitely, including surgical instruments, dental equipment, endoscopes, and others. Such equipment represent a significant portion of a hospital's inventory costs and recently have generated significant patient cross-contamination concerns due to reprocessing cleaning failures. This paper discusses recent applications of industrial and systems engineering (ISyE) methods within healt...

  12. 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

  13. Research on advanced aqueous reprocessing of spent nuclear fuel: literature study

    Energy Technology Data Exchange (ETDEWEB)

    Van Hecke, K.; Goethals, P.

    2006-07-15

    The goal of the partitioning and transmutation strategy is to reduce the radiotoxicity of spent nuclear fuel to the level of natural uranium in a short period of time (about 1000 years) and thus the required containment period of radioactive material in a repository. Furthermore, it aims to reduce the volume of waste requiring deep geological disposal and hence the associated space requirements and costs. Several aqueous as well as pyrochemical separation processes have been developed for the partitioning of the long-lived radionuclides from the remaining of the spent fuel. This report aims to describe and compare advanced aqueous reprocessing methods.

  14. Plutonium isotopic assay of reprocessing product solutions in the KfK K-edge densitometer

    International Nuclear Information System (INIS)

    Eberle, H.; Ottmar, H.; Matussek, P.

    1985-04-01

    The KfK K-edge densiometer, designed for accurate element concentration measurements using the technique of X-ray absorptiometry at the K absorption edge, provides as an additional option the possibility to determine the isotopic composition of freshly separated plutonium from an gamma-spectrometric analysis of its self-radiation. This report describes the underlying methodology and experimental procedures for the isotopic analysis in the K-edge densitometer. The paper also presents and discusses the experimental results so far obtained from routine measurements on reprocessing product solutions. (orig.)

  15. Possibilities of tritium removal from waste waters of pressurized water reactors and fuel reprocessing plants

    International Nuclear Information System (INIS)

    Ribnikar, S.V.; Pupezin, J.D.

    1975-01-01

    Starting from parameters known for heavy water production processes, a parallel was made with separation of tritium from water. The quantity in common is the total cascade flow. The most efficient processes appear to be hydrogen sulfide, water exchange, hydrogen- and water distillation. Prospects of application of new processes are discussed briefly. Problems concerning detritiation of pressurized water reactors and large fuel reprocessing plants are analyzed. Detritiation of the former should not present problems. With the latter, economical detritiation can be achieved only after some plant flow patterns are changed. (U.S.)

  16. 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”).

  17. Suomi NPP VIIRS Reflective Solar Bands Operational Calibration Reprocessing

    Directory of Open Access Journals (Sweden)

    Slawomir Blonski

    2015-12-01

    Full Text Available Radiometric calibration coefficients for the VIIRS (Visible Infrared Imaging Radiometer Suite reflective solar bands have been reprocessed from the beginning of the Suomi NPP (National Polar-orbiting Partnership mission until present. An automated calibration procedure, implemented in the NOAA (National Oceanic and Atmospheric Administration JPSS (Joint Polar Satellite System operational data production system, was applied to reprocess onboard solar calibration data and solar diffuser degradation measurements. The latest processing parameters from the operational system were used to include corrected solar vectors, optimized directional dependence of attenuation screens transmittance and solar diffuser reflectance, updated prelaunch calibration coefficients without an offset term, and optimized Robust Holt-Winters filter parameters. The parameters were consistently used to generate a complete set of the radiometric calibration coefficients for the entire duration of the Suomi NPP mission. The reprocessing has demonstrated that the automated calibration procedure can be successfully applied to all solar measurements acquired from the beginning of the mission until the full deployment of the automated procedure in the operational processing system. The reprocessed calibration coefficients can be further used to reprocess VIIRS SDR (Sensor Data Record and other data products. The reprocessing has also demonstrated how the automated calibration procedure can be used during activation of the VIIRS instruments on the future JPSS satellites.

  18. 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

  19. Spent fuel reprocessing and minor actinide partitioning safety related research at the UK National Nuclear Laboratory

    International Nuclear Information System (INIS)

    Carrott, Michael; Flint, Lauren; Gregson, Colin; Griffiths, Tamara; Hodgson, Zara; Maher, Chris; Mason, Chris; McLachlan, Fiona; Orr, Robin; Reilly, Stacey; Rhodes, Chris; Sarsfield, Mark; Sims, Howard; Shepherd, Daniel; Taylor, Robin; Webb, Kevin; Woodall, Sean; Woodhead, David

    2015-01-01

    The development of advanced separation processes for spent nuclear fuel reprocessing and minor actinide recycling is an essential component of international R and D programmes aimed at closing the nuclear fuel cycle around the middle of this century. While both aqueous and pyrochemical processes are under consideration internationally, neither option will gain broad acceptance without significant advances in process safety, waste minimisation, environmental impact and proliferation resistance; at least when compared to current reprocessing technologies. The UK National Nuclear Laboratory (NNL) is developing flowsheets for innovative aqueous separation processes. These include advanced PUREX options (i.e. processes using tributyl phosphate as the extractant for uranium, plutonium and possibly neptunium recovery) and GANEX (grouped actinide extraction) type processes that use diglycolamide based extractants to co-extract all transuranic actinides. At NNL, development of the flowsheets is closely linked to research on process safety, since this is essential for assessing prospects for future industrialisation and deployment. Within this context, NNL is part of European 7. Framework projects 'ASGARD' and 'SACSESS'. Key topics under investigation include: hydrogen generation from aqueous and solvent phases; decomposition of aqueous phase ligands used in separations prior to product finishing and recycle of nitric acid; dissolution of carbide fuels including management of organics generated. Additionally, there is a strong focus on use of predictive process modelling to assess flowsheet sensitivities as well as engineering design and global hazard assessment of these new processes. (authors)

  20. Elaboration of Safe Community Assessment System

    Directory of Open Access Journals (Sweden)

    Algirdas Astrauskas

    2011-12-01

    Full Text Available The paper aims to design an assessment system to monitor and evaluate safety parameters and administrative efforts with the purpose to increase safety in municipalities. The safety monitoring system considered is to be the most important tool for creation anddevelopment of safe communities in Lithuania. Several methods were applied to achieve this purpose. In order to determine the role of local government in ensuring the safety of people, property and environment at the local level of a meta-analysis of research reports,the Lithuanian national legislation, strategic planning documents of the state and local government were carried out. Analysis of statistical data, structural analysis, comparative analysis and synthesis methods were used while investigating the areas of safety uncertainty, risk groups, identifying safety risk factors, determining their relationship, and creating a safe community assessment system.A safe community assessment system, which consists of two types of criteria, has been elaborated. The assessment system is based on the multi-level criteria for safety monitoring and the multi-level criteria for the evaluation of municipal activities in the field of building safety. Links between the criteria, peculiarities of their application and advantages in the process of safe community creation and development are analyzed.Design and implementation of the safe community assessment system is one of the most important stages to implement the idea of safe communities. The proposed system integrates a variety of risk areas, the safety achievement criteria are linked to the criteria used in thestrategic planning. Periodic assessment of the safety situation using the proposed system ensures possibility to monitor current local safety conditions and assess the changes and the trends. A safe community assessment system is proposed to be used as a tool to unified municipalities safety comprehensiveness and compare safety level in

  1. Elaboration of Safe Community Assessment System

    Directory of Open Access Journals (Sweden)

    Birutė Mikulskienė

    2013-08-01

    Full Text Available The paper aims to design an assessment system to monitor and evaluate safety parameters and administrative efforts with the purpose to increase safety in municipalities. The safety monitoring system considered is to be the most important tool for creation and development of safe communities in Lithuania. Several methods were applied to achieve this purpose. In order to determine the role of local government in ensuring the safety of people, property and environment at the local level of a meta-analysis of research reports, the Lithuanian national legislation, strategic planning documents of the state and local government were carried out. Analysis of statistical data, structural analysis, comparative analysis and synthesis methods were used while investigating the areas of safety uncertainty, risk groups, identifying safety risk factors, determining their relationship, and creating a safe community assessment system. A safe community assessment system, which consists of two types of criteria, has been elaborated. The assessment system is based on the multi-level criteria for safety monitoring and the multi-level criteria for the evaluation of municipal activities in the field of building safety. Links between the criteria, peculiarities of their application and advantages in the process of safe community creation and development are analyzed. Design and implementation of the safe community assessment system is one of the most important stages to implement the idea of safe communities. The proposed system integrates a variety of risk areas, the safety achievement criteria are linked to the criteria used in the strategic planning. Periodic assessment of the safety situation using the proposed system ensures possibility to monitor current local safety conditions and assess the changes and the trends. A safe community assessment system is proposed to be used as a tool to unified municipalities safety comprehensiveness and compare safety level in

  2. Matter transfer during virgin olive oil elaboration

    Directory of Open Access Journals (Sweden)

    Gómez Herrera, Carlos

    2007-06-01

    Full Text Available In the course of the process of elaboration of virgin olive oil (whose main stages are crushing, malaxation and centrifugation the transfer of several minor components to the triacylglycerol constituent of the oily globules originally present in the cells of the fruit mesocarp is produced. Such minor components are chemical species present in the olive fruits, as well as those resulting from chemical or enzymatic processes which take place in the olive paste upon crushing. In this paper several types of transferable minor components, as well as those parameters affecting the rates of transfer are studied.Geometric and physical variations of interfacial regions between the oil and other systems in contact with it are discussed. These systems are olive vegetation water, olive pulp components, and fragments of the woody endocarp, as well as the atmospheric air and the tools and equipment of the oil mill.This article concludes with some considerations about the improvements of virgin olive oils achieved by controlling the transfer of minor components.Durante la elaboración del aceite de oliva virgen (cuyas principales etapas son molturación, batido y centrifugación se producen transferencias de diversos componentes menores a los triacilgliceroles originalmente presentes en los glóbulos oleosos de las células del mesocarpio de los frutos. Estos componentes menores son especies químicas presentes en las aceitunas, así como especies resultantes de procesos químicos o enzimáticos que se producen en la pasta a partir de la molturación. En este artículo se estudian diversos tipos de componentes menores transferibles, así como aquellos parámetros que afectan sus velocidades de transferencia.Se discuten las variaciones geométricas y físicas de las regiones interfaciales situadas entre el aceite y los otros sistemas en contacto con el mismo. Estos sistemas son el agua de vegetación, los componentes de la pulpa y los fragmentos de endocarpio

  3. Measuring and Visualizing Group Knowledge Elaboration in Online Collaborative Discussions

    Science.gov (United States)

    Zheng, Yafeng; Xu, Chang; Li, Yanyan; Su, You

    2018-01-01

    Knowledge elaboration plays a critical role in promoting knowledge acquisition and facilitating the retention of target knowledge in online collaborative discussions. Adopting a key-term-based automated analysis approach, we proposed an indicator framework to measure the level of knowledge elaboration in terms of coverage, activation, and…

  4. 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

  5. Storage and separation of gases

    International Nuclear Information System (INIS)

    Biloe, S.; Cagnon, B.; Goetz, V.; Guillot, A.; Mauran, S.; Mazet, N.; Menard, D.; Py, X.

    2005-01-01

    Various processes such as gas separation, gas storage (H 2 or CH 4 ) are known to be inhibited by intrinsic antagonistic material properties (texture, thermal conductivity, permeability). In the following document are gathered the last progress in adsorbent material elaboration and process engineering. (authors)

  6. Extraction separation of americium and curium. A review

    International Nuclear Information System (INIS)

    Petrzilova, H.

    1976-11-01

    A survey is given of extraction systems suitable for transplutonium element separation and preparation as well as for the practical application of their nuclear properties. Methods are discussed in detail of separating the actinide and the lanthanide fractions from fission and corrosion products and of separating americium from curium. The description is completed with flowsheets showing the separation of transplutonium elements from irradiated targets and waste solutions after spent fuel reprocessing. (L.K.)

  7. Applications of chemical sensors in spent fuel reprocessing and waste management

    International Nuclear Information System (INIS)

    Achuthan, P.V.

    2012-01-01

    Environmental friendly power generation is essential to preserve the quality of life for the future generations. For more than fifty years, nuclear energy has proven its potential as an economically and commercially viable alternative to conventional energy. More over it is a clean source of energy with minimum green house effect. Recent data on climate changes have stressed the need for more caution on atmospheric discharges, hence a revival of interest in nuclear energy is in the offing. The entire world is committed to protect the atmosphere from polluting agents. Even nuclear power plants and the fuel cycle facilities are looking forward to reduce the already low gaseous emissions further and also to develop ways and means of controlling the impact of the small but significant radiotoxicity of the wastes generated in the nuclear fuel cycle. Spent fuel reprocessing and associated waste management, an integral part of the nuclear fuel cycle, employs chemical processes for the recovery of fuel value and for the conditioning of the reprocessed waste. In this respect they can be classified as a chemical plant dealing with radioactive materials. Hence it is essential to keep the gaseous, liquid and solid discharges at the lowest possible levels to comply with the regulations of discharges stipulated by the regulatory authorities. Elaborate cleaning and detection systems are needed for effective control of these discharges from both radioactive and chemical contamination point of view. Even though radiation detectors, which are non specific to the analytes, are the major tools for these controls, analyte specific chemical sensors can play a vital role in controlling the chemical vapours/gases generated during processing. The presentation will cover the major areas where chemical sensors play a significant role in this industry. (author)

  8. Historic American Engineering Record, Idaho National Laboratory, Idaho Chemical Processing Plant, Fuel Reprocessing Complex

    Energy Technology Data Exchange (ETDEWEB)

    Susan Stacy; Julie Braun

    2006-12-01

    Just as automobiles need fuel to operate, so do nuclear reactors. When fossil fuels such as gasoline are burned to power an automobile, they are consumed immediately and nearly completely in the process. When the fuel is gone, energy production stops. Nuclear reactors are incapable of achieving this near complete burn-up because as the fuel (uranium) that powers them is burned through the process of nuclear fission, a variety of other elements are also created and become intimately associated with the uranium. Because they absorb neutrons, which energize the fission process, these accumulating fission products eventually poison the fuel by stopping the production of energy from it. The fission products may also damage the structural integrity of the fuel elements. Even though the uranium fuel is still present, sometimes in significant quantities, it is unburnable and will not power a reactor unless it is separated from the neutron-absorbing fission products by a method called fuel reprocessing. Construction of the Fuel Reprocessing Complex at the Chem Plant started in 1950 with the Bechtel Corporation serving as construction contractor and American Cyanamid Company as operating contractor. Although the Foster Wheeler Corporation assumed responsibility for the detailed working design of the overall plant, scientists at Oak Ridge designed all of the equipment that would be employed in the uranium separations process. After three years of construction activity and extensive testing, the plant was ready to handle its first load of irradiated fuel.

  9. Determination of {sup 2}30Th (Ionium) in uranium ores and wastes from uranium reprocessing. IV. Calculation of ionium separation yield; Determinacion de {sup 2}39Th (Ionio) en minerales y residuos del procesado de Uranio. IV: Determinacion del rendimiento en la separacion del {sup 2}30 Th

    Energy Technology Data Exchange (ETDEWEB)

    Galiano Sedano, J. A.; Acena Barrenechea, M. L.

    1974-07-01

    For determining ionium ({sup 2}30Th) in minerals and uranium processing wastes by precipitation with fluorhidric acid, using lanthanum as carrier, and selective extraction with tenoytrifluoroacetone (TTA) followed by radiometric determination of the isolated nuclide, it is necessary the use of a tracer since the chemical yield of the separation ranges between wide limits. In this paper, the use of the beta-emitter {sup 2}34Th as the most convenient tracer is discussed. Equations are derived for correcting for counting errors introduced by other thorium isotopes which are present either in the sample or in the tracer, as well as for calculating the chemical yield of the separation. These equations have been experimentally checked by ionium determinations carried out with different types of samples. (Author) 18 refs.

  10. 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

  11. 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

  12. Spent fuel surveillance at BNFL, Sellafield Nuclear Reprocessing Plant

    International Nuclear Information System (INIS)

    Addison, C.W.E.

    1988-01-01

    A wide range of irradiated nuclear fuels are stored in ponds in BNFL, Sellafield, UK, prior to reprocessing. Magnox fuel from the first UK power generating reactors has been stored and reprocessed since the mid 1950's, and stocks of irradiated AGR (Advanced Gas-cooled Reactor) and Water Reactor fuels are increasing prior to the start of reprocessing oxide fuel in the THORP (Thermal Oxide Reprocessing Plant) facility in the early 1990's. The methods of surveillance for each type of fuel are described. Underwater visual examination in ponds and more detailed examination in shielded caves are carried out. Limited surveillance is necessary for Magnox fuel as storage periods are short. For AGR fuels with longer storage periods the retrieval and element breakdown are described, followed by detailed metallurgical examination of pins and element components. The effect of water chemistry on corrosion performance of irradiated AGR fuel during pond storage is illustrated. The methods of confirming satisfactory water storage of water reactor fuel are outlined. The major results of surveillance of each type of fuel are summarised. The organisation of the work programmes is given. The paper concludes that, mainly through monitoring and surveillance, backed by experimental programmes optimum storage regimes have been developed for the various types of fuel, consistent with planned storage periods prior to reprocessing. (author). 1 ref., 14 figs

  13. Adverse staff health outcomes associated with endoscope reprocessing.

    Science.gov (United States)

    Gutterman, Elane; Jorgensen, Lindsay; Mitchell, Amber; Fua, Sherry

    2013-01-01

    There are occupational challenges associated with cleaning, disinfecting, storing, and transporting flexible endoscopes. Although the Occupational Safety and Health Administration (OSHA) has set standards to protect the safety of health workers in the United States, the standards are not specific to endoscope reprocessing, and the general standards that are in place are not fully implemented. Furthermore, adverse staff outcomes may not be fully preventable. To assess the evidence for adverse outcomes in staff associated with endoscope reprocessing, a literature review was performed in the PubMed database for articles on this topic published between Jan. 1, 2007 and March 7, 2012. Eight studies were identified, mainly European, which reported numerous adverse outcomes to healthcare personnel associated with endoscope reprocessing including respiratory ailments and physical discomfort. More scientifically rigorous studies are required to comprehensively describe adverse health outcomes in personnel engaged in reprocessing, particularly in the United States, and examine whether increased automation of the reprocessing process leads to decreased adverse health outcomes for staff.

  14. Current instrument reprocessing practices. Results of a national survey.

    Science.gov (United States)

    Muscarella, L F

    2001-01-01

    In June 1998, a questionnaire was mailed to approximately 2,900 healthcare professionals to assess current instrument reprocessing and infection control practices and determine whether they have changed during the past decade. Surveys were returned from 146 respondents whose facilities performed gastrointestinal endoscopy. Most respondents were registered nurses and almost all worked in healthcare facilities located in the United States. More than 75% of the respondents reported that infection control practices in endoscopy have improved during the past 10 years. Most respondents used glutaraldehyde to reprocess flexible endoscopes. Immersing endoscopes for 20 minutes at room temperature was commonly practiced. Almost 75% of respondents used an automated device to reprocess flexible endoscopes. Most respondents terminally rinsed the endoscope's channels with 70% alcohol followed by forced-air drying. Few respondents outsourced instruments to a commercial reprocessing company and almost 50% reused disposable items. While some practices in endoscope reprocessing have changed during the past several years, others have not. In general, infection controls appear to have improved during the past decade, with the possible exception of a trend to reuse single-use items.

  15. (reprocessed)CAGE_peaks_annotation - FANTOM5 | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available List Contact us FANTOM5 (reprocessed)CAGE_peaks_annotation Data detail Data name (reprocessed)CAGE_peaks_ann...rence sequences (hg38/mm10). Data file File name: (reprocessed)CAGE_peaks_annotation (Homo sapiens) File URL...: ftp://ftp.biosciencedbc.jp/archive/fantom5/datafiles/reprocessed/hg38_latest/extra/CAGE_peaks_annotation/ ...File size: 16 MB File name: (reprocessed)CAGE_peaks_annotation (Mus musculus) Fil...e URL: ftp://ftp.biosciencedbc.jp/archive/fantom5/datafiles/reprocessed/mm10_latest/extra/CAGE_peaks_annotat

  16. (reprocessed)pooled_ctss - FANTOM5 | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available List Contact us FANTOM5 (reprocessed)pooled_ctss Data detail Data name (reprocessed)pooled_ctss DOI 10.18908...hase2.0 are re-mapped for new reference sequences (hg38/mm10). Data file File name: (reprocess...ed)pooled_ctss (Homo sapiens) File URL: ftp://ftp.biosciencedbc.jp/archive/fantom5/datafiles/reprocess...ed/hg38_latest/extra/pooled_ctss/ File size: 6.5 GB File name: (reprocessed)pooled_ctss (Mus musculus...) File URL: ftp://ftp.biosciencedbc.jp/archive/fantom5/datafiles/reprocessed/mm10

  17. 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

  18. 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

  19. 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

  20. 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

  1. Process alternatives for HTGR fuel reprocessing wastes: an engineering evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Lin, K. H.

    1977-05-01

    An evaluation has been made of numerous process alternatives for different types of radioactive wastes resulting from reprocessing of HTGR fuels. Discussion of pertinent waste characteristics is followed by a description and an assessment of selected process alternatives. The final phase of the discussion is concerned with identification of research and development needs for specific alternatives. High-level solid wastes from the head-end system, which are unique to HTGR fuel reprocessing, require major process development efforts. Most other types of wastes can reasonably be expected to make use of technologies being developed for LWR wastes, and will require minor to moderate modifications.

  2. Elaboration of invariant safety properties from fault-tree analysis

    OpenAIRE

    Henry , Sébastien; Faure , Jean-Marc

    2003-01-01

    International audience; Formal verification of PLC programs using model-checking requires to elaborate previously temporal logic formulae which state in a formal way the properties that must be checked. Unfortunately temporal logic is a formalism totally unknown by automation engineers. This explains why PLC programs developers willing to verify the behavior of their programs are unable to use the existing modelchecking tools. Temporal logic formulae elaboration is a too difficult task. In or...

  3. Implementation of remote maintenance techniques at the La Hague reprocessing plants

    International Nuclear Information System (INIS)

    Saverot, P.M.; Dubois, G.

    1995-01-01

    The effective implementation of the safety objectives of the La Hague reprocessing plants called for several plant design criteria such as containment of radioactive materials and radiation shielding (both in normal operating conditions and off-normal conditions), equipment designs which minimize exposure from maintenance operations, and remote automated operations which can be completely controlled from the central control room. The design of the La Hague reprocessing plants incorporates innovative maintenance concepts to reduce integrated doses of maintenance personnel to ALARA levels. For instance, shearing-dissolution or vitrification cells have overhead remote maintenance cells designed for any type of preventive maintenance or repair of equipment, including replacement of certain items. Equipment and components are handled with remote wall-mounted master-slave manipulators as well as in-cell cranes. When the crane itself requires maintenance, it is brought in a ''garage'' at the extremity of the maintenance cell it services and separated from it by doors. These cranes have demonstrated good operating performance. Equipment such as pumps, valves, ejectors, vacuum filters, pH meter probes, mixer impellers require periodic maintenance during the reprocessing plants operations. This type of equipment is standardized, at La Hague, for a fast turn-around remote replacement without disconnecting process piping. Maintenance, is performed with a Mobile Equipment Replacement Cask (MERC) in a contained area, with temporary barrier modification but without breaching the containment barrier. A fleet of 19 MERCs services the plant and the MERC system has proved its reliability over the past five years in over 600 equipment replacement operations. Occupational dose linked to the operation of the remote maintenance MERC system is very low, close to the detection threshold and not contamination has resulted from it use. (author). 4 figs

  4. 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

  5. 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

  6. 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)

  7. 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)

  8. 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

  9. 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

  10. 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)

  11. Reprocessing of spent fuel, Dounreay and fast breeder reactors

    International Nuclear Information System (INIS)

    Lingjaerde, R.

    1986-11-01

    In the light of the public interest in Norway in the breeder reactor fuel reprocessing plant projected in Dounreay, Scotland, the report gives a description of the research center in Dounreay and the planned joint European demonstration facility (EDRP). Certain aspects of the fast breeder reactor are also explained

  12. 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 assessed using and 8x2x2 factorial design. Design Expert® v.8.01 software was employed for data analysis. Pure excipients were processed by direct compression, while the ibuprofen:excipient mixtures were ...

  13. Eye Movement Desensitization and Reprocessing: A Critical Analysis.

    Science.gov (United States)

    Erwin, Terry McVannel

    Since Shapiro's introduction of Eye Movement Desensitization and Reprocessing (EMDR) in 1989, it has been a highly controversial therapeutic technique. Critical reviews of Shapiro's initial study have highlighted many methodological shortcomings in her work. And early empirical research that followed Shapiro's original study has been criticized…

  14. 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)

  15. 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)

  16. Reprocessing and ultimate disposal of spent nuclear fuels

    International Nuclear Information System (INIS)

    Lukner, C.

    1986-01-01

    The booklet is intended as a source of information for school instruction or adult education. The material presented explains aspects of the nuclear fuel cycle, such as reprocessing and ultimate storage of spent nuclear fuels and radioactive waste. Safety engineering and research is dealt with, as well as aspects of a possible complete shut-down of nuclear installations in our country. (DG) [de

  17. 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.)

  18. 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

  19. 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

  20. 76 FR 24495 - Reprocessing of Reusable Medical Devices; Public Workshop

    Science.gov (United States)

    2011-05-02

    ... between patients can result in the retention of blood, tissue, and other biological debris (soil) in... Public Workshop The public workshop will be organized to discuss the following topic areas: 1. What are...? What are the causes of these problems? 2. What factors or criteria to facilitate reprocessing should be...

  1. Consolidated Fuel Reprocessing Program. Progress report, January 1 to March 31, 1979

    Energy Technology Data Exchange (ETDEWEB)

    Unger, W.E. (comp.)

    1979-06-01

    On Oct. 1, 1978, a transition phase was begun to concentrate all US fuel reprocessing research in one major program, the Consolidated Fuel Reprocessing Program (CFRP). The CFRP is organized into the following: process R and D, engineering research, engineering systems, technical support, HTGR fuel reprocessing, and pyrochemical and dry processing methods. Progress is reported in each area. (DLC)

  2. Combined orbits and clocks from the IGS 2nd reprocessing

    Science.gov (United States)

    Griffiths, J.; Ray, J.

    2016-12-01

    In early 2015, the Analysis Centers (ACs) of the International GNSS Service (IGS) completed their second reanalysis of the full history of globally distributed GPS and GLONASS data collected since 1994. The suite of reprocessed AC solutions includes daily product files containing station positions, Earth rotation parameters, satellite orbits and clocks. This second reprocessing—or repro2—provided the IGS contribution to ITRF2014; it follows the successful first reprocessing, which provided the IGS input for ITRF2008. For this poster, we will discuss the newly combined repro2 GPS orbits and clocks. We also revisit our previous analysis of orbit day-boundary discontinuities with several significant changes and improvements: 1) Orbit discontinuities for the contributing ACs were studied in addition to those for the IGS repro2 combined orbits. (2) Apart from homogeneous reprocessing with updated analysis models, the main difference compared to the IGS Final operational products is that NOAA/NGS inputs were not submitted for the IGS reprocessing, yet they contribute heavily in the operational orbits in recent years. (3) Also, during spring 2016, the ESA modified their orbit model so that it is no longer consistent with the one used for reprocessing. A much longer span of orbits was available now, up to 11.2 years for some individual satellites, which allows a far better resolution of spectral features. 4) The procedure to compute orbit discontinuities has been further refined to account for extrapolation edge effects, improved geopotential fields, and to allow for spectral analysis of a longer time series of jumps. The satellite position time series used are complete enough that linear interpolation is necessary for only sparse gaps. So the key results are based on standard FFT power spectra (stacked over the available constellation and lightly smoothed). However, we have also computed Lomb-Scargle periodgrams to provide higher frequency resolution of some spectral

  3. Combination and long term stability of the IGS Reprocessing campaign

    Science.gov (United States)

    Booker, David; Clarke, Peter J.; Lavallée, David A.

    2010-05-01

    During the relatively short life of the Global Positioning System (GPS) there have been several changes to the analysis procedure, leading to inhomogeneous coordinate time series. Although they have reduced systematic errors in more recent solutions, these changes have modified the apparent periodic signals observed and led to spurious discontinuities. The International GNSS Service (IGS) reprocessing campaign uses the latest operational models and techniques to reprocess the back catalogue of GPS data to produce remove inconsistencies caused by the various model changes, thus producing a homogeneous time series of station coordinates and Earth Rotation Parameters (ERPs). Weekly coordinate and ERP solutions from up to 11 reprocessing analysis centres (ACs) have been aligned to the ITRF and combined using the TANYA software in a rigorous weighted least-squares solution. Analysis of the time series of station coordinates and Helmert transformation parameters between the combined solution and the ITRF shows a at least a 50 percent improvement in the stability of the reprocessed weekly solutions compared with earlier operational products. There is a gradual decrease in the weighted root mean square coordinate difference, both between the combined weekly solutions and the ITRF and between the individual AC solutions and their weekly combination, which reaches a minimum around the end of 2005 with a slight increase thereafter. We observe clear differences in the periodicity of Helmert transformation parameters between the individual AC solutions and the combined solution, which presumably result from variations in AC processing strategy. There is a clear annual or near annual periodic variation in the scale difference between the combined solution and the ITRF05 and some less clear variation between the translation parameters, which needs further analysis as to its cause. Keywords: GPS, ITRF, IGS reprocessing campaign, periodic errors

  4. Separation of actinides and their transmutation

    International Nuclear Information System (INIS)

    Bouchard, M.; Bathelier, M.; Cousin, M.

    1978-08-01

    Neutron irradiation of long-half-life actinides for transmutation into elements with shorter half-life is investigated as a means to reduce the long-term hazards of these actinides. The effectiveness of the method is analysed by applying it to fission product solutions from the first extraction cycle of fuel reprocessing plants. Basic principles, separation techniques and transmutation efficiencies are studied and discussed in detail

  5. Estimated glycemic index and dietary fiber content of cookies elaborated with extruded wheat bran.

    Science.gov (United States)

    Reyes-Pérez, Faviola; Salazar-García, María Guadalupe; Romero-Baranzini, Ana Lourdes; Islas-Rubio, Alma Rosa; Ramírez-Wong, Benjamín

    2013-03-01

    The increasing demand for high-fiber products has favored the design of numerous bakery products rich in fiber such as bread, cookies, and cakes. The objective of this study was to evaluate the dietary fiber and estimated glycemic index of cookies containing extruded wheat bran. Wheat bran was subjected to extrusion process under three temperature profiles: TP1;(60, 75, 85 and 100 °C), TP2;(60, 80, 100 and 120 °C), and TP3;(60, 80, 110 and 140 °C) and three moisture contents: (15, 23, and 31 %). Cookies were elaborated using extruded wheat bran (30 %), separated into two fractions (coarse and fine). The dietary fiber content of cookies elaborated with extruded wheat bran was higher than the controls; C0 (100 % wheat flour) and C1 (30 % of no extruded bran coarse fraction) and C2 (30 % of no extruded bran fine fraction). The higher values of dietary fiber were observed on cookies from treatments 5 (TP1, 31 % moisture content and coarse fraction) and 11 (TP2, 31 % moisture content and coarse fraction). The estimated glycemic index of cookies ranged from 68.54 to 80.16. The dietary fiber content of cookies was increased and the lowest glycemic index corresponded to the cookies elaborated with extruded wheat bran. Cookie made with the treatment 11 had a better dietary fiber content and lower estimated glycemic index.

  6. Elaboration of remediation plan for contaminated sites of Puglia region

    International Nuclear Information System (INIS)

    Ferri, F.; Mura, A.; Tassoni, E.; Mazzotta, V.; Furgiuele, G.

    1995-01-01

    ENEA (Italian Agency for New Technologies, Energy and the Environment) was designated by the Ministry of Environment to elaborate the remediation plan for contaminated sites of Puglia region. The plan was developped by ENEA, following criteria and guidelines fixed by the Environment Department in a decree of may 16th 1989. The activities of the plan were conducted through the following four stages: census and mapping of potentially contaminated sites; settlement of the first list of contaminated sites to submit to remediation; program elaboration for short term interventions on site remediation and drafting general projects; program elaboration for middle term interventions on site remediation. The information collected about all sites during the investigations have been organized on a database, in which an algorithm permits the risk indexes for each site be calculated automatically

  7. An automatic system for elaboration of chip breaking diagrams

    DEFF Research Database (Denmark)

    Andreasen, Jan Lasson; De Chiffre, Leonardo

    1998-01-01

    A laboratory system for fully automatic elaboration of chip breaking diagrams has been developed and tested. The system is based on automatic chip breaking detection by frequency analysis of cutting forces in connection with programming of a CNC-lathe to scan different feeds, speeds and cutting...... depths. An evaluation of the system based on a total of 1671 experiments has shown that unfavourable snarled chips can be detected with 98% certainty which indeed makes the system a valuable tool in chip breakability tests. Using the system, chip breaking diagrams can be elaborated with a previously...

  8. Knowledge-based support system for requirement elaboration in design

    International Nuclear Information System (INIS)

    Furuta, Kazuo; Kondo, Shunsuke

    1994-01-01

    Design requirements are the seeds of every design activity, but elicitation and formalization of them are not easy tasks. This paper proposes a method to support designers in such requirement elaboration process with a computer. In this method the cognitive work space of designers is modeled by abstraction and structural hierarchies, and supporting functions of knowledge-based requirement elaboration, requirement classification and assessment of contentment status of requirements are provided on this framework. A prototype system was developed and tested using fast breeder reactor design. (author)

  9. Gas separation techniques in nuclear facilities

    International Nuclear Information System (INIS)

    Hioki, Hideaki; Morisue, Tetsuo; Ohno, Masayoshi

    1983-01-01

    The literatures concerning the gas separation techniques which are applied to the waste gases generated from nuclear power plants and nuclear fuel reprocessing plants, uranium enrichment and the instrumentation of nuclear facilities are reviewed. The gas permeability and gas separation performance of membranes are discussed in terms of rare gas separation. The investigation into the change of the gas permeability and mechanical properties of membranes with exposure to radiation is reported. The theoretical investigation of the separating cells used for the separation of rare gas and the development of various separating cells are described, and the theoretical and experimental investigations concerning rare gas separation using cascades are described. The application of membrane method to nuclear facilities is explained showing the examples of uranium enrichment, the treatment of waste gases from nuclear reactor buildings and nuclear fuel reprocessing plants, the monitoring of low level β-emitters in stacks, the detection of failed fuels and the detection of water leak in fast breeder reactors. (Yoshitake, I.)

  10. Alternatives to reduce 14C emissions in the reprocessing of HTR fuel elements

    International Nuclear Information System (INIS)

    Schmidt, P.C.

    1979-01-01

    The interest of the public and of experts has increasingly focused on the formation of 14 C in nuclear reactors and its release from reactors and reprocessing plants. The paper attempts an experimental check of the validity of theoretical estimations concerning 14 C production rates. In particular, the applicability of the 14 C analysis in irradiated LWR pellets is checked and transferred to HTR fuel concepts. Statements on the 14 C content in matrix graphite, coating, and fuel make it possible to determine those process steps in which 14 C release is highest. Possibilities to reduce 14 C emissions by improved fuel element production technologies and by mechanical separation of graphite before combustion are theoretically estimated. (orig./GL) [de

  11. Laser induced photochemical and photophysical processes in fuel reprocessing: present scenario and future prospects

    International Nuclear Information System (INIS)

    Bhowmick, G.K.; Sarkar, S.K.; Ramanujam, A.

    2001-01-01

    State-of-art lasers can meet the very stringent requirements of nuclear technology and hence find application in varied areas of nuclear fuel cycle. Here, we discuss two specific applications in nuclear fuel reprocessing namely (a) add-on photochemical modifications of PUREX process where photochemical reactors replace the chemical reactors, and (b) fast, matrix independent sensitive laser analytical techniques. The photochemical modifications based on laser induced valency adjustment offers efficient separation, easy maintenance and over all reduction in the volume of radioactive waste. The analytical technique of time resolved laser induced fluorescence (TRLIF) has several attractive features like excellent sensitivity, element selective, and capability of on line remote process monitoring. For optically opaque solutions, optical excitation is detected by its conversion into thermal energy by non-radiative relaxation processes using the photo-thermal spectroscopic techniques. (author)

  12. Handling and storage of high-level liquid wastes from reprocessing of spent fuel

    International Nuclear Information System (INIS)

    Finsterwalder, L.

    1982-01-01

    The high level liquid wastes arise from the reprocessing of irradiated nuclear fuels, which are dissolved in aqueous acid solution, and the plutonium and unburned uranium removed in the chemical separation plant. The remaining solution, containing more than 99% of the dissolved fission products, together with impurities from cladding materials, corrosion products, traces of unseparated plutonium and uranium and most of the transuranic elements, constitutes the high-level waste. At present, these liquid wastes are usually concentrated by evaporation and stored as an aqueous nitric acid solution in high-integrity stainless-steel tanks. There is now world-wide agreement that, for the long term, these liquid wastes should be converted to solid form and much work is in progress to develop techniques for the solidification of these wastes. This paper considers the design requirements for such facilities and the experience gained during nearly 30 years of operation. (orig./RW)

  13. [The role of eye movement desensitization and reprocessing (EMDR) in substance use disorders: A systematic review].

    Science.gov (United States)

    Pilz, René; Hartleb, Riccarda; Konrad, Gabriela; Reininghaus, Eva; Unterrainer, Human Friedrich

    2017-10-01

    Eye Movement Desensitization and Reprocessing (EMDR) is a therapeutic method that has been shown to be especially effective in traumatic disorders. Since the concept of an addiction memory has become widely accepted, the use of EMDR also in substance use disorders (SUD) treatment might count as a separate field. This review summarizes the current state of research on treatment effects EMDR in SUD. The literature search included the databases of PubMed and PsychInfo; four studies met the inclusion criteria. EMDR was found to be related to a decreased amount of craving, fear and depression and to an improvement of emotion regulation and management and self-esteem. Initial findings indicate a high therapeutic potential of EMDR in SUD treatment. Georg Thieme Verlag KG Stuttgart · New York.

  14. Advanced dry head-end reprocessing of light water reactor spent nuclear fuel

    Science.gov (United States)

    Collins, Emory D; Delcul, Guillermo D; Hunt, Rodney D; Johnson, Jared A; Spencer, Barry B

    2013-11-05

    A method for reprocessing spent nuclear fuel from a light water reactor includes the step of reacting spent nuclear fuel in a voloxidation vessel with an oxidizing gas having nitrogen dioxide and oxygen for a period sufficient to generate a solid oxidation product of the spent nuclear fuel. The reacting step includes the step of reacting, in a first zone of the voloxidation vessel, spent nuclear fuel with the oxidizing gas at a temperature ranging from 200-450.degree. C. to form an oxidized reaction product, and regenerating nitrogen dioxide, in a second zone of the voloxidation vessel, by reacting oxidizing gas comprising nitrogen monoxide and oxygen at a temperature ranging from 0-80.degree. C. The first zone and the second zone can be separate. A voloxidation system is also disclosed.

  15. 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

  16. Separation of Plutonium from Irradiated Fuels and Targets

    Energy Technology Data Exchange (ETDEWEB)

    Gray, Leonard W. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Holliday, Kiel S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Murray, Alice [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Thompson, Major [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Thorp, Donald T. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Yarbro, Stephen [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Venetz, Theodore J. [Hanford Site, Benton County, WA (United States)

    2015-09-30

    Spent nuclear fuel from power production reactors contains moderate amounts of transuranium (TRU) actinides and fission products in addition to the still slightly enriched uranium. Originally, nuclear technology was developed to chemically separate and recover fissionable plutonium from irradiated nuclear fuel for military purposes. Military plutonium separations had essentially ceased by the mid-1990s. Reprocessing, however, can serve multiple purposes, and the relative importance has changed over time. In the 1960’s the vision of the introduction of plutonium-fueled fast-neutron breeder reactors drove the civilian separation of plutonium. More recently, reprocessing has been regarded as a means to facilitate the disposal of high-level nuclear waste, and thus requires development of radically different technical approaches. In the last decade or so, the principal reason for reprocessing has shifted to spent power reactor fuel being reprocessed (1) so that unused uranium and plutonium being recycled reduce the volume, gaining some 25% to 30% more energy from the original uranium in the process and thus contributing to energy security and (2) to reduce the volume and radioactivity of the waste by recovering all long-lived actinides and fission products followed by recycling them in fast reactors where they are transmuted to short-lived fission products; this reduces the volume to about 20%, reduces the long-term radioactivity level in the high-level waste, and complicates the possibility of the plutonium being diverted from civil use – thereby increasing the proliferation resistance of the fuel cycle. In general, reprocessing schemes can be divided into two large categories: aqueous/hydrometallurgical systems, and pyrochemical/pyrometallurgical systems. Worldwide processing schemes are dominated by the aqueous (hydrometallurgical) systems. This document provides a historical review of both categories of reprocessing.

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

    International Nuclear Information System (INIS)

    Girardi, F.; Bertozzi, G.

    1974-01-01

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

  18. Narrative elaboration: test of a new procedure for interviewing children.

    Science.gov (United States)

    Saywitz, K J; Snyder, L

    1996-12-01

    Because young children provide incomplete accounts of the past and tend to acquiesce to leading questions, procedures are needed to help them describe past events fully, without contaminating memory. This study tests the efficacy of "narrative elaboration," an innovative procedure designed to expand children's spontaneous reports of past events, reducing the need for leading questions. One hundred thirty-two children from 2 age groups (7-8 years and 10-11 years) were assigned randomly to 1 of 3 preparation conditions: (a) narrative elaboration intervention, (b) instruction-based intervention, and (c) control group. After participating in a staged activity and subsequent preparation sessions, children were interviewed about the activity. Children in the narrative elaboration condition demonstrated a 53% improvement in spontaneous recall over the control group, without compromising accuracy. Younger children using the narrative elaboration procedure performed at the level of older children in the control group. Discussion centers on implications for interviewing child witnesses and preparing them for courtroom examination.

  19. Elaboration in the area of aluminium containing alloys

    International Nuclear Information System (INIS)

    Mirsaidov, U.M.

    2002-01-01

    In the Institute of Chemistry was elaborated the experimental-industrial installation and technology of deep aluminium purification by the methods of zone melting and recrystallization. The developed technology let receive the metal of model A5 N A6 N dependence from number of induction zone passage

  20. Elaborer un exercice de grammaire (Working Out a Grammar Exercise)

    Science.gov (United States)

    Principaud, Jeanne-Marie

    1977-01-01

    An elaboration of the official instruction on teaching French to native speakers in elementary school. The topics covered are: Methodological development of exercises; the linguistic ability and milieu of the students; operative criteria; and the question of a logical progression or spontaneous use of grammar exercises. (Text is in French.) (AMH)

  1. Challenging Stereotypes about Academic Writing: Complexity, Elaboration, Explicitness

    Science.gov (United States)

    Biber, Douglas; Gray, Bethany

    2010-01-01

    The stereotypical view of professional academic writing is that it is grammatically complex, with elaborated structures, and with meaning relations expressed explicitly. In contrast, spoken registers, especially conversation, are believed to have the opposite characteristics. Our goal in the present paper is to challenge these stereotypes, based…

  2. Elaborating on the attitude–behaviour gap regarding organic products

    DEFF Research Database (Denmark)

    Aschemann-Witzel, Jessica; Aagaard, Emilie Marie Niebuhr

    2014-01-01

    in the store and the personal context (moral beliefs, household member influence) impact the argumentations, which lead to a choice decision and subsequent elaboration of the consequences of this choice. Price is discussed as a main barrier, but a temporary one: young consumers argue that they postpone organic...... ethical values, instead of postponing it....

  3. Elaborating teaching materials for Baure: When teachers are learners

    NARCIS (Netherlands)

    Admiraal, F.

    2012-01-01

    This paper presents the first steps in the elaboration of teaching materials in Baure, a language on the verge of extinction, spoken in Bolivian Amazonia. The Baure speakers are all elderly people and fully bilingual in the dominant language Spanish. In Bolivia, indigenous language teaching in

  4. X-RAYS SEPARATOR: FORWARD STEP IN TECHNOLOGY OF OPTICAL SEPARATION

    OpenAIRE

    N. N. Potrakhov; S. L. Beletskiy; F. B. Musaev

    2017-01-01

    Presently the X-ray separation is used not only for research program, but it is also elaborated and applied for different sectors of economy. The seeds as biological objects that possess the complicated microstructure are very difficult to be exanimated by x-ray technology. The application of x-rays and further elaboration of optical  separators, principle  of action, basic specifications, way of their use and their efficiency was shown in the article. The x-ray separator may distinguish all ...

  5. 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

  6. 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.)

  7. 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.

  8. 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.)

  9. TOR: reprocessing of fuel from fast-breeder reactors

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    There have been three stages in the development of the fast-breeder and three stages in fuel reprocessing development. An experimental stage where the cycle was closed with Rapsodie and the fast-breeder fuel processing workshop a La Hague. A demonstration stage -operation TOR- which made it possible to close the Phenix cycle. An industrial prototype stage on an industrial scale which will be achieved with the coming onstream of the Rapid Reprocessing Plant (PURR) (Usine de Retraitement Rapide). The research and construction were carried out in such a way that the move from one stage to another was achieved with the maximum amount of continuity with the benefit of all the experience achieved previously [fr

  10. 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

  11. 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)

  12. 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

  13. 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.)

  14. 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

  15. 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.)

  16. 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

  17. Decommissioning experience of the reprocessing facility AT 1

    International Nuclear Information System (INIS)

    Montjoie, M.; Lurie, R.; Roger, J.

    1987-01-01

    AT1 was a pilot plant for reprocessing the mixed oxide fuel elements from the FBR program. It was operated successfully during ten years and definitively shut down in 1979. After two years of fissile material recovery and decontamination of the process line it was decided to decommission the unit to stage 3. Even though small in reprocessing capacity, it contained all the difficulties and specific problems of this type of facility, and needed the development of equipment such as: a remote controlled machine for dismantling the main cells; a modular α tight workshop to dismantle the glove boxes and α cells; and an α activity measurement station to be able to fit with the requirements of the disposal site. These activities are discussed

  18. 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

  19. Innovative electronic analysis device for nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Ash, D.C.; Joyce, M.J.; Garnham, G.W.; Port, S.N.; Barnes, C.

    2001-01-01

    Nuclear reprocessing uses a fluid interaction to recover unused fuel from the waste stream. A mixture of tri-n-butyl phosphate (TBP) and odorless kerosene (OK) is used to extract the unused plutonium and uranium from the aqueous waste stream. It is not surprising then that the liquid physical properties play an important role in the efficiency of the reprocessing process. Viscosity of the TBP/OK mixture used is a crucial area and the Quartz Crystal Microbalance (QCM) lends itself well to the function of testing this viscosity with minimum wastage of fluids and fluid samples. In this paper, we report on the latest results of this novel application of the QCM associated with the viscosity measurement of TBP/OK. (author)

  20. 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

  1. Inspiration fra New York - udforskende læreprocesser

    DEFF Research Database (Denmark)

    Jørgensen, Lone Tang

    2017-01-01

    Udforskende læreprocesser er inspireret af John Deweys filosofi og pædagogik og bygger på en didaktisk tilrettelæggelse, der vægter den demokratiske dannelse og børnenes medindflydelse på det, der arbejdes med i klasserummet. Børnenes erfaringer, interesser og engagement er selve afsættet for til...

  2. On the Reprocessing and Reanalysis of Observations for Climate

    Science.gov (United States)

    Bosilovich, Michael G.; Kennedy, John; Dee, Dick; Allan, R.; O'Neill, Alan

    2013-01-01

    The long observational record is critical to our understanding of the Earths climate, but most observing systems were not developed with a climate objective in mind. As a result, tremendous efforts have gone into assessing and reprocessing the data records to improve their usefulness in climate studies. The purpose of this paper is to both review recent progress in reprocessing and reanalyzing observations, and to summarize the challenges that must be overcome in order to improve our understanding of climate and variability. Reprocessing improves data quality through more scrutiny and improved retrieval techniques for individual observing systems, while reanalysis merges many disparate observations with models through data assimilation, yet both aim to provide an climatology of Earth processes. Many challenges remain, such as tracking the improvement of processing algorithms and limited spatial coverage. Reanalyses have fostered significant research, yet reliable global trends in many physical fields are not yet attainable, despite significant advances in data assimilation and numerical modeling. Oceanic reanalyses have made significant advances in recent years, but will only be discussed here in terms of progress toward integrated Earth system analyses. Climate data sets are generally adequate for process studies and large-scale climate variability. Communication of the strengths, limitations and uncertainties of reprocessed observations and reanalysis data, not only among the community of developers, but also with the extended research community, including the new generations of researchers and the decision makers is crucial for further advancement of the observational data records. It must be emphasized that careful investigation of the data and processing methods are required to use the observations appropriately.

  3. Risks of explosion associated with 'red oils' in reprocessing plants

    International Nuclear Information System (INIS)

    2008-01-01

    This note presents the risks of explosion associated with reactions between TBP (tributylphosphate), its degradation products and nitrates derived from nitric acid or associated with heavy metals (uranium and plutonium), leading to the formation of unstable compounds known as 'red oils'. Feedback from explosions associated with the formation of these compounds, occurring in reprocessing plants around the world, is dealt with concisely. The main measures for controlling these risks implemented in the French plants concerned are also presented. (authors)

  4. 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

  5. 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

  6. Legal implications of single-use medical device reprocessing.

    Science.gov (United States)

    Larose, Emily

    2013-01-01

    Over 10 years ago, the Public Health Agency of Canada released the results of a nation-wide survey of hospitals that demonstrated that the reuse of single-use medical devices was widespread in Canadian healthcare institutions. In this article, the author discusses the reuse and reprocessing of these devices, as well as the risks this practice presents. She then goes on to outline the legal implications of reusing single-use devices. Copyright © 2013 Longwoods Publishing.

  7. 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...

  8. Reprocessing of nuclear fuel elements from the Netherlands. An analysis

    International Nuclear Information System (INIS)

    Dodd, D.H.; Harry, R.J.S.; Kloosterman, J.L.; Konings, R.J.M.; Versteegh, A.M.

    1997-05-01

    The results of an analysis of a route for the processing and storage of spent fission fuel elements from Dutch nuclear power plants (Borssele and Dodewaard) are presented. Also an alternative route in which the fuel elements are stored without being reprocessed is discussed in detail. Environmental effects, proliferation aspects and the costs for each step in both routes are discussed where appropriate. 2 figs., 10 tabs., 14 refs

  9. Nuclear engineering questions: power, reprocessing, waste, decontamination, fusion

    International Nuclear Information System (INIS)

    Walton, R.D. Jr.

    1979-01-01

    This volume contains papers presented at the chemical engineering symposium on nuclear questions. Specific questions addressed by the speakers included: nuclear power - why and how; commercial reprocessing - permanent death or resurrection; long-term management of commercial high-level wastes; long-term management of defense high-level waste; decontamination and decommissioning of nuclear facilities, engineering aspects of laser fusion I; and engineering aspects of laser fusion II. Individual papers have been input to the Energy Data Base previously

  10. 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

  11. Reprocessing technology of liquid metal cooled fast breeder reactor fuel

    International Nuclear Information System (INIS)

    Baetsle, L.H.; Broothaerts, J.; Heylen, P.R.; Eschrich, H.; Geel, J. van

    1974-11-01

    All the important aspects of LMFBR fuel reprocessing are critically reviewed in this report. Storage and transportation techniques using sodium, inert gas, lead, molten salts and organic coolants are comparatively discussed in connection with cooling time and de-activation techniques. Decladding and fuel disaggregation of UO 2 -PuO 2 fuel are reviewed according to the present state of R and D in the main nuclear powers. Strong emphasis is put on on voloxidation, mechanical pulverization and molten salt disaggregation in connection with volatilization of gaseous fission products. Release of fission gases and the resulting off-gas treatment are discussed in connection with cooling time, burn up and dissagregation techniques. The review is limited to tritium, iodine xenon-krypton and radioactive airborne particulates. Dissolution, solvent extraction and plutonium purification problems specifically connected to LMFBR fuel are reviewed with emphasis on the differences between LWR and fast fuel reprocessing. Finally the categories of wastes produced by reprocessing are analysed according to their origin in the plant and their alpha emitters content. The suitable waste treatment techniques are discussed in connection with the nature of the wastes and the ultimate disposal technique. (author)

  12. Fuel reprocessing data validation using the isotope correlation technique

    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, and graphite reactors) operating in a variety of modes (power, research, and production reactors), 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

  13. Methodology for estimating reprocessing costs for nuclear fuels

    International Nuclear Information System (INIS)

    Carter, W.L.; Rainey, R.H.

    1980-02-01

    A technological and economic evaluation of reprocessing requirements for alternate fuel cycles requires a common assessment method and a common basis to which various cycles can be related. A methodology is described for the assessment of alternate fuel cycles utilizing a side-by-side comparison of functional flow diagrams of major areas of the reprocessing plant with corresponding diagrams of the well-developed Purex process as installed in the Barnwell Nuclear Fuel Plant (BNFP). The BNFP treats 1500 metric tons of uranium per year (MTU/yr). Complexity and capacity factors are determined for adjusting the estimated facility and equipment costs of BNFP to determine the corresponding costs for the alternate fuel cycle. Costs of capacities other than the reference 1500 MT of heavy metal per year are estimated by the use of scaling factors. Unit costs of reprocessed fuel are calculated using a discounted cash flow analysis for three economic bases to show the effect of low-risk, typical, and high-risk financing methods

  14. Study of an ADS Loaded with Thorium and Reprocessed Fuel

    Directory of Open Access Journals (Sweden)

    Graiciany de Paula Barros

    2012-01-01

    Full Text Available Accelerator-driven systems (ADSs are investigated for long-lived fission product transmutation and fuel regeneration. The aim of this paper is to investigate the nuclear fuel evolution and the neutronic parameters of a lead-cooled accelerator-driven system used for fuel breeding. The fuel used in some fuel rods was T232hO2 for U233 production. In the other fuel rods was used a mixture based upon Pu-MA, removed from PWR-spent fuel, reprocessed by GANEX, and finally spiked with thorium or depleted uranium. The use of reprocessed fuel ensured the use of T232hO2 without the initial requirement of U233 enrichment. In this paper was used the Monte Carlo code MCNPX 2.6.0 that presents the depletion/burnup capability, combining an ADS source and kcode-mode (for criticality calculations. The multiplication factor (keff evolution, the neutron energy spectra in the core at BOL, and the nuclear fuel evolution during the burnup were evaluated. The results indicated that the combined use of T232hO2 and reprocessed fuel allowed U233 production without the initial requirement of U233 enrichment.

  15. Reprocessing free nuclear fuel production via fusion fission hybrids

    Energy Technology Data Exchange (ETDEWEB)

    Kotschenreuther, Mike, E-mail: mtk@mail.utexas.edu [Intitute for Fusion Studies, University of Texas at Austin (United States); Valanju, Prashant; Mahajan, Swadesh [Intitute for Fusion Studies, University of Texas at Austin (United States)

    2012-05-15

    Fusion fission hybrids, driven by a copious source of fusion neutrons can open qualitatively 'new' cycles for transmuting nuclear fertile material into fissile fuel. A totally reprocessing-free (ReFree) Th{sup 232}-U{sup 233} conversion fuel cycle is presented. Virgin fertile fuel rods are exposed to neutrons in the hybrid, and burned in a traditional light water reactor, without ever violating the integrity of the fuel rods. Throughout this cycle (during breeding in the hybrid, transport, as well as burning of the fissile fuel in a water reactor) the fissile fuel remains a part of a bulky, countable, ThO{sub 2} matrix in cladding, protected by the radiation field of all fission products. This highly proliferation-resistant mode of fuel production, as distinct from a reprocessing dominated path via fast breeder reactors (FBR), can bring great acceptability to the enterprise of nuclear fuel production, and insure that scarcity of naturally available U{sup 235} fuel does not throttle expansion of nuclear energy. It also provides a reprocessing free path to energy security for many countries. Ideas and innovations responsible for the creation of a high intensity neutron source are also presented.

  16. Reprocessing free nuclear fuel production via fusion fission hybrids

    International Nuclear Information System (INIS)

    Kotschenreuther, Mike; Valanju, Prashant; Mahajan, Swadesh

    2012-01-01

    Fusion fission hybrids, driven by a copious source of fusion neutrons can open qualitatively “new” cycles for transmuting nuclear fertile material into fissile fuel. A totally reprocessing-free (ReFree) Th 232 –U 233 conversion fuel cycle is presented. Virgin fertile fuel rods are exposed to neutrons in the hybrid, and burned in a traditional light water reactor, without ever violating the integrity of the fuel rods. Throughout this cycle (during breeding in the hybrid, transport, as well as burning of the fissile fuel in a water reactor) the fissile fuel remains a part of a bulky, countable, ThO 2 matrix in cladding, protected by the radiation field of all fission products. This highly proliferation-resistant mode of fuel production, as distinct from a reprocessing dominated path via fast breeder reactors (FBR), can bring great acceptability to the enterprise of nuclear fuel production, and insure that scarcity of naturally available U 235 fuel does not throttle expansion of nuclear energy. It also provides a reprocessing free path to energy security for many countries. Ideas and innovations responsible for the creation of a high intensity neutron source are also presented.

  17. Reprocessed uranium recycling: the ideal and the facts

    International Nuclear Information System (INIS)

    Comte, D.

    1998-01-01

    Commercial reprocessing of Light Water Reactor (LWR) spent fuel provides Reprocessed Uranium (RepU) and plutonium, both products containing a large amount of energy. As the gap, already quite large, between uranium consumption and production threatens to grow, these materials show today a strong strategic benefit, constituting a substantial and reliable source of supply for nuclear fuel manufacturing. RepU, which represents about 96% of recycled materials, can be used in all major types of nuclear power reactor currently in operation. This paper focuses on RepU recycling in LWRs, the feasibility of which is technically well established world-wide, and industrially demonstrated through experience gained within the COGEMA Group. Contrary to a commonly accepted assumption, which probably derives from natural uranium prices remaining for more than a decade at a low level which cannot be sustained into the future, recycling RepU can also bring strong economic benefits to the utilities. It generates savings on uranium procurement that exceed expenditures associated with storing and processing RepU. Thus, the use of this product is an attractive option. The strategic and economic benefits of recycling RepU will become compelling in the near future. Anticipating these needs, the COGEMA Group has developed capabilities to offer utilities the services covering all steps from reprocessing of spent fuel to fuel fabrication using RepU. (author)

  18. On permission of reprocessing project change at the Reprocessing Works of the Japan Nuclear Fuel Ltd. (Reply)

    International Nuclear Information System (INIS)

    1997-01-01

    The Nuclear Safety Commission replied as follows to the Prime Minister on July 14, 1997 on permission of reprocessing project change at the Reprocessing Works of the Japan Nuclear Fuel Ltd. inquired on Dec. 26, 1996. Contents of the inquiry consisted of change of refinery facility and its related instruments, integration of low level wasted liquid treating instrument and change of low level solid waste treating instrument, integration of high level wasted liquid storing building and high level wasted liquid glassification building, installation of used fuel transporting container maintenance instrument and its relating instruments, and so forth. As a result of careful discussion at the Commission for these items, they were admitted to be valid on her technical ability and her safety. (G.K.)

  19. R and D on fast reactor fuel reprocessing

    International Nuclear Information System (INIS)

    Subba Rao, R.V.; Vijaya Kumar, V.; Natarajan, R.

    2012-01-01

    Development of Fast Reactor Fuel Reprocessing technology, with low out of pile inventory, is carried out at the Indira Gandhi Centre for Atomic Research (IGCAR). Based on the successful R and D programme which addressed specific issues of fast reactor fuels, a pilot plant called CORAL was set up. This plant is operational since 2003 and several reprocessing campaigns with spent FBTR fuels of varying burnups have been carried out. Based on the valuable operating experience of CORAL, the design of demonstration fast reactor fuel reprocessing plant (DFRP) and the commercial reprocessing plant, FRP have been taken up. Concurrently R and D efforts are continuing for improving the process and equipment performance apart from reducing the waste volumes and the radiation exposures to the operating personnel. Some important R and D efforts are highlighted in the paper. Reducing the dissolution time is one of the vital area of investigation especially for the high plutonium bearing MOX fuels which are known to dissolve slowly. To address this as well as criticality issues, continuous dissolvers are being developed. Solvent extraction based process is employed for getting highly pure nuclear grade uranium and plutonium. In view of the lower cooling time the fission product activity in the spent fuel is higher, formulation of process flowsheet with reduced number of solvent extraction cycles to improve the decontamination of ruthenium and zirconium without the formation of second organic phase due to plutonium loading, is under investigation. Retention of plutonium in lean organic is another issue to be addressed as otherwise it would lead to further deterioration of the solvent on storage. Several reagents to effectively wash the lean solvent have been investigated and flowsheets have been formulated to recover the retained plutonium with minimum secondary wastes. Partitioning of uranium and plutonium is an important step and methods reported in the literature have inherent

  20. Safe storage time for reprocessed flexible endoscopes: a systematic review.

    Science.gov (United States)

    Schmelzer, Marilee; Daniels, Glenda; Hough, Helen

    2015-09-01

    Flexible endoscopes are used to diagnose and treat gastrointestinal and pulmonary diseases. They have narrow, internal channels which are used to insert instruments, air and water into hollow organs and to remove tissues and secretions. Since endoscopes are contaminated during use and have heat sensitive components that cannot be sterilized, they are reprocessed with cleaning and high-level disinfection to destroy microorganisms. Knowing how long reprocessed endoscopes can be safely stored is essential for preventing infection and decreasing unnecessary costs. The objective was to systematically review the best available evidence related to safe storage time (in days) of flexible endoscopes that have undergone reprocessing in order to determine when they can be safely used again without posing any risk of contamination from pathogens. The types of equipment were flexible endoscopes that had been reprocessed according to recommended guidelines, stored for a specified period of time, and tested for microorganisms.The intervention was the length of time (in days) that reprocessed endoscopes were appropriately stored before use.This review included non-randomized controlled trials and prospective cohort studies.This review considered studies that included the outcome measure: microbial growth on endoscopes which was measured with microbiological cultures. The search strategy aimed to find studies in English and Spanish and included published and unpublished studies from 1990 to 2014. An initial search of CINAHL, MEDLINE/PUBMed and EMBASE was conducted followed by an analysis of the text words contained in the title and abstract and index terms used to describe the articles. Next, a search using all identified keywords and index terms was undertaken across all included databases. Then, the reference lists of all identified reports and articles were searched for additional studies. A citation search was performed in order to find additional studies that cited those

  1. Isotope separation

    International Nuclear Information System (INIS)

    Ravoire, Jean

    1978-11-01

    Separation of isotopes is treated in a general way, with special reference to the production of enriched uranium. Uses of separated isotopes are presented quickly. Then basic definitions and theoretical concepts are explained: isotopic effects, non statistical and statistical processes, reversible and irreversible processes, separation factor, enrichment, cascades, isotopic separative work, thermodynamics. Afterwards the main processes and productions are reviewed. Finally the economical and industrial aspects of uranium enrichment are resumed [fr

  2. Elaboration and validation of an assistive technology assessment questionnaire

    Directory of Open Access Journals (Sweden)

    Fernanda Jorge Guimarães

    2015-06-01

    Full Text Available Assistive Technologies consists of resources, methods, and strategies favoring autonomy and inclusion of elderly and people with disabilities, being scarce in the literature instruments assessing them. A methodology study conducted with a panel of specialists and people with visual impairment, aimed to elaborate and validate a questionnaire to assess educational assistive technology. To consider an item as valid, we used 80% as agreement percentage, and validity and reliability of the questionnaire were calculated. Assistive Technology was characterized in six attributes: objectives, access, clarity, structure and presentation, relevance and efficacy, interactivity, and 19 items were elaborated to compose the questionnaire. From those, 11 obtained percentages higher than 80%, seven were modified and one was excluded. The instrument Cronbach’s alpha was 0,822, guaranteeing validity and reliability of the tool to assess health education Assistive Technology, and therefore, its use is indicated.

  3. Elaboration and characterisation of plutonium waste reference materials

    International Nuclear Information System (INIS)

    Perolat, J.P.

    1990-01-01

    The Analysis Methods Establishment Commission (CETAMA) has set up a program for the elaboration and characterisation of plutonium waste reference materials. The object of this program is to give laboratories the possibility to test and calibrate apparatus used in non-destructive methods for the analysis of plutonium waste. The different parameters of this program are presented: - characterisation of plutonium, - type and number of containers, - plutonium distribution inside the different containers, - description of the matrix

  4. Systematic elaboration of online energy management laws for hybrid vehicles

    OpenAIRE

    SCORDIA, Julien; TRIGUI, Rochdi; JEANNERET, Bruno; BADIN, François; MALAQUIN, Bertrand

    2005-01-01

    In this paper, we describe a systematic methodology to elaborate hybrid vehicle energy management laws. "Systematic" means that this conception is done with minimal tuning, whatever the hybrid vehicle architecture and sizing are. A radial basis function type neural network is used to learn from the offline energy management laws given by an optimization tool named KOALA. Then the trained neural network can be used to control the hybrid vehicle online. The results are satisfactory as regards h...

  5. Consolidity: Stack-based systems change pathway theory elaborated

    OpenAIRE

    Dorrah, Hassen Taher

    2014-01-01

    This paper presents an elaborated analysis for investigating the stack-based layering processes during the systems change pathway. The system change pathway is defined as the path resulting from the combinations of all successive changes induced on the system when subjected to varying environments, activities, events, or any excessive internal or external influences and happenings “on and above” its normal stands, situations or set-points during its course of life. The analysis is essentially...

  6. Potential safety-related incidents with possible applicability to a nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Perkins, W.C.; Durant, W.S.; Dexter, A.H.

    1980-12-01

    The occurrence of certain potential events in nuclear fuel reprocessing plants could lead to significant consequences involving risk to operating personnel or to the general public. This document is a compilation of such potential initiating events in nuclear fuel reprocessing plants. Possible general incidents and incidents specific to key operations in fuel reprocessing are considered, including possible causes, consequences, and safety features designed to prevent, detect, or mitigate such incidents

  7. Ecological risk of reprocessing of uranium wastes of the Gafurov's tailing pit

    International Nuclear Information System (INIS)

    Khakimov, N.; Nazarov, Kh.M.; Kamalov, D.D.; Mirsaidov, U.M.

    2010-01-01

    Present article is devoted to assessment ecological risk of reprocessing of uranium wastes of the Gafurov's tailing pit. Authors set as their purpose the investigation of ecological risk of reprocessing of uranium wastes of the Gafurov-city's tailing pit. Having carried out their investigations, the authors came to the conclusion that the effect of radon gas during reprocessing to workers and specialists is minimal if they follow all the required safety rules.

  8. Signaling Elaboration: Combining French Gerund Clauses with Lexical Cohesion Cues

    Directory of Open Access Journals (Sweden)

    Marianne Vergez-Couret

    2012-07-01

    Full Text Available In this paper, we focus on the Elaboration relation and on its automatic identification in French, using the theoretical framework of Segmented Discourse Representation Theory (SDRT. One of the information sources identified by the SDRT framework to infer the Elaboration relation is based on the existence of a potential subsumption link between the eventualities at stake, depending on lexical semantics and world knowledge. We investigate this claim by combining a weak syntactic marker of the Elaboration relation, namely the gerund clause, with lexical cohesion cues. We aim at automatically identifying gerund clauses which are Elaborations by finding cohesive links between the host main clause and the gerund clause. This approach makes it possible to accurately detect few cases of intra-sentential Elaborations in our corpus, confirming the fact that lexical cohesion cues are relevant for this task.Dans cet article, nous nous focalisons sur la relation d’Élaboration en français, telle qu’elle est décrite dans le modèle théorique de la SDRT (Segmented Discourse Representation Theory, et sur son identification automatique. Selon la SDRT, une des sources d’information permettant d’inférer la relation d’Élaboration est basée sur l’existence d’un lien de subsomption entre les types des éventualités des segments à relier, indiquant que le type de la seconde éventualité est un sous-type de celui de la première dans la sémantique lexicale des éventualités ou grâce à des connaissances du monde. Nous proposons de contribuer à cette question en combinant un indice de la relation d’Élaboration, i. e. la construction syntaxique du gérondif, et des indices de cohésion lexicale. Notre objectif est d’identifier automatiquement des propositions gérondives qui sont des Élaborations en repérant des indices de cohésion lexicale entre la proposition principale et la proposition gérondive. Cette approche permet de d

  9. Study on reprocessing plant for the transition period from LWR to FBR. Concept for the next reprocessing plant from the viewpoint of plutonium supply and demand

    International Nuclear Information System (INIS)

    Shimada, Takashi; Matsui, Minefumi; Nishimura, Masashi; Ishida, Yasuhiro; Mori, Yukihide; Kuroda, Kazuhiko

    2011-01-01

    This paper discusses the reprocessing plant concept suitable for the transition period from the Light Water Reactors (LWRs) to the Fast Breeder Reactors (FBRs). This transition requires the reprocessing of spent fuels in order to supply an adequate volume of fissile plutonium (Pu-fissile) for the FBRs. The transition period would continue for more than 60 years, and the reprocessing plant should match with the change in the power generation plan during the transition period. The ability to supply Pu-fissile has been evaluated for two plant concepts. One is the independent-type concept, which contains two processes for reprocessing either LWR or FBR fuels. The other is the modularized-type concept, which contains only one process for reprocessing both the LWR and FBR fuels. The result showed the superiority of the modularized-type concept over the independent-type concept, because the former can enhance the ability to supply Pu-fissile with less reprocessing capacity. Therefore, the reprocessing plant suitable for the transition period is that based on the modularized-type concept. (author)

  10. The transport of irradiated fuel. An activity closely related to reprocessing

    International Nuclear Information System (INIS)

    Lenail, B.; Curtis, H.W.

    1987-01-01

    With a proven reprocessing capacity of 400 tonnes of uranium per year and the rapid expansion of this capacity, the need to feed the reprocessing plants at La Hague has become vital to ensure continuous and economic reprocessing. The programming of transports by the reprocessor and transporter to ensure a constant supply of fuel for reprocessing has therefore become increasingly important. These transports use the public roads and the railway system and the reprocessor and transporter must cooperate in maintaining the highest possible standards of safety. Safety must take priority over all other factors, including the economics of the operation

  11. Consolidated fuel reprocessing program. Progress report, January 1-March 31, 1981

    International Nuclear Information System (INIS)

    1981-06-01

    Progress and activities are reported on process development, laboratory R and D, engineering research, engineering systems, Integrated Equipment Test (IET) facility operations, and HTGR fuel reprocessing

  12. Quantitative analysis of residual protein contamination of podiatry instruments reprocessed through local and central decontamination units

    Directory of Open Access Journals (Sweden)

    Ramage Gordon

    2011-01-01

    Full Text Available Abstract Background The cleaning stage of the instrument decontamination process has come under increased scrutiny due to the increasing complexity of surgical instruments and the adverse affects of residual protein contamination on surgical instruments. Instruments used in the podiatry field have a complex surface topography and are exposed to a wide range of biological contamination. Currently, podiatry instruments are reprocessed locally within surgeries while national strategies are favouring a move toward reprocessing in central facilities. The aim of this study was to determine the efficacy of local and central reprocessing on podiatry instruments by measuring residual protein contamination of instruments reprocessed by both methods. Methods The residual protein of 189 instruments reprocessed centrally and 189 instruments reprocessed locally was determined using a fluorescent assay based on the reaction of proteins with o-phthaldialdehyde/sodium 2-mercaptoethanesulfonate. Results Residual protein was detected on 72% (n = 136 of instruments reprocessed centrally and 90% (n = 170 of instruments reprocessed locally. Significantly less protein (p Conclusions Overall, the results show the superiority of central reprocessing for complex podiatry instruments when protein contamination is considered, though no significant difference was found in residual protein between local decontamination unit and central decontamination unit processes for Blacks files. Further research is needed to undertake qualitative identification of protein contamination to identify any cross contamination risks and a standard for acceptable residual protein contamination applicable to different instruments and specialities should be considered as a matter of urgency.

  13. Consolidated fuel reprocessing program. Progress report, January 1-March 31, 1981

    Energy Technology Data Exchange (ETDEWEB)

    1981-06-01

    Progress and activities are reported on process development, laboratory R and D, engineering research, engineering systems, Integrated Equipment Test (IET) facility operations, and HTGR fuel reprocessing. (DLC)

  14. Robustness of advanced nuclear fuel reprocessing processes. Study on solvent extraction processes adjusted to advanced reprocessing process. Document on collaborative study

    International Nuclear Information System (INIS)

    Yamamoto, Ichiro; Enokida, Youichi; Kobayashi, Noboru; Takanashi, Mitsuhiro; Aoshima, Atsushi; Nomura, Kazunori; Shibata, Atsuhiro

    2002-05-01

    The advanced nuclear fuel reprocessing process with crystallization uranium recovery has been proposed to enhance economical incentive and to reduce amount of discharged waste. Because a solvent extraction process following the crystallization uranium recovery will be operated with new process parameters due to different parameters of loading of heavy metals, decontamination factors, flow rates etc, fundamental studies on chemical flowsheet of the process are required to verify robustness of the process and to understand influence of process variation upon process performance. In this study, theoretical and computational studies were performed from this kind of aspect. Firstly, separation characteristics with the chemical flowsheet were studied for the steady-state, and recovery yields of uranium and plutonium, decontamination factor, process waste amount were computated for the normal process condition. Secondary, transient behaviors were computated with some variations in flow rates, heavy metal loading and so on from the normal process condition. Finally, influence of small fluctuation of the process condition was analyzed and the robustness of the new solvent extraction process was verified. This work was performed by Nagoya University and Japan Nuclear Cycle Development Institute under the JNC Cooperative Research Scheme on the Nuclear Fuel Cycle. (author)

  15. CAD system applications to the nuclear fuel reprocessing facilities

    International Nuclear Information System (INIS)

    Morita, Eiji; Matsumoto, Tadakuni; Shikakura, Sakae; Furuya, Kousei; Sakurai, Shin-ichi.

    1994-01-01

    Effective supporting techniques of design, operation, and maintenance of the reprocessing facility have been developed using the Intergraph CAD system. Two and three dimensional views of the process cells were utilized to rationalize the equipment layout and material handling flows, and to check the piping interference. Interferences of the remote maintenance equipment with the process equipments were also evaluated by the pictures on the CAD display. The newest virtual reality technology will help our future development of the more natural simulation for the remote maintenance operator training. (author)

  16. Outline of material accountancy system for Rokkasho reprocessing plant

    International Nuclear Information System (INIS)

    Kitamura, Touko; Yamazaki Yoshihiro; Ai, Hironobu

    2004-01-01

    In January 2004, Facility Attachment (FA) for Rokkasho Reprocessing Plant (RRP) was entered into force and the safeguards has been implemented in accordance with the FA. So operator must carry out the effectual material accountancy on the basis of facility operation. RRP is large and complex facility and operated based on automatic and remote system. For efficient material accounting viewpoint, the system especially automatic data collection is established using RRP computer network. The paper describes the outline of material accountancy system, the structure of RRP computer network including how to collect the source data, to convert the batch data and the reporting. (author)

  17. Reprocessing in France. Some aspects of process chemistry

    International Nuclear Information System (INIS)

    Chesne, A.; Sauteron, J.

    1986-10-01

    Like any young industry, reprocessing has, from the outset, been the focus of successive improvements to raise it to a satisfactory level of reliability, both in process design and implementation. This paper deals with the chemistry aspect of the process. The subject is obviously too vast to make a complete review, in the time allowed, of process development in French plants and of the research work conducted for improvements. We shall therefore discuss the main guidelines and the development trends, illustrating them with a number of examples

  18. Materials management in an internationally safeguarded fuels reprocessing plant

    International Nuclear Information System (INIS)

    Hakkila, E.A.; Baker, A.L.; Cobb, D.D.

    1980-04-01

    The following appendices are included: aqueous reprocessing and conversion technology, reference facilities, process design and operating features relevant to materials accounting, operator's safeguards system structure, design principles of dynamic materials accounting systems, modeling and simulation approach, optimization of measurement control, aspects of international verification problem, security and reliability of materials measurement and accounting system, estimation of in-process inventory in solvent-extraction contactors, conventional measurement techniques, near-real-time measurement techniques, isotopic correlation techniques, instrumentation available to IAEA inspectors, and integration of materials accounting and containment and surveillance

  19. Materials management in an internationally safeguarded fuels reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Hakkila, E.A.; Baker, A.L.; Cobb, D.D.

    1980-04-01

    The following appendices are included: aqueous reprocessing and conversion technology, reference facilities, process design and operating features relevant to materials accounting, operator's safeguards system structure, design principles of dynamic materials accounting systems, modeling and simulation approach, optimization of measurement control, aspects of international verification problem, security and reliability of materials measurement and accounting system, estimation of in-process inventory in solvent-extraction contactors, conventional measurement techniques, near-real-time measurement techniques, isotopic correlation techniques, instrumentation available to IAEA inspectors, and integration of materials accounting and containment and surveillance. (DLC)

  20. 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.)

  1. The reprocessing pilot plant at Marcoule: the TOR project

    International Nuclear Information System (INIS)

    Sauteron, Jean; Calame-Longjean, Andre

    1987-01-01

    The irradiated fuel reprocessing pilot plant has recently been renovated and enlarged by the structures of the TOR project (traitement d'oxydes rapides). A new building to house the head end of the process and packaging the corresponding wastes has been built. The general principles underlying this new TOR head end and the guidelines for the telemanipulation functions are given. The processing is shown in a schematic layout. At TOR there has been considerable research and development of mechanics and telemanipulation equipment and of the chemical processing required. This development is described. (UK)

  2. Extending Spent Fuel Storage until Transport for Reprocessing or Disposal

    Energy Technology Data Exchange (ETDEWEB)

    Carlsen, Brett; Chiguer, Mustapha; Grahn, Per; Sampson, Michele; Wolff, Dietmar; Bevilaqua, Arturo; Wasinger, Karl; Saegusa, Toshiari; Seelev, Igor

    2016-09-01

    Spent fuel (SF) must be stored until an end point such as reprocessing or geologic disposal is imple-mented. Selection and implementation of an end point for SF depends upon future funding, legisla-tion, licensing and other factors that cannot be predicted with certainty. Past presumptions related to the availability of an end point have often been wrong and resulted in missed opportunities for properly informing spent fuel management policies and strategies. For example, dry cask storage systems were originally conceived to free up needed space in reactor spent fuel pools and also to provide SFS of up to 20 years until reprocessing and/or deep geological disposal became available. Hundreds of dry cask storage systems are now employed throughout the world and will be relied upon well beyond the originally envisioned design life. Given present and projected rates for the use of nuclear power coupled with projections for SF repro-cessing and disposal capacities, one concludes that SF storage will be prolonged, potentially for several decades. The US Nuclear Regulatory Commission has recently considered 300 years of storage to be appropriate for the characterization and prediction of ageing effects and ageing management issues associated with extending SF storage and subsequent transport. This paper encourages addressing the uncertainty associated with the duration of SF storage by de-sign – rather than by default. It suggests ways that this uncertainty may be considered in design, li-censing, policy, and strategy decisions and proposes a framework for safely extending spent fuel storage until SF can be transported for reprocessing or disposal – regardless of how long that may be. The paper however is not intended to either encourage or facilitate needlessly extending spent fuel storage durations. Its intent is to ensure a design and safety basis with sufficient margin to accommodate the full range of potential future scenarios. Although the focus is primarily on

  3. Will the world SNF be reprocessed in Russia?

    International Nuclear Information System (INIS)

    Gagarinski, A.

    2000-01-01

    Russia's possibilities in nuclear fuel reprocessing are well known. RT-1 plant with 400 tons/year in the Chelyabinsk region can provide reprocessing of fuel from Russian and Central European WWER-440 reactors, as well as from transport and research reactors. Former military complex Krasnoyarsk-26 with unique underground installations situated in rock galleries, already has an aqueous facility for storage of 6000 tons of spent nuclear fuel (SNF), half-built plant RT-2 for nuclear fuel reprocessing with 1500 tons/year capacity, as well as the projects of dry storage facility for 30000 tons of SNF and of MOX fuel production plant. Russian nuclear specialists understand well, that the economic efficiency of nuclear fuel reprocessing industry is shown only in case of large-scale production, which would require consolidation of the countries, which develop nuclear energy. They also understand, that Russia has all the possibilities to become one of the centers of such a consolidation and to use these possibilities for the benefit of the country. The idea of foreign nuclear fuel reprocessing (for a long time realized for East and Central European countries, which operate Soviet-design reactors) has existed in the specialists' minds, and sometimes has appeared in the mass media. On the other hand, rehabilitation of territories of nuclear fuel cycle enterprises in Russia continues, including the Karachai lake, which contains 120 million Curie of radioactivity. Unfortunately, Russia simply has no money for complete solution of the problems of radiation military legacy. During discussion of the budget for 2000, the Russian Minatom has made a daring step. A real program, how to find money needed for solving the 'radiation legacy' problem, was proposed. With this purpose, it was proposed to permit storage and further reprocessing of other countries' SNF on Russian territory. It is well known, that another countries' SNF is accepted for reprocessing by UK and France, and Russia

  4. Eye movement desensitization and reprocessing: a conceptual framework.

    Science.gov (United States)

    Menon, Sukanya B; Jayan, C

    2010-07-01

    Eye movement desensitization and reprocessing (EMDR) is a method which was initially used for the treatment of post-traumatic stress disorder. But it is now being used in different therapeutic situations. EMDR is an eight-phase treatment method. History taking, client preparation, assessment, desensitization, installation, body scan, closure and reevaluation of treatment effect are the eight phases of this treatment which are briefly described. A case report is also depicted which indicates the efficacy of EMDR. The areas where EMDR is used and the possible ways through which it is working are also described.

  5. Sexual violence: psychiatric healing with eye movement reprocessing and desensitization.

    Science.gov (United States)

    Posmontier, Bobbie; Dovydaitis, Tiffany; Lipman, Kenneth

    2010-08-01

    Sexual violence, which affects one in three women worldwide, can result in significant psychiatric morbidity and suicide. Eye movement desensitization and reprocessing (EMDR) offers health care providers the option of a brief psychiatric intervention that can result in psychiatric healing in as few as four sessions. Because health care providers often hear stories of sexual violence from their patients, they are in an ideal position to make recommendations for treatment. The purpose of this article is to introduce health care providers to the technique of EMDR, review safety and appropriateness, and discuss clinical and research implications.

  6. Sleep, learning, and dreams: off-line memory reprocessing.

    Science.gov (United States)

    Stickgold, R; Hobson, J A; Fosse, R; Fosse, M

    2001-11-02

    Converging evidence and new research methodologies from across the neurosciences permit the neuroscientific study of the role of sleep in off-line memory reprocessing, as well as the nature and function of dreaming. Evidence supports a role for sleep in the consolidation of an array of learning and memory tasks. In addition, new methodologies allow the experimental manipulation of dream content at sleep onset, permitting an objective and scientific study of this dream formation and a renewed search for the possible functions of dreaming and the biological processes subserving it.

  7. The reprocessing of fast reactor fuels - the TOR project

    International Nuclear Information System (INIS)

    Calame-Longjean, A.; Le Bouhellec, J.; Schwob, Y.

    1982-01-01

    A description is given of development work on the proposed new French facility for the reprocessing of fast reactor fuel. This is the TOR facility (Traitement des Oxydes Rapides). Block diagrams give details of the TOR project as a whole and of the main line and R and D line of the TOR 1 facility which is a new works devoted to the head of the process. Modifications to existing plant which will form the TOR 2 and TOR 3 facilities are also described. (U.K.)

  8. Plan for the civil reprocessing pilot plant of China

    International Nuclear Information System (INIS)

    Wang, D.Y.; Chen, M.

    1987-01-01

    Based on the R and D work, experience on plant operation and site situation, the necessity and feasibility of building a pilot plant for civil reprocessing in China are discussed. The capacity of 100 kg HM/day (LWR) and 3 kg HM/day (MTR) has been proposed. The plant consists of cold testing facility and hot pilot facility. It is expected to complete the pilot plant in 1990's. This paper also describes the purpose, scale, process and equipment of the pilot plant

  9. A separator

    Energy Technology Data Exchange (ETDEWEB)

    Prokopyuk, S.G.; Dyachenko, A.Ye.; Mukhametov, M.N.; Prokopov, O.I.

    1982-01-01

    A separator is proposed which contains separating slanted plates and baffle plates installed at a distance to them at an acute angle to them. To increase the effectiveness of separating a gas and liquid stream and the throughput through reducing the secondary carry away of the liquid drops and to reduce the hydraulic resistance, as well, openings are made in the plates. The horizontal projections of each opening from the lower and upper surfaces of the plate do not overlap each other.

  10. Improvements and experience in the analysis of reprocessing samples

    International Nuclear Information System (INIS)

    Koch, L.; Cricchio, A.; Meester, R. de; Romkowski, M.; Wilhelmi, M.; Arenz, H.J.; Stijl, E. van der; Baeckmann, A. von

    1976-01-01

    Improvements in the analysis of input samples for reprocessing were obtained. To cope with the decomposition of reprocessing input solutions owling to the high radioactivity, an aluminium capsule technique was developed. A known amount of the dissolver solution was weighed into an aluminium can, dried, and the capsule was sealed. In this form, the sample could be stored over a long period and could be redissolved later for the analysis. The isotope correlation technique offers an attractive alternative for measuring the plutonium isotopic content in the dissolver solution. Moreover, this technique allows for consistency checks of analytical results. For this purpose, a data bank of correlated isotopic data is in use. To improve the efficiency of analytical work, four automatic instruments have been developed. The conditioning of samples for the U-Pu isotopic measurement was achieved by an automatic ion exchanger. A mass spectrometer, to which a high vacuum lock is connected, allows the automatic measurement of U-Pu samples. A process-computer controls the heating, focusing and scanning processes during the measurement and evaluates the data. To ease the data handling, alpha-spectrometry as well as a balance have been automated. (author)

  11. Spent fuel management in France: Reprocessing, conditioning, recycling

    International Nuclear Information System (INIS)

    Giraud, J.P.; Montalembert, J.A. de

    1994-01-01

    The French energy policy has been based for 20 years on the development of nuclear power. The some 75% share of nuclear in the total electricity generation, representing an annual production of 317 TWh requires full fuel cycle control from the head-end to the waste management. This paper presents the RCR concept (Reprocessing, Conditioning, Recycling) with its industrial implementation. The long lasting experience acquired in reprocessing and MOX fuel fabrication leads to a comprehensive industrial organization with minimized impact on the environment and waste generation. Each 900 MWe PWR loaded with MOX fuel avoids piling up 2,500 m 3 per year of mine tailings. By the year 2000, less than 500 m 3 of high-level and long-lived waste will be annually produced at La Hague for the French program. The fuel cycle facilities and the associated MOX loading programs are ramping-up according to schedule. Thus, the RCR concept is a reality as well as a policy adopted in several countries. Last but not least, RCR represents a strong commitment to non-proliferation as it is the way to fully control and master the plutonium inventory

  12. Decontamination and remote dismantling tests in the Itrec reprocessing plant

    International Nuclear Information System (INIS)

    Candelieri, T.; Gerardi, A.; Soffietto, G.

    1993-01-01

    The scope of this research is to evaluate the advantages of the rack removal system in the dismantling of reprocessing installations. The objective of this work is to verify experimentally the possibility of the decontamination of any particular module and the capability of the remote dismantling of components installed in the mobile rack. In particular, the main objective is to develop remotely operated equipment for the dismantling of centrifugal contactors. The decontamination of the equipment which represents the most important preliminary phase of the decommissioning operation, allowed to obtain low-level radioactivity. A supporting programme has been performed in order to collect sufficient data for the project and design of the remote dismantling machine. On the basis of technological cold test results, the project of the dismantling machine's construction has been optimized. Positive results obtained during the hot dismantling operations on the Rack 6 bis attested the effectiveness of the rack removal system as an original design which facilitates decommissioning of reprocessing plants. 2 tabs., 18 figs

  13. IAEA verification of materials accounting in commercial reprocessing plants

    International Nuclear Information System (INIS)

    Gutmacher, R.G.; Hakkila, E.A.

    1987-01-01

    The reprocessing plants currently under International Atomic Energy Agency (IAEA) safeguards have design capacities up to 210 tonnes of heavy metal per year. All of the plants use conventional materials accounting for safeguards. However, several larger commercial reprocessing plants are being designed with capacities of 350 to 1200 tonnes of heavy metal per year. It is likely that many of these plants, as well as some of the existing smaller ones, will adopt near-real-time materials accounting. The major effect of the combination of larger plants and near-real-time accounting on IAEA safeguards will be the demand for greater timeliness of verification. Continuous inspector presence may be required, as well as more on-site measurements by the inspector. In this paper, the authors review what needs to be verified, as well as current inspector activities in the process area. The bulk of the paper describes rapid, easy-to-use measurement techniques and instruments that may be applied to on-site verification measurements

  14. About possibility of uranium industry wastes reprocessing in Tajikistan

    International Nuclear Information System (INIS)

    Khakimov, N.; Barotov, B.B.; Mirsaidov, I.U.; Barotov, A.M; Akhmedov, M.Z.

    2012-01-01

    One of the main basic fields of economy in Tajikistan is mining industry. Its development in the past lead to accumulation of huge amount of wastes basically from uranium reprocessing enterprises, containing radionuclides in anthropogenic highly concentrations (basically uranium-thorium chain) and other harmful substances. They are located in zones very close to residential as well as in upper course of water inflow of such main rivers of the region as Amudarya and Syrdarya. Sulphates, heavy metals, cyanides and others (basically with water flow) released to the environment besides uranium reprocessing wastes and other mining enterprises. This makes it necessary to restore in the region the complex coordinated monitoring programs with the purpose of their actual assessment and potential impact on environment as well as priority justification of possible remediation measures. One of the important are balance assessment and trans-boundary radionuclide re-deposition of uranium-thorium chain and other toxic elements in Syrdarya and Amudarya rivers with the purpose of regional formation character revealing of radiation and other ecological risks for saving the normal vital activity in the region.

  15. Æstetiske læreprocesser som performative handlinger

    DEFF Research Database (Denmark)

    Illeris, Helene

    2009-01-01

      Med afsæt i en analyse af et samtidskunstværk undersøger artiklen nogle af de konsekvenser, forskellen mellem en repræsentativ og en performativ tilgang til begrebet form kan tænkes at have for begrebet 'æstetiske læreprocesser'. Teoretisk bygger artiklen på den amerikanske kønsforsker Judith...... Butlers teori om subjektet som performativt konstitueret, hvor 'identitet' ikke er noget på forhånd givet, men noget, der bliver til gennem performativitet, dvs. reproduktion af handlemønstre, relateret til eksisterende kulturelt og socialt bestemte 'identitetsmatricer'. Som en modsætning hertil bruger...... Butler betegnelsen performance om bevidst konstruerede og iscenesatte handlinger, der tager afsæt i identitetsmatricerne med henblik på at udforske, udfordre og evt. forandre dem. Butlers teori anvendes til problematisere gængse teorier om æstetiske læreprocesser,  som, ifølge forfatteren, har en ikke...

  16. The conditioned reprocessing waste returns. An overview of the question

    International Nuclear Information System (INIS)

    Donato, A.

    1987-01-01

    Although the spent nuclear fuel reprocessing is at present under careful reconsideration and analysis in several countries, the economics, the environmental and health protection aspects being taken into consideration by many experts, it is nevertheless currently carried out in Great Britain and in France as a commercial service offered to the domestic utilities an to foreign customers, according to the contracts and the agreements signed in the past. Such contracts have been signed with COGEMA and/or BNFL by seven countries: Germany, Sweden, Japan, Belgium, Switzerland, Italy, Holland. As a consequence of this, a big number of high level radioactive glass containers and of cemented and bituminized waste will be returned in order to be stored and disposed off in these European countries and in Japan. The disposal of the conditioned wastes will only be possible if their characteristics comply with the acceptance criteria established or to be established in each customer country. A brief review of the situation will be presented in this paper, particular attention being given to the problems possibly arising from the acceptance point of view of the different reprocessing waste categories

  17. Development of remote maintenance technology for nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    Kawahara, Akira; Saito, Masayuki; Kawamura, Hironobu; Yamade, Atsushi; Sugiyama, Sen; Sugiyama, Sakae.

    1986-01-01

    In the plants for reprocessing spent nuclear fuel containing fission products, due to the facts that the facilities are in high radiations fields, and the surfaces of equipments are contaminated with radioactive substances, the troubles of process equipments are directly connected to the remarkable drop of the rate of operation of the facilities. Therefore, the development of various remote maintenance techniques has been carried out so far, but this time, Hitachi Ltd. got a chance to take part in the repair of spent fuel dissolving tanks in the Tokai Reprocessing Plant of Power Reactor and Nuclear Fuel Development Corp. and the development of several kinds of remote checkup equipment related to the repair work. Especially in the repair of the dissolving tanks, a radiation-withstanding checkup and repair apparatus which has high remote operability taking the conditions of radioactive environment and the restriction of the repaired objects in consideration was required, and a dissolving tank repairing robot composed of six kinds has been developed. The key points of the development were the selective use of high radiation-withstanding parts and materials, small size structure and the realization of full remote operability. The full remote maintenance apparatus of this kind is unique in the world, and applicable to wide fields. (Kako, I.)

  18. Remote repair and inspection technics in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Koyama, Kenji; Ishibashi, Yuzo; Otani, Yosikuni

    1986-01-01

    Tokai reprocessing plant of Power Reactor and Nuclear Fuel Development Corp. is the only factory in Japan which treats 0.7 t/day of the spent fuel from LWR power stations and recovers remaining uranium and newly produced plutonium. Since the reprocessing plant started the hot test in September, 1977, about eight years have elapsed, and 233 t of spent fuel was treated as of August, 1985. During this period, the development of various remote working techniques have been carried out to cope with the failure of equipment and to strengthen the preventive maintenance of equipment. In this report, the development of the techniques for the remote repair of leaking dissolving tanks and the development of the remote inspection system for confirming the soundness of equipment in cells are described. In nuclear facilities, from the viewpoint of the reduction of radiation exposure accompanying the works under high radiation, labor saving, the increase of capacity factor by shortening the period of repair works, the improvement of safety and reliability of the facilities by perfecting checkup and inspection and so on, it is strongly desired to put robots in practical use for maintenance and inspection. (Kako, I.)

  19. Application of probabilistic safety assessment to Rokkasho reprocessing plant, (2)

    International Nuclear Information System (INIS)

    Miyata, Takashi; Takebe, Kazumi; Tamauchi, Yoshikazu

    2008-01-01

    A probabilistic safety assessment (PSA) is made on the boiling accident of a highly active liquid waste tank, which may result in significant consequences, in accordance with the procedure for PSA developed for nuclear power plants. Obtained as results are the frequency of boiling accident of a certain tank of 2.0x10 -8 /y (frequency of boiling accident of any tank of 4.1x10 0-8 /y), its error factor of approx. 6, and information on the relative risk importance based on the FV index and RAW for various components, systems and activities of personnel and on the sensitivity of key parameters. Furthermore, the effect of the time required for repairing failed instruments on the frequency of accident, how to deal with the common cause of failure of the duplicated dynamic components, one of which is at least in operation, and conservative exposure dose in the event of an accident are examined. The database for the Rokkasho reprocessing plant has not been established yet, but the PSA results utilizing available failure rate databases of existing nuclear power plants and reprocessing plants in Japan and abroad can be used effectively to optimize operations and maintenance, if they are interpreted properly and some uncertainties are taken into account. (author)

  20. Morphology of reprocessing: a case for regional utility planning

    International Nuclear Information System (INIS)

    Stoller, S.M.

    1976-01-01

    The change in entrepreneurial climate in reprocessing and recycle, which has taken place in the last few years, is reviewed. The climatic change, which has reached the point where the economic benefits of that fuel cycle segment are being questioned, is characterized. The author outlines the reasons he feels the benefits are positive. Some of the principal risks facing the entrepreneur are outlined and the suggestion is made that participation by the utility customers for a major project throughout its planning process is critical. In this context, the logic for a regional organization of such utilities, customers, drawing heavily from a study conducted by a group of utilities in the western United States during 1975, is outlined. The paper concludes with some general observations in support of the thesis that new structural forms are likely required for reprocessing facilities, as well as those for other major segments of the fuel cycle, if utilities are to be able to view with confidence the prospect of having such facilities in place in a timely fashion

  1. ELABORATION OF THE SUPERSTRUCTURE OF THE BULGARIAN HOTEL INDUSTRY

    Directory of Open Access Journals (Sweden)

    Tanya Dabeva

    2010-12-01

    Full Text Available The purpose of the paper is to suggest some terms of reference for the elaboration of the superstructure of the Bulgarian hotel industry. The suggestions are based on the analysis of the superstructure at present. Its capacity, main types of accommodation establishments and their distribution by categories and territory are examined. An analysis is made of some resulting indices such as overnight stays and average stay. The main positive, respectively negative features of the superstructure have been analyzed. Concrete terms of reference have been given in order to overcome the problems specified.

  2. Australian food life style segments and elaboration likelihood differences

    DEFF Research Database (Denmark)

    Brunsø, Karen; Reid, Mike

    As the global food marketing environment becomes more competitive, the international and comparative perspective of consumers' attitudes and behaviours becomes more important for both practitioners and academics. This research employs the Food-Related Life Style (FRL) instrument in Australia...... in order to 1) determine Australian Life Style Segments and compare these with their European counterparts, and to 2) explore differences in elaboration likelihood among the Australian segments, e.g. consumers' interest and motivation to perceive product related communication. The results provide new...

  3. Isotope separation

    International Nuclear Information System (INIS)

    Eerkens, J.W.

    1979-01-01

    A method of isotope separation is described which involves the use of a laser photon beam to selectively induce energy level transitions of an isotope molecule containing the isotope to be separated. The use of the technique for 235 U enrichment is demonstrated. (UK)

  4. A Green Approach to SNF Reprocessing: Are Common Household Reagents the Answer?

    International Nuclear Information System (INIS)

    Peper, Shane M.; McNamara, Bruce K.; O'Hara, Matthew J.; Douglas, Matthew

    2008-01-01

    It has been discovered that UO2, the principal component of spent nuclear fuel (SNF), can efficiently be dissolved at room temperature using a combination of common household reagents, namely hydrogen peroxide, baking soda, and ammonia. This rather serendipitous discovery opens up the possibility, for the first time, of considering a non-acidic process for recycling U from SNF. Albeit at the early stages of development, our unconventional dissolution approach possesses many attractive features that could make it a reality in the future. With dissolution byproducts of water and oxygen, our approach poses a minimal threat to the environment. Moreover, the use of common household reagents to afford actinide oxide dissolution suggests a certain degree of economic favorability. With the use of a ''closed'' digestion vessel as a reaction chamber, our approach has substantial versatility with the option of using either aqueous or gaseous reactant feeds or a combination of both. Our approach distinguishes itself from all existing reprocessing technologies in two important ways. First and foremost, it is an alkaline rather than an acidic process, using mild non-corrosive chemicals under ambient conditions to effect actinide separations. Secondly, it does not dissolve the entire SNF matrix, but rather selectively solubilizes U and other light actinides for subsequent separation, resulting in potentially faster head-end dissolution and fewer downstream separation steps. From a safeguards perspective, the use of oxidizing alkaline solutions to effect actinide separations also potentially offers a degree of inherent proliferation resistance, by allowing the U to be selectively removed from the remaining dissolver solution while keeping Pu grouped with the other minor actinides and fission products. This paper will describe the design and general experimental setup of a 'closed' digestion vessel for performing uranium oxide dissolutions under alkaline conditions using gaseous

  5. A Green Approach to SNF Reprocessing: Are Common Household Reagents the Answer?

    Energy Technology Data Exchange (ETDEWEB)

    Peper, Shane M.; McNamara, Bruce K.; O' Hara, Matthew J.; Douglas, Matthew

    2008-04-03

    It has been discovered that UO2, the principal component of spent nuclear fuel (SNF), can efficiently be dissolved at room temperature using a combination of common household reagents, namely hydrogen peroxide, baking soda, and ammonia. This rather serendipitous discovery opens up the possibility, for the first time, of considering a non-acidic process for recycling U from SNF. Albeit at the early stages of development, our unconventional dissolution approach possesses many attractive features that could make it a reality in the future. With dissolution byproducts of water and oxygen, our approach poses a minimal threat to the environment. Moreover, the use of common household reagents to afford actinide oxide dissolution suggests a certain degree of economic favorability. With the use of a “closed” digestion vessel as a reaction chamber, our approach has substantial versatility with the option of using either aqueous or gaseous reactant feeds or a combination of both. Our approach distinguishes itself from all existing reprocessing technologies in two important ways. First and foremost, it is an alkaline rather than an acidic process, using mild non-corrosive chemicals under ambient conditions to effect actinide separations. Secondly, it does not dissolve the entire SNF matrix, but rather selectively solubilizes U and other light actinides for subsequent separation, resulting in potentially faster head-end dissolution and fewer downstream separation steps. From a safeguards perspective, the use of oxidizing alkaline solutions to effect actinide separations also potentially offers a degree of inherent proliferation resistance, by allowing the U to be selectively removed from the remaining dissolver solution while keeping Pu grouped with the other minor actinides and fission products. This paper will describe the design and general experimental setup of a “closed” digestion vessel for performing uranium oxide dissolutions under alkaline conditions using

  6. Ecological risk of reprocessing of uranium wastes of the Gafurov-city's tailing pit

    International Nuclear Information System (INIS)

    Hakimov; Nazarov, H.M.; Mirsaidov, U.M.

    2005-01-01

    The authors set as their purpose the investigation of ecological risk of reprocessing of uranium wastes of the Gafurov-city's tailing pit. Having carried out their investigations, the authors came to the conclusion that the effect of radon gas during reprocessing to workers and specialists is minimal if they follow all the required safety rules

  7. Quantitative analysis of residual protein contamination of podiatry instruments reprocessed through local and central decontamination units

    Science.gov (United States)

    2011-01-01

    Background The cleaning stage of the instrument decontamination process has come under increased scrutiny due to the increasing complexity of surgical instruments and the adverse affects of residual protein contamination on surgical instruments. Instruments used in the podiatry field have a complex surface topography and are exposed to a wide range of biological contamination. Currently, podiatry instruments are reprocessed locally within surgeries while national strategies are favouring a move toward reprocessing in central facilities. The aim of this study was to determine the efficacy of local and central reprocessing on podiatry instruments by measuring residual protein contamination of instruments reprocessed by both methods. Methods The residual protein of 189 instruments reprocessed centrally and 189 instruments reprocessed locally was determined using a fluorescent assay based on the reaction of proteins with o-phthaldialdehyde/sodium 2-mercaptoethanesulfonate. Results Residual protein was detected on 72% (n = 136) of instruments reprocessed centrally and 90% (n = 170) of instruments reprocessed locally. Significantly less protein (p decontamination unit and central decontamination unit processes for Blacks files. Further research is needed to undertake qualitative identification of protein contamination to identify any cross contamination risks and a standard for acceptable residual protein contamination applicable to different instruments and specialities should be considered as a matter of urgency. PMID:21219613

  8. Consolidated fuel reprocessing. Program progress report, April 1-June 30, 1980

    Energy Technology Data Exchange (ETDEWEB)

    1980-09-01

    This progress report is compiled from major contributions from three programs: (1) the Advanced Fuel Recycle Program at ORNL; (2) the Converter Fuel Reprocessing Program at Savannah River Laboratory; and (3) the reprocessing components of the HTGR Fuel Recycle Program, primarily at General Atomic and ORNL. The coverage is generally overview in nature; experimental details and data are limited.

  9. Using Eye Movement Desensitization and Reprocessing To Enhance Treatment of Couples.

    Science.gov (United States)

    Protinsky, Howard; Sparks, Jennifer; Flemke, Kimberly

    2001-01-01

    Eye Movement Desensitization and Reprocessing (EMDR) as a clinical technique may enhance treatment effectiveness when applied in couple therapy that is emotionally and experientially oriented. Clinical experience indicates EMDR-based interventions are useful for accessing and reprocessing intense emotions in couple interactions. EMDR can amplify…

  10. Chemical process developments in reprocessing from 1965--1975 in the Institute for Hot Chemistry

    International Nuclear Information System (INIS)

    Baumgaertner, F.

    Work on the aqueous reprocessing of fuels is described. The following are discussed: LABEX (laboratory-scale extraction), MILLI facility (1 kg/day), problems of aqueous reprocessing, centrifugal extractor development, radiolytic products from Purex process, and TAMARA facility. Results of the MILLI operation are reviewed. Solutions to problems are discussed

  11. Quantitative analysis of residual protein contamination of podiatry instruments reprocessed through local and central decontamination units.

    Science.gov (United States)

    Smith, Gordon Wg; Goldie, Frank; Long, Steven; Lappin, David F; Ramage, Gordon; Smith, Andrew J

    2011-01-10

    The cleaning stage of the instrument decontamination process has come under increased scrutiny due to the increasing complexity of surgical instruments and the adverse affects of residual protein contamination on surgical instruments. Instruments used in the podiatry field have a complex surface topography and are exposed to a wide range of biological contamination. Currently, podiatry instruments are reprocessed locally within surgeries while national strategies are favouring a move toward reprocessing in central facilities. The aim of this study was to determine the efficacy of local and central reprocessing on podiatry instruments by measuring residual protein contamination of instruments reprocessed by both methods. The residual protein of 189 instruments reprocessed centrally and 189 instruments reprocessed locally was determined using a fluorescent assay based on the reaction of proteins with o-phthaldialdehyde/sodium 2-mercaptoethanesulfonate. Residual protein was detected on 72% (n = 136) of instruments reprocessed centrally and 90% (n = 170) of instruments reprocessed locally. Significantly less protein (p podiatry instruments when protein contamination is considered, though no significant difference was found in residual protein between local decontamination unit and central decontamination unit processes for Blacks files. Further research is needed to undertake qualitative identification of protein contamination to identify any cross contamination risks and a standard for acceptable residual protein contamination applicable to different instruments and specialities should be considered as a matter of urgency.

  12. CENTRIFUGAL SEPARATORS

    Science.gov (United States)

    Skarstrom, C.

    1959-03-10

    A centrifugal separator is described for separating gaseous mixtures where the temperature gradients both longitudinally and radially of the centrifuge may be controlled effectively to produce a maximum separation of the process gases flowing through. Tbe invention provides for the balancing of increases and decreases in temperature in various zones of the centrifuge chamber as the result of compression and expansions respectively, of process gases and may be employed effectively both to neutralize harmful temperature gradients and to utilize beneficial temperaturc gradients within the centrifuge.

  13. Separated Shoulder

    Science.gov (United States)

    ... ligaments that hold your collarbone (clavicle) to your shoulder blade. In a mild separated shoulder, the ligaments might ... the ligaments that hold your collarbone to your shoulder blade. Risk factors Participating in contact sports, such as ...

  14. Isotopic separation

    International Nuclear Information System (INIS)

    Chen, C.L.

    1979-01-01

    Isotopic species in an isotopic mixture including a first species having a first isotope and a second species having a second isotope are separated by selectively exciting the first species in preference to the second species and then reacting the selectively excited first species with an additional preselected radiation, an electron or another chemical species so as to form a product having a mass different from the original species and separating the product from the balance of the mixture in a centrifugal separating device such as centrifuge or aerodynamic nozzle. In the centrifuge the isotopic mixture is passed into a rotor where it is irradiated through a window. Heavier and lighter components can be withdrawn. The irradiated mixture experiences a large centrifugal force and is separated in a deflection area into lighter and heavier components. (UK)

  15. Isotopic separation

    International Nuclear Information System (INIS)

    Castle, P.M.

    1979-01-01

    This invention relates to molecular and atomic isotope separation and is particularly applicable to the separation of 235 U from other uranium isotopes including 238 U. In the method described a desired isotope is separated mechanically from an atomic or molecular beam formed from an isotope mixture utilising the isotropic recoil momenta resulting from selective excitation of the desired isotope species by radiation, followed by ionization or dissociation by radiation or electron attachment. By forming a matrix of UF 6 molecules in HBr molecules so as to collapse the V 3 vibrational mode of the UF 6 molecule the 235 UF 6 molecules are selectively excited to promote reduction of UF 6 molecules containing 235 U and facilitate separation. (UK)

  16. Defining the Costs of Reusable Flexible Ureteroscope Reprocessing Using Time-Driven Activity-Based Costing.

    Science.gov (United States)

    Isaacson, Dylan; Ahmad, Tessnim; Metzler, Ian; Tzou, David T; Taguchi, Kazumi; Usawachintachit, Manint; Zetumer, Samuel; Sherer, Benjamin; Stoller, Marshall; Chi, Thomas

    2017-10-01

    Careful decontamination and sterilization of reusable flexible ureteroscopes used in ureterorenoscopy cases prevent the spread of infectious pathogens to patients and technicians. However, inefficient reprocessing and unavailability of ureteroscopes sent out for repair can contribute to expensive operating room (OR) delays. Time-driven activity-based costing (TDABC) was applied to describe the time and costs involved in reprocessing. Direct observation and timing were performed for all steps in reprocessing of reusable flexible ureteroscopes following operative procedures. Estimated times needed for each step by which damaged ureteroscopes identified during reprocessing are sent for repair were characterized through interviews with purchasing analyst staff. Process maps were created for reprocessing and repair detailing individual step times and their variances. Cost data for labor and disposables used were applied to calculate per minute and average step costs. Ten ureteroscopes were followed through reprocessing. Process mapping for ureteroscope reprocessing averaged 229.0 ± 74.4 minutes, whereas sending a ureteroscope for repair required an estimated 143 minutes per repair. Most steps demonstrated low variance between timed observations. Ureteroscope drying was the longest and highest variance step at 126.5 ± 55.7 minutes and was highly dependent on manual air flushing through the ureteroscope working channel and ureteroscope positioning in the drying cabinet. Total costs for reprocessing totaled $96.13 per episode, including the cost of labor and disposable items. Utilizing TDABC delineates the full spectrum of costs associated with ureteroscope reprocessing and identifies areas for process improvement to drive value-based care. At our institution, ureteroscope drying was one clearly identified target area. Implementing training in ureteroscope drying technique could save up to 2 hours per reprocessing event, potentially preventing expensive OR delays.

  17. Deep-Elaborative Learning of Introductory Management Accounting for Business Students

    Science.gov (United States)

    Choo, Freddie; Tan, Kim B.

    2005-01-01

    Research by Choo and Tan (1990; 1995) suggests that accounting students, who engage in deep-elaborative learning, have a better understanding of the course materials. The purposes of this paper are: (1) to describe a deep-elaborative instructional approach (hereafter DEIA) that promotes deep-elaborative learning of introductory management…

  18. Separations chemistry

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    Results of studies on the photochemistry of aqueous Pu solutions and the stability of iodine in liquid and gaseous CO 2 are reported. Progress is reported in studies on: the preparation of macroporous bodies filled with oxides and sulfides to be used as adsorbents; the beneficiation of photographic wastes; the anion exchange adsorption of transition elements from thiosulfate solutions; advanced filtration applications of energy significance; high-resolution separations; and, the examination of the separation agents, octylphenylphosphoric acid (OPPA) and trihexyl phosphate (THP)

  19. Product separator

    International Nuclear Information System (INIS)

    Welsh, R.A.; Deurbrouck, A.W.

    1976-01-01

    A description is given of a secondary light sensitive photoelectric product separator for use with a primary product separator that concentrates a material so that it is visually distinguishable from adjacent materials. The concentrate separation is accomplished first by feeding the material onto a vibratory inclined surface with a liquid flow, such as a wet concentrating table. Vibrations generally perpendicular to the stream direction of flow cause the concentrate to separate from its mixture according to its color. When the concentrate and its surrounding stream reach the recovery end of the table, a detecting device notes the line of color demarcation and triggers a signal if it differs from a normal condition. If no difference is noted, nothing moves on the second separator. However, if a difference is detected in the constant monitoring of the color line's location, a product splitter and recovery unit normally positioned near the color line at the recovery end, moves to a new position. In this manner the selected separated concentrate is recovered at a maximum rate regardless of variations in the flow stream or other conditions present

  20. Kr/Xe Separation over a Chabazite Zeolite Membrane

    Energy Technology Data Exchange (ETDEWEB)

    Feng, Xuhui; Zong, Zhaowang; Elsaidi, Sameh K.; Jasinski, Jacek B.; Krishna, Rajamani; Thallapally, Praveen K.; Carreon, Moises A.

    2016-08-10

    Cryogenic distillation, the current conventional technology to separate Krypton and Xenon from air, and from nuclear reprocessing technologies, is an energy-intensive and expensive process. Membrane technology could potentially make this challenging industrial separation less energy intensive and economically viable. We demonstrate that chabazite zeolite SAPO-34 membranes effectively separated Kr/Xe gas mixtures at industrially relevant compositions. Control over membrane thickness and average crystal size led to industrial range permeances and high separation selectivities. Specifically, SAPO-34 membranes can separate Kr/Xe mixtures with Kr permeances as high as 361.4 GPU and separation selectivities of 34.8 for molar compositions close to typical concentrations of these two gases in air. In addition, SAPO-34 membranes separated Kr/Xe mixtures with Kr permeances as high as 525.7 GPU and separation selectivities up to 45.1 for molar compositions as might be encountered in nuclear reprocessing technologies. Molecular sieving and differences in diffusivities were identified as the dominant separation mechanisms.

  1. Elaboration over a discourse facilitates retrieval in sentence processing

    Directory of Open Access Journals (Sweden)

    Melissa eTroyer

    2016-03-01

    Full Text Available Language comprehension requires access to stored knowledge and the ability to combine knowledge in new, meaningful ways. Previous work has shown that processing linguistically more complex expressions (‘Texas cattle rancher’ vs. ‘rancher’ leads to slow-downs in reading during initial processing, possibly reflecting effort in combining information. Conversely, when this information must subsequently be retrieved (as in filler-gap constructions, processing is facilitated for more complex expressions, possibly because more semantic cues are available during retrieval. To follow up on this hypothesis, we tested whether information distributed across a short discourse can similarly provide effective cues for retrieval. Participants read texts introducing two referents (e.g., two senators, one of whom was described in greater detail than the other (e.g., ‘The Democrat had voted for one of the senators, and the Republican had voted for the other, a man from Ohio who was running for president’. The final sentence (e.g., ‘The senator who the {Republican / Democrat} had voted for…’ contained a relative clause picking out either the Many-Cue referent (with ‘Republican’ or the One-Cue referent (with ‘Democrat’. We predicted facilitated retrieval (faster reading times for the Many-Cue condition at the verb region (‘had voted for’, where readers could understand that ‘The senator’ is the object of the verb. As predicted, this pattern was observed at the retrieval region and continued throughout the rest of the sentence. Participants also completed the Author/Magazine Recognition Tests (ART/MRT; Stanovich & West, 1989, providing a proxy for world knowledge. Since higher ART/MRT scores may index (a greater experience accessing relevant knowledge and/or (b richer/more highly-structured representations in semantic memory, we predicted it would be positively associated with effects of elaboration on retrieval. We did not observe

  2. Total data management in the La Hague reprocessing plant

    International Nuclear Information System (INIS)

    Berthion, Y.; Perot, J.P.; Silie, P.

    1993-01-01

    Due to the complexity of a spent fuel reprocessing plant and its nuclear characteristics, the operators must have real-time access to updated information on many subjects. To meet these requirements effectively, Cogema has installed a number of diversified data processing systems linked by a communications network called Haguenet. The whole system forms the La Hague Total Data Management System (TDMS) which performs a full range of functions, namely production data management, maintenance data management, technical documentation and miscellaneous. Some examples of the main process data management applications implemented within the La Hague TDMS are briefly described (nuclear materials and waste follow-up, analytical data management, operating procedures management and site inspection management). Also presented are some examples of the maintenance-related systems implemented within the La Hague TDMS (diagnostic assistance system, software maintenance center, maintenance interventions demand and spare parts data management). (Z.S.)

  3. Microbial transformations of radionuclides released from nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    Francis, A.J.

    2007-01-01

    Microorganisms can affect the stability and mobility of the actinides U, Pu, Cm, Am, Np, and the fission products Tc, I, Cs, Sr, released from nuclear fuel reprocessing plants. Under appropriate conditions, microorganisms can alter the chemical speciation, solubility and sorption properties and thus could increase or decrease the concentrations of radionuclides in solution and the bioavailability. Dissolution or immobilization of radionuclides is brought about by direct enzymatic action or indirect non-enzymatic action of microorganisms. Although the physical, chemical, and geochemical processes affecting dissolution, precipitation, and mobilization of radionuclides have been investigated, we have only limited information on the effects of microbial processes. The mechanisms of microbial transformations of the major and minor actinides and the fission products under aerobic and anaerobic conditions in the presence of electron donors and acceptors are reviewed. (author)

  4. Safety demonstration test on solvent fire in fuel reprocessing plant

    International Nuclear Information System (INIS)

    Nishio, Gunji; Hashimoto, Kazuichiro

    1989-03-01

    This report summarizes a fundamental of results obtained in the Reprocessing Plant Safety Demonstration Test Program which was performed under the contract between the Science and Technology Agency of Japan and the Japan Atomic Energy Research Institute. In this test program, a solvent fire was hypothesized, and such data were obtained as fire behavior, smoke behavior and integrity of exhaust filters in the ventilation system. Through the test results, it was confirmed that under the fire condition in hypothetical accident, the integrity of the cell and the cell ventilation system were maintained, and the safety function of the exhaust filters was maintained against the smoke loading. Analytical results by EVENT code agreed well with the present test data on the thermofluid flow in a cell ventilation system. (author)

  5. On-line control of nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Parus, I.; Kierzek, J.; Zoltowski, T.

    1977-01-01

    The development trends in the field of chemical processes control and the present state of the development of continuous composition analysers has been described. On this background the peculiarities of on-line control methods for spent nuclear fuel reprocessing have been discussed. The measuring methods for direct and indirect determination of chemical composition and nuclear safety are reviewed in detail. The review comprises such methods as: measurement of α, γ and neutron radiation emitted both by nuclides present in technological solutions and using external sources of different radiation, X-ray fluorescence, measurements of physicochemical parameters connected with the composition (pH, density, electrical conductivity), polarography and spectrophotometry. At the end of this review some new trends in process control based on dynamic process models have been presented. (author)

  6. The reprocessing plant as a problem of international law

    International Nuclear Information System (INIS)

    Guendling, L.

    1987-01-01

    The planned construction of the reprocessing plant creates problems with regard to transfrontier environmental protection, due to the potential hazards involved, and these problems institute obligations of the Federal Republic of Germany under contractual law and under customary international law. Particularly under customary international neighbour law the F.R.G. is obliged to prevent and abstain from transfrontier activities entailing environmental effects with considerable damaging potential in the neighbouring states, which also includes the duty of providing for protection against accidents. It is, however, a clear fact that the states decided the peaceful uses of atomic energy to be admissible, and accept the risk of possible catastrophic damage. The interpretation of existing international laws has to take this fact into account. (orig./HSCH) [de

  7. The trapping of iodine in spent fuel reprocessing plants

    International Nuclear Information System (INIS)

    Hamon, D.

    1988-01-01

    The study shows the interest of using catalyst supports impregnated with silver nitrate instead of zeolites exchanged with silver. AC.1620 which is an amorphous silica impregnated with silver nitrate (12 wt % of Ag) is especially studied. This material is experimented for qualification in next French reprocessing plants. Main characteristics are determined (grain size distribution, porosity, density pore diameter, specific area, Ag distribution). A simple method is developed for silver content determination. Influence of various parameters on methyl iodide decontamination factor is examined: temperature, material size, NO content in the gas, ratio NO 2 /NO, aging, iodine content and gas velocity. Trapping by physisorption and isotopic exchange on the iodine saturated product is evidenced. Regeneration of the N0 degraded material is investigated [fr

  8. MICROBIAL TRANSFORMATIONS OF RADIONUCLIDES RELEASED FROM NUCLEAR FUEL REPROCESSING PLANTS.

    Energy Technology Data Exchange (ETDEWEB)

    FRANCIS,A.J.

    2006-10-18

    Microorganisms can affect the stability and mobility of the actinides U, Pu, Cm, Am, Np, and the fission products Tc, I, Cs, Sr, released from nuclear fuel reprocessing plants. Under appropriate conditions, microorganisms can alter the chemical speciation, solubility and sorption properties and thus could increase or decrease the concentrations of radionuclides in solution and the bioavailability. Dissolution or immobilization of radionuclides is brought about by direct enzymatic action or indirect non-enzymatic action of microorganisms. Although the physical, chemical, and geochemical processes affecting dissolution, precipitation, and mobilization of radionuclides have been investigated, we have only limited information on the effects of microbial processes. The mechanisms of microbial transformations of the major and minor actinides and the fission products under aerobic and anaerobic conditions in the presence of electron donors and acceptors are reviewed.

  9. The use of spectrophotometry in FBR reprocessing analysis

    International Nuclear Information System (INIS)

    Brown, M.L.; Mills, C.L.; Kyffin, T.W.

    1986-09-01

    The spectrophotometric methods of analysis currently in use at DNPDE are described. It considers the ways in which the problems of containment and physical handling of active solutions have been overcome, and summarises performance of the methods during several PFR fuel reprocessing campaigns. The introduction of a new micro-computer controlled fibre-optic spectrophotometer is considered in terms of its advantages over the existing systems, both in safe sample handling and computational abilities. Its performance is compared with existing methods. Finally, a novel system for measurement of plutonium valency, and americium in plutonium using a ''spectral stripping'' technique, is discussed. The results of this method are compared with those obtained using conventional techniques. (author)

  10. Dynamic response of high speed centrifuge for reprocessing plant

    International Nuclear Information System (INIS)

    Rajput, Gaurav; Satish Kumar, V.; Selvaraj, T.; Ananda Rao, S.M.; Ravisankar, A.

    2012-01-01

    The standard for balancing the rotating bowl describes only the details about the selection of balance quality grade and the permissible residual unbalance for different operating speeds. This paper presents the effects of unbalance on the rotating bowl of high speed centrifuge used in reprocessing of spent nuclear fuel. In this study, the residual unbalance is evaluated for different recommended balancing grades in accordance with the ISO 1940. This unbalance mass generates dynamic force which acts on the rotor. The dynamic response of the rotor like displacements and stresses under this dynamic force are studied by numerical simulation. Finally, the effect of residual unbalance on the rotating bowl performance for different balancing grades is discussed. The experimental measurements are also carried out for the case of G 1.0 grade balanced rotating bowl to validate the resonance frequency as well as vibration amplitudes. (author)

  11. Thermochemical test of solvent in nuclear fuel reprocessing plants

    Energy Technology Data Exchange (ETDEWEB)

    Nishio, Gunju; Koike, Tadao; Takada, Junichi; Watanabe, Kouzou [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Miyata, Sadajirou

    1995-03-01

    In a Russian reprocessing plant in Tomsk, an explosive event occurred on April 6, 1993 due to pressurization of a tank containing uranyl nitrate solution by a rapid thermal decomposition of solvent with nitric acid. This event shows a singular reaction behavior that a large amount of heat is evolved under a boiling point (121degC) of nitric acid solution, even though a valve at the exhaust pipe of tank is reported to be opened. Accumulation of unstable decomposition materials is inferred in the tank due to a degradation of solvent caused by reactions with nitric acid. The chemical analysis of the degraded solvent was performed and chemical forms of these decomposition materials were identified. Also, the reaction heat of these materials was measured by a differential thermal analyzer (DTA) and a differential scanning calorimeter (DSC). (author).

  12. 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

  13. Qualitative simulation for supervision of a nuclear reprocessing plant

    International Nuclear Information System (INIS)

    Leyval, L.; Ledoux, A.

    1991-01-01

    This paper deals with the first application of a supervision support system to a part of a nuclear reprocessing plant. The system is called DIAPASON; its role is to help the operators to understand the behaviour of the process, and to diagnose failures if needed. This paper is only concerned with the simulation of the behaviour of the process and the associated explanations provided by DIAPASON during the normal operation periods. The modeling, simulation techniques are presented, when applied to a nuclear process. A causal graph linking the relevant variables by Qualitative Transfer Functions models the process behaviour. The simulation consists in propagating through the entire graph the significant events detected on the input variables or on measurable disturbances of the process. As a result, the evolutions of all the other variables are obtained. The explanations that can be provided at the present time are deduced from the simulation

  14. Safeguarding of large scale reprocessing and MOX plants

    International Nuclear Information System (INIS)

    Howsley, R.; Burrows, B.; Longevialle, H. de; Kuroi, H.; Izumi, A.

    1997-01-01

    In May 97, the IAEA Board of Governors approved the final measures of the ''93+2'' safeguards strengthening programme, thus improving the international non-proliferation regime by enhancing the effectiveness and efficiency of safeguards verification. These enhancements are not however, a revolution in current practices, but rather an important step in the continuous evolution of the safeguards system. The principles embodied in 93+2, for broader access to information and increased physical access already apply, in a pragmatic way, to large scale reprocessing and MOX fabrication plants. In these plants, qualitative measures and process monitoring play an important role in addition to accountancy and material balance evaluations in attaining the safeguard's goals. This paper will reflect on the safeguards approaches adopted for these large bulk handling facilities and draw analogies, conclusions and lessons for the forthcoming implementation of the 93+2 Programme. (author)

  15. Mine... electricity... reprocessing... Nuclear energy, how and why? Second edition

    International Nuclear Information System (INIS)

    Grisez, F.

    2003-01-01

    This book makes a short and consistent synthesis of nuclear power: how electricity can be generated by braking up atoms and what is the advantage of this mean with respect to the use of fossil fuels or renewable energy sources. Beside the text, this book contains transparency-like illustrations which give a general overview of the civil nuclear domain. Content: 1 - introduction; 2 - radioactivity and nuclear safety: natural and artificial atoms, radioactivity, exposure, nuclear safety; 3 - nuclear fuel cycle: uranium mines and yellow cake, uranium conversion, uranium enrichment, fuel fabrication, nuclear power plants, reprocessing, recycling and conditioning, wastes, statuses, needs, companies and industrial capacities, R and D; 4 - energy consumption; 5 - what energy sources for even more electricity: available energies, environmental impact and accidents, costs of electricity, energy reserves, summary, opinions and conclusions. (J.S.)

  16. Origin, development, and evolution of eye movement desensitization and reprocessing

    Directory of Open Access Journals (Sweden)

    Carolina Marín

    2016-12-01

    Full Text Available Eye movement desensitization and reprocessing (EMDR has led to a great number of studies since its appearance in 1989. The aim of this article is to describe EMDR development and evolution to the present day. With this purpose a search was carried out on MEDLINE and PsycINFO with the entry "eye movement desensitization". After revising the resulting 797 articles, those that because of their relevance explained best the development and evolution of the technique were chosen and shaped into a lifeline graphically representing the history of EMDR. Despite the fact that during the first years the focus of research was on the validation of the technique for post-traumatic disorder (PTSD, it was soon applied to other areas. Only 14% of the articles found account for controlled studies. Up to date, in spite of the effectiveness of EMDR for the treatment of PTSD that has been proven, many different explanatory hypotheses are still up for discussion.

  17. Advanced teleoperation in nuclear applications: consolidated fuel reprocessing program

    International Nuclear Information System (INIS)

    Hamel, W.R.; Feldman, M.J.; Martin, H.L.

    1984-01-01

    A new generation of integrated remote maintenance systems is being developed to meet the needs of future nuclear fuel reprocessing at the Oak Ridge National Laboratory. Development activities cover all aspects of an advanced teleoperated maintenance system with particular emphasis on a new force-reflecting servomanipulator concept. The new manipulator, called the advanced servomanipulator, is microprocessor controlled and is designed to achieve force-reflection performance near that of mechanical master/slave manipulators. The advanced servomanipulator uses a gear-drive transmission which permits modularization for remote maintainability (by other advanced servomanipulators) and increases reliability. Human factors analysis has been used to develop an improved man/machine interface concept based upon colographic displays and menu-driven touch screens. Initial test and evaluation of two advanced servomanipulator slave arms and several other development components have begun. 9 references, 5 figures

  18. Remote repair of the dissolvers in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Otani, Yosikuni

    1985-01-01

    In the Tokai fuel reprocessing plant, there occurred failures (pinholes) in two dissolver tanks successively in 1982 and 1983. These dissolvers are set under high radiation field, not permitting access of the personnel. So, repair works were carried out after development of the remotely operated repair system. For repair of the failed dissolver tanks, after tests and studies, the means was employed of grinding off the wall surface to small depth and then forming over it a corrosion resistant sealing layer by padding welding. The repair system which enabled the repair and the inspection in the cell by remote operation consisted of six devices including polishing, welding, dye penetration test, etc. Repair works on the dissolvers took two months and a half from September 1983. (Mori, K.)

  19. Inklusion gennem æstetiske læreprocesser

    DEFF Research Database (Denmark)

    Elbæk, Sandy; Kirkeby, Anja

    2017-01-01

    ”Inklusion gennem æstetiske processer” introduceres den æstetiske dimension gennem spørgsmålet om, hvorvidt der kan registreres en sammenhæng mellem inklusion og æstetiske læreprocesser i dagtilbud. Artiklen er skrevet på baggrund af et forsøgs- og udviklingsprojekt, der blev gennemført i perioden...... 2014-2016 med det formål at undersøge, hvorvidt æstetiske processer organiseret i projektforløb, der tager udgangspunkt i temaer, som optager mindre grupper af børn, kan have en inkluderende effekt. Artiklen diskuterer, hvordan definitionen af begrebet inklusion er altafgørende for, om man kan etablere...

  20. Molten tin reprocessing of spent nuclear fuel elements

    Science.gov (United States)

    Heckman, Richard A.

    1983-01-01

    A method and apparatus for reprocessing spent nuclear fuel is described. Within a containment vessel, a solid plug of tin and nitride precipitates supports a circulating bath of liquid tin therein. Spent nuclear fuel is immersed in the liquid tin under an atmosphere of nitrogen, resulting in the formation of nitride precipitates. The layer of liquid tin and nitride precipitates which interfaces the plug is solidified and integrated with the plug. Part of the plug is melted, removing nitride precipitates from the containment vessel, while a portion of the plug remains solidified to support the liquid tin and nitride precipitates remaining in the containment vessel. The process is practiced numerous times until substantially all of the precipitated nitrides are removed from the containment vessel.

  1. Investigation of pharmaceuticals and medical devices containing 90Y extracted from high radioactive liquid waste in spent-fuel reprocessing

    International Nuclear Information System (INIS)

    Hosoma, Takashi

    2012-07-01

    Pharmaceuticals and medical devices containing radioactive 90 Y are realized, approved and placed on the international market where three products are available in Europe and the United States, and one product in Japan. These products are used not for diagnosis but for treatment by internal irradiation. It was estimated from the deliberative report of the approval in Japan that 90 Y was extracted in Europe from high radioactive liquid waste (HALW) yielded in spent-fuel reprocessing. In this report, products placed on the market and physical properties were reviewed, reasons of the realization and conditions to realize succeeding products were estimated, extraction method was compared with other methods, technical subjects, and relevant regulations were investigated. Although a medical device containing radioactive 90 Y has been studied in Japan and one pharmaceutical product was approved, a breakthrough would be necessary to put 90 Y utilization beyond alternative treatments. The breakthrough would become be promising; for example, if conventional treatments could be supported by technical development to deliver 90 Y more sharply to the target with shorter serum half-life. Extraction of 90 Y nuclide from HALW has advantages over thermal neutron irradiation of natural nuclide, a system is envisioned where 90 Sr as a parent nuclide is separated in the reprocessing then transported to and stored in a factory of radiopharmaceuticals followed by 90 Y extraction on demand. (author)

  2. Measurement of fiber bundle volume in reprocessed dialyzers.

    Science.gov (United States)

    Narsipur, S S

    2004-02-01

    Fiber bundle volume (FBV) is an important determinant of dialyzer re-use efficiency. This measurement is performed after the dialyzer has been pressure cleaned and may underestimate the degree of clotted fibers a patient actually encounters while on dialysis. Real-time online measure of FBV has been validated using an ultrasound dilution method and the Transonic HD01 monitor (Ithaca, NY, USA). Thirty-one stable chronic hemodialysis patients were studied during the first hour and then during the last 30 minutes of a typical dialysis session. Ultrasound velocity curves using a saline bolus were recorded by flow dilution sensors placed directly on the blood tubing using methods described previously. Blood volume within the dialyzer compartment was determined using a mathematical extrapolation of the measured transit time for a bolus of saline to pass through the dialyzer. These data were compared to FBV obtained using a Seartronics DRS4 (Fresinius, Walnut Creek, CA, USA) reprocessing machine both before and after the same dialysis session. At onset of treatment mean FBV by ultrasound was 100.0 +/- 2.7 ml and was unchanged at the end of the session at 100.0 +/- 3.1 ml (p = 0.49). Before a dialysis session, mean FBV measured on the DRS4 reprocessing machine was 123.5 +/- 2.1 ml and was unchanged following cleaning after dialysis at 121.7 +/- 2.0 ml (p = 0.20). The correlation coefficient between methods was 0.78. FBV did not change during a dialysis session using an online real-time measure. The results of this study do not support concerns that hemodialysis patients may experience considerably less efficient dialysis than standard FBV determination would suggest due to undetected clotting.

  3. Design verification for large reprocessing plants (Proposed procedures)

    International Nuclear Information System (INIS)

    Rolandi, G.

    1988-07-01

    In the 1990s, four large commercial reprocessing plants will progressively come into operation: If an effective and efficient safeguards system is to be applied to these large and complex plants, several important factors have to be considered. One of these factors, addressed in the present report, concerns plant design verification. Design verification provides an overall assurance on plant measurement data. To this end design verification, although limited to the safeguards aspects of the plant, must be a systematic activity, which starts during the design phase, continues during the construction phase and is particularly performed during the various steps of the plant's commissioning phase. The detailed procedures for design information verification on commercial reprocessing plants must be defined within the frame of the general provisions set forth in INFCIRC/153 for any type of safeguards related activities and specifically for design verification. The present report is intended as a preliminary contribution on a purely technical level, and focusses on the problems within the Agency. For the purpose of the present study the most complex case was assumed: i.e. a safeguards system based on conventional materials accountancy, accompanied both by special input and output verification and by some form of near-real-time accountancy involving in-process inventory taking, based on authenticated operator's measurement data. C/S measures are also foreseen, where necessary to supplement the accountancy data. A complete ''design verification'' strategy comprehends: informing the Agency of any changes in the plant system which are defined as ''safeguards relevant''; ''reverifying by the Agency upon receiving notice from the Operator on any changes, on ''design information''. 13 refs

  4. Ecofriendly bricks elaborated from coal waste of Moroccan Jerrada Mining

    Directory of Open Access Journals (Sweden)

    Ez-zaki H.

    2018-01-01

    Full Text Available Solid waste generated during mining is one of the major environmental problems associated with this industrial activity. The best solution to overcome the environmental impact of this waste is to find recycling facilities in mass-produced products that can absorb the large quantities of these available byproducts. The present study shows the feasibility of using the coal waste of Moroccan Jerrada mining in the production of ecological brick. The first step consists of consecutive stages of crushing, grinding and heating at 650°C of the coal waste with a small amount of lime in order to promote the reactive products of elaborated binders. The second step of the process consists of mixing treated coal waste with a small amount of marble dust, sand, gravel, and water, then pressed and dried at room temperature to manufacture a laboratory ecofriendly bricks. The mechanical strength and thermal conductivity are investigated.

  5. A radical-local perspective on curriculum elaboration

    DEFF Research Database (Denmark)

    Chaiklin, Seth

    be used to conceptualise the elaboration and concretization of a formal curriculum, an example of radical-local teaching and learning is presented. The key point is the need to create conditions for subject-matter learning that supports personality development. This perspective provides useful principles......Education, as a societal practice, is aimed at supporting human development. Formal curricula are understood to be a means toward that end, and not an end in itself. That is, curricula are meant to express the qualities and capabilities that students are supposed to acquire as a consequence...... of educational actions. In practice, a curriculum does not provide much analytic insight for how to realise the ideals which they express, nor does it provide insight into the interactions that arise as students engage with the content of the curriculum. To illustrate how a cultural-historical perspective can...

  6. SEED QUALITY PARAMETERS OF PURPLE HORSEMINT FOR ELABORATION OF STANDART

    Directory of Open Access Journals (Sweden)

    L. V. Pavlov

    2016-01-01

    Full Text Available Purple horsemint (Monarda citriodora L. is a perennial plant belonging to Lamiaceae family and being cultivated as aromatic and ornamental crop in many countries of Europe and America. Last years this plant actively gains popularity among gardeners. To elaborate the standard of organization with title 'Seeds of Monarda citriodora L. Sowing qualities. Technical conditions' the basis data has been collected from laboratory of leafy, aromatic, scented and ornamental plant breeding, laboratory of stardatization, rationing and metrology at VNIISSOK. The standard for seeds of Monarda citriodora L.includes the following sections: field of utilization; normative references; terms, definition, abbreviation, classification; technical requirements; order for receiving and sample piking;method of control; transportation and storage; security requirements.

  7. A Novel Hall Effect Sensor Using Elaborate Offset Cancellation Method

    Directory of Open Access Journals (Sweden)

    Vlassis N. Petoussis

    2009-01-01

    Full Text Available The Hall effect is caused by a traverse force that is formed in the electrons or holes of metal element or semiconductor when are polarized by current source and simultaneously all the system it is found vertical in external magnetic field. Result is finally the production of difference of potential (Hall voltage in address vertical in that of current and magnetic field directions. In the present work is presented a new Hall sensor exploiting the former operation. In combination with his pioneering form and using dynamic spinning current technique with an elaborate sequence, it leads to satisfactory results of produced Hall voltage with small noise in a presence of external magnetic field. Anyone can see both the spinning current and anti-Hall technique in the same sensor simultaneously.

  8. EVALUATING LEARNING ISSUES ON ELABORATING WORK BREAKDOWN STRUCTURES

    Directory of Open Access Journals (Sweden)

    Marcelo Werneck Barbosa

    2013-10-01

    Full Text Available There is increasing demand for project management knowledge and experience as well as non-trivial ways of teaching those who are not experienced in this field. Teaching this subject must provide solid theory basis, especially in PMBoK good practices and processes, as well as the capacity of properly executing tools and techniques defined in this document. One of the processes that students in undergraduation and graduation courses find more difficult is the elaboration of the WBS. This work is aimed at assessing such difficulties, proposing mechanisms to reduce them and increasing the quality of this artifact produced by students. Results have shown that students in general have problems in representing the total scope of the project and also in decomposing deliverables until the appropriate level.

  9. Elaboration of titanium nitride coatings by activated reactive evaporation

    International Nuclear Information System (INIS)

    Granier, Jean

    1978-01-01

    As titanium nitride is a very interesting and promising material for the protection against wear and corrosion of metals and alloys with a low fusion point, and notably steels, this research thesis reports the study of the elaboration of a TiN coating by activated reactive evaporation. In a first part, the author describes deposition processes based on evaporation and their characteristics. He explains the choice of the studied process. He discusses published data and results related to the titanium-nitrogen system. He describes the apparatus and reports the operation mode adjustment, and reports the study of the influence of operating conditions (substrate temperature, nitrogen pressure, evaporation rate, possible use of a discharge) on growth kinetics and on coating properties. A reaction mechanism is then proposed to describe and explain the obtained results [fr

  10. Verbal elaboration of distinct affect categories and BPD symptoms.

    Science.gov (United States)

    Lecours, Serge; Bouchard, Marc-André

    2011-03-01

    The present study explores the relationship between the mentalization of distinct affect categories and the severity of borderline personality disorder (BPD) symptoms. Mentalization is assessed by both the level of verbal elaboration (VE) achieved by discrete affects (explicit mentalization) and the proportion of these individual affects in verbal expression (implicit mentalization). Sixty-four outpatients completed a series of questionnaires and took part in an interview designed to produce eight relationship episodes that involved four basic emotions: sadness, joy, anger, and fear (two of each). Affect mentalization was assessed with the Grille de l'Élaboration Verbale de l'Affect (GEVA), an observer-rated measure of levels of elaboration of verbalized affect, and the measure of affect content (MAC), which identifies the content of the verbalized affect (e.g., anger). Diagnostic criteria were obtained with the BPD scale of the Structured Clinical Interview for DSM-IV (SCID-II) questionnaire. Alexithymia was assessed with the 20-item Toronto Alexithymia Scale (TAS-20). The severity of BPD symptoms was related to lower levels of VE of sadness. It was also associated with a higher frequency of hostility directed against others. The level of VE of sadness and the proportion of hostility showed incremental predictive value of borderline symptomatology over demographic information, the presence of a depressive disorder and alexithymia. These findings point to an association between the severity of BPD symptoms and a difficulty mentalizing specific affective domains largely recognized as being central to borderline pathology, namely sadness and hostility. © 2011 The British Psychological Society.

  11. Elaboration of new ceramic composites containing glass fibre production wastes

    International Nuclear Information System (INIS)

    Rozenstrauha, I.; Sosins, G.; Krage, L.; Sedmale, G.; Vaiciukyniene, D.

    2013-01-01

    Two main by-products or waste from the production of glass fibre are following: sewage sludge containing montmorillonite clay as sorbent material and ca 50 % of organic matter as well as waste glass from aluminium borosilicate glass fibre with relatively high softening temperature (> 600 degree centigrade). In order to elaborate different new ceramic products (porous or dense composites) the mentioned by-products and illitic clay from two different layers of Apriki deposit (Latvia) with illite content in clay fraction up to 80-90 % was used as a matrix. The raw materials were investigated by differential-thermal (DTA) and XRD analysis. Ternary compositions were prepared from mixtures of 15 - 35 wt % of sludge, 20 wt % of waste glass and 45 - 65 wt % of clay and the pressed green bodies were thermally treated in sintering temperature range from 1080 to 1120 degree centigrade in different treatment conditions. Materials produced in temperature range 1090 - 1100 degree centigrade with the most optimal properties - porosity 38 - 52 %, water absorption 39 -47 % and bulk density 1.35 - 1.67 g/cm 3 were selected for production of porous ceramics and materials showing porosity 0.35 - 1.1 %, water absorption 0.7 - 2.6 % and bulk density 2.1 - 2.3 g/cm 3 - for dense ceramic composites. Obtained results indicated that incorporation up to 25 wt % of sewage sludge is beneficial for production of both ceramic products and glass-ceramic composites according to the technological properties. Structural analysis of elaborated composite materials was performed by scanning electron microscopy(SEM). By X-ray diffraction analysis (XRD) the quartz, diopside and anorthite crystalline phases were detected. (Author)

  12. Separable algebras

    CERN Document Server

    Ford, Timothy J

    2017-01-01

    This book presents a comprehensive introduction to the theory of separable algebras over commutative rings. After a thorough introduction to the general theory, the fundamental roles played by separable algebras are explored. For example, Azumaya algebras, the henselization of local rings, and Galois theory are rigorously introduced and treated. Interwoven throughout these applications is the important notion of étale algebras. Essential connections are drawn between the theory of separable algebras and Morita theory, the theory of faithfully flat descent, cohomology, derivations, differentials, reflexive lattices, maximal orders, and class groups. The text is accessible to graduate students who have finished a first course in algebra, and it includes necessary foundational material, useful exercises, and many nontrivial examples.

  13. Isotope separation

    International Nuclear Information System (INIS)

    Bartlett, R.J.; Morrey, J.R.

    1978-01-01

    A method and apparatus is described for separating gas molecules containing one isotope of an element from gas molecules containing other isotopes of the same element in which all of the molecules of the gas are at the same electronic state in their ground state. Gas molecules in a gas stream containing one of the isotopes are selectively excited to a different electronic state while leaving the other gas molecules in their original ground state. Gas molecules containing one of the isotopes are then deflected from the other gas molecules in the stream and thus physically separated

  14. Isotopic separation

    International Nuclear Information System (INIS)

    Chen, C.

    1981-01-01

    Method and apparatus for separating isotopes in an isotopic mixture of atoms or molecules by increasing the mass differential among isotopic species. The mixture containing a particular isotope is selectively irradiated so as to selectively excite the isotope. This preferentially excited species is then reacted rapidly with an additional preselected radiation, an electron or another chemical species so as to form a product containing the specific isotope, but having a mass different than the original species initially containing the particular isotope. The product and the remaining balance of the mixture is then caused to flow through a device which separates the product from the mixture based upon the increased mass differential

  15. Introduction of the Large Scale Spent Fuel Reprocessing Plant in China

    International Nuclear Information System (INIS)

    Dai, Y.

    2015-01-01

    According to Chinese nuclear power development program, nuclear power has entered into the period of rapid development, which means that a large amount of spent fuel will be discharged from NPPs. China has always pursued the reprocessing technical route on the management policy of spent fuel. The construction of the large-scale spent fuel reprocessing plant is an important activity on the management of the spent fuel, and it is an important assurance of sustainable development of nuclear energy in China. China has accumulated a great deal of experience in construction of reprocessing plant for the production reactor spent fuel and the pilot reprocessing plant for power reactor spent fuel, established a technical team of R&D, design, construction and operation in reprocessing. Furthermore, Chinese government has approved the R&D program, further intensifying R&D efforts in reprocessing technology, which will make China confident that the large plant can be successfully constructed. At present, the project is implemented by China National Nuclear Corporation (CNNC). The preliminary feasibility study report and the project proposal have been submitted to the government, according to the results of the preparatory works. The product form, plant capacity, main technical options, site characteristics, R&D of reprocessing and several considerations for the project etc. are presented in this paper. (author)

  16. Optimal measurement uncertainties for materials accounting in a fast breeder reactor spent-fuel reprocessing plant

    International Nuclear Information System (INIS)

    Dayem, H.A.; Kern, E.A.; Markin, J.T.

    1982-01-01

    Optimization techniques are used to calculate measurement uncertainties for materials accountability instruments in a fast breeder reactor spent-fuel reprocessing plant. Optimal measurement uncertainties are calculated so that performance goals for detecting materials loss are achieved while minimizing the total instrument development cost. Improved materials accounting in the chemical separations process (111 kg Pu/day) to meet 8-kg plutonium abrupt (1 day) and 40-kg plutonium protracted (6 months) loss-detection goals requires: process tank volume and concentration measurements having precisions less than or equal to 1%; accountability and plutonium sample tank volume measurements having precisions less than or equal to 0.3%, short-term correlated errors less than or equal to 0.04%, and long-term correlated errors less than or equal to 0.04%; and accountability and plutonium sample tank concentration measurements having precisions less than or equal to 0.4%, short-term correlated errors less than or equal to 0.1%, and long-term correlated errors less than or equal to 0.05%

  17. BNFL's application of computer aided engineering to 'THORP' thermal oxide reprocessing plant

    International Nuclear Information System (INIS)

    Hall-Wilton, M.J.

    1990-01-01

    BNFL are currently constructing facilities at Sellafield, Cumbria to reprocess thermal oxide fuel for U.K., European and Japanese utilities. Faced with a 3.5bn pound capital program to provide new facilities at Sellafield, BNFL took the opportunity to embrace the new computer aided engineering technologies then emerging in 1981. To give some idea of the commitment made by BNFL to the above many millions of pounds has been invested in hardware, and more on software and people. The 'THORP' (Head End and Chemical Separation Plant) project represents 1.5bn pounds. The introduction of computer aided engineering has provided a clash free design with full assurance that all materials and components used are compatible. Planning in the design offices in conjunction with an experienced construction management team enables the sequence of piping installation to be determined long before the construction teams enter the work area. This planning aspect has been significantly improved by using EVS (Enhanced Visualisation System). The use of supercomputing graphics facilities is stimulating demands from areas of engineering who have previously not sought to use magnetic data from a variety of sources. The result is mainly due to the data being easily accessible to users who have very little computing experience. (N.K.)

  18. Waste management system alternatives for treatment of wastes from spent fuel reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    McKee, R.W.; Swanson, J.L.; Daling, P.M.; Clark, L.L.; Craig, R.A.; Nesbitt, J.F.; McCarthy, D.; Franklin, A.L.; Hazelton, R.F.; Lundgren, R.A.

    1986-09-01

    This study was performed to help identify a preferred TRU waste treatment alternative for reprocessing wastes with respect to waste form performance in a geologic repository, near-term waste management system risks, and minimum waste management system costs. The results were intended for use in developing TRU waste acceptance requirements that may be needed to meet regulatory requirements for disposal of TRU wastes in a geologic repository. The waste management system components included in this analysis are waste treatment and packaging, transportation, and disposal. The major features of the TRU waste treatment alternatives examined here include: (1) packaging (as-produced) without treatment (PWOT); (2) compaction of hulls and other compactable wastes; (3) incineration of combustibles with cementation of the ash plus compaction of hulls and filters; (4) melting of hulls and failed equipment plus incineration of combustibles with vitrification of the ash along with the HLW; (5a) decontamination of hulls and failed equipment to produce LLW plus incineration and incorporation of ash and other inert wastes into HLW glass; and (5b) variation of this fifth treatment alternative in which the incineration ash is incorporated into a separate TRU waste glass. The six alternative processing system concepts provide progressively increasing levels of TRU waste consolidation and TRU waste form integrity. Vitrification of HLW and intermediate-level liquid wastes (ILLW) was assumed in all cases.

  19. Waste management system alternatives for treatment of wastes from spent fuel reprocessing

    International Nuclear Information System (INIS)

    McKee, R.W.; Swanson, J.L.; Daling, P.M.

    1986-09-01

    This study was performed to help identify a preferred TRU waste treatment alternative for reprocessing wastes with respect to waste form performance in a geologic repository, near-term waste management system risks, and minimum waste management system costs. The results were intended for use in developing TRU waste acceptance requirements that may be needed to meet regulatory requirements for disposal of TRU wastes in a geologic repository. The waste management system components included in this analysis are waste treatment and packaging, transportation, and disposal. The major features of the TRU waste treatment alternatives examined here include: (1) packaging (as-produced) without treatment (PWOT); (2) compaction of hulls and other compactable wastes; (3) incineration of combustibles with cementation of the ash plus compaction of hulls and filters; (4) melting of hulls and failed equipment plus incineration of combustibles with vitrification of the ash along with the HLW; (5a) decontamination of hulls and failed equipment to produce LLW plus incineration and incorporation of ash and other inert wastes into HLW glass; and (5b) variation of this fifth treatment alternative in which the incineration ash is incorporated into a separate TRU waste glass. The six alternative processing system concepts provide progressively increasing levels of TRU waste consolidation and TRU waste form integrity. Vitrification of HLW and intermediate-level liquid wastes (ILLW) was assumed in all cases

  20. Purification of uranium products in crystallization system for nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Takeuchi, Masayuki; Yano, Kimihiko; Shibata, Atsuhiro; Sanbonmatsu, Yuji; Nakamura, Kazuhito; Chikazawa, Takahiro; Hirasawa, Izumi

    2016-01-01

    Uranium crystallization system has been developed to establish an advanced aqueous reprocessing for fast breeder reactor (FBR) fuel cycle. In the crystallization system, most part of uranium in dissolved solution of spent FBR-MOX fuels is separated as uranyl nitrate hexahydrate (UNH) crystals by a cooling operation. The targets of U yield and decontamination factor (DF) on the crystallization system are decided from FBR cycle performance and plutonium enrichment management. The DF is lowered by involving liquid and solid impurities on and in the UNH crystals during crystallization. In order to achieve the DF performance (more than 100), we discuss the purification technology of UNH crystals using a Kureha Crystal Purifier (KCP). Results show that more than 90% of uranium in the feed crystals could be recovered as the purified crystals in all test conditions, and the DFs of solid and liquid impurities on the purified UNH crystals are more than 100 under longer residence time of crystals in the column of KCP device. The purification mechanism is mainly due to the repetition of sweating and recrystallization in the column under controlled temperature. (author)

  1. Spectroscopic Online Monitoring for Process Control and Safeguarding of Radiochemical Fuel Reprocessing Streams - 13553

    International Nuclear Information System (INIS)

    Bryan, S.A.; Levitskaia, T.G.; Casella, Amanda; Peterson, James

    2013-01-01

    There is a renewed interest worldwide to promote the use of nuclear power and close the nuclear fuel cycle. The long term successful use of nuclear power is critically dependent upon adequate and safe processing and disposition of the used nuclear fuel. Liquid-liquid extraction is a separation technique commonly employed for the processing of the dissolved spent nuclear fuel. The instrumentation used to monitor these processes must be robust, require little or no maintenance, and be able to withstand harsh environments such as high radiation fields and aggressive chemical matrices. This paper discusses application of absorption and vibrational spectroscopic techniques supplemented by physicochemical measurements for radiochemical process monitoring. In this context, our team experimentally assessed the potential of Raman and spectrophotometric techniques for on-line real-time monitoring of the U(VI)/nitrate ion/nitric acid and Pu(IV)/Np(V)/Nd(III), respectively, in solutions relevant to spent fuel reprocessing. Both techniques demonstrated robust performance in the repetitive batch measurements of each analyte in a wide concentration range using simulant and commercial dissolved spent fuel solutions. Static spectroscopic measurements served as training sets for the multivariate data analysis to obtain partial least squares predictive models, which were validated using on-line centrifugal contactor extraction tests. Satisfactory prediction of the analytes concentrations in these preliminary experiments warrants further development of the spectroscopy-based methods for radiochemical safeguards and process control. (authors)

  2. Chemical technology of the systems, partitioning and separation, disposal

    International Nuclear Information System (INIS)

    Volk, V.I.

    1997-01-01

    A reactor-accelerator reprocessing complex is described. The complex comprises an electronuclear transmutation installation and chemical and technological support units for maintenance of the steady-state of the blanket, separation of short-lived transmutation products to be disposed of from other components of the blanket, chemical conversion to relevant stable species of products to be disposed of for interim storage and disposal

  3. Kr/Xe Separation over a Chabazite Zeolite Membrane.

    Science.gov (United States)

    Feng, Xuhui; Zong, Zhaowang; Elsaidi, Sameh K; Jasinski, Jacek B; Krishna, Rajamani; Thallapally, Praveen K; Carreon, Moises A

    2016-08-10

    Herein we demonstrate that chabazite zeolite SAPO-34 membranes effectively separated Kr/Xe gas mixtures at industrially relevant compositions. Control over membrane thickness and average crystal size led to industrial range permeances and high separation selectivities. Specifically, SAPO-34 membranes can separate Kr/Xe mixtures with Kr permeances as high as 1.2 × 10 (-7) mol/m(2) s Pa and separation selectivities of 35 for molar compositions close to typical concentrations of these two gases in air. In addition, SAPO-34 membranes separated Kr/Xe mixtures with Kr permeances as high as 1.2 × 10 (-7) mol/m(2) s Pa and separation selectivities up to 45 for molar compositions as might be encountered in nuclear reprocessing technologies. Molecular sieving and differences in diffusivities were identified as the dominant separation mechanisms.

  4. (reprocessed)HeliscopeCAGE sequencing, Delve mapping and CAGE TSS aggregation - FANTOM5 | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available List Contact us FANTOM5 (reprocessed)HeliscopeCAGE sequencing, Delve mapping and CAGE TSS aggregation Data detail Data name (reproces...ls.zip File size: 237 KB File name: (reprocessed)basic (Homo sapiens) File URL: f...tp://ftp.biosciencedbc.jp/archive/fantom5/datafiles/reprocessed/hg38_latest/basic/ File size: 1.4 TB File name: (reprocess...ed)basic (Mus musculus) File URL: ftp://ftp.biosciencedbc.jp/archive/fantom5/datafiles/reprocess...A format) About This Database Database Description Download License Update History of This Database Site Policy | Contact Us (reproce

  5. Multi-society guideline for reprocessing flexible gastrointestinal endoscopes. Society for Healthcare Epidemiology of America.

    Science.gov (United States)

    Nelson, Douglas B; Jarvis, William R; Rutala, William A; Foxx-Orenstein, Amy E; Isenberg, Gerald; Dash, Georgia R; Alvarado, Carla J; Ball, Marilee; Griffin-Sobel, Joyce; Petersen, Carol; Ball, Kay A; Henderson, Jerry; Stricof, Rachel L

    2003-07-01

    Flexible gastrointestinal endoscopy is a valuable diagnostic and therapeutic tool for the care of patients with gastrointestinal and pancreaticobiliary disorders. Compliance with accepted guidelines for the reprocessing of gastrointestinal endoscopes between patients is critical to the safety and success of their use. When these guidelines are followed, pathogen transmission can be effectively prevented. Increased efforts and resources should be directed to improve compliance with these guidelines. Further research in the area of gastrointestinal endoscope reprocessing should be encouraged. The organizations that endorsed this guideline are committed to assisting the FDA and manufacturers in addressing critical infection control issues in gastrointestinal device reprocessing.

  6. Analysis of the options - rationale for servomanipulator maintenance in future reprocessing plants

    International Nuclear Information System (INIS)

    Herndon, J.N.; Hamel, W.R.

    1984-04-01

    The currently available maintenance systems which can be applied, in various combinations, to large-volume in-cell maintenance operations are: (1) contact, (2) overhead cranes, (3) power manipulators, (4) mechanical master/slave manipulators, and (5) servomanipulators. The requirements for reprocessing plant maintenance are reviewed, and the capabilities of remote maintenance systems are described. A basic trade-off analysis of these remote maintenance systems considering reprocessing plant requirements is given. Justification is given for selecting the overhead crane/servomanipulator-based maintenance concept as the option most desirable for future large reprocessing plant maintenance. 23 references, 6 tables

  7. Analysis of the implications of the USSR providing reprocessing and MOX fabrication services to other countries

    International Nuclear Information System (INIS)

    1994-01-01

    This brief analysis, which is based on unclassified sources, seeks to identify what some of the implications would be if the Soviets started to move actively to try to provide reprocessing and MOX fabrication services to the US and other countries. While information on Soviet intentions is limited, it postulates that the Soviets would offer to reprocess spent LWR at competitive prices, fabricate the plutonium and reenrich the uranium, and sell these products back to the customer. Since it is not known whether they would insist on returning the waste from reprocessing or would be prepared to keep it, we comment briefly on what the implications of either of these actions might be

  8. Guide to the selection, training, and licensing or certification of reprocessing plant operators. Volume I

    International Nuclear Information System (INIS)

    1976-06-01

    The Code of Federal Regulations, Title 10, Part 55, establishes procedures and criteria for the licensing of operators, including senior operators, in ''Production and Utilization Facilities'', which includes plants for reprocessing irradiated fuel. A training guide is presented which will facilitate the licensing of operators for nuclear reprocessing plants by offering generalized descriptions of the basic principles (theory) and the unit operations (mechanics) employed in reprocessing spent fuels. In the present volume, details about the portions of a training program that are of major interest to management are presented

  9. On-line reprocessing of a molten salt reactor: a simulation tool

    International Nuclear Information System (INIS)

    Simon, Nicole; Gastaldi, Olivier; Penit, Thomas; Cohin, Olivier; Campion, Pierre-Yves

    2008-01-01

    The molten salt reactor (MSR) is one of the concepts studied in the frame of GEN IV road-map. Due to the specific features of its liquid fuel, the reprocessing unit may be directly connected to the reactor. A modelling of this unit is presented. The final objective is to create a flexible computer reprocessing code which can use data from neutron calculations and can be coupled to a neutron code. Such a code allows the description of the whole behaviour of MSR, including, in a coupled manner, both the design of the core and the optimised reprocessing scheme effects. (authors)

  10. Harmless recycling of radioactive residues through reprocessing in other EC Member States

    International Nuclear Information System (INIS)

    Rengeling, H.W.

    1991-01-01

    The reprocessing of spent fuel elements in other Member States of the EC is legally permissible under the condition that the obligation to perform 'harmless recycling' as set out in Para. 9a (1) of the German Nuclear Energy Act ('Atomgesetz') is observed, and that the impositions of international law are observed. The demand voiced in certain quarters that reprocessing in France and Great Britain be made dependent upon the compliance with German environmental standards (for reprocessing plants) is in contravention of European Community law, which has priority over German national law. (orig.) [de

  11. Guide to the selection, training, and licensing or certification of reprocessing plant operators. Volume I

    Energy Technology Data Exchange (ETDEWEB)

    None

    1976-06-01

    The Code of Federal Regulations, Title 10, Part 55, establishes procedures and criteria for the licensing of operators, including senior operators, in ''Production and Utilization Facilities'', which includes plants for reprocessing irradiated fuel. A training guide is presented which will facilitate the licensing of operators for nuclear reprocessing plants by offering generalized descriptions of the basic principles (theory) and the unit operations (mechanics) employed in reprocessing spent fuels. In the present volume, details about the portions of a training program that are of major interest to management are presented. (JSR)

  12. Separations and Actinide Science -- 2005 Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    2005-09-01

    The Separations and Actinide Science Roadmap presents a vision to establish a separations and actinide science research (SASR) base composed of people, facilities, and collaborations and provides new and innovative nuclear fuel cycle solutions to nuclear technology issues that preclude nuclear proliferation. This enabling science base will play a key role in ensuring that Idaho National Laboratory (INL) achieves its long-term vision of revitalizing nuclear energy by providing needed technologies to ensure our nation's energy sustainability and security. To that end, this roadmap suggests a 10-year journey to build a strong SASR technical capability with a clear mission to support nuclear technology development. If nuclear technology is to be used to satisfy the expected growth in U.S. electrical energy demand, the once-through fuel cycle currently in use should be reconsidered. Although the once-through fuel cycle is cost-effective and uranium is inexpensive, a once-through fuel cycle requires long-term disposal to protect the environment and public from long-lived radioactive species. The lack of a current disposal option (i.e., a licensed repository) has resulted in accumulation of more than 50,000 metric tons of spent nuclear fuel. The process required to transition the current once-through fuel cycle to full-recycle will require considerable time and significant technical advancement. INL's extensive expertise in aqueous separations will be used to develop advanced separations processes. Computational chemistry will be expanded to support development of future processing options. In the intermediate stage of this transition, reprocessing options will be deployed, waste forms with higher loading densities and greater stability will be developed, and transmutation of long-lived fission products will be explored. SASR will support these activities using its actinide science and aqueous separations expertise. In the final stage, full recycle will be

  13. Management of low level wastes at Rokkasho reprocessing plant

    International Nuclear Information System (INIS)

    Moriya, N.; Ochi, E.

    2006-01-01

    Full text: At Rokkasho Reprocessing Plant (RRP), after start-up of the commercial operation, radioactive wastes will be generated. Wastes generated from a reprocessing plant generally consist of many kinds of characteristics in view of ''activity level'', ''nuclide composition'', ''chemical properties'', ''physical properties'', and so on. For stable operation of a reprocessing plant, we should t reat , ''condition'' and ''dispose'' these wastes considering these wastes characteristics. To contribute to the nuclear fuel cycle project, it is important to evaluate technologies such as, ''Treatment'', ''Conditioning'' and ''Final Disposal'', not only for technical but also for economical aspects. Considering the final disposal in the future, the basic policy in ''Treatment'' and ''Conditioning'' at RRP is shown below: Recover and reuse chemicals (such as nitric acid and TBP, etc.) in plant; Radioactive waste shall be divided, classified and managed according to activity level, nuclide composition, the radiation level, its physical properties, chemical properties, etc.; Treat them based on ''classification'' management with proper combination; Condition them as intermediate forms in order to keep flexibility in the future disposal method; Original volume of annually generated wastes at RRP is estimated as 5600m3 except highly radioactive vitrified waste, and these wastes shall be treated in the following units, which are now under commisioning, in order to reduce and stabilize wastes. Low-level concentrated liquid waste to be treated with a ''Drying and peptization'' unit; Spent solvent to be treated with a ''Pyrolysis and hydrothermal solidification'' unit; Relatively low-level non-alfa flammable wastes to be treated with a ''Incineration and hydrothermal solidification'' unit; CB/BP (Channel Box and Burnable Poison) to be processed with a ''Cutting'' unit; Other wastes to be kept as their generated state with a ''Intermediate storage''. As a result of these

  14. Interactions of the IGS reprocessing and the IGS antenna phase center model (Invited)

    Science.gov (United States)

    Schmid, R.; Steigenberger, P.; Dach, R.; Schmitz, M.; Dilssner, F.; Hugentobler, U.

    2009-12-01

    to ITRF2008, consistent z-offsets for all GPS satellites can be estimated. As PCV estimates are not contained in the SINEX files, the block-specific igs05.atx values for the GPS satellites will have to be kept fixed. As GLONASS observations were not reprocessed by the IGS ACs, a separate solution by CODE and ESOC will be necessary. This allows the simultaneous update of PCO and PCV values for GLONASS.As regards the receiver antennas, the overall update of igs05.atx provides the opportunity to consider the latest calibration results. As the accuracy of type-mean calibrations depends on the number of individually calibrated antennas, it is worth taking all calibrations from recent years into account. Whereas the update of robot calibrations will have minor influence on the coordinate estimates, the replacement of converted field calibrations probably requires the elimination of several reference frame stations. Besides, GLONASS-specific PCVs will be considered.The presentation will focus on the timeline of the various updates as well as on their impact on the coordinate results. We will highlight the benefit for the overall consistency of IGS products, but also demonstrate several remaining consistency problems.

  15. Simulation of atmospheric krypton-85 transport to assess the detectability of clandestine nuclear reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Ross, Jens Ole

    2010-02-02

    The radioactive noble gas krypton-85 is released into the atmosphere during reprocessing of spent nuclear fuel or irradiated breeding targets. This is a necessary step for plutonium separation. Therefore the {sup 85}Kr signature of reprocessing could possibly be used for the detection of undeclared nuclear facilities producing nuclear weaponusable material. The {sup 85}Kr content of the atmosphere has grown over the last decades as the emissions from military and civilian nuclear industry could not be compensated by the decay with a half-life of 10.76 years. In this study, the global {sup 85}Kr background distribution due to emissions of known reprocessing facilities for the period from 1971 until 2006 was simulated using the atmospheric general circulation model ECHAM5 applying the newest available annual emission data. The convective tracer transport scheme and the operator splitting for the physical calculations in the model were modified in order to guarantee physically correct results for tracer point sources, in particular non negative concentrations. An on-line routine controlling the {sup 85}Kr -budget in the model enforced exact mass conservation. The results of the simulation were evaluated by extensive comparison with measurements performed by the German Federal Office for Radiation Protection with very good agreement at most observation sites except those in the direct vicinity of {sup 85}Kr sources. Of particular interest for the {sup 85}Kr detection potential was the variability of {sup 85}Kr background concentrations which was evaluated for the first time in a global model. In addition, the interhemispheric transport as simulated by ECHAM5 was analyzed using a two-box model providing a mean exchange time of τ {sub ex} = 10.5 months. The analysis of τ{sub ex} over simulated 35 years indicates that in years with strong South Asian or African Monsoon the interhemispheric transport is faster during the monsoon season. A correlation analysis of

  16. Smartphone Cortex Controlled Real-Time Image Processing and Reprocessing for Concentration Independent LED Induced Fluorescence Detection in Capillary Electrophoresis.

    Science.gov (United States)

    Szarka, Mate; Guttman, Andras

    2017-10-17

    We present the application of a smartphone anatomy based technology in the field of liquid phase bioseparations, particularly in capillary electrophoresis. A simple capillary electrophoresis system was built with LED induced fluorescence detection and a credit card sized minicomputer to prove the concept of real time fluorescent imaging (zone adjustable time-lapse fluorescence image processor) and separation controller. The system was evaluated by analyzing under- and overloaded aminopyrenetrisulfonate (APTS)-labeled oligosaccharide samples. The open source software based image processing tool allowed undistorted signal modulation (reprocessing) if the signal was inappropriate for the actual detection system settings (too low or too high). The novel smart detection tool for fluorescently labeled biomolecules greatly expands dynamic range and enables retrospective correction for injections with unsuitable signal levels without the necessity to repeat the analysis.

  17. Technical feasibility of advanced separation; Faisabilite technique de la separation poussee

    Energy Technology Data Exchange (ETDEWEB)

    Rostaing, Ch

    2004-07-01

    Advanced separation aims at reducing the amount and toxicity of high-level and long lived radioactive wastes. The Purex process has been retained as a reference way for the recovery of the most radio-toxic elements: neptunium, technetium and iodine. Complementary solvent extraction processes have to be developed for the separation of americium, curium and cesium from the high activity effluent of the spent fuel reprocessing treatment. Researches have been carried out with the aim of demonstrating the scientifical and technical feasibility of advanced separation of minor actinides and long lived fission products from spent fuels. The scientifical feasibility was demonstrated at the end of 2001. The technical feasibility works started in the beginning of 2002. Many results have been obtained which are presented and summarized in this document: approach followed, processes retained for the technical feasibility (An/Ln and Am/Cm separation), processes retained for further validation at the new shielded Purex installation, technical feasibility of Purex adaptation to Np separation, technical feasibility of Diamex (first step: (An+Ln)/other fission products) separation), technical feasibility of Sanex process (second step: An(III)/Ln(III) separation), technical feasibility of Am(III)/Cm(III) separation, cesium separation, iodine separation, technical-economical evaluation, conclusions and perspectives, facilities and apparatuses used for the experiments. (J.S.)

  18. Isotope separation

    International Nuclear Information System (INIS)

    Coleman, G.H.; Bett, R.; Cuninghame, J.G.; Sims, H.

    1982-01-01

    In the separation of short-lived isotopes for medical usage, a solution containing sup(195m)Hg is contacted with vicinal dithiol cellulose which adsorbs and retains the sup(195m)Hg. sup(195m)Au is eluted from the vicinal dithiol cellulose by using a suitable elutant. The sup(195m)Au arises from the radioactive decay of the sup(195m)Hg. The preferred elutant is a solution containing CN - ion. (author)

  19. Gas separating

    Science.gov (United States)

    Gollan, Arye Z.

    1990-12-25

    Feed gas is directed tangentially along the non-skin surface of gas separation membrane modules comprising a cylindrical bundle of parallel contiguous hollow fibers supported to allow feed gas to flow from an inlet at one end of a cylindrical housing through the bores of the bundled fibers to an outlet at the other end while a component of the feed gas permeates through the fibers, each having the skin side on the outside, through a permeate outlet in the cylindrical casing.

  20. Elaboration of optical glass-ceramic for frequency doubling

    International Nuclear Information System (INIS)

    Vigouroux, H.

    2012-01-01

    The High power laser development required the need of materials with nonlinear properties. Glass materials can be considered as ideal materials as they can be transparent and elaborated in very large dimension. Precipitation of non-centro symmetric crystalline particles in bulk glass leads to a material with bulk nonlinear properties. This glass-ceramic should be then easily integrated in such laser facilities. In this thesis, the results concerning the precipitation of the phase LiNbO 3 in the glassy-matrix 35 Li 2 O - 25 Nb 2 O 5 - 40 SiO 2 are detailed. The crystallization mechanism of this phase is studied through thermal analysis, optical and electronic microscopy as well as in-situ analyses. These studies reveal glass-ceramics are obtained through a precipitation of the lithium niobate crystalline phase in spherulite shape. The nonlinear optical properties are investigated on this materials and an original, isotropic Second Harmonic Generation Signal (SHG) is registered in the bulk glass-ceramic. A complete study using a multi-scale approach allows the correlation between the spherulite structure and the nonlinear optical properties. A mechanism at the origin of the SHG signal is proposed. This leads to a new approach for transparent inorganic materials development for isotropic SHG conversion. (author) [fr

  1. Aluminosilicate glass thin films elaborated by pulsed laser deposition

    Energy Technology Data Exchange (ETDEWEB)

    Carlier, Thibault [Univ. Lille, CNRS, Centrale Lille, ENSCL, Univ. Artois, UMR 8181 – UCCS – Unité de Catalyse et Chimie du Solide, F-59000 Lille (France); Saitzek, Sébastien [Univ. Artois, CNRS, Centrale Lille, ENSCL, Univ. Lille, UMR 8181, Unité de Catalyse et de Chimie du Solide (UCCS), F-62300 Lens (France); Méar, François O., E-mail: francois.mear@univ-lille1.fr [Univ. Lille, CNRS, Centrale Lille, ENSCL, Univ. Artois, UMR 8181 – UCCS – Unité de Catalyse et Chimie du Solide, F-59000 Lille (France); Blach, Jean-François; Ferri, Anthony [Univ. Artois, CNRS, Centrale Lille, ENSCL, Univ. Lille, UMR 8181, Unité de Catalyse et de Chimie du Solide (UCCS), F-62300 Lens (France); Huvé, Marielle; Montagne, Lionel [Univ. Lille, CNRS, Centrale Lille, ENSCL, Univ. Artois, UMR 8181 – UCCS – Unité de Catalyse et Chimie du Solide, F-59000 Lille (France)

    2017-03-01

    Highlights: • Successfully deposition of a glassy thin film by PLD. • A good homogeneity and stoichiometry of the coating. • Influence of the deposition temperature on the glassy thin-film structure. - Abstract: In the present work, we report the elaboration of aluminosilicate glass thin films by Pulsed Laser Deposition at various temperatures deposition. The amorphous nature of glass thin films was highlighted by Grazing Incidence X-Ray Diffraction and no nanocristallites were observed in the glassy matrix. Chemical analysis, obtained with X-ray Photoelectron Spectroscopy and Time of Flight Secondary Ion Mass Spectroscopy, showed a good transfer and homogeneous elementary distribution with of chemical species from the target to the film a. Structural studies performed by Infrared Spectroscopy showed that the substrate temperature plays an important role on the bonding configuration of the layers. A slight shift of Si-O modes to larger wavenumber was observed with the synthesis temperature, assigned to a more strained sub-oxide network. Finally, optical properties of thins film measured by Spectroscopic Ellipsometry are similar to those of the bulk aluminosilicate glass, which indicate a good deposition of aluminosilicate bulk glass.

  2. Nursing Care Interpersonal Relationship Questionnaire: elaboration and validation

    Directory of Open Access Journals (Sweden)

    José Wicto Pereira Borges

    2018-01-01

    Full Text Available ABSTRACT Objective: to elaborate an instrument for the measurement of the interpersonal relationship in nursing care through the Item Response Theory, and the validation thereof. Method: methodological study, which followed the three poles of psychometry: theoretical, empirical and analytical. The Nursing Care Interpersonal Relationship Questionnaire was developed in light of the Imogene King’s Interpersonal Conceptual Model and the psychometric properties were studied through the Item Response Theory in a sample of 950 patients attended in Primary, Secondary and Tertiary Health Care. Results: the final instrument consisted of 31 items, with Cronbach’s alpha of 0.90 and McDonald’s Omega of 0.92. The parameters of the Item Response Theory demonstrated high discrimination in 28 items, being developed a five-level interpretive scale. At the first level, the communication process begins, gaining a wealth of interaction. Subsequent levels demonstrate qualitatively the points of effectiveness of the interpersonal relationship with the involvement of behaviors related to the concepts of transaction and interaction, followed by the concept of role. Conclusion: the instrument was created and proved to be consistent to measure interpersonal relationship in nursing care, as it presented adequate reliability and validity parameters.

  3. Soundscape elaboration from anthrophonic adaptation of community noise

    Science.gov (United States)

    Teddy Badai Samodra, FX

    2018-03-01

    Under the situation of an urban environment, noise has been a critical issue in affecting the indoor environment. A reliable approach is required for evaluation of the community noise as one factor of anthrophonic in the urban environment. This research investigates the level of noise exposure from different community noise sources and elaborates the advantage of the noise disadvantages for soundscape innovation. Integrated building element design as a protector for noise control and speech intelligibility compliance using field experiment and MATLAB programming and modeling are also carried out. Meanwhile, for simulation analysis and building acoustic optimization, Sound Reduction-Speech Intelligibility and Reverberation Time are the main parameters for identifying tropical building model as case study object. The results show that the noise control should consider its integration with the other critical issue, thermal control, in an urban environment. The 1.1 second of reverberation time for speech activities and noise reduction more than 28.66 dBA for critical frequency (20 Hz), the speech intelligibility index could be reached more than fair assessment, 0.45. Furthermore, the environmental psychology adaptation result “Close The Opening” as the best method in high noise condition and personal adjustment as the easiest and the most adaptable way.

  4. The elaborate plumage in peacocks is not such a drag.

    Science.gov (United States)

    Askew, Graham N

    2014-09-15

    One of the classic examples of an exaggerated sexually selected trait is the elaborate plumage that forms the train in male peafowl Pavo cristatus (peacock). Such ornaments are thought to reduce locomotor performance as a result of their weight and aerodynamic drag, but this cost is unknown. Here, the effect that the train has on take-off flight in peacocks was quantified as the sum of the rates of change of the potential and kinetic energies of the body (P(CoM)) in birds with trains and following the train's removal. There was no significant difference between P(CoM) in birds with and without a train. The train incurs drag during take-off; however, while this produces a twofold increase in parasite drag, parasite power only accounts for 0.1% of the total aerodynamic power. The train represented 6.9% of body weight and is expected to increase induced power. The absence of a detectable effect on take-off performance does not necessarily mean that there is no cost associated with possessing such ornate plumage; rather, it suggests that given the variation in take-off performance per se, the magnitude of any effect of the train has little meaningful functional relevance. © 2014. Published by The Company of Biologists Ltd.

  5. The need for and the safety of the German spent fuel reprocessing plant at Wackersdorf

    International Nuclear Information System (INIS)

    1987-02-01

    The reprocessing of spent fuel elements from LWR-type reactors is a technically mature and marketable process. The German spent fuel reprocessing plant under construction at Wackersdorf is expected to bring in foreign exchange savings in the Federal household amounting to several hundred millions of DM a year, thus contributing in the long run to the energy political independence of the F.R.G. At the same time, reduced exploitation of resources for uranium production will cut back the effects on the natural environment. Reprocessing technology last not least meets an obligation set by law, namely to recycle the radioactive wastes from nuclear fuel utilisation in a way avoiding harm to the environment. The alternative waste management option, i.e. direct ultimate disposal of spent fuels, does not offer significant advantages over the reprocessing concept in terms of safety, environmental protection, or economics. (orig./HSCH) [de

  6. Description of solid waste expected from a large commercial reprocessing plant

    International Nuclear Information System (INIS)

    Keely, R.B.

    1979-01-01

    Both low-level and high-level solid wastes generated during reprocessing of spent nuclear fuel are characterized in this paper with respect to source, quantity, content, radioactivity, potential volume reduction, and transuranic content

  7. Seismic analysis of the Nuclear Fuel Service Reprocessing Plant at West Valley, New York: documentation

    International Nuclear Information System (INIS)

    Murray, R.C.; Nelson, T.A.; Davito, A.M.

    1977-01-01

    This material was generated as part of a seismic case review of the NFS Reprocessing Plant. This study is documented in UCRL-52266. The material is divided into two parts: mathematical model information, and ultimate load calculations and comparisons

  8. A review of liquor transfer systems for use in nuclear reprocessing plants

    International Nuclear Information System (INIS)

    Singh, J.

    1982-01-01

    Liquor pumping systems for use in nuclear fuel reprocessing plants are described. Comparison of the operating characteristics and system constants are made between the air lift/Vacuum Operated Slug Lift, power fluidics and ejector pump systems. (author)

  9. Corrosion resistance of metallic materials for use in nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Pinard Legry, G.; Pelras, M.; Turluer, G.

    1988-01-01

    The main of this review is to reassess the corrosion resistance properties required from metallic materials to be used in the various developments of the Purex process applied for nuclear fuel reprocessing

  10. Health Care: Reprocessed Medical Single-Use Devices in DoD

    National Research Council Canada - National Science Library

    2002-01-01

    ... for decontamination and resterilization. The emergence of new materials and sterilization methods, and the increasing costs of health care, resulted in the development of medical single-use devices and the practice of reprocessing the devices...

  11. Summary table of base case and national reference case reprocessing plants

    International Nuclear Information System (INIS)

    1979-09-01

    This paper summarises in tabular form the main specifications of the base case reprocessing plant, together with those of the national reference case plants contributed by France, Federal Republic of Germany, India, Japan and the United Kingdom

  12. EdF speaks about economic advantages of fuel reprocessing as compared with interim storage

    International Nuclear Information System (INIS)

    Anon.

    1997-01-01

    The French company Electricite de France (EdF) will prefer nuclear fuel reprocessing and plutonium recycling to spent fuel storage also in the years after 2000. This option is economically advantageous if the proportional cost of reprocessing does not exceed 1900 FRF/kg heavy metal. Economic analysis shows that this is feasible. EdF will soon have to reprocess annually about 1000 Mt spent fuel to supply enough plutonium for MOX fuel fabrication to feed as many as 28 PWR units and the Superphenix reactor. Spent fuel reprocessing is seen as promising as long as the efficiency of the MOX fuel approaches that of natural uranium based fuel. The French national industrial, political and legal context of EdF operations is also considered. (P.A.)

  13. Remote systems and remote maintenance of a reprocessing plant in Japan

    International Nuclear Information System (INIS)

    Funaya, T.

    1977-01-01

    The design concept and overall maintenance philosophy applied in the Power Reactor and Nuclear Fuel Development Corporation Reprocessing Plant at Tokai-mura, Japan, are briefly introduced. Details on remote systems and remote maintenance in mechanical processing areas are described

  14. Catalogue and classification of technical safety rules for light-water reactors and reprocessing plants

    International Nuclear Information System (INIS)

    Bloser, M.; Fichtner, N.; Neider, R.

    1975-08-01

    This report on the cataloguing and classification of technical rules for land-based light-water reactors and reprocessing plants contains a list of classified rules. The reasons for the classification system used are given and discussed

  15. Consolidated fuel reprocessing program. Progress report, July 1-September 30, 1981

    International Nuclear Information System (INIS)

    1981-12-01

    Technical progress is reported in overview fashion in the following areas: process development, laboratory R and D, engineering research, engineering systems, integrated equipment test facility (IET) operations, and HTGR fuel reprocessing

  16. Cesium and Strontium Separation Technologies Literature Review

    Energy Technology Data Exchange (ETDEWEB)

    T. A. Todd; T. A. Todd; J. D. Law; R. S. Herbst

    2004-03-01

    Integral to the Advanced Fuel Cycle Initiative (AFCI) Program’s proposed closed nuclear fuel cycle, the fission products cesium and strontium in the dissolved spent nuclear fuel stream are to be separated and managed separately. A comprehensive literature survey is presented to identify cesium and strontium separation technologies that have the highest potential and to focus research and development efforts on these technologies. Removal of these high-heat-emitting fission products reduces the radiation fields in subsequent fuel cycle reprocessing streams and provides a significant short-term (100 yr) heat source reduction in the repository. This, along with separation of actinides, may provide a substantial future improvement in the amount of fuel that could be stored in a geologic repository. The survey and review of the candidate cesium and strontium separation technologies are presented herein. Because the AFCI program intends to manage cesium and strontium together, technologies that simultaneously separate both elements are of the greatest interest, relative to technologies that separate only one of the two elements.

  17. X-RAYS SEPARATOR: FORWARD STEP IN TECHNOLOGY OF OPTICAL SEPARATION

    Directory of Open Access Journals (Sweden)

    N. N. Potrakhov

    2017-01-01

    Full Text Available Presently the X-ray separation is used not only for research program, but it is also elaborated and applied for different sectors of economy. The seeds as biological objects that possess the complicated microstructure are very difficult to be exanimated by x-ray technology. The application of x-rays and further elaboration of optical  separators, principle  of action, basic specifications, way of their use and their efficiency was shown in the article. The x-ray separator may distinguish all hidden seed defects as it was described by a programmer, where owing to the use of the optical separating block in visual range it is possible to add some more details as a shape, brightness and a color of object surface being exanimated. The elaboration of such separation equipment is scientifically hard work requiring time and expenses. Last year researchers of ‘LETI’ developed the working model of industrial x-ray separator for examination of grains and nuts in different crops. This model was made on the basis of photoseparator F-5 manufactured at OAO ‘Voronezhselmash’. The instrument state and its mechanism operation are highlighted on monitor. In the regime of processing (separation and examination of each controlled batch, the passport is produced with  following  information on identification  code,  time of material receiving, time of test passed, number of grains or seeds tested. The code of receiver of material is given to each of established characteristics when working the regime of separation, determination of number of objects with characteristics tested and number of unidentified objects. The application of x-ray separators constructed on the basis of photoseparator F-5 enables to carry out the complex estimation on seed quality and separation in only instrument with the development of electronic protocol with many characteristics.

  18. Reprocessability of molybdenum and magnesia based inert matrix fuels

    Directory of Open Access Journals (Sweden)

    Ebert Elena L.

    2015-12-01

    Full Text Available This work focuses on the reprocessability of metallic 92Mo and ceramic MgO, which is under investigation for (Pu,MA-oxide (MA = minor actinide fuel within a metallic 92Mo matrix (CERMET and a ceramic MgO matrix (CERCER. Magnesium oxide and molybdenum reference samples have been fabricated by powder metallurgy. The dissolution of the matrices was studied as a function of HNO3 concentration (1-7 mol/L and temperature (25-90°C. The rate of dissolution of magnesium oxide and metallic molybdenum increased with temperature. While the MgO rate was independent of the acid concentration (1-7 mol/L, the rate of dissolution of Mo increased with acid concentration. However, the dissolution of Mo at high temperatures and nitric acid concentrations was accompanied by precipitation of MoO3. The extraction of uranium, americium, and europium in the presence of macro amounts of Mo and Mg was studied by three different extraction agents: tri-n-butylphosphate (TBP, N,Nʹ-dimethyl-N,Nʹ-dioctylhexylethoxymalonamide (DMDOHEMA, and N,N,N’,N’- -tetraoctyldiglycolamide (TODGA. With TBP no extraction of Mo and Mg occurred. Both matrix materials are partly extracted by DMDOHEMA. Magnesium is not extracted by TODGA (D < 0.1, but a weak extraction of Mo is observed at low Mo concentration.

  19. Development of remote fuel pushing system in Reprocessing Plant, Tarapur

    International Nuclear Information System (INIS)

    Chandra, Munish; Coelho, G.; Kodilkar, S.S.; Mishra, A.K.; Bajpai, D.D.; Nair, M.K.T.

    1990-01-01

    Power Reactor Fuel Reprocessing Plant (PREFRE), Tarapur has been processing spent fuel arising from Pressurized Heavy Water Reactors for quite some time. The process adopted in the plant is purex process with chopleach head end treatment. The head end treatment involves loading of ten spent fuel bundles in the charging cask at a time in the fuel bay and aligning the cask with the transfer port and subsequently pushing all the ten bundles together into the fuel magazine. At present the fuel is pushed into the magazine manually. Since the ten bundles weigh approximately 200 Kg. and involves pushing of 9.4 meters length, the operation is carried out using stainless steel screwed pipes, in steps of five lengths. The entire operation requires a large number of trained skilled workers and is found to be tedious. To solve this problem a hydraulic cum pneumatic fuel pushing system has been designed, fabricated, tested and is in the process of installation in the fuel handling area. This paper describes various requirements, constraints and dimensional details arising in the incorporation of such a system to be back fitted in an existing plant, though many of these constraints can be avoided in future plants. Further, complete sequence of operations, technical specifications regarding the telescopic hydraulic power pack and associated controls incorporated in the system are highlighted. (author). 2 figs

  20. Radiation protection aspects in decommissioning of a fuel reprocessing plant

    International Nuclear Information System (INIS)

    Kotrappa, P.; Joshi, P.P.; Theyyunni, T.K.; Sidhwa, B.M.; Nadkarni, M.N.

    1980-01-01

    The decontamination of a fuel reprocessing plant which underwent partial decommissioning is described. The following radiation protection aspects of the work are discussed: dismantling and removal of process vessels, columns and process off-gas filters; decontamination of various process areas; and management of liquid and solid wastes. The work was completed safely by using personnel protective equipment such as plastic suits and respirators (gas, particulate and fresh air). Total dose commitment for this work was around 3000 man-rems, including dose received by staff for certain jobs related to the operation of a section of the plant. The external dose was kept below the annual limit of 5000 mrems for any individual. No internal contamination incident occurred which caused a dose commitment in excess of 10% of the annual limit. The fact that all the work was completed by the staff normally associated with the operation of the plant contributed significantly to the management and control of personnel exposures. (H.K.)

  1. Aerosols released from solvent fire accidents in reprocessing plants

    International Nuclear Information System (INIS)

    Jordan, S.; Lindner, W.

    1985-01-01

    Thermodynamic, aerosol characterizing and radiological data of solvent fires in reprocessing plants have been established in experiments. These are the main results: Depending on the ventilation in the containment, kerosene-TBP mixtures burn at a rate up to 120 kg/m 2 h. The aqueous phase of inorganic-organic mixtures might be released during the fire. The gaseous reaction products contain unburnable acidic compounds. Solvents with TBP-nitrate complex shows higher (up to 25%) burning rates than pure solvents (kerosene-TBP). The nitrate complex decomposes violently at about 130 0 C with a release of acid and unburnable gases. Up to 20% of the burned kerosene-TBP solvents are released during the fire in the form of soot particles, phosphoric acid and TBP decomposition products. The particles have an aerodynamic mass median diameter of about 0.5 μm and up to 1.5% of the uranium fixed in the TBP-nitrate complex is released during solvent fires. (orig.)

  2. Crud in the solvent extraction process for spent fuel reprocessing

    International Nuclear Information System (INIS)

    Chen Jing

    2004-01-01

    The crud occurred in Purex process is caused by the degradations of extractant and solvent and the existence of insoluble solid particle in the nuclear fuel reprocessing. The crud seriously affects the operation of the extraction column. The present paper reviews the study status on the crud in the Purex process. It is generally accepted that in the Purex process, particularly in the first cycle, the crud occurrence is related to the capillary chemistry phenomena resulting from the deposits of Zr with TBP degradation products HDBP, H 2 MBP, H 3 PO 4 and the insoluble particle RuO 2 and Pd. The occurrence of deposits and the type of crud are tightly related to the molar ratio of HDBP and Zr, and the aqueous pH. In addition, the effect of degradation products from the diluent, such as kerosene, is an unnegligible factor to cause the crud. The crud can be discharged from the extraction equipment with Na 2 CO 3 or oxalic acid. In the study on simulating the crud, the effects of the deposits of Zr with TBP degradation products HDBP, H 2 MBP and H 2 PO 4 , and the insoluble particle RuO 2 and Pd should be considered at the same time. (authors)

  3. Diagnostic aid and maintenance at the La Hague reprocessing plants

    International Nuclear Information System (INIS)

    Bern, J.B.; Chabert, J.

    1989-01-01

    The Cogema plant at La Hague is the world's leading nuclear fuel reprocessing plant. A major extension program was initiated in 1980. It includes the construction of a new 800 t/year capacity plant (UP3), to be commissioned in 1989, and the doubling of the capacity of the present plant (UP2 800) scheduled to go on stream in 1992. On the occasion of this huge capital investment, an overall assessment was made of the operating and maintenance systems of the site. The general objective was to achieve maximum productivity and availability, in view of: - the extreme importance of safety for the protection of workers and the environment, - the high level of automation required by the complexity of the process, - the inaccessibility of the nuclear equipment, the scale of the investment. To achieve this goal, a set of diagnostic and maintenance aid systems were developed and installed. A general site data network serves to link these systems and to distribute the corresponding data to the different users. This paper describes these different systems, presents the functionalities of the network and demonstrates the sequencing of the operations in a typical maintenance application

  4. Status of radioiodine control for nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    Burger, L.L.; Scheele, R.D.

    1983-07-01

    This report summarizes the status of radioiodine control in a nuclear fuel reprocessing plant with respect to capture, fixation, and disposal. Where possible, we refer the reader to a number of survey documents which have been published in the last four years. We provide updates where necessary. Also discussed are factors which must be considered in developing criteria for iodine control. For capture from gas streams, silver mordenite and a silver nitrate impregnated silica (AC-6120) are considered state-of-the-art and are recommended. Three aqueous scrubbing processes have been demonstrated: Caustic scrubbing is simple but probably will not give an adequate iodine retention by itself. Mercurex (mercuric nitrate-nitric acid scrubbing) has a number of disadvantages including the use of toxic mercury. Iodox (hyperazeotropic nitric acid scrubbing) is effective but employs a very corrosive and hazardous material. Other technologies have been tested but require extensive development. The waste forms recommended for long-term storage or disposal are silver iodide, the iodates of barium, strontium, or calcium, and silver loaded sorbents, all fixed in cement. Copper iodide in bitumen (asphalt) is a possibility but requires testing. The selection of a specific form will be influenced by the capture process used

  5. Development of PSA procedure for a criticality in reprocessing facilities

    International Nuclear Information System (INIS)

    Endo, Shigeki; Takanashi, Mitsuhiro; Ueda, Yoshinori

    2012-08-01

    Utilization of risk information for the nuclear safety regulation is being discussed in Japan. The development of probabilistic safety assessment (PSA) procedure is indispensable for the utilization of risk information. The Japan Nuclear Energy Safety Organization (JNES) has been conducting trial PSA to a model plant for major events, i.e. hydrogen explosion, solution boiling, rapid decomposition of TBP complexes, criticality, solvent fire, leakage of molten glass, leakage of high active concentrated liquid waste, loss of all AC electricity, drop of a fuel assembly, for the purpose of developing the PSA procedure for reprocessing facilities. For criticality events results of trial PSA were summarized as a report in which how to evaluate an amount of radioactive materials released from a facility and a health effect on the public were emphasized. Therefore, for criticality events the results of trial PSA were summarized in this report to emphasize procedures from making event progression scenarios to quantifying event sequences, which were not handled in the previous report, in a style of a document describing PSA procedures. (author)

  6. Authentication of reprocessing plant safeguards data through correlation analysis

    International Nuclear Information System (INIS)

    Burr, T.L.; Wangen, L.E.; Mullen, M.F.

    1995-04-01

    This report investigates the feasibility and benefits of two new approaches to the analysis of safeguards data from reprocessing plants. Both approaches involve some level of plant modeling. All models involve some form of mass balance, either applied in the usual way that leads to material balances for individual process vessels at discrete times or applied by accounting for pipe flow rates that leads to material balances for individual process vessels at continuous times. In the first case, material balances are computed after each tank-to-tank transfer. In the second case, material balances can be computed at any desired time. The two approaches can be described as follows. The first approach considers the application of a new multivariate sequential test. The test statistic is a scalar, but the monitored residual is a vector. The second approach considers the application of recent nonlinear time series methods for the purpose of empirically building a model for the expected magnitude of a material balance or other scalar variable. Although the report restricts attention to monitoring scalar time series, the methodology can be extended to vector time series

  7. Use of fuel reprocessing plant instrumentation for international safeguards

    International Nuclear Information System (INIS)

    Ayers, A.L.

    1977-01-01

    The International Atomic Energy Agency has a program for developing instrumentation to be used by safeguards inspectors at reprocessing facilities. These instruments have generally been individual pieces of equipment for improving the accuracy of existing measurement instrumentation or equipment to perform nondestructive assay on a selected basis. It is proposed that greater use be made of redundant plant instrumentation and data recovery systems that could augment plant instrumentation to verify the validity of plant measurements. Use of these methods for verfication must be proven as part of an operating plant before they can be relied upon for safeguards surveillance. Inspectors must be qualified in plant operations, or have ready access to those so qualified, if the integrity of the operation is to be properly assessed. There is an immediate need for the development and in-plant proof testing of an integrated gamma, passive neutron, and active neutron measurement system for drum quantities of radioactive trash. The primary safeguards effort should be limited to plutonium and highly enriched uranium

  8. Eye movement desensitization and reprocessing for adolescent depression.

    Science.gov (United States)

    Bae, Hwallip; Kim, Daeho; Park, Yong Chon

    2008-03-01

    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-related disorders such as posttraumatic stress disorder. Two teenagers with major depressive disorder (MDD) underwent three and seven sessions of EMDR aimed at memories of stressful life events. After treatment, their depressive symptoms decreased to the level of full remission, and the therapeutic gains were maintained after two and three months of follow up. The effectiveness of EMDR for depression is explained by the model of adaptive information processing. Given the powerful effects observed within a brief period of time, the authors suggest that further investigation of EMDR for depressive disorders is warranted.

  9. Recent R/D towards aqueous reprocessing of FBR fuels

    Energy Technology Data Exchange (ETDEWEB)

    Mallika, C.; Pandey, N.K.; Kumar, S.; Kamachi Mudali, U. [Materials, Process and Equipment Development Group, Indira Gandhi Centre for Atomic Research, Kalpakkam 603102 (India)

    2016-07-01

    The mixed Pu-rich carbide spent fuel with a burn up of 155 GWd/t from the Fast Breeder Test Reactor is being reprocessed in a hot-cell facility by PUREX process. Based on the input from the operation of this facility, research and development activities were carried out to improve the recovery, decontamination factors, economy and to reduce the waste volumes. Reduction of uranyl ions in a continuous flow electrochemical reactor and electrolytic as well as chemical reduction of 4 M HNO{sub 3} from liquid waste could be performed in continuous mode. Using the optimized parameters, suitable electrolytic cells/experimental setups were designed for the plant capacity of 6 L/h. Studies on the extraction kinetics of Ru with 30% TBP (tributyl phosphate) in NPH revealed that better decontamination factor with respect to Ru can be achieved using fast contactors like centrifugal extractors (CEs). Towards developing a spent solvent recovery system to reduce organic waste volumes, a pilot plant was set up, which could recover diluent as top product of distillation column and 40% TBP as bottom product from inactive degraded solvent. A solvent recovery system using short path distillation was also developed for installation in hot cells. (authors)

  10. Remote repair robots for dissolvers in nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    Sugiyama, Sen; Hirose, Yasuo; Kawamura, Hironobu; Minato, Akira; Ozaki, Norihiko.

    1984-01-01

    In nuclear facilities, for the purpose of the reduction of radiation exposure of workers, the shortening of working time and the improvement of capacity ratio of the facilities, the technical development of various devices for remote maintenance and inspection has been advanced so far. This time, an occasion came to inspect and repair the pinhole defects occurred in spent fuel dissolving tanks in the reprocessing plant of Tokai Establishment, Power Reactor and Nuclear Fuel Development Corp. However, since the radiation environmental condition and the restricting condition due to the object of repair were extremely severe, it was impossible to cope with them using conventional robot techniques. Consequently, a repair robot withstanding high level radiation has been developed anew, which can work by totally remote operation in the space of about 270 mm inside diameter and about 6 m length. The repair robot comprises a periscope reflecting mirror system, a combined underwater and atmospheric use television, a grinder, a welder, a liquid penetrant tester and an ultrasonic flaw detector. The key points of the development were the parts withstanding high level radiation and the selection of materials, to make the mechanism small size and the realization of totally remote operation. (Kako, I.)

  11. The life prediction study of Rokkasho reprocessing plant materials

    International Nuclear Information System (INIS)

    Kiuchi, K.; Yano, M.; Takizawa, M.; Shibata, S.

    1998-01-01

    The life prediction study of major equipment materials used in heavily corrosive nitric acid solutions of the RRP was carried out. The nitric acid recovery made of type 304ULC austenitic steel and the dissolver made of type 705 metallic zirconium are selected on the present study. This study is composed of major three programs, namely, the mock-up tests by small-sized equipments simulated to the practical design, laboratory tests for examining corrosion controlling factors by small specimens and to establish the data base system for the life prediction. Important parameters on this study was extracted with analyzing the past data of the life prediction on the Tokai reprocessing equipments. The mock-ups design was made by considering the quantitative evaluation of the most important parts on objective equipments, namely, heat conducting tubes in an acid recovery evaporator and a thermal jacket in a dissolver. From pre-examinations, the effects of radioactive species, nitric acid solution chemistry, the corrosion mechanisms were elucidated. Mock-up testing conditions corrosion monitoring methods and a data base concept for the the life prediction were selected from pre-examination data by referencing the plant operation planning. (author)

  12. Eye Movement Desensitization and Reprocessing (EMDR as a Neurorehabilitation Method

    Directory of Open Access Journals (Sweden)

    Afsaneh Zarghi

    2013-01-01

    Full Text Available   A variety of nervous system components such as medulla, pons, midbrain, cerebellum, basal ganglia, parietal, frontal and occipital lobes have role in Eye Movement Desensitization and Reprocessing (EMDR processes. The eye movement is done simultaneously for attracting client's attention to an external stimulus while concentrating on a certain internal subject. Eye movement guided by therapist is the most common attention stimulus. The role of eye movement has been documented previously in relation with cognitive processing mechanisms. A series of systemic experiments have shown that the eyes’ spontaneous movement is associated with emotional and cognitive changes and results in decreased excitement, flexibility in attention, memory processing, and enhanced semantic recalling. Eye movement also decreases the memory's image clarity and the accompanying excitement. By using EMDR, we can reach some parts of memory which were inaccessible before and also emotionally intolerable. Various researches emphasize on the effectiveness of EMDR in treating and curing phobias, pains, and dependent personality disorders. Consequently, due to the involvement of multiple neural system components, this palliative method of treatment can also help to rehabilitate the neuro-cognitive system.

  13. Operational experience in remote handling during the reprocessing of PFR fuel elements

    International Nuclear Information System (INIS)

    Bailey, G.

    1982-01-01

    The reprocessing of PFR fuel elements at DNE was achieved using new techniques of remote handling as well as standard manipulative procedures. This engineering balance was justified in the successful completion of two PFR reprocessing campaigns, where the personnel involved received low radiation doses. Development work is progressing along the lines of minimizing in-cell equipment, improved remote viewing, and the modular assembly and construction of equipment and cells

  14. Research and development on air cleaning system of reprocessing plant in Japan

    International Nuclear Information System (INIS)

    Naruki, K.

    1985-01-01

    Present status in Japan of R and D on air cleaning systems, especially of the fuel reprocessing plant is summarized. The description is centered on the R and D and experience of Tokai-reprocessing plant, which covers the plant air cleaning system, effort carried out for decreasing I 2 effluence in the actual vented off-gas, and R and D for recovery of Kr and 3 H. Some experimental results for the evaluation of HEPA filter are also described

  15. Design aspects of water usage in the Windscale nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    Wharton, J.; Bullock, M.J.

    1982-01-01

    The safeguard requirements of a nuclear fuel reprocessing plant place unique constraints on a designer which, in turn, affect the scope for the exercise of water economy. These constraints are examined within the context of the British Nuclear Fuels Limited reprocessing plants at Windscale and indicate the scope for water conservation. The plants and their design principles are described with particular reference to water services and usage. Progressive design development is discussed to illustrate the increasing importance of water economy. (author)

  16. The future of reprocessing: a synergy of enhanced processes and new approaches

    International Nuclear Information System (INIS)

    Boullis, B.; Josso, F.; Montmain, J.; Buffereau, M.

    1996-01-01

    The December 30, 1991 french law has led scientists to develop new reprocessing processes in order to implement different strategies for the management of long-lived radioactive wastes from spent fuels. Various existing reprocessing processes and facility operation supervision and control techniques (PUREX, DIAMEX, SESAME, ACTINEX, DIAPASON) are briefly described. Three leading CEA scientists discuss the challenges of the future and according research programs. (C.B.)

  17. Hybrid KED/XRF measurement of minor actinides in reprocessing plants

    International Nuclear Information System (INIS)

    Hsue, S.T.; Collins, M.L.

    1996-01-01

    Minor actinides have received considerable attention recently in the nuclear power industry. Because of their potential value as recycle fuels in thermal and breeder reactors, reprocessing plants may have an economic incentive to extract Np, Am, and Cm from their waste streams. This report discusses the technique of hybrid densitometry and its potential to measure Np and Am in reprocessing plants. Precision estimates are made for the hybrid analysis of Np and Am in two types of dissolver solutions

  18. Handling of spent nuclear fuel and final storage of vitrified high level reprocessing waste

    International Nuclear Information System (INIS)

    1978-01-01

    The report gives a general summary of the Swedish KBS-project on management and disposal of vitrified reprocessed waste. Its final aim is to demostrate that the means of processing and managing power reactor waste in an absolutely safe way, as stipulated in the Swedish so called Conditions Act, already exist. Chapters on Storage facility for spent fuel, Intermidiate storage of reprocessed waste, Geology, Final repository, Transportation, Protection, and Siting. (L.E.)

  19. Particle separation

    International Nuclear Information System (INIS)

    Baker, C.A.

    1990-01-01

    Solid particles are separated from a liquid which also contains ferric hydroxide by subjecting the liquid to ultrasonic agitation from a transducer in order to break up the flocs so that they will pass with the liquid through a filter belt. The belt thus retains the solid particles without interference from the flocs. As shown the woven nylon belt collects rare radioactive solid particles from liquid and carries them under sensors. The belt is washed clean, with further ultrasonic agitation in a trough on its return run. (author)

  20. Isotope separation

    International Nuclear Information System (INIS)

    Rosevear, A.; Sims, H.E.

    1985-01-01

    sup(195m)Au for medical usage is separated from sup(195m)Hg in a solution containing ions of sup(195m)Hg by contacting the solution with an adsorbing agent to adsorb 195 Hgsup(H) thereon, followed by selective elution of sup(195m)Au generated by radioactive decay of the sup(195m)Hg. The adsorbing agent comprises a composite material in the form of an inert porous inorganic substrate (e.g. Kieselguhr),the pores of which are occupied by a hydrogel of a polysaccharide (e.g. agarose) carrying terminal thiol groups for binding Hgsup(H) ions. (author)